ML20212E181
| ML20212E181 | |
| Person / Time | |
|---|---|
| Issue date: | 10/31/1997 |
| From: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| To: | |
| References | |
| NUREG-0304, NUREG-0304-V22-N02, NUREG-304, NUREG-304-V22-N2, NUDOCS 9711030077 | |
| Download: ML20212E181 (47) | |
Text
_
Vol. 22, No. 2 Regulatory and Technical Reports (Abstract Index Journal) l Compilation for Second Quarter 1997 April - June U.S. Nuclear Regulatory Commission Omce cfInformation Resources Management y(&
1 9710gf971031 f$lh,}fdll} lll$l[]l((jl
]
0304 R PDR
~
AVAILABILITY NOTICE I
Avai!aulity of Referents Materials Cited in NRC Publications Most documents cited in NRC publications wi:1 be available from one of the following sources:
1.
The NRC Public Document Room 2120 L Street, NW., Lower Level, Washington, DC 20555-0001 2.
The Superintendent of Documents, U.S. Government Printing Office, P. O. Box 37082.
Washington, DC 20402-9328 3.
The National Technical information Service Springfield, VA 22161-0002 Although the listing that follows represents the majonty of documents cited in NRC putstica-tions, it is not intended to be exhaustive, Referenced documents available for inspectica and copying for a fee from tlie NRC Public Document Room include NRC correspondence and internal NRC memoranda: NRC bulletins, circulars, information notices, inspection and investigation notices; licensee event reports; vendor reports and correspondence Commission papers; and applicant and licensee docu-ments and correspondence, The following documents in the NUREG series are available for purchase from the Government Printing Office: formal NRC staff and contractor reports, NRC sponsored conference pro-ceedings, internationaf agreement reports, grantee reports, and NRC booklets and bro-chures. Also available are reculatory guides, NRC regulations in the Code of Federal Regula-tions, and Nuclear Regulatory Commission issuances.
Documents available from the National Technical information Service include NUREG-series reports and technical reports prepared by other Federal agencies and reports prepared by the Atomic Energy Commission, forerunner agency to the Nuclear Regulatory Commission.
Documents available from public rnd special technical libraries include all open literature items, such as books, journal articles, and transactions. Federal Register notices, Federal and State legislation, and congressional reports can usually be obtained from these libraries.
Documents such as theses, dissertations, foreign reports and transtations, and non-NRC con-f arence proceedings are available for purchase from the organization sponsoring the publica-tion cited.
Single copies of NRC draft reports are available free, to the extent of supply, upon wntten request to the Office of Administration, Distribution and Mail Services Section, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, Copies of industry codes and s;andards used in a substantive manner in the NRC regulatory process are maintained at the NRC Library, Two White Flint North,11545 Rockville Pike, Rock-ville, MD 20852-2738, for use by the public. Codes and standards are usually copyrighted and may be purchased from the originating organization or, if they are American National Standards, from the American National Standards Institute,1430 Broadway, New York, NY 10018-3308.
A year's subscription of this report consists of four qutarterly issues.
l
NUREG4304 Vol 22, No. 2 I
Regulatory and Technical Reports l
(Abstract Index Journal) 1 Compilation for l
Second Quarter 1997 April-June i
Date Published: October 1997 L L Stevenson,ProjectManager Publications Branch Omce ofInformation and Resources Management U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
/
g,
\\,.....
L F
L t
CONTENTS Preface..................................................................,,,,,,,,,,
y index Tab Main Citations and Abstracts.......................................................... 1 o Staff Reports.
Conference Proceedings e
Contractor Reports e
e Grant Reports e International Agreernent Reports Secondary Report Nurnber index........................................................ 2 Personal Author index................................................................. 3 Subject index........................................................................ 4 NRC Originating Organization index (Staff Report?........................................ 5 NRC Originating Organization inder ' International Agreernents).............................. 6 NRC Contract Sponsor index (Contractor Reports).....................,.................. 7 Contractor index..................................................................... 8 Interndtlonal Organization index.........................
4 9
Licensed Facility index...............,,........................,,.................. 10 i
I til
PREFACE This compilation consists of bibliographic data and abstracts for the formal reguistory ano wcnnical reports issued by the U.S. Nuclear Regulatory Commission (NRC) Staff and its contractors. it is NRC's intention to 1
publish this compilation quarterly and to cumulate it annually. Your comments will be appreciated. Please i
send them to:
4 Publications Branch Office of information Resources Management T-6 E7 U.S. Nuc5ar Regulatory Commission Washington, D.C. 20555-0001 The main citations and abstracts in this compilation are listed in NUREG number order: NUREG-)000(, NU-REG /CP-)000(, NUREG/CR-)000(, and NUREG/lA-)000(. These precede the following indexes:
Secondary Report Number index Personal Author Index Subject Index NRC Origir:ating Organization Index (Staff Reports)
NRC Originating Organization Index (International Agreements)
NRC Contract Sponsor index (Contractor Reports)
Contractor index Intemational Organization index Ucensed Facility Index A detailed explanation of the entries precedes each inder The bibiiographic elements of the main citations are the following:
Staff Report NUREG-0808: MARK ll CONTAINMENT PROGRAM EVALUATION AND ACCEPTANCE CRITERIA. ANDER-SON, C. J. Division of Safety Technology. August 1981. 90 pp. 8109140048. 09570:200.
> Where the entries are (1) report number, (2) report titiv, (3) report author, (4) organizational unit of author, (5) date report was published, (0) number of pages in the report, (7) the NRC Document Control System acces-sion number, (8) the microfiche address (for internal NRC use).
Conference Report NUREG/CP-0017: EXECUTIVE SEMINAR ON THE FUTURE ROLE OF RISK ASSESSMENT AND REUABIL-l ITY 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 proveedings, (5) date report was 3.ublished, (6) number of pages in the report, (7) the NRC Document Con-trol System accession number, (8) the report number of the originating organization, (9) the microfiche ad-dress (for NRC intemal use).
i
- - ~
l l
Contractor Report NUREG/CR 1556: STUDY OF ALTERNATE DECAY HEAT REMOVAL CONCEPTS FOR UGHT WATER REACTORS-CURRENT S VSTEMS AND PROPOSED OPTIONS. BERRY, D.L.; BENNETT, RR. Sandia Labo-ratories. May 1981.100 pp. 8107010e49. 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 Con-trol System accession number, (8) the report number of the originating organization (if given), (9) the micro-fiche address (for NRC internal use).
Grant Report NUREG/GR-0013: APPUCATIONS OF A NEW MAGNETIC MONITORING TECHNIQUE TO IN SITU EVAL-UATION OF FATIOUE DAMAGE IN FERROUS COMPONENTS. J1LES, D.C.; BINER, S.B.; GOVINDARAJU, M.; et al. Iowa State Univ., Ames, IA. June 1944,41 pp. 9407250286,80328:195.
Where the entries are(1) report number, (2) report title, (3) report authors, (4) organizational uni + of authors or publisher, (5) date report was published, (6) number of pages in the report, (7) the NRC Document Con-trol System accession number, (8) the report number of the originating organization (4 given), (9) the micro-fiche address (for NRC internal use).
International Agreement Report NUREG/lA-0001: ASSESSMENT OF TRAC-PD2 USING SUPER CANNON AND HDR EXPERIMENTAL DATA. NEUMANN, U. Kraftweek Union. August 1986. 223 pp. 8608270424. 37659:138.
Where the entries are(1) report number, (2) report title, (3) report author, (4) organizational unit of author, (5) date report was published, (6) number of pages in the report, (7) the NRC Document Control System acces-sion 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 ',dentify the document status of a report:
ADD
- addendum APP appenoix DRFT - draft ERR errata N - number R
revision S
supplement V
volume Availability of NRC Publications Copies of NRC staff and contractor reports may be purchased either from the Govemment Printing Office (GPO) or from the National Technical information Service, Springfield, Virginia 22161. To purchase docu-ments from the GPO, send a check or money order, payable to the Superintendent of Documents, ta the following address:
Superintendent of Documents U.S. Government Printing Office Post Office Box 37082 Washington, DC 20013-7082 You may charge any purchase to your GPO Deposit Account, MasterCard charge card, or VISA charge card by calling the GPO on (202) 512-2249 or (202) 512-2171. Non U.S. customers must make payment in ad-vance either oy International Postal Money Order, payable to the Superintendent of Documents, or by draft on a United States or Canadian bank, payable to the Superintendent of Documents.
)
vi
~ _. _.
- NRC Report Codes The NUREG designation, NUREG-X)0OC, indicates that the docurnent is a formal NRC staff generated re.
port. Contractor prepared formal NRC reports carry the report code NUREG/CR-)000(. This type efidentifi-cation repleoes contractor established codes such as ORNtJNUREG/TM-)00( and TREE NUREG-)0OO(, as well as various other numbers that could net be correlated with NRC sponsorship or the work being re-ported.
In addition to the NUREG and NUREG/CR codes, NUREG/CP is used for NRC sponsored conference pro-coedings NUREG/GR is used for NRC grant reports, and NUREG/lA is used for international agreement reports.
All these report codes are controlled and assigned by the staff of the Publications Branch of the NRC Office 2
of ln;wTastion Resources Management.
i s
E i
vil
.rL='mpm.Mme amp ns-.Me-V.mMse e.JKee..
m W Wmm *. 4 m.
- AeePE.-W a 4 E MN mAmesh m% ham-
-M.,shm--
" _N Mad AAJdda f @W ws,a
I I
4 e
);
8 P
i I
i l
l 1
i 1
i I
a -,-,,,,--, - -.,-
-,.n..
c Main Citations and Abstracts The report listings in this compilation are arranged by report number, where NUREG XXXX is an NRC staff onginated report, NUREG/CP-XXXX is an NRC sponsored conferenco report, NUREG/CR XXXX is an NRC contractor-prepared report, and NUREG/lA-XXXX is an inter-national agreement reaort. The bibliographic information (see Prefcce for details) is followed by a brief abstract of tils report.
NUMEG 0090 V19: REPORT TO CONGRESS ON ABNORMAL NUREG-0540 V19 N04: TITLE LIST OF DOCUMENTS MADE OCCURRENCES Fiscal Year 1996.
- Offee for Analysis & Eval.
PUBLICLY AVAILABLE. April 1 30, 1997,
- Offce of Informaton uaten of Operatonal Data, Director. Apr61 1997, 47pp.
Resources Management (Post 890205). June 1997. 405pp.
9704250153. 92624:314.
9707180204. 93804:001.
Section 208 of the Energy Reorganization Act of 1974 (PL See NUREG-0540,V19,N02 abstract 93-438) identifies an abnormal occurrence (AO) as an unsched-uled incident or event that the Nuclear Ragulatory Commission NUREG-0750 V44102: INDEXES TO NUCLEAR REGULATORY (NRC) determines to be significant from the standpoint of pubic COMMISSION ISSUANCES. July December 1996. ' Office of in-health or safety. The Federal Reports Ehminaten and Sunset formaton Rosources Mana0ement (Post *90205). April 1997, Act of 1995 (PL 104-66) requires *, hat AOs be reported to Con-52pp. 9704300062. 92696:262.
gress on an annual basis. This report includes those events that Digests and indexes for issuances tn ue Commission, the NRC determined to be AOs dunng fiscal year 1996. This report Atome Safety and Licensing Board Panel, the Administrative addresses eighteca AOs at NRC-hcensed facihties. Two in-Law Judges, the Directors' Decisions, and the Decisions on Pe-volved events at nuclear power plants, eleven involved medical 1: tons for Rulemaking are presented.
brachytherapy misadministrations, and five involved radiophar-maceutcal misadministrations. Eight AOs submitted by the NUREG-0750 V45 N02: NUCLEAR REGULATORY COMMISSION Agreement States are included. One involved stolen radiogra' ISSUANCES FOR FEBRUARY 1997, Pages 49-93.
- Offee of phy Cameras, one involved a ruptured source, one involved re-information Resources Management (Post 890205). April 1937, 52pp. 9705090049. 92827:001, lease of radioactive material whi8e being transported, one in-volved a lost sourco, two involved medical brachytherapy mis' Legalissuances of the Commisson, the Atomic Safety and Li-administrations, and two involved radiopharmaceutcal misad' censing Board Fanel, the Administrative Law Judges, and NRC ministratons. Four updates of previously reported AOs are in-Program Offces are presented.
cluded in this report Three "Other Events of interest" events NUREG-0750 V45 NO3: NUCLEAR REGULATORY COMMISSION are being reported, and one previously reported "Other Events ISSUANCES FOR MARCH 1997.Pages95-263.
- Offee of in-of Interest" event is being updated.
formation Resources Management (Post 090205). May 1997.
NUREG-0304 V21 N04: REGULATORY AND TECHNICAL RE.
N EG 750, N 2 abstract PORTS (ABSTRACT INDEX JOURNAL). Annual Compilation For 1996.
- Office of Information Resources Management (Post NUREG-0750 V45 N04: NUCLEAR REGULATORY COMM:SSION 890205). Apnl 1997,93pp. 9705010326. 92697:233.
ISSUANCES FOR APRIL 1997.Pages 265-353.
- Office of infor-This joumal includes all formal reports in the NUREG senes mation Resources Management (Post 890205). June 1997, prepared by the NRC staff and contractors; proceedings of con.
96pp. 9707140026. 93738:001, forences and workshops; as well as internatonal agreement re.
See NUREG-0750,V45,N02 abstrect.
a abstract a da e ra a NUREG-0837 V17 N01: NRC TLD DIRECT RADIATION MONI-subject, NRC organization for staff and intemational agree, TORING NETWORK. Progress Report January-March 1997, ments, contractor, intemational organization, and hcensed facili STRUCKMEYER,R. Region 1 (Post 820201). May 1997. 238pp.
ty' 9706160216. 93368:001.
This report provides the status and results of the NRC Ther-NUREG-0540 V19 N02: TITLE LIST OF DOCUMENTS MADE moluminescent Dosimeter (TLD) Direct Radiaton Monitonng PUBLICLY AVAILABLE. February 1 28, 1997.
- Offee of infor-Network, it presents the radiation levels measured in the vicinity maton Resources Management (Post 890205). April 1997.
of NRC hcensed facihties throughout the country for the first 370pp. 9706130158, 93345:026.
quarter of 1997.
ton of m
r o ed a ea by U.
NUREG-0940 V15 N2 P1: ENFORCEMENT ACTIONS: SIGNIFl.
Regulatory Commission (NRC). This information includes (1)
CANT ACTIONS RESOLVED INDIVIDUAL docketed material associated with civilian nuclear power plants ACTIONS. Semiannual Progress ReportJuly-December 1996.
- and other uses of radcactive materials, and (2) nondocketed Ofc of Enforcement (Post 870413). April 1997. 407pp.
material received and generated by NRC pertinent to its role as 9705230 93068 1 Th hor rporat Re N
and oss that have been resolved during the penod (July December Reference of Enclosures to Principal Documents.
1996) and includes copies of Orders and Notices of Violation sent by the Nuclear Regulatory Commission to individuals with NUREG-0540 V19 NO3: TITLE LIST OF DOCUMENTS MADE respect to these enforcement actions. It is anticipated that the PUBLICLY AVAILABLE. March 1 31, 1997.
- Offee of Informa-Information in this pubhcation will be widely disseminated to tion Resources Management (Post 890205). May 1997,382pp.
managers and employees engaged in activities licensed by the 9706130161. 93344:001.
NRC. The Commission believes this information may be useful See NUREG-0540,V19,N02 abstract.
to heensees in making enforcemer.t decisions.
1
2 Main Citations and Abstracts NUREG-0940 V15 N2 P2: ENFORCEMENT ACT'ONS; SIGNIFl-NUREG-1503 S01: FINAL SAFETY EVALUATION REPORT RE-CANT ACTIONS RESOLVED REACTOR LATED TO THE CERTIFICATION OF THE ADVANCED BOIL-LICENSEES. Semiannual Progress Rept July December 1996.
- ING WATER REACTOR DESIGN Supplement No 1. Docket No.
Ofc of Enforcemerit (Post 870413). April 1997, 400pp.52-001.(General Electnc Nuclear Energy)
- Office of Nuclear Reactor Regulaton (Post 941001). May 1997. 49pp.
9705210290. 93063:001.
9706120299. 93337:217.
TNs compitabon summarizes sigmficant enforcement actons TNs report supplements the firial safety evaluation report that have been reso'ved dunng the period (Jufy December (FSER) for the U.S. Advanced Boiling Water Reactor (ABWR) 1996) and includes copies of letters, Notees, and Orders sent standard design. The FSER was issued by the U.S. Nuclear by the Nuclear Regulatory Comrmsson to reactor teensees with Wawy hmsson W% staN as WEN h M respect to these enforcement actons. It is anbcipated that the 1994 to document the NRC staff,a review of the U.S. ABWR 6nformat.on in this pubicaton will be widely uisseminated to design. The U.S. ABWR design was s bmitted by GE Nuclear managers and employees engaged in activities heensed by the Energy (GE)in accordance with the procedures of Subpart B to NRC, so that actons can be taken to improve tafety by avoid-Part 52 of Title 10 of the Code of Federal Regulatons. This ing future violatons similar to those described in this pubica' supplement documents the NRC staffs review of the changes to ton.
the U.S ABWR design documentation since the issuance of the FSER. GE made these changes primanly as a result of first-of.
NUREG-0940 V15 N2 P3: ENFORCEMENT ACTIONS: SIGNIFl.
a-kind-engineering (FOAKE) and as a result of the design certifi-CANT ACTIONS RESOLVED MATERIAL cabon rutemeking for the ABWR design. On the basis of its LICENSEES. Semiannual Progress Report, July December 1096.
evaluaton, the NRC staff concludes that the confirmatory
- Ofc of Enforcement (Post 870413). April 1997, 300pp.
issues in NU3EG-1503 are resolved, that the changes to the 9705140378. 92886:001.
ABWR design documentaten are acceptable, and that GE's ap-This compilation summarizes signifcant enforcement actont phcaten for design certifcaton meets the requirements of Sub-that have been resolved during the penod (July December part B to 10 CFR Part 52 that are apphcable and technically rel-1996) and trx:tudes copies of letters, Notees, and Orders sent evant to the U.S. ABWR design.
by the Nuclear Regulatory Commission to matenal Icensees NUREG-1516: MANAGEMENT OF RADIOACTIVE MATERIAL with respect to these enforcement actions. It is anteipated that SAFETY PROGRAMS AT MEDICAL FACILITIES. Final Report the informaton in this publication will be widely disseminated to CAMPER,LW.; SCHLUETER J.; WOODS,S.; et al. Division of in-managers and employees engaged in activit>es licensed by the dustrial & Ms inc08 Nuclear Safety (Post 870729). May 1997, NRC, so that actions can be taken to improve safety by avoid-193p 7 4 1 ing future violations similar to those described in tNs pubica-Commission and two Agreement State program staff members developed the guidance contained in this report The purpose of UREG 1125 V18: A COMPILATION OF REPORTS OF THE AD-this report is to descnbe a systematic approach for effective VISORY COMMITTEE ON REACTOR SAFEGUARDS.1996 managoment of radiaton safety programs at medical facihtes.
Annual
- ACRS Advisory Comwittee on Reactor Safe 9uards, This is accomplished by emphasizing the roles of institution ex-April 1997,128pp. 9706250071. $ 3502:001.
ecutve managevent, radiation safety committee, and radiation This compilation contains 47 tiCRS reports submitted to the safety oftcer. Vanous aspects of program management are dis-Commission, or to the Executive Director for Operations, dunng cussed and include guidance on selecting the radiaton safety calendar year 1996. It also includes a report to the Congress on offcer, determining adequate resources for the program, the the NRC Safety Research Program. All reports have been made use of contractual services such as consultants and service available to the pubic through the NRC Pubic Document companies, the conduct of audits, the roles of authon2ed users Room, the U.S. Library of Congress, and the Internet at http://
and supervised individuals, NRC's reportng and notificabon re-www.nre gov /ACRSACNW. The reports are divided into two quirements, and a general descripton of how NRC's Icensing, groups: Part 1: ACRS Reports on Project Reviews, and Part 2:
inspection, and enforcement programs work. Appendices pro-ACRS Reports on Genenc Subjects. Part 1 contains ACRS re-vide detailed guidance on specific aspects of a radiahon safety ports by project name and by chronological order within protect program and the glossary defines terms used throughout the name. Part 2 categonzes the reports by the most appropriate report. The guidance contained herein does not represent new generic subject area and by chronological order within subject or proposed e qutatory requirements and hcensees will not be inspected acanist any porton of it. Additionally, regulatory com-area.
piiance with all apphcable regulations is not assured by licens-NUREG-1350 V09: NUCLEAR REGULATORY COMMISSION IN.
ees who adopt any portion of, or appty the pnnciples desenbed FORMATION DIGEST,1997 Edition. GARVER.M. Division of in, this report.
I' NUREG-1542 V02: ACCOUNTABILITY REPORT FISCAL YEAR 7
0165 5 45 C0 The Nuclear Regulatory Commission information Digest gy 3997 2pp 970521 2 8 3 001 (digest) provides a summary of information about the U.S. No-The U.S. Nuclear Regulatory Commission (NRC) is one of six clear Regulatory Commission (NRC) NRC's regulatory responsi-Federal agencies participating in a pilot project to streamhne fi-bihties, NRC heensed activities, and general information on do-nancial management reportmg. The goal of this pilot is to con-meste and wortdwide nuclear energy. The digest pubhshed an-sohdate performance-related reporting into a single accountabil-nually, is a compilation of nuclear and NRC-related data and is ity report in accordance with the Govemment Management designed to provide a quck reference to major facts about the Reform Act (GMRA) of 1994. The NRC's second accountability agency and the industry it regulates in general, the data cover report consohdates the information previously reported in the 1975 through 1996, with exceptions noted. Information on gen-NRC's annual financial statement required by the Chief Finan-erating capacity and average capacity factor for operating U.S.
cial Officers Act of 1990, as amended, the chairman's annual commercial nuclear power reactors is obtained from monthly report to the President and the Congress, required by the Fed-operahng reports that are submitted directfy to the NRC by the eral Managers' Financial Integnty Act of 1982; and the Chair-I censoe. This information is reviewed by the NRC for consisten-man's semiannual report to the Congress on management deci-cy only and no independent validation and/or verification is per-sions and final actions on Office of Inspector General (OlG)
- formed, audit recommendations, required by the inspector General Act l
1 1
1 Main Citations and Abstracts 3
I s
j of 1978, as amended.'TNs report also includes performance of an acceptable PRA for such regulatory activities. Detailed measures, as required by the CNef Financial Offcers Act of descussion is provided for a full-scope PRA (i.e., a PRA that 1990.
conseders both intomal and extemal events for all modes of op.
m t
NUREG 1694 V01: CONSOLIDATED GUIDANCE ABOlIT MATE.
. eraton). In additon, discussions are provided for the use and
+
- RIALS LICENSES. Program-Specife Guidance About Portable brMatons of importance messe and 3ensibvity studies. Final-1
. Gauge Licenses. Final Report VACCA,P.C.: WHITTEN.J.E.;
ly, me subsKt of peer review of a _PRA is also descussed.
- PELCHAT.J.M.; et at Division of industrial & Medcal Nuclear Safety -- (Post 870729). - May' 1997, 146pp. 9706180459' NUREG 1803 DMFT: INDIVIDUAL PLANT EXAMINATION 4
93393.214.
DATABASE. User's GuHe. SU,T.M. Offee of Nuclear Regulatory
- As part of its redesign of the materials bcenseg process, Research (Post 941217). DANZlGER.L.M. Orfee of Information
- NRC is consohdatmg and updating numerous guidance docu-.
Resources Manageraent (Post 890205). LIN.C.C.; et al. Brook-monts into a single comprehensive repository as described in haven Nahmal LabwaWy. AprH 1997,150pp. 9705010320.
NUREG-1539 and draft NUREG 1541 NUREG-1556, Vol.1, is.
92697$69.
4 g -
~ the first program-specific guidance developed for the new proc-The individual Plant Examinaten (IPE) database stores struc-j oss and will serve as a template for subsequent program specif.
tured intwmat on about plant designs, core damage frequency
' ic guidance. TNs document is intended for use by appicants, (CDF) and containment performance, it records the presence or i.
Tcensees, and NRC staff and win also be available to Agree, absence of hardware in each design, charactertzes its functonal j
ment States. This docurnent supersedes the guidance previous, dependencies, and relates these features to the CDF and con ~
j ly found in draft Regulatory Guide DG 0008, "Appicatens for tamme t performance. The IPE database supports detaned in-the Use of Scaled Sources in Portable GW Devces," and quiries into these characteristics for a specife plant or class of in NMSS Policy and Guidance Directive 2-07, " Standard Review,
plants. In partcular, the IPE database is designed to answer Plan for Applications for Use of Sealed Sources in Portable questens that enable interested parties to compare the CDF Gautyng Devices." This final report takes a more risk 4nformed, and containment performarce of boiling-and p'essunzed-water j.
perfumance-based approach to hcensmg portable gauges; and reactors (BWRs and PWRs) as a functon of their design fea-reores the informaton (amount and level of detail) needet to tures, on the basis of informaton found in the IPE submittals.
j support an apphcation to use these devees. It incorporates To query the IPE database, two programs have been devel-t.
l many suggestens submitted during the comment period on oped. The first is a self contained, user friendly, menu-drtven Caft NUREG tS56, Vol.1. When pubhshed, tNs fmal report program written in Merosoft's Visual Basic language. TNs pro-
' should be used in preparing portable gauge license applicatons.
gram answers the " basic queries" mo6t often asked about the NRC staff wHi use this final report in reviewing these applica-iPEs, through a process of sorting records witNn the iPE data-l tons. -
base. Quenos of tNs typs can be improvised on the spot. Other
- I **" I" **
"I*"**
- I d'I*
NURIG 1572: SAFETY EVALUATION REPORT RELATED TO 4
YHE RENEWAL OF THE OPERATING LICENSE FOR THE RE-es a fa w swho m e f ca em can be SEARCH REACTOR AT NORTH CAROLINA STATE UNIVERSI-performed using the programming language within such person.
TY.
- Office of Nuclear Reactor Regulaton (Post 9410"1). April al canpuW data managemem aQatens as dBaw, Access, 1997 120pp. 9705280265. 93126:178 m
a database uses gee pMes gWance TNs safety evaluaton report (SER) summarizes the findings tumulahng ba* and advanced quenes. N gudame tw of a safety review conducted by the staff of the U.S. Nuclear advaW quenos is given in tenne of Meroson Access 2A Regulatory Commission (NRC), Offee of Nuclear Reactor Reg
- NUREG 1604: CIRCUMFERENTIAL CRACKING OF STEAM GEN.
. laten (NAR). The staff conducted this review in response to a i!
. timely appleahon filed by North Carohna State Uruverssty (the 11-ERATOR TUBES. KARWOSKI,K.J. Ottee of Nuclear Reactor coneee or NCSU) for a 20-year renewal of Facihty Operahng Li.
Reguistion (Post 9410C1). April 1997.171pp. 9705160211.'
93024:113 conee R-120 to continue to operate the NCSU PULSTAR re.
On Apd28,1995, the U.S. Nuclear Regulatory Commission a
search reactor, The facihty is located in the Burlington Engineer-
. Ing Laboratory complex on the NCSU campus in Raleigh, North (NRC) issued Generic Letter (GL) 95-03 "Circumferenhal Carolina, in its safety review, the staff considered information Cracking of Steam Generator Tubes." GL 95-03 was issued to submitted by the licensee (including past operating history re-In h h W b % h m W W 2 e corded in the licensee's annual reports to the NRC), as well as ishng Watwy requirwnents regardmg me integnty of steam Ir, spectron reports prepared by NRC Region li personnel and generator tubes in domeste pressunzed-water reactors (PWRs).
. first-hand observatons. On the basis of tNs review, the staff a repwt bneny desates me W and fecM of daneshc concludes that NCSU can conhnue to operate the PULSTAR re-steam generators and summarizes the staffs assessment of the L
sewch react % in accwdence wim Ms applicam MW en-responses to GL 95-03. The report concludes with several ob-dangenng the health and safety of the public. -
swvams related to Meam genwata opwahng expenence.
This report is intended to be representative of signifcant operat-NUREG 1602 DRFT FC: THE USE OF PRA IN RISK INFORMED ing experience pertaining to circumferential cracking of steam APPUCATIONS. Draft Rapt For Comment.
- Division of Systems generator tubes from April 1995 through December 1996. Oper.
Technology (Post 941217). June 1997.150pp f?Q7140029.
ahng expcience prior to April 1995 is discussed throughout the i
93737:167.-
report, as necessary, for completeness.
In August 1995, the Nuclear Regulatory Commiss#on issued a 1
policy statement proposing improved regulatory doctesonmaking NUREG 1606 DRFT FC: PROP 0 SED REGULATORY GUIDANCE "by increasing the use of PRA [probabilistic risk assessment /
RELATED. TO IMPLEMENTATION OF 10.CFR 50.59 analysis] in all regulatory matters to the extent supported by the (CHANGES, TESTS, OR EXPERIMENTS). Draft Report ' For i.
- state of-the-art in PRA methods and data." To support the im-Comment. MCKENNA,E.M. Offce of Nuclear Reactor Regula.
4 piementation of the Commission's policy, regulatory guidance ton (Post 941001). April 1997, 61pp. 9705140368. 92887:102.
documents have been developed by the staff (as drafts for The Nuclear Regulatory Commission is issuing this draft guid-public comment) desenbing how PRA can be used in specific ance document for public comment that describes current inter-regulatory activities, many of which relate to hcense& proposed pretations related to the process by which power reactor hcens-j-
- changes to their current licensing basis (CLB). In addition, a ees may make certain plant changes without prior NRC approv.
' more general regulatory guide has been 'teveloped which de-al. The draft guidance reaffirms existing regulatory practce in l.
scnbes an overall approach to using PRA m : i " formed regu-
. many areas; clanfies the staff's expectatens in areas where in-Otiort One key aspect of tNs general guidance is the attributes dustry practice or position differs from the staff's and estab-
[
l I
1 i
4 Main Citations and Abstracts hshes guidarwe in areas where guidance did not previously censing nuclear power reactors, siting of plants, developing exist.
standards for radaten protection, and disposing of radioactrve wastes.
NUREG-1607: SAFETY EVALUATION REPORT RELATED TO THE DEPARTMENT OF ENERGY'S PROPOSAL FOR THE IR-HUREG/CP-0155: PROCEEDINGS OF THE SEMINAR ON LEAK RADIATION OF LEAD TEST ASSEMBLIES CONTAINING TRIT.
BEFORE BREAK IN REACTOR PLPING AND VESSELS IUM-PRODUCtNG BURNABLE ABSORBER RODS IN COM' MERCIAL LIGHT WATER REACTORS. Ofice of Nuclear Pe-F.AfDY,C. France. GILLES,PH. FRAMATOME. April 1997.
- N* pp. 9704240208. 92599:001 actor R taten (Post 941001). May 1997. 78pp. 9706190451, The sixth in a senes of intemational laak-Befo,e-Break (LBB)
Seminars was held at Hotel Sofitel in Lyon, France on October The NRC staff has reviewed a report, submitted by DOL to determine whether the use of a commercial ligM water reactor 9 through 11,1995. The seminar updated intematonal pohcies and supporting research on LBB. Attendees included represent-(CLWR) to irradiale a hmited number of tribum-producing burn.
able absorber rods (TPBARs) in lead test assemblies (LTAs) atives from regulatory agencies, electnc utility representatives, fabncators d nuclear power plants, research organizatons, and raises generic issues involving an unreviewed safety queshon.
academic institutons. The objective of the seminar was to The staff has prepared this safety evaluation to address the ac, ceptability of these LTAs in accordance with the provision of 10 present the current state of the art in LBB methodology devel.
opment, vahdation, and apphcaton in an internebonal forum.
CFR 50.59 without NRC bcensing acton. As summarized in Secton 10 of this safety evaluaton, the staff has identified With particular emphasis on industnal appicatens and regula-lasues that requiro NRC review. The staff has also identified a tory policies, the seminar prov6ded an opportunity to compare number of areas in which an individual heensee undertaking irra, approaches, experiences, and codif cations developed by differ-ent countnes. De serCar was organized into four topic ar6as:
diaton of TPBAR LTAs will have to supplement the informaton in the DOE report before the staff can determine whether the Status of LBB Aphcabons Technical issues in LBB, Methodol-proposed irradtation is acceptable at a particular facihty. The ogy, Complementary Requirements (Leak Detection and inspec-staft emcludes that a licensee undertaking irradiaton of TPBAR tion), and LBB Assessment and Margins. In addition to the LTAs in a CLWR will have to submit an apphcahon for amend.
formal sessons where papers were prosented by parbeipants ment to its facihty operahng hcense before inserting the LTAs from France, Germany, Japan, Korea, Belgium, the United King-dom, the Czech Repubhc, Finland, Russia, Sweden, Canada, into the reactor, the Netherlands, and the United States, informal LBB poster NUREG-1608 DRFT FC: CATEGORIZLNG AND TRMSPORTING sessions were available outside the presentaten hall As a LOW SPECIFIC ACTIVITY MATERIALS AND SURFACE CON' result of this semenar, better eshmates of the hmits to the LBB TAMINATED OBJECTS Draft Rept For Comment.
- Office of approach should follow, as well as an improvement in codifying Nuclear Material Safety & Safeguards.
- Transportaten, Dept.
methodologies, of June 1997, 60pp. 9707140018. 93738:098.
The primary purpose of this guidance is to assist shippers in NUREG/CP-0158: PROCEEDINGS OF THE OECD/CSNI SPE-preparing low spec 6c actvity materials (LSA) and surface con.
CIALISTS MEETING ON BORON DILUTION REACTIVITY timinated objects (SCOs) for shyment in compliance with Fed-TRANSIENTS. Held in State College, Pennsylvania. USA October eral regulatons. Guidance is provided in queston and answer 18-20,1995,
- Organizaten for Economic Cooperation & Devel-format on the classificaton, charactenzation, packaging and opment.
- Pennsylvania State Univ., University Park, PA. June transportaten of LSA and SCOs, including the definition of LSA 1997,468pp.9707180208. NEA/CSNI/R(96)3,93800:001, and SCOs, the determination of distnbuton on of activity in LSA A CSNI Specialist Meebng on Boron Diluton Reactivity Tran-matenal or on SCO surfaces, mixing LSA and SCOs in a pack-sients was held in State College, Pennsytvania, USA, from Oc-age, radiation level measurements, and vanous other aspects of tober 18-20,1995. The meebng was sponsored by the United transporting LSA and SCOs. There are many requirements' States Nuclear Regulatory Commission (USNRC) in collabora-other than those addressed herein, imposed in the shipment of ton with the Committee on the Safety of Nuclear installation LSA and SCOs. The guidance represents one or more methods (CSNI) of the OECD Nuclear Energy Agency (NEA) and the of demonstratng comphance with the regulatory requirements Pennsytvania State University, The objective of the meeting was for LSA material and SCOs that have been found acceptable to to bring together experts involved in the different activities relat-NRC staff; however, additional methods may also be found to ed to boron ddution transients, to promoto discussion among be acceptable with adequate justification. This document is these experts, and to focus on the technical issues of concem being issued for pubhc comment. As a result of the pubhc com-in resolving the safety significance of such events.
ments, or internal peer rev ew and discussions, the content of the final guidance may be significantfy different from that pre-NUREG/CR-0200 R$V1P1: SCALE: A MODULAR CODE sented in this document.
SYSTEM FOR PERFORMING STANDARDIZED COMPUTER NUREG-1610: CONTROLLING THE ATOM.The Beginnings Of ANALYSES FOR LICENSING EVALUATION. Control Modules Nuclear Regulabon, 1946-1962. MAZUZAN,G.T.; WALKER,S.
C4, C8.
- Oak Ridge National Laboratory. March 1997, 599pp.
Office of the Secretary of the Commission. May 1997. 558pp.
9705120302. ORNLNUREGCSD2R5. 92830:001, 9707220273. 93827:001.
SCALE a modular code system for Standardized Computer Controlhng the Atom is a study of the early history of nuclear Analyses Licensing Evaluaton-bas been developed by Oak regulaten. It focuses on the activities of the U.S. Atomic Energy Ridge National Laboratory at the request of the U.S. Nuclear Commission (predecessor of the Nuclear Regulatory Commis-Regulatory Commission. The SCALE system ublizes well-estab-sion), the agency that exercised primary responsibility for safe-hshed computer codes and methods within standard analysis guarding public health and safety from the hazards of nuclear sequences that (1) allow an input format designed for the occa-power. The book reconstructs the context in which the AEC es-sional user and/or novice, (2) automated the data processing tabhshed its regulatory program, weQhing the relationship be-and couphng between modules, and (3) provide accurate and tween the AEC's regulatory programs and its other maior func-reliable results. System development has tren directed at prob-tens: developing and tesbng of nuclear weapons and encourag-lem-dependent cross-section processing a-
- nalysis of cntical-ing expanded use of civilian nuclear energy. A persistent theme ity safety, shielding. heat transfer, and dep.etion/ decay prob-is the AEC's effort to ensure adequate protecten of pubhc lems. Since the initial release of SCALE in 1980, the code health and safety without imposing restnctive or inflexible regu-system has been heavily used for evaluabon of nuclear fuel fa-lations that would impede the growth of the nuclear industry, cihty and package designs. Th:s revision documents Version 4.3 The book provides detailed accounts of key issues such as li-of the system.
Main Citations and Abstracts 5
NUREG/CR 0200 R5V1P2: SCALE: A MODULAR CODE nessments. Selected events underwent engineering evaluaton SYSTEM FOR PERFORMING STANDARDIZED COMPUTER that identified, analyzed, and documented the precursors. Other ANALYSES FOR LICENSING EVALUATION. Control Modules events designated by the Nuclear Regulatory Commission S1 H1,
- Oak Ridge National Laboratory. March 1997,556pp.
(NRC) also underwent a similar evaluaton. Finally, documented 9705120305. ORNLNUREGCSO2R5. 92832:001, precursors were submitted for review by beensees and NRC See NUREG/CR 0200,R5,V1.P1 abstract staff to ensure that the plant design and its response to the pre.
NUREG/CR 0200 R$V2P14 SCALE: A MODULAR CODE cursor were correctly charactertred. TNs study is a continuaton SYSTEM FOR PERFORMING STANDARDlZED COMPUTER of eaN wak, which waluated M9-M1 and 19846 ANALYSES FOR LICENSING EVALUATION. Functional Modules events. The report discusses the general ratonale for this F1. F8.
- Oak Ridge National Laboratory. March 1997,705pp, study, the selecton and documentation of events as precursors, 9705120317. ORNLNUREGCSO2R5. 92843.001, and the estsnaten of conditional probabilities of subsequent
- See NUREG/CR-0200,R5,V1,P1 abstract, severe core damage for events.
NUREG/CR-0200 R5V2P2: SCALE: A MODULAR CODE NUREG/CR-4474 V24: PRECURSORS TO POTENTIAL SEVERE SYSTEM FOR PERFORMING STANDARDIZED COMPUTER CORE DAMAGE ACCIDENTS: 1982-83A Status Report.
ANALYSES FOR LICENSING EVALUATION.Funcbonal Modules FORESTER,J A.: SCHRINER,H.K.; et al. Sandia Natonal Lab-F9. F11,
- Oak Ridge National Laboratory. March 1997.832pp.
. oratories. MINAR!CX,J.W. Science Apphcaborn Internabonal 9705120321; ORNLNUREGCSD2RS, 92866:001, Corp. (formedy Science Applicatons, Inc.). April 1997, 515pp.
See NUREG/CR-0200,R5,V1,P1 abstract.
9706120352. SAND 97 0807,93338.001.
NUREG/CR 0200 R5V2P3: SCALE: A MODULAR CODE TNs study is a centinuation of earlier work that evaluated SYSTEM FOR PERFORMING STANDARDIZED COMPUTER 1969-1981 and 19841994 events affechng commercial light-ANALYSES FOR LICENSING EVALUATION. Functional Modules water reactors. One hundred nine operatonal events that affect.
F16 F17,
- Oak Ridge Natonal Laboratory. March 1997, ed 51 reactors turing 1982 and 1983 and that are considered 606pp. 9705120322. ORNLNUREGCSD2R5. 92869:001, to be proces to potenbal severe core damage are de-See NUREG/CR 0200,R5,V1,P1 abstract.
scribed. All these events had conditional probabihties of subse-quent severe core damage greater than or equal to 1.0 x 10( 6).
NUREG/CR 0200 R5V3: SCALE: A MODULAR CODE SYSTEM These events were identified by fust computer screening the FOR PERFORMING STANDARDIZED COMPUTER ANALYSES 1982 83 heensee event reports from commercial light-water re-FOR UCENSING EVALUATION. Miscellaneous.
- Oak Ridge actors to select events that could be precursors to core National Laboratory, March 1997. 764pp. 9705120311.
ORNLNUREGCSD2RS. 92840:001-damage. Canddates underwent engineering evaluation that See NUREG/CR 0200,RS,V1,P1 abstract.
identified, anatyred, and documented the precursors. TNs report discusses the general ratonale for the study, the selec-NUREG/CR-4467 V22: ENVRONMENTALLY ASSISTED CRACK.
ton and documentaten of events as precursors, and the esti-ING IN LIGHT WATER REACTORS.
Semiannual mation of condtional probabilibes of subsequent severe core Report, January 1096 June 1996. CHOPRA.O.K.; CHUNG,H.M.;
damage for the events.
7 1011. N 9
NUREG/CR 5691 V07 N1: HEAVY SECTION STEEL IRRADIA-TNs report summanzes work performed by Argonne Natonal TION PROGHAM.Serdannual Progress Report For October Laboratory on fatigue and environmentally assisted cracking 1995 Through March 1996. CORWIN,W.R. Oak Ridge National (EAC) in hght water reactors from January 1996 to June 1996.
Laboratory. April 1997, 63pp. 0705120292. ORNL/TM 11560.
Topics that have been investigated include (a) fatigue of 92828:054, carbon, low-alloy, and austenstic stainless steels (SSa) used in The goal of the Heavy-Secten Steel irradiation Program is to reactor papeng and pressure vressels, (b) Irradaten assisted provide a thorough, quantitative assessment of effects of neu-stress corrosen cracking of Type 304 SS, and (c) EAC of Alloys tron irradaten on matenal behavior, and in y.icular the frac-600 and 690. Fabgue tests were conducted on femtic and aus-ture toughness properties, of typical pressure vessel steels as tenitic SSs in water that contained various concentratens of they relate to light-water reactor pressure-vesset integnty. El-dissolved oxygen (DO) to determine whether a slow strain rate fects of specimen size, material chemistry, product form and mi-apphed during various portens of a tensile-loadng cycle are crostructure, Irradaten fluence, flux, temperature and spectrum, equally effective in decreasing f.ntsgue life. Slow-strain-rate-ten-and posWadaten anneahng are bemg examined on a wide sine tests were conducted in simulated boiling water reactor range of fracture proper;,es. The HSSI Program is arranged into (BWR) water at 288 degrees C on SS specimens irradiated to a 14 tasks: (1) program management (2) fracture toughness low fiuence in the Halden reactor and the results were com-(K(Ic)) curve sNft in high copper welds, (3) crack-arrest tough-pared with similar data from a control-blade sheath a.nd neu-ness (K(la)) curve shift in high-copper welds, (4) irradiaton ef-tror> absorber tubes irradiated in BWRs to the same fluence facts on cladding, (5) K(Ic) and K(la) curve shits in low upper-level Crack growth-rate tests were conducted on compact ten-shelf welds, (6) annealing effects in low upper-shelf welds, (7) sion specimens from several heats of Alloys 600 and 690 in air irradaten effects in a commercial low upper shelf weld, (8) mi-and Ngh-punty, low-DO water, crostmetwal anahsis of kradauon ehets, (9) WseMce aged material evaluatons (10) correlation monitor materials, (11)
NUREG/CR-4474 V23: PRECURSORS TO POTENTIAL SEVERE special technical assistance, (12) JPOR steel examinahon, (13)
CORE DAMAGE ACCIDENTS: 1995. A Status Report.
technical assistance for JCCCNRS Working Groups 3 and 12,
_ BELLES,R J.; CLETCHER,J.W.; COPINGER.D.A.; et al Oak and (14) additonal requirements for matenals. TNs report pro-Ridge Nabonal Laboratory. April 1907, 300pp. 9706120307, vides an overview of the activibes within each of these tasks ORNL/NOAC-232. 93343:041, from October 1995 Through March 1996.
' Ten operational events that affected ten commercial light-water reactors (LWRs) during 1995 that are considered to be NUREG/CR-5681: RECOMMENDATIONS FOR PREPARING THE precursors to potential severe core damage are descr! bed. All CRITICALITY SAFETY EVALUATION OF TRANSPORTATION of these events had conditional probabilities of subsequent core PACKAGES. DYER,H.R.; PARKS.C.V. Oak Ridge National Lab-damage greater than or equal to 1.0 x 10(-6). These events oratory. April 1997, 58pp. 9705160214. ORNL/TM-11936.
were identified t:y computer screening the 1995 licensee event 93024:284.
reports from commercial LWRs to identify those that could be This report provides recommendabons on prepanng the criti-potential precursors. Candidate precursors were then selected cality safety secten of an applicahon for approval of a transpor-and evaluated in a process similar to that used in previous as-tation package containing hssile matenal. The analytical ap-
l t
6 Maln Citations and Abstracts proach to the evaluaton is emphasized rather than the perform-tainty distnbuton are used to construct a simphfied model of de-ance standards that the package must meet. Where perform-contaminaten by steam suppression pools.
ance standards are addressed, this report incorporates the re-querements of 10 CFR Part 71.
NUREG/CR-6167: LATE PHASE MELT PROGRESSION EXPERI.
MENT MP 2.Results And Analysis.
GASSER.R.D.;
NUREG/CR-6037: MEASUREMENT OF RESIDUAL RADIOAC-TIVE SURFACE CONTAMINATION BY 2 0 LASER HEATED GAUNTT.R.O.; BOURCIER.S.C.; et al. Sandia Natonal Labora-tones. May 1997, 275pp. 9707180201. SAND 93-3931.
TLD. JONES.S C. Keithley instruments, Inc. June 1997,100pp.
9706240042. 93499:00 t, 93801:105.
The feasibihty of applying and adaptng a two-dimensional A series of in pile experiments addressing the phenomenolo-laser heated thermoluminescence dosimetry system to the gy associated with Late Phase processes in Light Water Reac-problem of surveying for radioactive surface contamination was tors (LWRs) has been performed in the Annular Core Research studied. The system consists of a CO(2) laser-based reader and Reactor (ACRR) at Sandia National Laboratones. The Melt Pro-monohthic arrays of than dosameter elements. The anays consist gresson (MP) expenments were designed to provide informa-of 10,201 thermoluminescent phosohor elements of 40 micron tion as part of the effort to develop and venfy computer models thickness, covering a 900 CM(2) area. Array substrates are 125 for the LWR core damage during severe accidents. The MP-2 micron th6ck polyimide sheets, enabling them to easily conform expenment is the second expenment in this senes. The 81P-2 to regular surface shapes, especially for survey of surfaces that experiment examine the formation and movement of ceramic are inaccessible for standard survey instruments. The passive, molten pools that form in the disrupted regions of a reactor integrating radiaton detectors are sensitive to alpha and beta core. The MP-2 experiment assembly consisted of three re-radiation at contaminaton levels below release guideline limits.
gions: (1) a rubble bed composed of ennched UO(2) and ZrO(2)
Required contact times with potentally contaminated suriaces that simulated the severely disrupted regens of the reactor a'e under one hour to achieve detecten of transuranic alpha core, (2) a composite ceramic / metallic crust whch represented emission at 100 dpm/100 cm(2). Positonal informaton obtained the blockage formed by the early phase melting, relocation, and from array evaluabon is useful for locating contaminaton zones.
refreezing of mostly metalhc core components, and (3) an intact Unique capabikties of this s('9m for survey of sites, facilities rod stub regon that remained in place below the blockage and matenal include measurement inside pipes and other geo-metrcal configuratons that prevent standard surveys, and region. The test assembly was fission heated in the central below-surface measurement of alpha and beta emitters in con-cavity of the ACRR at an average rate of -0.2 K/s ultimately taminated soils. These apphcsti "y a reducten of matenal achieving a peak temperature in the molten pool of 3400 K, that must be classified as '
waste by virtue of its pos-As ACRR power levels were 1,1 creased over time, the crust stbehty of contaminaton, t.
iavings in soil sampling at gradually remelted and reformed, penetrating into and attacking contaminated sites.
the ceramic /metalisc blockage. The metalle components of the blockage region melted and relocated downward to the bottom NUREG/CR-6074 V03: SEALED dOURCE AND DEVICE DESIGN of the intact rod stub regson. The ceramic pool penetrated half-SAFETY TESTING.Techncal Report On The Findings Of Task way into the blockage region at the end of the expenment. Pos-4 Investigaton Of A Failed Brachytherapy Needle Applicator.
texpenment exam:naten of the assembly with the associated LUKEZlCH.S.J. Southwest Research institute. May 1997, 77pp-material interactions and metallurgy are discussed in detail to-ge w
analyses aM Weveta%n d N reds.
A a res 11 f an en h a radioactive brachyther-apy treatment source was temporarily unable to be retracted, an NUREQ/CR 6233 V02: STABILITY OF CRACKED PIPE UNDER analysis was performed on the needle apphcstor usod dunng SEISMIC / DYNAMIC DISPLACEMENT CONTROLLED the treatment. In this report, the results of laboratory evalua.
STRESSES. Subtask 1.2 Final Report. KRAMER,G.; VitiTH,P.;
tions of the physical, mecharscal, and metallurgical conditon of the subject appleator and two addi'ional applicators are pre.
MARSCHALL,C.; et al. Battelle Memonal insttute, Columbus Laboratories. June 1997, 170PP. 9707140055. BMI-2177' sented. A kink formed in the subject applicator dunng the inci-93737 M dont. The laboratory investigation focused on identifying charac-teristes whch would increase the susceptbihty of an applcator Results of displacement-controlled pipe fracture experiments, to form a kink when subjected to bending loads. The results ob.
analyses, and mateqal charactenzaton efforts performed within tained dunng ttvs investigabon could not conclusively identify the International Piping Integnty Research Group, IPIRC, Pro-the cause of the kink. The subject applicator exhibited no gram Subtask 1.2 are discussed. Effects of dynamic versus unique features which would have made it particularty suscepti-quasi-state and monotonic versus cyche loading were evaluated ble to forming a kink. The three appkcators examined represent for ductle teanng of two materials, A106 Grade B femtic steel two methods of manufactunng. A number of charactenstics in-and TP304 austenitic steel. Twelve through-wall-cracked pape herent to the method used to manufacture the subect apphca-expenments were conducted on 6-inch diameter Schedule 120 t
tor whch could lead to an increased susceptbihty to oie tu,,.ia-pipe at 288 C (550 F). The results indicated dynamic loaciang at tion of a kink were observed. The use of an insertion device, seismic strain rates marginally increased the load-carrying ca-such as the biopsy needle used dunng this incident, could also pacity of austenitic steel. The femtic steel tested was sensitive dramatically increase the hkelihood of the formabon of a kink if to dynamic strain-aging, and consequently, its load-carrying ca-the apphcator is subjected to bending loads-pacity decreased at dynamic strain rates. Two parameters were NUREG/CR-6153: A SIMPLIFIED MODEL OF DECONTAMINA.
found to affect the apparent ductile crack growth resistance TION BY BWR STEAM SUPPRESSION POOLS. POWERS,0.A.
dunng cyche loading, load ratio (R) and incremental plastic dis-Sandia National Laboratones. May 1997. 463pp. 9706120310.
placement that occurs in a cycle. Cyclic (R = 0) loading had 93340:001.
minimal effect on ductile teanng for both matenals. However, An uncertainty analysis of aerosol removal by nuclear reactor fully reversed loading decreased the load-carrying capacity and steam suppressen pools is desenbed. Uncertainties considered toughness for both matenals. The incremental plastic displace-in the analyses include uncertaintes in boundary conditions dic-ment can be as important as the load ratio; however, it is harder tated by accident progression, uncertainties in buoble behaver.
to quantify from design stress reports. Large plestic displace-and uncertainties in aerosol properties. Uncertainty distnbuton ments will minimize the effect of negative load ratios.
for decontamination factors, aerosol particle sizes, and the geo-metre standard deviation of the size distnbutions are developed NUREQ/CR-6233 V03: CRACK STABILITY IN A REPRESENTA-as functions of suppressor pool depth. Results of the uncer-
Main Citations and Abstracts 7
TIVE PIPING SYSTEM UNDER COMBINED INERTIAL AND control room air intakes that would be exceeded no more than SEISMIC / DYNAMIC OtSPLACEMENT-CONTROLLED five percent of the time. These concentratons are calculated for STRESSES. Subtask 1.3 Final Report. SCOTT,P.; OLSON.R.;
averaging penods ranging from one hour to 30 days in duration.
WILKOWSK1,G.; et al. Battel % Memorial Inst tute, Columbus ARCON96 is a revised verson of ARCON95, which was devel-Laboratones, June 1997. 55Bpp. 9707140064. BMI-2177, oped for the NRC Office of Nuclear Regulatory Research.
Ts presents the results from Subtask 1.3 of the inter.
U O'"O natonal Piping integnty Research Group (IPIRG) program. The c nc aWs pen s lov an 2 Ws has also h objective of Subtask 1.3 is to develop dam to assess analysis methoCologies for characterizing the fracture behavior of cir-go awagN PWures hereasM rda-cumferentially cracked pipe in a representatrve piping system two concentratons for these averaging perods in general, the under combined inertial and displacement-controlled stresses. A Increase in concentratons is less than a factor of two. The in-unique expenmental facihty was designed and constructed. The crease is greatest for relatively short averaging penods, for ex.
piping system evaluated is an expansion loop with over 30 ample O to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and drminishes as the duration of the aver-meters of 164nch diameter Schedule 100 pipe. The expenmerp aging pered increases.
tal facihty is eouipped with special hardware to ensure system boundary condatens could be appropnately modeled. The test NUREQ/CR-6361: CRITICALITY BENCHMARK GUIDE FOR matnx h,volved one uncracked and five cracked dynamic ppe-UGHT WATER-REACTOR FUEL IN TRANSPORTATION ANO system expenments. The uncracked experiment was conducted STORAGE PACKAGES. LICHTENWALTER; BOWMAN.S.M.;
to evaluate piping system damping and natural frequency char.
DEHART M.D.; et al. Oak Ridge National Laboratory. March actenstics. The cracked-pipe orpenments evaluated the fracture 1997.358pp.9705120283. ORNUTM-13211. 92829:001, behaver, pipe system response, and stabihty charactenstics of This report is designed as a guide for performing cnticahty five different matenals. All cracked-pipe expenments were cork benchmark calculations for light water reactor (LWR) fuel apph-ducted at PWR conditons. Matenal characterization efforts pro-cations. The guide provides documentaten of 180 criticahty ex-vided tensile and fracture toughness properties cf the ditferent penments with geometries, matenals, and neutron interaction pipe materials at vanous strain rates and temperatures. Results charactensbcs representative of transportaton packages con-from all pipe system experiments and matenal charactenzation taining LWR fuel or uranium oxide pellets or powder. These ex-efforts are presented. Results of fracturo mechanics analyses, penments should benefit the U.S. Nuclear Regulatory Commis-dynamic finite element stress analyses, and stabihty analyses are presented and compared with expenmental results' son (NRC) staff and heensees in validation of computational methods used in LWR fuel storsge and transportation concerns.
HUREGICR 3233 V04: INTERNATIONAL PIPING INTEGRITY The expenments are classified by key parameters such as en.
RESEARCH PROGRAM (IPIRG) PROGRAM. Program Final nchtnsnt, water / fuel volume, hydrogen-to-fissile rato (H/X), and Report. WILKOWSKI.G.; SCHMIDT,R.; SCOTT,P.; et al. Battelle lattice pitch. Groups of expenments with common features such Memonal Institute, Columbus Laboratones. June 1997. 320pp.
as separator plates, shgiding walls, and soluble boron are also 9707140072. BMb2177. 93736:001.
identifiad. In addition, a sample validaten using these experi.
This is the final report of the internetional Piping integnty Re-ments and a statistical analysis of the results are provided. Rec.
search Group (IPIRG) Program. The IPIRG Program was an ommendations for selecting suitable expenments and determi-internatior al group program managed by the U.S. Nuclear Reg-ulatory Commission and funded by a consortum of organiza*
naten of calculabonal bias and uncertain */ are presented as tions from nine nations: Canada, France, Italy, Japan, Sweden, part of this benchmark guide.
Switzerland Taiwan, the United Kmgdom, and the United NUREG/CR-6363: EFFECTS OF THERMAL AGING AND NEU-States. The program objec*ive was to develop data needed to TRON IRRADIATION ON THE MECHANICAL PROPERTIES OF venty engineenng methods for assessing the mtegrity of circum-THREE.uVIRE STAINLESS STEEL WELD OVERLAY CLAD-ferentially crsched nuclear power plant piping. The primary focus was an expenmental task that investigated the behavior DING. HAGGAG,F.M.; NANSTAD,R.K. Oak Ridge Nabonal Lab-of circumferentially flawed piping systems sub octed to high-rate oratO'Y. May 1997. 39pp. 9705280200. ORNL/TM-13047.
l loadings typical of seismic events. To accomphsh these oblec-93126:281 tives a pipe system fabncated as an expansion loop with over Thwmal aging of three-wire senes. arc stainless steel weld 30 meters of 16-inch diameter pipe and five long radius elbows overlay cladding at 288 degrees C for 1605 h resulted in an ap-was constructed. Five dynamic, cyche, flawed piping experi.
preciable decrease (16%) in the Charpy V-notch (CVN) upper-ments were conducted using this facihty. This report (1) pro-shelf energy (USE), but the effect on the 414 transiten temper.
vides background information on leak before-break and flaw sture shift was very srnell (3 degrees C). The combined effect evaluaton procedures for piping, (2) summanzes technical re-of aging and neutron irradiaton at 288 degrees C to a fluence suits of the program, (3) gives a relatwely detailed assessment of 5 x 10(19) neutrons /cm(2) (> 1 MeV) was a 22% reducten of the results from the pipe fracture expenments and comple-in the USE and a 29 degrees C shift in the 41 J transition tem-mentary analyses, and (4) summanzes advances in the state-of-perature. The effect of thermal aging on tensile properbes was the-art of pipe fracture technology resutbng from the IPIRG pro-very small. However, the combmed effect of irradiation and gram.
aging was an increase in the yield strength (8 to 34% at test NUREG/CR 6331 R01: ATMOSPHERIC RELATIVE CONCEN.
temperatures from 288 to -125 degrees C) but no apparent TRATIONS IN BUILDING WAKES.
RAMSDELL,J.V.;
change in ultimate tensile strength or total elongation. Noutron SIMONEN.C.A. Battelle Memonal Institute, Pacific Northwest irradiation reduced the initiation fracture toughness (J(ic)) much Natonal Laboratory. May 1997.1500p. 9706120318. PNNL.
more than did thermal aging alone, Irradiatson slightly decreased 12521. 93339:152.
the teanng modulus, but no reduction was caused by thermal This report documents the ARCON96 computer code devel-aging alone. Other results from tensile, CVN, and fracture oped for the U.S. Nuclear Regulatory Commission Offse Of Nu-toughness specimens showed that the effects of thermal aging clear Reactor Regulation for use in contro( room habr< ability as-at 288 or 343 degrees C for 20,000 h each were very small and sessments. It includes a user s guide to tne code, a descnption similar to those et 288 degrees C for 1605 h. The effects of of the technical basis for the code, and a programmer's guide long-term thermal exposure time (50,000 h and greater) at 288 to the code. The ARCON96 code uses hourly meteorological degrees C will be investigated as the specimens become avail-data and recemly developed methods for estimating dispersion able in 1996 and beyond.
in the vicinity o' buildings to calculate retabve concentrahons at
~ -. - -- -. - -.-
8 Main Citations and Abstracts NUREG/CR4372 V01: RECOMMENDATIONS FOR PROBABI-pretest procedures. The thrust of this discussion is intended to
' LISTIC SEISMIC HAZARD ANALYSIS: GUIDANCE ON UNCER-provide the informahon necessary to understand the experimen-TAINTY AND USE OF EXPERTS Main Report. BUDNITZ,R.J.;
tal setup and to provide rne background necessary to under.
APOSTOLAKIS,G.; BOORE.D.M.; et al. Lawrence Livermore Na-stand the experimental results. The discussion on the expert-
. tonal Laborp'ory. April 1997, 277pp. 9705280207. UCRL ID-mental procwdures cnd results includes the seismic input test j
122160. 93137 001.
procedures, test runs, and measured excitabon and response i
Probabilistic Seismic Hazard Analysis (PSHA) is a methodolo-hme histories. The closure of the tunnel due to various levels of gy that estimates. the hkelihood that varcus levels of earth-seismic activity is p esented. A threshold level of seismic input 1
1 quake-caused ground moton will be exceeded at a given loca-amplitude was required before significant rock mass mobon oc-tion in a given future time pered. Due to large uncertainbes in curred. The expenment, thrngte designed as a two-dimensional l
all the geosciences data and in their modehng, multiple nodel representaton of a rock 'rass, behaved in a somewhat three-j interpretatonc are often possible. This leads to disagreement dimensonal manner, which will have an effect on subsequent I
among experts, which in the past has led to disagreement on analytical model comparinon.
the soleebon of ground motion for design at a given site. The Senior Seismic Hazards Analysis Comrmttee (SSHAC) reviewed MUREG/CR4504 V01: AN UPDATED NllCLEAR CRITICALITY 4
past studies,includeng the Lawrence Livermore National Labora-SLIDE RULE. Technical Basis.
BROADHEAD.B.L; l
tory and the EPRIlandmark PSHA studies of the 1980's and ex.
HOPPER.C.M.; CHILDS.R.L; et al. Oak Ridge National Labora-armned ways to improve on the present state of-the-art. The tory. April 1997. 95pp. 9705090043. ORNL/Twe-13322.
Committee's most impMtant conclusion is that differences in 92826.233.
PSHA results are due to procedural rather than techrwcal differ.
In January 1974, a hmited distributen report, entitled "A SMe ences. Thus, in additon to providing a detailed documentaten Rule for Est mahng Nuclear Cr'tcality Infon1aton," was wrWen i
on state-of the-art elements of a PSHA, this report provides a by C.M. Hopper for the Oak Ridge Y 12 Plant as a tool for senes of procedural recommendations. The role of experts is emergency response to nuclear entcality accidents. Because of analged in detail. Two entities are formally defined. the Tech-several shortcomings of the original shde rule, work began re-nical Integrator (TI) and the Techrwcal Facahtator integrator (FI).
cently to update the 1,hde rule using modern computatonal 4
to account for the various levels of complexity in the technical tools. Volume 1 of this report describes the analyses performed issues and different levels of efforts needed in a given study.
In support of this updated slide-rule tool and includas a sample, NUREG/CR4372 V02: RECOMMENDATIONS FOR PROBABI-the tu raion of s
e ne LISTIC SEISMIC HAZARD ANALYSIS: GUIDANCE ON UNCER*
provides capabihbes for the continued updahng of accident in-TAINTY AND USE OF EXPERTS. Appendices. BUDNITZ,R.J.;
formaton dunng the evolution of emergency response, including
' APOSTOLAKIS,G.; BOORE.D.M.; et al. Lawrence Livermore Na-victim exposure information; potentsal exposures to emergoney tional Laboratory. April 1997. 750pp. 9705280212. UCRLID-reentry personnel; eshmates of future radiabon 6 elds; and fis-122160. 93127:001.
sion-yield estimates.
See NUREG/CR-6372,V01 abstract.
NUREG/CR-4390: RESULTS OF CHARPY V-NOTCH (MPACT NUREG/CR4505 V01: THE POTENTIAL FOR CRITICALITY FOL.
LOWING DISPOSAL OF URANIUM AT LOW LEVEL WASTE TESTING OF STRUCTURAL STEEL SPECIMENS IRRADIATED FACILITIES.Urardim Blended With Soil.
TORAN,LC.;
AT 30 DEGREES C TO 1 X 10(16) NEUTRONS / CM(2) IN A COMMERCIAL REACTOR
- CAVITY, ISKANDER.S.K.;
HOPPER,C.M.; NANEY M.T.; et al. Oak Ridge National Labora-STOLLER.R.E. Oak Ridge Natonal Laboratory. April 1997, tory. June 1997, 137pp. 9707180200. ORNL/TM-13323.
93805:187.
51pp. 9705120288. ORNL-6886. 92828:001.
A capsule containing Charpy V notch (CVN) and mini-tensile The purpose of this study was to evaluato whether or not fis-specimens was irradiated at - 30 degrees C (. 85 degrees F) site uranium in low 4evel waste (LLW) facihties can be concen-in the cavity of a commercial nuclear power plant to a fluence, trated by hydrogeochemical processes to permit nuclear cribcal-of 1 x 10 (16) neutrons /cm(2) (> 1 MeV). The capsule included ity. A team of experts in hydrology, geology, geochemistry, soil six CVN impact specimens of archival High Flux Isotope Reac, chemistry, and cntcahty safety was formed to develop achieva-tor A212 grade B femtc steel and five CVN impact specimens ble scenanos for hydrogeochemical increases in concentration e
of k well-studied A36 structural steel. This irradiabon was part of of special nuclear rnatenal (SNM), and to use these scenarios to and in evaluating the potential for nuclear entcahty. The l
' the ongoing study of neutron-induced damage effects at the low temperature and flux experienced by reactor supports. Tiw team's approach was to perform simultaneous hydrogeochemi-3 cal and nuclear cnticahty studies to (1) identify sorne achievable plant operators shut down the plant before the planned expo, sure was reached. The exposure of these specimens produced scenarios for uranium migraton and concentraton increase at LLW disposal facihties. (2) model groundwater transport and no significant irradiation-induced embnttlement.
subsequent concentration increase via sorption or precipitahon NUREQ/CR4404: %N EXPERIMENTAL SCALE-MODEL STUDY of uranium, and (3) evaluate the potential for nuclear enticality OF SEISMIC RESPONSE OF AN UNDERGROUND OPENING resulting from potential increases in uranium concentration over IN JOINTED ROCK MASS. KANA,D.D.; FOX,0.J.; HSIUNG S.;
disposal limits. The analysis of SNM was restncted to (235)U in et al. Center for Nuclear Waste Regulatory Analyses. February the present scope of work. The outcome of the work indicates 1997. 200pp. 9704250163. CNWRA 95-012. 92625:095.
that criticahty is possible given estabhshed regulatory hmits on This report describes an experimental invesbgation conducted SNM disposal. However, a review based on actual disposal by the Center for Nuchat Waste Regulatory Analyses (CNWRA) records of an existing site operation indicates that the potential to (i) obtain a better understanding of the seismic response of for cnticahty is not a concem under current bunal practices, an underground opening in a highly-fractured and jointed rock mass and (ii) generate a data set that con be used to evaluate NUREG/CR4507: CRITICAL HEAT FLUX (CHF) PHENOMENON the capabihties (analytical methods) to calculate such response.
ON A DOWNWARD FACING CURVED SURFACE.
This report describes the design and implementation of simulat-CHEUNG,F.84 HADDAD.K.H.;
L'U,Y.C.
Pennsylvania State ed seismic experiments and results for a 1/15 scale model of a Univ., University Park, PA. June 1997.171pp. 9706200256.
jointed rock mass with a circular tunnel in the middle. The dis-PSU/ME 97 7321. 93422:007.
cussion on the design of the scale model includes a desenpton This report desenbas a theoretical and expenmental study of of the associated simihtude theory, physical design rationale, the boundary layer boshng and entical heat flux phenomena on a model material development, prehminary analytical evaluation, downward facing curved heating surface, including both hemi-instrumentation design and cahbraton, and model assembly and spherical and torotdat surfaces. A subscale boundary layer boil-
.~.
Main Citations and Abstracts 9
ing (SBLB) test facihty was developed to measure the spahal NUMEG/CR4515: BLT.EC (BREACH, LEACH. AND TRANS-variaton of the critical heat flux and observe the undertying PORT. EQUILIBRIUM CHEMISTRY) DATA INPUT GUIDE.A mechanisms. Transient quenching and steady-state boshng ex-Computer Model For Simulating Release And Coupled Geo-periments were performed in the SBLB facihty under both satu-chemical Transport Of Contamnants From A Subsurface Dis-rated and subcooled conditons to obtain a complete database posal Facility. MACKINNON.R.J. Ecodynamics Research Asso-on the critical heat flux. To complement the expenmental effort, ciates, Inc, SULLIVAN.T.M.; KINSEY,R.R. Brookhaven Natonal an advanced hydrodynamic CHF model was developed from the Laboratory. May 1997, 240pp. 9706180471. BNL-NUREG.
conservation laws along with sound physical arguments. The 52516.93484:001.
model provides a clear physical explanetson for the spat al varia.
The BLT.EC computer code has been developed, irnplement-ton of the CHF observed in the SBLB experiments and for the ed, and tested. BLT-EC is a two-dimensional finite element
}
weak dependence of the CHF data on the physical size of the computer code capable of simulating the time-dependent re-vesful Based upon the CHF rnodel, a scahng law was estab-lease and reactive transpor1 of aqueous phase species in a sub-4'
$shed for estimating the local critical heat flux on the outer sur.
surface soil system. BLT EC contains models to simulate the '
face of a heated hemispherical vessel that is fully submerged in processes (container degradaton, waste-form performance, water, The scaling law, which compares favorably with all the transport, chemical reactions, and radcactive production and available local CHF data obtained for various vessel sizes, can decay) most relevant to estimahng the release and transport of be used to predict the local CHF limits on large comrnercial-size centaminants from a subsurface disposal system. Water flow is vessels.
provided through tabular input or auxiliary files. Container degra-dation considers localized failure due to pitting corrosion and NUREG/CR4511 V01: STEAM GENERATOR TUBE INTEGRITY general failure due to uniform surface deg.adation processes.
PROGRAM. Semiannual Report. August 1995 March 1996.
Waste-form performance considers release to be limited by one DIERCKS,0.R.; BAKHTIARl,S.; CHOPRA,0.K.; et al. Argonne of four mechanisms: rinse with partitioning, diffusion, uniform Natonal Laboratory. April 1997.114pp. 9705120295. ANL-96/
surface degradaton, and solubikty, Chemical reactons account.
17,92828:117, od for include complexaton, sorpton, dissolution-precipitaton, This report summart2es work performed by Argonne National oxidaton-reducton, and ion exchange. Radioactwo producton Laboratory on the Steam Generator Tube Integnty Program and deca / in the waste form is simulated. Transport considers from the inception of that program in August 1995 through the processes of advecten, dispersion, diffusion, chemical reac-March 1996. The program is divided into five tasks, namely (1) tion, radcactive production and decay, and sources (weste form Asbessment of inspection Reliabihty, (2) Research on ISI (in.
releases). To improve the usefulness of BLT EC, a pre-proces-serv 6ce-inspecton) Technology, (3) Research on Degradaten sor, ECIN, which assists in the creation of chemistry input files, Modes and integrity, (4) Development of Methodology and and a post-processor, BLTPLOT, which provides a visual es-Technical Requirements for Current and Emerging Regulatory play of the data have been developed. BLT.EC a:so includes an
- lasues, and (5) Program Management. Under Task 1, progress extonsive database of thermodynamic data that is also accessi-is reported on the preparabon of and evaluaton of Nondestruc-ble to ECIN. This document reviews the models implemented in trve evaluaton (NDE) techniques for inspecting a mock up BLT EC and Serves as a guide to creating input files and apply-steam generator for round-robin testing, the development of ing BLT EC.
better ways to correlate burst pressure and leak rate with eddy current (EC) signals, the inspe:tton of sleeved tubes, workshop NUREG/CR 6530: DELIBERATE IGNITION OF HYDROGEN-AIR-and training activities, and the evaluaton of emerging NDE STEAM MIXTURES tN f'ONDENSING STEAM ENVtRON-MENTS. BLANCHAT,T.K. Sandia National Laboratones.
technology, Under Task 2, results are reported on closed. form
. solutons and finite element electromagnetic modeling of EC STAMPS.D.W. Evansvule Unrv. of, Evansville, IN May 1997.
probe response for various probe designs and flaw charactens' 93pp. 9706240048. SANL941676. 93489:266.
tics. Under Task 3, fachtios are being desi ned and built for the Large scale experiments were performeo at the Surtsey Test 9
producten of cracked tubes under aggressive and near prototy' Facihty for the Nuclear Regulatory Commission to determine the pical conditions and for the testing of flawed and unflawed effectweness of thermal glow igniters to burn hydrogen in a rap-tubes under normal operating, accident, and severe accident idly condensing steam environment due to the presence of conditions. In addition, crack behavior and stabihty are being water sprays. The exnenments were designed to determine if a modeled to provide guidance on test facihty design, to develop detonaton or an accelerated f'ame could occur in a hydrogen-an improved understanding of the expe:tod rupture beha' 3r of air-steam mixture which was hitially nonflammable due to steam tubes witi circumferential cracks, and to predict the behaver of diution but was subsequently rendered flammable by rapid con-flawed and unflawed tubes under severe accident conditons.
densation of steam due to water sprays. The experiments were Task 4 is concerned with the cracking and failure of tutss that conducted under conditons scaled to be nearly prototypic of a
have been repasred by sleeving, and with a review of hterature those expected in Advanced Light Water Reactors (such as the I.
on this subWt.
Combuston Engineenng (CE) System 80+). with prototypic spray drop dameter, spray mass thu, steam condensaton NUREG/CR-6514: ANALYSIS OF POTENTIAL SELF GUARAN-rates, hydrogen injection flow rates, and using the actual pro.
TEE TESTS FOR DEMONSTRATING FINANCIAL ASSURANCE posed plant igniters. The lack of any significant pressure in-BY NON-PROFIT COLLEGES, UNIVERSITIES, AND HOSPl' crease du ing the inajonty of the burn and condensaton events, TALS AND BY BUSINESS FIRMS THAr DO NOT ISSUE signified that locahzed, benign hydrogen deflagration (s) oc-BONOS. BAILEY,P ; DEAN C.; COLLIER,J.; et al. ICF, Inc. June curred with no significant pressure load on the Surtsey contain-1997. 70pp. 9706200262. 93422:175.
ment vessel This report desenbes these experiments, gives the This report describes powntial financial tests which could be experimental results, and provides interpretation of the results.
used by NRC as a basis for allowing certain fituncially strong NUREG/CR 6535: DEVELOPMENT OF CONFORMAL RESPIRA-nonprofit licensees, and also non-bond issumg licensees, to use TOR MONITORING TECHNOLOGY.
SHONKA,J.J.;
self guarantee as a mecharusm for meeting NRC financial as-WEISMANN.J.J.; LOGAN.R.J.; et al. Affiliation Not Assigned.
surance requirements. The analysis focusas on three categories April 1117. 28pp. 9705210294. 93061:317, of licensees; colleges or universities, hospitals, and commercial This report summarizes the results of a Small Business inno-firms that do not issue bonds. The report assesses the financial vative Research Phase 11 project to develop a modular, su face assurance nsk of various financial tests, and also estimates the conforming respirator morntor to improve upon the manual number of licensees which could quahfy for self-guarantee survey techniques presently used by the nuclear bdustry. Re-3 under different financial test alternatives.
search was performed witn plastic scintillator and gas propor-l
10 Main Citations and Abstracts tional rnodules in an effort to find the moht conducive geometry tor will sirrLitaneously survey both surfaces of the respirator.
for a surface conformal, position sensitive morutor, The respira-The proportional counter prototype was also designed to incor.
tor monitor prototype developed is a computer controlled, posi-porate Shonka Research Associates' previously developed ten-sensitive detection system employing 56 modular propor.
charge-division electronics. This research provided valuable ex.
i tional counters mounted in molds conforming to the inner and perience into pixellated posrtion sensitive detec on systems.
The technology developed can be adapted to other monitoring E outer surfaces of a commonly used respirator (Sc 801450 40). The molds are housed in separate enclosures and applicet)ons where there is a need for deployment of inany tra-hinged to create a " waffle-iron" effect so that the closed moni.
ditional radiation detectors.
1 I
l
4 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-r:ferenced to the NUREG number for the report and to the 10 digit NRC Document Control System accession number.
I i
SECONDARY REPO67 NUMSER NEPORT NUMSER SECONDARY REPORT NUMSER REPORT NUMSER st*#,t' l$l8',$ 2 =
ORin:Wu "0:18'8:22 voi ANL-97/9 NUREG/CR-4667 V22 hk(U j8Rj 1
. BMI-2177..
NUREG/CR4233 V02 R$
VIP 1 ORNLNURgGCSDPR5 NUREG/g4200 R5 VIP 2 ORNORE8CSOhA5 7
R 3 V U EG/CR 200 P1
!" "RX"95 J!
"$!8R*ds 82t:0!8828!1 M8:18?8 2!88 !MT4 e5 NEA/CSNt/R(96)3 NUREG/CP 0168 PNNt 12521 NUREG/CR4331 ROI ORNL4886 NUREG/CR4309 k h 732I ORNL/NOAC-232 NUREGICR-4674 V23 1
NU E /
67 SAND 97-0607 NUREG/CR-4674 V24 ORNL/TM-11568 NUREG/CR 5501 V07 N1 sANtg41676 NUREG/CR4530 ORNL/TM-11936 NUREG/CR 5661 UCRL 10122160 NUREG/CR 6372 V01 ORNL/TM-13047 NUREG/CR4363 UCRL lO 122160 NUREG/CR4372 V02 11
Personal Author index This index lists the personal authors of NRC staff, contractor, and international agreement reports b alphabetical order. Each name is followed by the NUREG number and the title of the reportW) prepared by the author. If further information is needed, refer to the main cita-tion by the NUREG number.
- (LEN,K.
BURNS,R.E.
MEG 1516: MANAGEMENT OF RADIOACTIVE MATERIAL SAFETY NUREG/CR4535: DEVELOPMENT OF CCHFORMAL RESPIRATOR PROGRAMS AT MEDICAL FACluTIES. Final Report MONITORING TECHNOLOGY, APOSTOLAKIS,0.
CAMP 9ELI,Y.
NUREG/CR4372 V01: RECOMMENDATIONS FOR PROBABluSTC SEISMC HAZARD ANALYSIS: GUIDANCE ON UNCERTAINTY AND NUREG 1516: MANAGEMENT OF RADIOAC11VE MATERIAL SAFETY USE OF EXPERTS Man R PROGRAMS AT MEDCAL FACIUTIES Final Report NUREG/CR4372 V02: RE -
NOAH 0NS FOR PROBABlWSTIC SEISMC HAZARD ANALYSIS, GUIDANCE ON UNCERTAINTY AND CAMPER,LW.
USE OF EXPERTSAppendices.
NUREG-1516: MANAGEMENT OF RADIOACTIVE MATERIAL SAFETY PROGRAMS AT MEDCAL FACluTIES. Final Report ARREDONDO,S.A.
NUREG-1556 V01: CONSOUDATED GUIDANCE ABOUT MATERIALS CHE M,M LICENSES PrograrmSpecmc Guidance About Portable Gauge NUREG/CR4507; CRITK.AL HEAT FLUX (CHF) PHENOMENON ON A Uconnes. Final Report DOWNWARD FACING CURVED SURFACE.
SAILEY,P.
CHILDSAL NUREG/CR4514: ANALYSIS OF POTENTIAL SELF GUARANTEE NUREG/CR4504 V01: AN UPDATED NUCLEAR CRITCAUTY SUDE TESTS FOR DEMONSTRATING FA41AL ASSURANCE BY NON.
RULE.Technmal Bass.
PROFIT CO'.LEGES, UNIVERSITIES, AND HOSPITALS AND BY BUSI-NESS FIRMS THAT DO NOT ISSUE BONDS.
CHOPRA.O.K.
NUREG/CFM667 V22: ENVIRONMENTALLY ASSISTED CRACKING IN SAKHT1 ARIA UGHT WATER REACTORS. Sermannual Report, January 1996. June NUREG/CR4511 V01: STFAM GENERATOR TUBE INTEGRITY 1996.
PROGRAM.Sermannual Report, August 1995. March 1996.
NUREG/CR4511 V01: STEAM GENERATOR TUBE INTEGRITY PROGRAM.Sermannual Report, August 1995. March 1996.
NUREG/CR 4674 V23. PRECURSORS TO POTENTIAL SEVERE CORE CHOWDHUptY,A.H.
DAMAGE ACCIDENTS: 190E A Status Report NUREG/CR4m AN EXPERIMENTAL SCALE MODEL STUDY OF gg g SEISMIC RESPONSE OF AN UNDERGROUND OPENING IN JOINTED NUREG-1516: nt*,NAGEMENT OF RADIOACTIVE MATERIAL SAFETY ROCK MASS, PF0 GRAMS AT MEDICAL FACluTIES.Flnal Report CHUNG,H.M.
BLANCHAT T.K.
NUREG/CR.4667 V22 ENVIRONNIENTALLY ASSISTED CRACKING IN NUREG/CR4530 DEUBERATE 4GNITION OF HYDROGEN AIR-STEAM UGHT WATER REACTORS. Sermannual Report January 1996. June MIXTURES IN CONDENSING STEAM ENVIRONMENTS.
1996.
POORE,D.M.
CLETCHER,J.W.
NUREG/CR4372 V01: RECOMMENDATIONS FOR PROBABILISTC NUREG/CR-4674 V23: PRECURSORS TO POTENTIAL SEVERE CORE SEISMC HAZARD ANALYSIS. GUIDANCE ON UNCERTAINTY AND DAMAGE ACCIDENTS: 1995. A Status Report USE OF EXPERTS Man Report NUREG/CR4372 V02 RECOMMENDATIONS FOR PROBABluSTIC CLUFF,LS.
SEISMC HAZARD ANALYSIS: GUIDANCE ON UNCERTAINTY AND NUREG/CR4372 V01: RECOMMENDATIONS FOR PROBABluSTO USE OF EXPERTS.Apowdces.
SE!SMIC HAZARD ANALYSIS: GUIDANCE ON UNCERTAINTY AND BOURCIERAC.
USE OF EXPERTS.Mann Report NUREG/CR.616h LATE PHASE WELT PROGFESSION EXPERIMENT NUREG/CR4372 V02: RECOMMENDATIONS FOR PROBABluSTIC MP 2.Results And Analyss.
SEISMC HAZARD ANALMIS: GUIDANCE ON UNCERTAINTY AND USE OF EXPERTSAppendices.
90Waaans a na NUREG/CR4361: CRITICAUTY BENCHMARK GUIDE FOR UGHT.
U""'#
WATER-REACTOR FUEL IN TRANSPORlATION AND STORAGE NUREG/CR45R ANAWSIS OF POMNTIAL SENARANHE PACKAGES' TESTS FOR DEMONSTRATING FINANCIAL ASSURANCE BY NON-PROFIT COLLEGES, UNIVERSITIES, AND HOSPITALS AND BY BUSI-BROADHEAD,s.L NESS FIRMS THAT DO NOT ISSUE BONDS.
NUREG/CR-6504 V01: AN UPDATED NUCLEAR CRITICAUTY SUDE RULE.Techncal Base.
COLLINS.DJ.
' NUREG/CR4505 V01: THE POTENTIAL FOR CRITICAUTY FOLLOW.
NUREG 1556 V01: CONSOUDATED GUIDANCE ABOUT M%TERRLS ING DISPOSAL OF URANIUM AT LOW LEVEL WASTE UCENSES.PrograrwSpecmc Guidance About Portable Gauge FACILITIES.Uratuurn Blended With Sod.
Ucenses. Final Report
- SUDNITIAa.
COLTEN BRADLEY NUREG/CR4372 V01: RECOMMENDATIONS FOR PROBABluSTC NUREG/CR4505 VO1: THE POTENTIAL FOR CRITCALITY FOLLOW-SEISMC HAZARD ANALWS: GUIDANCE ON UNCERTAINTY AND ING DISPOSAL OF URANIUM AT LOW-LEVEL WASTE USE OF EXPERTS Man R4 sort.
FACIUTIES.Uratuurn 86anded With Sod.
NUREG/CR4372 V02: RECOMMENDATIONS FOR PROBABluSTC SEISMC HAZARD ANALYSIS: GUIDANCE ON UNCERTAINTY AND CONNELLY,8.R.
USE OF EXPERTSApporoces.
NUREG 1542 V02: ACCOUNTABluTY REPORT FISCAL YEAR 1996.
13
14 Personal Author Index COPINGER.D.A.
GARVER.M.
NUREG/CR-4674 V23: PRECURSORS TO POTENTIAL SEVERE CORE NUREG-1350 V00. NUCLEAR REGULATORY COMMISSION INFORMA.
DAMAGE ACCIDENTS.1995. A Status Report TION DIGEST.1997 E&tiort COPPERSMITH.K.
GASSER R.D.
NUREG/CR-6372 V01: RECOMMENDATONS FOR PROBABILISTC NUREG/CR-6167: LATE PHASE MELT PROGRESSON EXPERIMENT SEISMC HAZARD ANALYSIS: GUIDANCE ON UNCERTAINTY AND yp.2.Results And Aradywa USE OF EXPERTS Man Report NUREG'CR4372 V02: RECOMMENDATONS FOR PROBABluSTC GAUMTTAO.
SEISMC HA2ARD ANALYSIS GUIDANCE ON UNCERTAINTY AND NUREG/CR-6167: LATE. PHASE MELT PROGRESSION EXPERIMENT USE OF EXPERTS Appeneces.
up-2.Results And Analyse.
CORNELL,CA GAVENDA.D.J.
NUREG/CR4372 VOI: RECOMMENDATONS FOR PROBABluSTIC SEISMC HA1ARD ANALYSIS: GUCANCE ON UNCERTAINTY AND NUREG/CR-4667 V22: ENVIRONMENTALLY ASSISTED CRACKING IN USE OF EXPERTS Man Rwrt LIGHT WATER REACTORS. Serniannual Report. January 1996 - June 1996-M) REG /CR-6372 V02: RECOMMENDATIONS FOR PROBABILISTC SEISMC HAZARD ANALYS S: GUIDANCE ON UNCERTAINTY AND GILLES.PH.
USE OF EXPERTS. Appendices' NUREG/CP.0155: PROCEEDINGS OF THE SEMINAR ON LEAK CORWIN,W.R.
BEFORE BREAK IN REACTOR PIP 1NG AND VESSELS-NUREG/CR 5591 Vu? N1: HEAVY-SECTON STEEL IRRADIATON N EG/C'R 514: ANALYSIS OF POTENTIAL SELF-GUARANTEE TESTS FOR DEMONSTRATING FINANCIAL ASSURANCE BY NON.
DANZlGER.L.M.
PROFIT COLLEGES, UNIVERSITIES. AND H0SNTALS AND BY BUST-NUREG 1603 DRFT:
INDIVIDUAL PLANT EXAMINATON NESS FIRMS THAT 00 NOT ISSUE BONOS.
DATACASE. User's Guide.
C RUBER,E.E.
DASAPPA,V.
NUREGICR-4667 V22: ENVIRONMENTALLY ASSISTED CRACKING IN NUREG/CR-6514: ANALYSIS OF POTENTIAL SELF-GUARANTEE UGH 1 WATER REACTORS. Semiannual Report. January 1996 June TESTS FOR DEMONSTRATING FINANCIAL ASSURANCE BY NON-
- 1996, PROrlT COLLEGES. UNIVERSITIES, AND HOSPITALS AND BY BUSI-l NESS FIRMS THAT DO NOT ISSUE BONOS.
HADDAD,K.H.
NUREG/CR 6507. CRITCAL HEAT FLUX (CHF) PHENOMENON ON A DEAN.C.
DOWNWARD FACING CURVED SURFACE.
NUREG/CR4514 ANALYSIS OF POTENTIAL SELF GUARANTEE TESTS FOR DEMONSTRATING RNANCIAL ASSURANCE BY NON.
HAGGAG,F.M.
PROFIT COLLEGES, UNIVERSITIES. AND HOSPITALS AND BY BUSI-NUREG/CR4363; EFFECTS OF THERMAL AGING AND NEUTRON IR-NESS FIRMS THAT DO NOT ISSUE BONDS-RADIATON ON THE MECHANICAL PROPERTIES OF THREE. WIRE DEBORO,DR.
NUREG/CR-6535: DEVELOPMENT OF CONFORMAL RESPIRATOR HENDERSON,P, MONITORING TECHNOLOGL NUREG-1516: MANAGEMENT OF RADIOACTIVE MATERIAL SAFETY DEHAAT.MfL PROGRAMS AT MEDICAL FACIUTIES. Foal Report NUREG/CF6-6361: CHITICAU'/ BENCHMARK GUIDE FOR UGHT.
HOPPER C.M.
WAT cACTC9 FUEL IN TRANSPORTATON AND STORAGE
~
NUREG/CR 6361: CRITICAUTY BENCHMARK GUIDE FOR UGHT.
WATER-REACTOH FUEL IN TRANSPORTATON AND STORAGE DIERCKS.D.R.
PACKAGES.
NUREG/CR4511 V01: STEAM GENERATOR TUBE INTEGRITY NUREG/CR-6504 V01: AN UPDATED NUCLEAR CRITICAUTY SUDE PROGRAM.Sennannua; Report. August iip 95. March 1996.
UL T nica B s DOLAN.B.W.
ING DISPOSAL OF URANtVM AT LOW LEVEL WASTE NUREG/CR-4674 V23: PRECURSORS TO POTENTIAL SEVERE CORE FACluTIES.Urarnum B6 ended With Soil.
DAMAGE ACCOENTS: 1995. A Status R NUREG/CR-4674 V24: PRECURSORS TO TENTIAL SEVERE CORE HSIUNG,S.
CAMAGE ACCIDENTS. 198243 A Status Report NUREG/CR4404. AN EXPERIMENTAL SCALE MODEL STUDY OF SEISMC RESPONSE OF AN UNDERGROUND OPENING IN JOINTED GYER.HA ROCK MASS.
NUREG/CR 5661: RECOMMENDATIONS FOR PREPARING THE CRITI-CAUTY SAFETY EVALUATON OF TRANSPORTATION PACKAGES.
HUGHES,T.H.
NUREG/CR-4667 V22; ENVIRONMENTALLY ASSISTED CRACKING IN UR'EG/CP-0155. PROCEEDINGS OF THE SEMINAR ON LEAK 996' BEFORE BREAK IN REACTOR PIPING AND VESSELS.
HUMPHRIES,L.L.
UAE /R 674 V24: PRECURSORS TO POTENTIAL SEVERE CORE NUREG/CR-6167; LATE-PHASE MELT PROGRESSON EXPERIMENT DAMAGE ACCOENTS: 1982-83.A Status Report W2.Rosuns And Anahsis.
FOX,0.J.
ISKANDER.S.K.
NUREG/CR-6404: AN EXPERIMENTAL SCALE MODEL STUDY OF NUREG/CR-6399: RESULTS OF CHARPY V NOTCH IMPACT TESTING SEISMIC RESPONSE OF AN UNDERGROUND OPENING IN JOINTED OF STRUCTURAL STEEL SPECIMENS IRRADIATED AT 30 DE.
ROCK MASS.
GREES C TO 1 X 10(16) NEUTRUS/ CV(2) IN A COMMERCIAL RE-ACTOR CAVITY.
FRANCINI,R NUREG/CR-6233 V02: STABILITY OF CRACKED PIPE UNDER SEIS.
JENSEN,J.J.
MIC/ DYNAMIC DISPLACEMENT CONTROLLED STRESSES. Subtask NUREG/CR-4674 V24. PRECURSORS TO POTENTIAL SEVERE CORE 12 Foal Report DAMAGE ACCIDENTS: 1982 83.A Status Report FULLFR,M.
JONES.J.
NUREG 1516: MANAGEMENT OF RADIOACTIVE MATERIAL SAFETY NUREG-1516. MANAGEMENT OF RADIOACTIVE MATERIAL SAFETY j
PROGRAMS AT MEDICAL F ACluTIES Fmal Report PROGRAMS AT MEDICAL FACIUTIES Final Report j
l
Personal Author index 15 jones,$.C.
MARsCHALL,C, NUREG/CR4037: MEASUREMENT OF RESIDUAL RADIOACTIVE SUR-
. NUREG/CR4233 V02: STABluT) OF CRACKED PIPE UNDER SEIS-FACE CONTAMINATION BY 2-0 LASER HEATED TLD.
MC/DYNAMC DISPLACEMENTCONTROLLED STRESSES. Subtask KANA.D.D.
1.2 Foal Report.
l_
NUREG/CR4404; AN EXPERIMENTAL SCALE MODEL STUDY OF NUREG/CR4233 V03. CRACK STABlUTY IN A REPRESENTATIVE SEISMC RESPONSE OF AN UNDERGROUND OPENING ;N JOINTED PIPtNG SYSTEM UNDER COMBINED INERTIAL AND SEIEWC/DY.
ROCK MASS.
NAMC DISPLACEMENT CONTROLLED STRESSES. Subtask 1.3 Fmal Report NUREG/CR4233 V04 INTERNATONAL PIPING INTEGRfTY RE-I CIRCUMFERENTIAL CRACKING OF STEAM GENERA-^" "
NUR 1
l TOR TUBES.
MATSON,EA NUREG 1556 V01: CONSOUDATED GUIDANCE ABOUT MATERIALS G CR 667 V22: ENVIRONMENTALLY ASSISTED CRACKING IN f
UGHT WATER REACTORS. Sermarmuel Report. January 1996 June 11ML MA2UZAN,0.T.
gg,g, NUREG-1610 CONTROLUNG THE ATOM.The Begmrvngs Of Nuclear NUREG/CR4511 V01: STEAM GENERATOR TUBE INTEGRITY Reguaton, M1962.
PROGRAM.Serrmarmual Report August 194. March 1996.
MCCARTHYJ.F.
KWetEY,RA NUREG/CR4505 V01: THE POTENTIAL FOR CRITICAUTY FOLLOW.
NUREG/CR4515: BLT.EC (BREACH, LEACH. AND TRANSPORT-EOUl-ING DISPOSAL OF URANIUM AT LOW LEVEL WASTE UBRIUM CHEMISTRY) DATA INPUT GUIDE.A Computer Modof Fo, FACluTIES Urarnum Blended With Soil Sernulatmg Release And Coupled Geochemmal Trancport Of Cwtarm.
nants From A Subsurface Deposal Facility.
MCKENNA,E.M NUREG 1606 DRFT FC-PROPOSED REGULATORY GUIDANCE RE-KRAMER,0.
LATED TO IMPLEMENTATION OF 10 CFR 50.59 (CHANGES, TESTS, NUREG/CR4233 V02 STABluTY OF CRACKED PIPE UNDER SEIS.
OR EXPERIMENTS). Draft Report For Comment MC/ DYNAMIC DISPLACEMENT-CONTROLLED STRESSES. Subtask 1.2 Fool Report.
M ANCKJE 5'
NUREG/CR4233 V04: INTERNATIONAL PtPING INTEGRITY RE.
NOREG/CR4674 V23: PRECURSORS TO POTENTIAL SEVERE CORE SEARCH PROGRAM (IPIRG) PROGRAM. Program Foal Report DAMAGE ACCIDENTS: 1995. A Status Report.
NUREG/CR-4674 V24: PRECURSORS TO POTENTIAL SEVERE CORE KUPPERMAND.S.
DAMAGE ACCIDENTS: 196243 A Status Report NUREG/CR4511 V01: STEAM GENERATOR TUBE INTEGRITY PfACRAM.Sermannual Rept rt Augtest 1995. March 1996.
MIT S
LEHNERJA DAMAGE ACCOENTS: 196243.A Status Report.
NUREG-1603 DRFT:
INDIVIDUAL PLANT EXAMINATON DATABASE. User a Gude, MONTGOMERY,J.
LEW18,$R NUREG 1516: MANAGEMENT OF RADIOACTIVE MATERIAL SAFETY NUREG 155e V01: CONSOUDATED GUIDANCE ABOUT MATEFJALS PROGRAMS AT MEDCAL FACluTIES.Fmal Report UCENSES. Program-Specific Guidance About Portable Gauge MORRIS,P.A.
Ucenses.F1ral Report NUREG/CR 6372 V01: RECOMMENDATIONS FOR PROBABluSTIC UCHTENWALTER SEISMIC HAZARD ANALYSIS: GUIDANCE ON UNCERTAINTY AND NunEG/CR4361: CRITICAUTY BENCdMARK GUIDE FOR UGHT.
USE OF EXPERTS.Mem Report WATER-REACTOR FUEL IN T5tANSPO6TATION AND STORAGE NUREG/CR4372 V02-RECOMMENDATONS FOR PROBABluSTIC PACKAGES.
SEISMC HAZARD ANALYSlQ GUIDANCE ON UNCERTAINTY AND USE OF EXPERTS.Appendmet.
UN,C.C.
MUHLHEIM,M.D.
NUREG 1603 DRFT:
INOtVOUAL PLANT EXAM 1NATON DATABASE. User's Guide.
NUREG/CR-4674 V23: "RECURSORS TO POTENTIAL SEVERE CORE DAMAGE ACCCENTS: 1995. A Status Report UU Y.C.
NUREG/CR4407; CRITICAL HEAT FLUX (CHF) PHENOMENON ON A NANEY,M.T DOWNWARD FACING CURVED SURFACE.
NUREG/CR4505 V01: THE POTENTIAL FOR CRITCAUTY FOLLOW.
ING DISPOSAL OF URANIUM AT LOW LEVEL WASTE LOGANAJ.
FACILITIES.Oratuum Blended With Soil.
NUREG/CR4535: DEVELOFMENT OF CONFORMAL RESPIR AT.)R NG TECHRM REG / 4363: EFFECTS OF THERMAL AGING AND NEUTRJN IR-LUESSER6,PA RADIATON ON THE MECHANICAL PROPERTIES OF THREE-WIRE NUREG/CR 4667 V22: ENVIRONMENTALLY AESISTED CRACKING IN STAINLESS STEEL WELD OVERLAY CLADDtNG.
WATER REACTORS. Sermannual Report January 1996 June NUREG/CR4233 V03: CRACK STABluTY IN A REPRESENTATIVE LUKEZKM,S.J.
PIPtNG SYSTEM UNDER COMBINED INERTIAL AND SEISMIC /DY.
NUPEG/CR-6074 V03: SEALED SOURCE AND DEVICE DESIGN NAMC DISPLACEMENT CON 1ROU.ED STRESSES Subtash 1.3 Foal SAFETY TEST!NG.Technmal Report On the Fedmos Of Task 4.Inves.
Report tigaion Of A Failed Brachytherapy Needle Applicator.
NUREG/CR4233 V04: INTERNATONAL PIPING INTEGRITY RE-MACK NNON,R.J.
SEARCH PROGRAM (IPIR3) PROGRAM Program Final Report NUREG/CR4515; BLT EC (BREACH, LEACH. AND TRAN' PORT EQUI.
PARK,JR UBRIUM CHEMISTRY) DATA INPUT GUIDE.A Computer Model For NUREG/CR 4667 V22; ENVIRONMENTALLY ASS:STED CRACKING IN Semulatmg Reteese And Coupled Geochemmal Transport Of Contanw-UGHT WATER REACTORS. Senuannual Report, January 1996 June nanta From A Subaurtace Disposat Fac61 sty.
1996.
MAJUMDAR.S.
PARK,J.V.
NURFG/CR4511 V01: STEAM GENERATOR TUBE INTEGRITY NUREG/CR4511 V01: STEAM GENERATOR TUBE INTEGRITY PROGRAM,Se mannua Report, August 1995. March 1996.
PROGRAM.Sermannual Report, August 1995 - March 1996.
s
. 16 Personal Author IMax e
PARKS.C.V.
00PPE1,WA NUREG/CR 5661: RECOMMENDATIONS FOR PRtPAR90 THE CRITI-NUREG/CR-4667 V22: ENVIRONMENTALLY ASSISTED CRACKING IN
)
CAUTY SAFETY EVAL.UATION OF TRANSPORTA10N PACKAGES.
UGHT WATER REACTORS. 3emannual Report, January 199d. Ju%
NUREG/CR4505 V01: THE POTENTIAL FOR CRITICALHV FOLLOW.
1996.
ING DISPOSAL OF URANfUM AT LOW-LEVEL WASYE FACluTIES. Uranium B6 ended with Scd.
STAMPS,0.W.
NUREG/CR4530: DELIBERATE IGNITION OF HYDROGEN.AlR-STEAM N E'G/CR4233 VOC INTERNATIONAL PIPINC INTEGRITY RE.
SEARCH PROGRAM (IPIRG) PROGRAM. Program Final Report STOLi.ER,RL NU6EG/CR 6399: RESULTS OF CHARPY V NOTCH IMPACT TESTING PELCHATM-OF STRUCTURAL STEEL SPECIMENS 1RRADIATED AT 30 DE.
NUREG-1556 V01: CONSOUDATED GUIDANCE ABOUT MATERIALS GREES C TO 1 X 10(16) NEUTRONS / CM(2) IN A COMMERCIAL RE-UCENSES Program Specthe Gudance About Portable Ga;ge ACTOR CAVITY.
Uconses.Finct Report STRAIN,R.V.
NUREG/CR 4867 V22: ENVIRONMENTALLY ASSISTED CRACKING IN NU G/ -46C7 V22 ENVISONMENTALLY ASSISTED CRACKING IN WATER REANS. Sennannual RWanuary M. M UGHT WATER REACTORS. Semiannual Report. January 1996 June 1996.
STRUCKMEYER,R.
POWERS,D.A.
NUREG-0637 V17 N01: NRC TLD DIRECT RADIATION MONITORING NUCG/CR4153. A SIMPLIFIED MODEL OF DECONTAMINATION BY BWR STEAM SUPPRESSON POOLS.
NETWORV. Progress Report. January March 1997.
RAMSOELL.J.V.
SU,T.M.
NUREG/CR4331 R01: ATMOSPHERIC RELATIVE CONCENTRATIONS NUREG-1603 DAFT:
INDIVIDUAL PLANT EXAMINATION IN BUILDING WAKES.
DATABASE. User's Guide.
REIL,K.0, SUKALAC,TA NUREG/CR4167: LATE-PHASE MELT PROGRESSION EXPERIMENT NUREG/CR4535: DEVELOPMENT OF CONFORMAL RESPIRATOR MP 2.Resulta And Analysis.
MONITORING TECHNOLOGY.
I FsUTHER,W L SULLIVAN,7.M.
NUREG/CR-4667 V22: ENVIRONMENTALLY ASSISTED CRACKING IN NUREG/CR4515: BLT-EC (BREACH, LEACH. AND TRANSFORT-EQUI-LIGHT WATER REACTORS. Sermannual Report, January 1996. June LIBRIUM CHEMISTRY) DATA INPUT GUIDE.A Computer Model For 1996.
Simulaang Release And Coupled G achermcal Transport Of Contami-nants From A Subsurface Disposal Facety.
NUREG-1556 V01: CONSOUDATED GUIDANCE ABOUT MATERIALS TANO J.S.
UCENSES. Program-Specthe Guidance About Portable Gauge NUREG/CR4504 V01: AN UPDATED NUCLEAR CRITICALITY SLIDE Ucenees. Final Report RULE.Techncal Basis.
SCHLUETER,J.
TINGLE,W, NUREG 1516: MANAGEMENT OF RADIOACTIVE MATERIAL SAFETY NUREG-1556 V01: CONSOUDATED GUDANCE ABOUT MATERIALS PROGRAMS AT MEDICAL FACILITIES. Final Repert UCENSES Program-Specific Guidance About Portable Gauge SCHANDT,R.
NUREGICR4233 V03: CRACK STABluTY IN A REPRESENTATNE TORAN.LE.
PIPtNG SYSTEM UNDER COMBINED INERTIAL AND bEISMIC/DY-NUREG/CR4505 V01: THE POTENTIAL FOR CRITICAUTY FOLLOW-NAMIC DISPLACEMENT 40NTROLLED STRESSES. Subtask 1.3 Final ING DISPOSAL OF URANIUM AT LOW-LEVEL WASTE NUR CR4233 VD4: INTERNATIONAL PIPING INTEGRITY RE-SEARCH PROGRAM (IPIRG) PROGRAM. Program Final Repot VACCA,P.C.
1
' NURFG-1556 V01: CONSOUDATED GUIDANCE ABOUT MATERIALS SCHANOTE LICENSES Program &ecific Guidance About Portable Gauge NURE3/CR4167: LATE-PHASE MELT PROGRESSION EXPERIMENT UcensesFinal Report MP-2.Results And Anatysis.
VIETH,P.
SCHRONER.HL NUREG/CR4233 V02: STABluTY OF CRACKED HPE UNDER SEIS.
NUREG/CR-4674 V24: PRECURSORS TO FOTENTIAL SEVERE CORE MIC/ DYNAMIC DISPLACEMENT CONTROLLED STRESSES. Subtask DAMAGE ACCIDENTS: 198243.A Status Report 1.2 Final Report
. SCOTT P.
NUREG/CR4233 V03: CRACK STAB 4UTY IN A REPRESENTAT.VE WALKER,5.
PIPING SYSTEM UNDER COMBINED INERTwL AND SEISMIC /DY.
NUREG 1610: CONTROLUNG THE ATOM.The Beginnings Of Nuclear NAMIC DISPLACEMENT. CONTROLLED STRESSES Subtask 1.3 Final Regulaton, 1946 1962.
WE13MA*fNJ.J.
NUR CR4233 V04. INTERNATIONAL PIPING INTEGRITY RE-NUREG/CR4535: DEVELOPMENT OF CONFORMAL RESPIRATOR SEARCH PROGRAM (IPIRG) PROGRAM. Program Final Report MOritTORING TECHNOLOGY.
SHACK.WJ, NUREG/CR-4667 V22: ENVIRONMENTALLY ASSISTED CRACKING IN WHITEHEAD D.W.
UGHT WATER REACTORS. Semiannual RepartJanuary 1996
- June NUREG/CR-4674 V24: PRECURSORS TO POTENTIAL SEVERE CORE DAMAGE ACCIDENTS: 1982 83.A Status Report 1996.
NUREG/CR4511 V01: STEAM GENERATOR TUBE INTEGRITY WH PFiOGRAM.Sermannual Report. August 1995 March 1996.
N
- 556 V01: CONSOLIDATED GUIDANCE # BOUT MATERIALS SHrweKA,J.J.
UCENSES Program-Specific Guidance About Portable Gauge
= NUREG/CR-6535: DEVELOPMENT OF CONFORMAL RESPtRATOR Ucenses Final Report MONITORING TECHNOLOGL WILKOWSK1,0.
SIMONEN,C.A.
NUREG/CR-6233 V02: STABILITY OF CRACKED PIPE UNDER SEIS-NUREG/CR4331 RO1: ATMOSPHFRIC RELATIVE CONCENTRATIONS MIC/ DYNAMIC DISPLACEMENT. CONTROLLED STRESSES. Subtask IN BUILDING WAKES.
1.2 Final Report
s Personal Author index 17.
NUREG/CR4r*3 Y01 CRACK STAbiUTY IN A REPRESENTATNE.
NuhdG/CR4233 M INTERNATIONAL PtPING INTEORITY RE.
MPING SYSTEM UNDER COM8INF.D INERTIAL AND SELSMC/DY.
SEARCH PROGP AM (IPIRG) PROGRAM. Program Feel Report i
NAMIC Dl8PLACEM2NTWROLLED STHESSES.Subiack 1.3 Feel l-M -
NUREG-1616: LANAGEMENT OF RADIOACTIVE MATERIAL SAFETY PROGRAMS AT MEDICAL FACILITIES Foal Report i
i l
I 1
B m
R Y
M
_m_
Subject index This index was developed from keywords and word strings in titles and abstracts. During this development period, there will be some redundancy, which will be removed later when a rea-sonable thesaurus has been developed through experience. Suggestions for improvements tre welcome.
10 CFR $0 Charpy V-Notch NUREG-1606 DRFT FC: PROPOSED REGULATOF.Y GUIDANCE RE-NUREG/CR4399 RESULTS OF CHARPY V NOTCH IMPACT TESTING LATED TO IMPLEMENTATION OF 10 CFR 50.59 (CHANGES TESTS, OF STRUCTURAL STEEL SPECIMENS IRRADIATED AT 30 DE-4 OR EXPERIMENTS) Dram Report For Comrnent.
GREES C TO 1 X 10(16) NEUTRONS / CM(2)IN A COMMERCIAL RE-ACTOR CAVtTY.
ACMS Report
- NUREG-1125 V18: A COMPILATON OF REPORTS OF THE ADVISORY C4rcumferential Cracking COMMITTEE ON REACTOR SAFEGUARDS.1996 Annual.
NUREG-1604: CIRCUMFERENTIAL CRACKING OF STEAM GENERA.
TOR TUBES.
NUREG-0090 V19: REPORT TO CONGRESS ON ABNORMAL Consolidated Guidance OCCURRENCES. Fiscal Year 1996.
NUREG 1556 V01: CONSOUDATED GUIDANCE ABOUT HATERIALS l
Accident Sequence Procursor l
NUREG/CR4874 V23: PRECURSORS TO POTENTIAL SEVERE CORE DAMAGE ACCOENTS.1995. A Status Report Contaminent NUREG/CR-4674 V24 PRECURSORS TO POTENTIAL SEVERE CORE DAMAGE ACCOENTS: 198243.A Status Report NUREG/CR4515: BLT EC (BREACH, LEACH AND TRANSPORT EQUI-UBRIUM CHEMISTRY) DATA INPUT GUIDE.A Computer Model For Accountatety Report Sanulaeng Release And Couplej Geochermcal Transport Of Contarrd-NUREG-1542 V02: ACCOUNTABluTY REPORT FISCAL YEAR 1996.
nants From A Subsurface Deposal Facility.
Advanced salieng Water Reactor Contaminated Ot4ect NUREG-1503 S01: FINAL SAFETY EVALUATION REPORT RELATED NUREG 1608 DAFT FC: CATEGORIZlNG AND TRANSPORTING LOW TO THE CERTIFICATION OF THE ADVANCED BOluNG WATER RE.
- PECIFIC ACTIVITY MATERIALS AND SURFACE CONTAMINATED ACTOR DESIGN. Supplement No.1. Docket No. 52401.(General Elec.
OEUECTS. Draft Rept For Comment.
Inc Nuclear Energy)
Atmospheric Diepersion NUREG/CR-6037: MEASUREMENT OF RESIDUAL RADIOACTIVE SUR-NU'IEG/CR4331 Rot: ATMOSPHERIC RELATIVE CONCENTRATONS FACE CONTAMINATON BY 2-0 LASER HEATED TLD.
IN BUILDING WAKES.
Control Room Habitability Atom NUREG/CR4331 R01: ATMOSPHERIC RELAllVE CONCENTRATONS NUREG-1610 CONTROLUNG THE ATOM.ine Begemngs Of Nuclear IN BUILDING WAKES.
Regulatert 1946 1962.
Core Damage SLT EC NUREG/CR-4674 V23: PRECURSORS TO POTENTIAL SEVERE CORE NUREG/CR4515. BLT EC (BREACH, LEACH. AND TRANSPORT EQUI-DAMAGE ACCIDENTS: 19si A Status Report LIBRIUM CHCMISTRY) DATA INPUT GUIDE.A Computer Model For NUREG/CR-4674 V24: PRECURSORS TO POTENTIAL SEVERE CORE Swnulating Reisene And Coupled Geochermcal Transport Of Contar*
DAMAGE ACCIDENTS: 198243,A Status Report nants Frora A Subsurta :e Deposal Faculty, l
Corrosion Fatigue EWN NUREG/CR4667 V22: ENVIRONMENTALLY ASSISTED CRACKING IN NUREG/CR4153: A SIMPUFIED MODEL OF DECONTAMINATON BY LIGHT WATER REACTORS. Semiannual Report, January 1996. June BWR STEAM SUPPRESSION POOLS.
1996.
- "*h"*'"
Crack Statety NUREG/CR4361: CRITICALITY BENCHMAFK GUIDE FOR LIGHT.
NUREG/CR4233 V03: CRACK STABluTY IN A REPRESENTATIVE WATER 4tEACTOR FUEL IN TRANSPORTATION AND STORAGE PIP.MIC DISPLACEMENT CONTROLLED STRESSES tNG SYSTEM UNDER COMBINED INERTIAL AND SEISMIC /DY.
PACKAGES.
gi Boiling Water Reactor Report NJREG/CR4153: A SIMPUFIED MODEL OF DECONTAMINATON BY C
BWR STEAM SUPPRESSION POOLS.
AG R-6233 V02: STABluTY OF CRACKED PIPE UNDER SEIS-moron Dilutton MIC/ DYNAMIC DISPLACEMENT CONTROLLED STRESSES. Subtask NUREG/CP-0158: PROCEEDINGS OF THE OECD/CSNt SPECIALISTS 1.2 Final Report MEETING ON BORON DILUTION REACTMTY TRANSIENTS. Held in 8'
Y State Conego. Pennsytvana. USA. October 18-20, 1995.
p gy pg Brechtherapy PERFORMING STANDARD 12ED COMPUTER ANALYSES FOR LI-NUREGICR4074 V03: SEALED SOURCE AND DEVICE DESIGN CENSING EVALUATON. Control Modules C4, C6.
SAFETY TESTING.Techrucal Report On The Fmdmgs Of Task 4.Inves.
'dVREG/CR-0200 R5V1P2 SCALE: A MODULAR CODE SYSTEM FOR bget on Of A Failed Bracitytherapy Needle Applicator.
PERFORMING STANDARDIZED COMPUTER ANALYSES FOR U-CENSING EVALUATON Control Modules S1. Hl.
Culldmg Wake NUREG/CR 0200 R5V2P1: SCALE: A MODULAR CODE SYSTEM FOR NUREG/CR4331 Rot: ATMOSPHERIC RELATIVE CONCENTRATONS PERFORMING STANDARDIZED COMPUTER ANALYSES FOR U-IN BUILDING WAKES.
CENSING EVALUATION.Funchonal Modules F1 FB.
19
l
(
f 20 Subject Index
~
NUREG/CR-0200 R5V2P2: SCALE: A MODULAR CODE SYSTEM FOR PROFIT COLLEGES UNIVERSITIES AND HOSPITALS AND BY BUSb PERFORM 6NG STANDARDIZED COMPUTER ANALYSES FOR U-NESS FIRMS THAT DO NOT ISSUE BONDS.
CENSING EVALUATON Functonal Modules F9 F11.
NUREG/CR-0200 R5V2P3: SCALE: A MODULAR CODE SYSTEM FOR Financial Statement PERFORM:NG STANDAROZED COMPUTER ANALYSES FOR LL NUREG-1542 V02: ACCOUNTABluTY REPORT FISCAL YEAR 1996 CENSING EVALUATON Functonal Modules F16 F17.
NUREG/CR-0200 RSV3. SCALE: A MODULAR CODE SYSTEM FOR Fleelle Mateftal PERFORMING STANDARDIZED COMPUTER ANALYSES FOR Lb NUREG/CR-5661: RECOMMENDATONS FOR PRZPARING THE CRITI-MFOR PREPARING THE CRITl-CAUTY SAFETY EVALVATON OF TRANSPORTATION PACl< AGES, N E
- 1 RE M
CALITY SAFETY EVALUATON OF TRANSPORTATON PACKAGES Fracture Mechanics NUREG/CR4381: CRITICAUTY BENCHMARK GUIDE FOR UGHT-NUREG/CR4233 V02: STABluTY OF CRACKED PIPE UNDER SEIS-WATER-REACTOR FUEL IN TRANSPORTATION AND STORAGE M!C/DYNAMC DISPLACEMENT-CONTROLLED STRESSES. Subtask PACKAGES.
1.2 Final Report Database NUREG/CR4233 V03: CRACK STABlUTY IN A REPRESENTATIVE NUREG-1603 ORFT:
INDIVIDUAL PLANT EXAMINATON PIPING SYSTEM UNDER COMBINED INERTIAL AND SEISMIC /DY.
DATABASE. User's Guide NAMIC DISPLACEMENT CONTROLLED STRESSES. Subtask 1.3 Final Report Decommisolon NUREG/CR4233 V04: INTERNATONAL PnPING INTEGRITY RE-NUREG/CR4037: MEASUREMENT OF RESIDUAL RADIOACTIVE SUR-SEARCH PROGRAM (IPIRG) PROGRAM. Program Final Report FACE CONTAMINATON BY 2-0 LASER HEATED TLD.
Fracture Toughnese NVREG/CR-6233 V02: STABluTY OF CRACKED PIPE UNDER SEIS-t EG 4: ANALYSIS OF POTENTIAL SELF GUARANTEE MIC/ DYNAMIC DISPLACEMENT-CONTROLLED STRESSES Subtask TESTS FOR DEMONSTRATING FINANCIAL ASSURANCE BY NON-OES N R lES. A D PITALS AND BY BUSI-N EG C 2 V03: CRACK STABluTY IN A REPRESENTATIVE 3 g
~
PIPING SYSTEM UNDER COMBINED INERTIAL AND SEISMIC /DY-NAMIC DISPLACEMENT CONTROLLED STRESSES. Subtask 1.3 Final DecontaminaHon NUREG/CR-6037: MEASUREMENT OF RESIDUAL RADIOACTIVE SUR-Report FACE CONTAMINATON BY 2 D LASER HEATED TLD.
NUREG/CR4363: EFFECTS OF THERMAL AGING AND NEUTRON IR.
NUREG/CR4153: A SIMPLIFIED MODEL OF DECONTAMINATION BY RADIATON ON THE MECHANICAL PROPERTIES OF THREE WIRE BWR STEAM SUPPRESSON POOLS.
STAINLESS STEEL WELD OVERLAY CLADD8NG.
Detection System Fuel NUREG/CR 6535: DEVELOPMENT OF CONFORMAL RESPIRATOR NUREG/CR4361: CRITICAUTY BENCHMARK GUIDE FOR LIGHT-MONITORING TECHNOLOGY.
WATER REACTOR FUEL IN TRANSPORTATION AND STORAGE PACKAGES.
DW Design NUREG/CR4074 V03: SEALED SOURCE AND DEVICE DESIGN 4 15 T EC (BREACH. LEACH. AND TRANSPORT EOUl-tion O A F led B a
to,'
UBRIUM CHEMISTRY) DATA INPUT GUIDE.A Cornputer Model For D6eplacernent Controlled Stroes Semulatin0 Release And Coupled Geochemical Transport Of Contami-NUREG/CR4233 V03-CRACK STABluTY IN A REPRESENTATIVE nants From A Subsurface Disposal Facihty, PIPING SYSTEM UNDER COMBINED INERTIAL AND SEISMIC /DY-NAMIC DISPLACEMENT CONTROLLED STRESSES Subtask 1.3 Foal Geosciences Data Report NUREG/CR4372 V01: RECOMMENDATONS FOR PROBABILISTIC NUREG/CR4233 V04: INTERNATONAL PIPING INTEGRITY RE-SEISMIC HAZARD ANALYSIS. GUIDANCE ON UNCERTAINTY AND SEARCH PROGRAM (IPIRG) PROGRAM. Program Final Report USE OF EXPERTS.Maan Report NUREG/CR4372 V02 RECOMMENDATONS FOR PROBABluSTIC
/CR4372 V01: RECOMMENDATIONS FOR PROBABluSTIC U
E A
SEISMIC MAZARD AMALYSIS. GUIDANCE ON UNCERTAINTY AND USE OF EXPERTS Main Report Guidance NUREG/CR4372 V02: HECOMMENDATONS FOR PROBABluSTIC NUREG-1608 DRFT FC: CATEGORIZING AM TRANSPORTING LOW SEISMIC HAZARD ANALYSIS GUIDANCE ON UNCERTAINTY AND SPECIFIC ACTIVITY MATERIALS AND SURFACE CONTAHINATED N R G CR A
MENTAL SCALE-MODEL STUDY OF OBJECTS Draft Rept For Comment SEISMIC RESPONSE OF AN UNDERGROUND OPENING IN JOINTED NR /CR4507: CRITICAL HEAT FLUX (CHF) PHENOMENON ON A Emergency Planning DOWNWARD FACING CURVED SURFACE.
NUREG/CR4504 V01: AN UPDATED NUCLEAR CRITICALITY SLIDE RULE. Technical Basis.
Heat Transfer NUREG/CR-0200 R5V1P1: SCALE: A MODULAR CODE SYSTEM FOR Enforcement Action PERFORMING STANDARDIZED COMPUTER ANALYSES FOR U-NUREG-0940 V15 N2 Pt: ENFORCEMENT ACTIONS: SIGNIFICANT AC*
CENSING EVALUATION. Control Modules C4. C8.
TONS RESOLVED INDIVOUAL ACTIONS Sermannual Progress NUREG/CR-0200 R5 VIP 2: SCALE: A MODULAR CODE SYSTEM FOR Report.JulrDecember 1996.
PERFORMING STANDARDIZED COMPUTER ANALYSES FOR U-NUREG-0940 V15 N2 P2: ENFORCEMENT ACTIONS-SIGNIFICANT AC-CENSING EVALUATION. Control Modules S1 H1.
TIONS RESOLVED REACTOR UCENSEES.Semannual Pro 0ress NUREG/CR-0200 R5V2P1: SCALE: A MODULAR CODE SYSTEM FOR PERFORMif4G STANDARDIZED COMPUTER ANALYSES FOR Ll-NUR 15 NFORCEMENT ACTON& SIGNiFICANT AC-CENSING EVALUATON. Functional Modules F1 - F8.
TiONS RESOLVED MATERIAL UCENSEES.Semannual Progress NUREG/CR 0200 R5V2P2: SCALE: A MODULAR CODE SYSTEM FOR ReportJuly December 1996.
PERFORMING STANDARDIZED COMPUTER ANALYSES FOR U-CENSING EVALUATION Functional Modules F9 F11.
Final Safety Eveiustion Report NUREG/CR 0200 R5V2P3. SCALE: A MODULAR CODE SYSTEM FOR NUREG-1503 S01: FINAL SAFETY EVALUATIOG REPORT RELATED TO THE CERTIFICATION OF THE ADVANCED BOILING WATER RE-PERFORMING STANDARDilED COMPUTER ANALYSES FOR U-CENSING EVALUATON Functional Modules F16 Ft7.
ACTOR DESIGN Supplement No.1. Docket No.52-001,(General Elec.
NUREG/CR-0200 R$V3: SCALE: A MODULAR CODE SYSTEM FOR Inc Nuclear Energy)
PERFORMING STANDARDIZED COMPUTER ANALYSES FOR U-Financial Assurance CENSING EVALUATON. Miscellaneous.
NUREG/CR4514: ANALYSIS OF POTENTIAL SELF GUARANTEE NUREG/CR4167: LATE PHASE MELT PROGRESSION EXPCRIMENT TESTS FOR DEMONSTRATING FINANCIAL ASSURANCE BY NON-MP 2.Results And Analysis.
l l
Subject index 21 Heavy Section eteel irrede* ten Program Low-Level Weete NUREG/CR-5591 V07 Nt: HEAVY-SECTION STEEL IRRADIATION NUREG/CR4505 V01: THE POTENTIAL FOR CRITICAU'Y FOLLOW.
PROGRAM Sermannual Progrote Report For October 1995 Through ING DISPOSAL OF URANIUM AT LOW LEVEL WASTE March 1996.
FACtWTIES Uranium Blended With Soit Hydrogen Combustion Low-Specif6c ActMey Meterial NUREG/CR 4530 DEUBERATE IGNITION OF HYDROC *N-AIR-STEAM NUREG-1606 DRFT FC: CATEGORIZING AND TRANSPORTING LOW MtXTURES IN CONDENSING STEAM ENVIRONMENTS.
e,PECIFIC ACTMTY MATERIALS AND SURFACE CONTAMINATED
-; _ %,g OBJECTS. Draft Rept For Comment.
NUREG/CR4505 V01: THE POTENTIAL FOR CRITICAUTY FOLLOW.
W Hood Inkedty j
ING DISFt SAL OF URANIUM AT LOW-LEVEL WASTE FACIUTIES Uraruurn Blended With Soil.
NU9EG/CR 6507: CRITICAL HEAT FLUX (CHF) PHENOMENON ON A COWNWARD FACING CURVED SURFACE.
EG/CR45M: NUBERATE IGNITION OF HYDROGEN-AIR STEAM
"*" * U**"***
(
MIXTURES IN CONDENSING biEAM ENVIRONMENTS.
NURLG 1556 V01: CONSOUDATED GUIDANCE ABOUT MATERIALS LICI'NSES.Prograrn-Spec 6c Guidance About Portable Gauge I-In-Veeest Rotentior Uces ses. Final Report NUREG/CR4507; CRITICAL HEAT FLUX (CHF) PHENOMENON ON A l
DOWNWARD FA'.ING CURVED SURFACE.
Meecal FocNny NUREGC 516: MANAGEHENT OF RADtOACTIVE MATERIAL SAFETY IndMdual Ptent Enamireetion PROGilAMS AT MEDICAL FACluTIES Final Report NUREG-1603 DRFT:
INDIVIDUAL PLANT EXAMINATION DATABASE. User's Guide.
Mett Progreeelon NUREG/CR4167: LATE PHASE MELT PROGRESSION EXPERIMENT leformation Digest MP-2.Results And Analyws NUREG 1350 V09: NUCLEAR REGULATORY COMMISSION INFORMA-TION LAGEST.1997 Editort Molten Pool NUREGICR-6167: LATE PHASE MELT PROGRESSION EXPERIMENT E2hauns And AnaWs-t 5
V01: STEAM GENERATOR TUBE INTEGRITY l
PROGRAM.Semmennual Report August 1995. March 1996.
Noodle Appucator NUREG/CR4074 V03: SEALED SOURCE AND DEVICE DESIGN
/CR4363; EFFECTS OF THERMAL AGING AND NEUTRON IR-SAFETY TESTING.Techrucal Report On The Firengs Of Task 4.Inves.
RADIATION ON THE MECHANICAL PROPERTIES OF THREE-WIRE tigaton Of A Failed Brachytherapy Needle Apphcator.
STAINLESS STEEL WELD OVERLAY CLADDING Nuclear CriticeNt NUREG/CR4399: RESULTS OF CHARPY V-NOTCH IMPACT TESTING OF STRUCTURAL STEEL SPECIMENS IRRADIATED AT 30 DE-NUREG/CR45 4 V01: AN UPDATED NUCLEAR CRITICAUTY SUDE GREES C TO 1 X 10(16) NEUTRONSI CM(2) IN A COMMERCIAL RE.
NURE /C 5
- THE POTENTIAL FOR CRITICALITY FOLLOW-ACTOR CAM ING D:SPOSAL OF URANIUM AT LOW LEVEL WASTE Lwn FACluTIES. Uranium Blended With Soit NUREG/CR-4667 V22-ENVIRONMENTALLY ASSISTED CRACKING IN LIGHT WATER REACTORS. Sermannual Report. January 1996 June EG CONTROLUNG THE ATOM The Beginnengs Of Nuclear 1.UREG/CR4361: CRITICAUTY BENCHMARK GUIDE FOR LIGHT.
Regulation, 1946-1962.
WATER-REACTOR FUEL IN TRANSPORTATION AND STORAGE NUREG-1602 DRFT FC THE USE OF PRA IN RISK INFORMED Leak Rate APPUCATIONS. Draft Rept For Commer t HUREG/CP 0155: PROCEEDINGS OF THE SEM!NAR ON LEAK BEFORE BREAK IN REACTOR PIPING AND VESSELS-Pedormance Moeouro NUREG-1542 Vol: ACCOUNTABluTY REPORT FISCAL YEAH 1996.
Leek tetore treek NUREG/CP-0155: PaOCEEDINGS OF THE SEMINAR ON LEAK Piping Integrtty BEFORE BREAK IN REACTOR P! PING ANO VESSELS.
NUREG/CR4233 V04-INTERNATIONAL PIPING INTEGRITY RE.
NUREG/CR4233 V02 STABlWTY OF CRACKED PIPE UNDER SEIS-SEARCH PROGRAM (IPIRG) PROGRAM Program Final Report MIC/ DYNAMIC DISPLACEMENT 4X)NTROLLED STRESSES. Subtask 1.2 Final Report..
Ptping System NUREG/CR4233 V04: INTERNATIONAL PIPING thTEGRITY RE-NUREG/CR4233 V03: CRACK STABluTY IN A REPRESENTATIVE SEARCH PROGRAM (IPIRG) PPOGRAM.Piograrn 9nal Ruport.
PIPING SYSTEM UNDER COMBINED INERTIAL AND SEISMIC /DY-NA DISPLACLMENT CONTROLLED STRESSES, Subtask 1.3 Final NUREG0750 V44 '02 INDEXEi TO NUCLEAR REGULATORY COM-MISSION ISSUANCES.Juiv-D. comber 1998.
Plastic ScintNietor NUREG0750 V45 NO2-NUCLEAR REGULATORY COMMISSION IS" NUREG/CF1-6535: DEVELOPMENT OF CONFOHMAL RESPIRATOR RWUL 1 RY COMMISSION IS-MONITORING TECHNOLOGY, Nt EG
- NUC A SUANCES FOR MARCH 1997.P 95-263 Portab4e Gauge
^
I SUA F APR 199 ega NUREG 1556 V01: CONSOUDATED GUIDANCE ABOUT MATERIALS UCENSES Program Soecific Guidance About Pcrtable Gauge Licensee Event Report Licenses. Final Report NUREG'CR-4674 V23: PRECURSORS TO POTENTIAL SEVERE CORE DAMAGE ACCIDENTS 1995. A Status Report Probah4Hetic Riek Aseeeement NUREG/CR-4674 V24: PRECURSORS TO POTENTIAL SEVERE CORE NUREG-1602 DAFT FC: THE USE OF PRA IN RISK-INFORMED DAMAGE ACCIDENTS: 198243.A Status Report APPUCATIONS. Draft Rept For Comment
{
Ught Water Reactor ProbeeMietic Setemic Hazard Analyele NUREG/CR-4667 V22 ENVIRONMENTALLY ASSISTED CRACKING IN NUREG/CR4372 V01: RECOMMENDATIONS FOR PROBABluSTIC UGHT WATER REACTORS. Sermannual ReportJanuary 1996 June SEISMIC HAZARD ANALYS S: GUIDANCE ON UNCERTAINTY AND t %6.
USE OF EXPERTS. Main Rep 3rt NUREG/CR-6361: CRITICAUTY BENCHMARK GUIDE FOR UGHT.
NUREss/CR-6372 V02: REC (>MMENDATIONS FOR PROBABluSTIC WATER-REACTOR FUEL IN TRANSPORTATION AND STORAGE SEISMIC HAZARD ANALYLS: GUIDANCE ON UNCERTAINTY AND l
PACKAGES.
USE OF EXPERTS Appendi es.
~.....
22 Subject index Program-Specific NUREG-1607: SAFETY EVALUATON REPORT RELATED TO THE DE-NUREG 1556 V01: CONSOLCATED GUIDANCE ABOUT MATERIALS PARTMCNT OF ENERGY'S PROPOSAL FOR THE IRRADIATION OF LICENSES Program Specmc Guidance About Portable Gauge LEAD TEST ASSEMBLIES CONTAINING TRITIUM-PRODUCING Licenses. Final Report BURNABLE ABSORBER RODS IN COMMERCIAL LIGHT-WATER RE-Radiation Protection NUREG 1610: CONTROLLING YHE ATOM.The Begmnngs Of Nuclear Safety Program Re0Jiaton, 1946-1962.
NURE+1516: MANAGEMENT OF RADIOACTIVE MATERIAL SAFETY NUREG/CR4504 V01: AN UPI)ATED NUCLEAR CRITICALITY SLIDE PULE. Technical Basa PROGRAMS AT MEDOAL FACILITIES Foal Report Radioactive Maiorial Sealed Source NOREG/CR4fd4 V03. SEALED SOURCE AND DEVCE DESIGN NUREG-1516: MANAGEMENT OF RADIOACTIVE MATERIAL SAFETY PROGRAMS AT MEDICAL F#CILt lES Final Report SAFETY TESTING Techrwal Report On The Fmdings Of Task 4 inves-tigation Of A Faded Brachytherapy Needle Applicator, Reactivtry Tre? Aint NUREG/CP0158: PROCEEDINGS OF THE OECD/CSNI SPECIALISTS MEETING ON BORON DILLITION REACTIVITY TRANSIENTS. Held in NU EG/CR 04: AN EXPERIMENTAL SCALE MODEL STUDY OF State College, Pennsytvansa JSA,0ctober 18-20.199*
SEISMIC RESPONSE OF AN UNDERGROUND OPENING IN JOINTED ROCK MASS.
Reactor Ptping NUREG/CP 0155: PRUCEEDINGS OF THE SEMINAR ON LEAK Severo Reactor Accident DEFORE BREAK IN REAC'OR PIPING AND VESSELS.
NUREG/CR4167; LATE PHASE MELT PROGRESSON EXPERIMENT MP 2 Results And Analysis.
Reactor Pressure Vesset NUREG/CR4399 RESULTE OF CHARPY V NOTCH IMPACT TESTING SHde Hule OF STRUCTURAL STEEL SPECIMENS IRRADIATED AT 30 DE.
NUREG/CR-6504 V01: AN UPDATED NUCLEAR CR, NCALITY SLIOE GREES C TO 1 X 10(16) NEUTRONS / CH(2) IN A COMMERCIAL RE, RULE. Technical Bams.
ACTOR CAVITY.
Regulatory And Technical Report NUREG/CR 0200 R5 VIP 1: SCALE: A MODULAR CODE SYSTEM F-NUREG-0304 V21 N04: REGULATORY AND TECHNICAL REPORTS PERFORMING STANDARDIZED COMPUTER ANALYSES FOF u-(ABSTRACT INDEX JOURNAL). Annual Compilation For 1996.
CENSING EVALUATON Control Modules C4. C6.
NUREG/CR 0200 R5V1P2: SCALE: A MODULAR CODE SYSTEM FOR Regulatory Guidance PERFORMING STANDARDIZED COMPUTER ANALYSES FOR Li-NUREG-1606 DRFT FC: PROPOSED REGULATORY GUIDANCE RE-CENSING EVALUATON. Control Modules S1 H1.
LATED TO IMPLEMENTATION OF 10 CTR 50 59 (CHANGES, TESTS, NUREG/CR-0200 R5V2P1: SCALE A MODULAR CODE SYSTEM FOR OR EXPERIMENTS) Draft Report For Comment.
PERFORMING STANDARDIZED COMPUTER ANALYSES FOR Li-Report To Congrese CENSING EVALUATION. Functional Modules F1. F8.
NUREG/CR-0200 R5V2P2: SCAI.E: A MODULAR CODE SYSTEM FOR NUREG 0090 Vt 9: REPORT TO CONGRESS ON ABNORMAL PERFORMLNG STANDARDlZED COMPUTER ANALYSF.S FOR Ll-OCCURRENCES. Fiscal Year 1996.
CENSING EVALUATON.Functonal Modules F9 - F11.
NUREG/CR-0200 R5V2P3: SCALE: A MODULAR CODE SYSTEM FOR N
D @MM ANMSES M W N EG 453 DEVELOPMENT OF CONFORMAL RESPIRATOR MONITORNG TECHNOLOGY
- CENSING EVALUATION Functional Modules F16 F17.
NUREG/CR 0200 R$V3: SCALE: A MODULAR CODE SYSTEM FOR Risk-informed Appuestion PERFORMING STANDARDIZED COMPUTER ANALYSES FOR Ll-NUREG 1602 DRFT FC THE USE OF PRA iN RISK-INFORMED CENSING EVALUATON. Miscellaneous.
APPLICATONS. Draft Rept For Comment.
Stainnees Steel Rock Mese NUREG/CR4363: EFFECTS OF THERMAL AGING AND NEUTRON IR-NUREG/CR4404: AN EXPERIMENTAL SCALE *tODEL STUDY OF RADIATION ON THE MECHANICAL PROPERTIES OF THREE-W1RE SEISMIC RESPONSE OF AN UNDERGROUND OPENING IN JOINTED STAINLESS STEEL WELD OVERLAY CLADDING.
Steam Costdensation SCALE NUREG/CR4530: DEllBERATE IGNITON OF HYDROGEN-AIR-STEAM NUREG/CR-0200 R5 VIP 1: SCALE: A MODULAR CODE SYSTEM FOR MIXTURES IN CONDENSING STEAM ENV RONMENTS.
PERFORMING STANDARDIZED COMPUTER ANALYSES FOR Li-CENSING EVALUATION Control Modules C4, C6.
S*eam Generator NUREG/CR 0200 R5Y1P2 SCALE: A MODULAR CODE SYSTEM FOR NUh3160d. CIRCUMFEREN'lAL CRACKING OF STEAM GENERA-PERFORMtNG STANDARDIZED COMPUTER ANALYSES FOR Lb TOR TUuES.
CENSING EVALUATION. Control Modules S1 H1.
NUREG/CR4511 V01. STEAM GENERATOR TUBE INTEGRITY NUREG/CR4200 R$V2Pt: SCALE: A MODULAR CODE SYSTEM FOR PROGRAM Semiannual Report, August 1995 March 1996.
PERFORMING STANDARDIZED COMPUTER ANALYSES FOR Lk CENSING EVALUATON. Functional Modules F1 F8 Strese Corroelon Cracking NUREG/CR-0200 R5V2P2: SCALE: A MODULAR CODE SYSTEM FOR NUREG/CR-4667 V22-ENVIRONMENTALLY ASSISTED CRACKING IN PERFORMING STANDARDIZED COMPUTER ANALYSES FOR Lk LIGHT WATER REACTORS, Semiannual Report January 1996 June CENSING EVALUATION. Functional Modules F9 F11.
1996.
NUREG/CR-0200 R5V2P3-SCALE: A MODULAR CODE SYSTEM FOR NUREG/CR4511 V01: STEAM GENERATOR TUBE PTEGRITY PERFORMING STANDARDIZED COMPLTTFR ANALYSES FOR Ll-PROGRAM Semiannual Report. August 1995 March 1996.
CENSING EVALUATON Functional Modules F16 F17.
NUREG/CR 0200 RSV3. SCALE: A MODULAR CODE S(STEM FOR Structurat Steel PERFORMING STANDARDl2ED COMPUTER ANALYSES FOR LL NUREG/CR4399-RESULTS OF CHARPY V-NOTCH IMPACT TESYlNG CENSING EVALUATON. Miscellaneous.
OF STRUCTURAL STEEL SPECIMENS IRRADIATED AT 30 DE-GREES C TO 1 X 10(16) NEUTRONS / CM(2) IN A COMMERC'AL RE-Safety Evaluation ACTOR CAVITY.
NUREG-1606 DRFT FC PROPOSED REGULATORY GUIDANCE RE.
LATED TO IMPLEMENTATON OF 10 CFR 50.59 (CHANGES, TESTS.
Suppression Pool OR EXPERIMENTS). Draft Report For Comment.
NURECJCR-6153: A SIMPLIFIED MODEL OF DECONTAMINATION BY Safety Evaluation Report NUREG-1572: SAFETY EVALUATON REPORT FtELATED TO THE RE-Surface Crack NEWAL OF THE OPERATING 1ICENSE FOR THE RESEARCH REAC-NUREG/CR4233 V04: INTERNATONAL PIPING INTEGRITY RE-TOR AT NORTH CAROLIM SLATE UNIVERSITY.
SEARCH PROGRAM (IPIRG) PROGRAM Program Final Report.
l
.=
Subject Index 23 Surtesy Ter* Faculty Trewportetton NUREG/C 4-e330 DEllBERATE IGNITION OF HYDROGEN-AIR-STEAM NUREG-1606 DRFT FC: CATEGORIZING AND TRANSPORTING LOW MIXTURES IN CONDENSING STEAM ENVIRONMENTS.
SPEC 1FIC ACTIVITY MATERIALS AND SURFACE CONTAMINATED OBJECTS. Draft Rept For Comment NUREG4837 V17 N01: HRC TLD DRECT RADATION MONITORING Treneportetton Pectiage NETWORK.Progrees Report January-March 1997.
NUREG/CR 5661: RECOMMENDATION:s FOR PREP /QING THE CRITl-NUREG/CR4037: MEASUREMENT OF RES40 VAL RADIOACTIVE SUR-CALITY SAFETY EVALUATION OF TRANSPORTATION PACKAGES.
' FACE CONTAMINATION SY 2 D LASER HEATED TLD.
Tube G
4363: EFFECTS OF THERMAL AGING AND NEUTRON IR-TU RADATION ON THE MECHANICAL PROPERitES OF THREE WIRE NUREG/CR45'11 V01: STEAM GENERATOR TUBE INTEGRITY STAINLESS STEEL WELD OVERLAY CLADDNG.
PROGRAM,Sermannual Report August 1995 March 1096.
58: PROCEEDINGS OF THE OECD/CSNI SPECIALISTS MEETING ON BORON DLUTION REACTIVITY TRANSIENTS. Held in NUREG/CR 6515: BLT EC (BREACH, LEACH, AND TRANSPORT EQUl-State College, Penneytverna. USA October 18-20,1995.
LIBRIUM CHEMISTRY) DATA INPUT GUIDE.A Cornputer Model For Sanuletog Re6 ease And Coupled C--,-.
Transport Of Contamh Thermoluminescent Doetmeter nants From A Subourface Dsposal Fac6kty.
NUREG-0837 V17 N01: NRC TLD DIRECT RADATION MONITORING U
NETWORK.Progrees Agort January-March 1997.
g TItte List ING DISPOSAL OF URANIUM AT LOW LEVEL WASTE NUREG-0540 V10 NO2 TITLE LIST OF DOCUMENTS MADE PUBLICLY FACILITIES.Uratuum Blended With Sod.
AVAILABLE.F 1 28,1997.
NUREG-0540 V19
- TITLE LtST OF DOCUMENTS M, JE PUBLICLY Wold Overley AVAla,ABLE. March 131,1997.
NUREG/CR4363: EFFECTS OF THERMAL AGING AND NEUTRON IR-NUREO4540 V19 N04: TITLE LIST OF DOCUMENTS MADE PUBLCLY RADATION ON THE MECHANICAL PROPERTIES OF THREE W)RE AVAILABLE.Apr8130,1997.
STAINLESS STEEL WELD OVERLAY CLADDtNG.
2 4
j
I 1
I I
l 5
NRC Originating Organization Index (Staff Reports)
This index lists those NRC organizations that have published staff reports. The index is ar.
ranged alpnabetically by ma,or NRC organizations (e.g., program offices) and then by sub.
sections of these (e g., divls ons, branches) where appropriate. Each entry is followed by a NUREG number and title of the report (s), if further information is needed, refer to the main citation by NUREG number.
ADVISORY C04tMITTEE(S)
NURLG 1603 DRFT INDlylDUAL PLANT EKAMINATON ACRS. ADVISORY COMMITTEE ON RE ACTOR SAFEGUARDS DAT ABASE UWs Guide.
NUREG-1125 Vit A COMPiLATON OF REPOR18 OF THE ADVISO.
RY COMMITTEE ON REACTOR SAFEGUARDS 1996 Annual EDO. OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS OFFICE OF NUCL E AR MATERIAL SAF ETY & SAFEGUARDS OFFICE OF EMECUTIVE DIRECTOR FOR OPERAfl0NS (EDO)
NUREG 1600 DRFT FC. CATEGOR121NG AND TRANSPORTING LOW i
FNRC TLD DIRECT RADIAT,0N MONITORING NU G
? 1 a
1 t
n7pg OFC OF RC T(
i 87 1J NUREG4940 V15 N2 P1: ENFORCEI ENT ACTIONS. SIGNIFICANT ACTIONS RESOLVED INDIVIDUAL ACTIONS Semiannual Proyees NUREG 1616: MANAGEMENT GF RADOACTIVE MATERIAL SAFEf f N'PO'tMDecenter 1696.
PROGRAMS AT MEDICAL FACILITIES Fmal Report.
NUREG4940 V16 N2 P2: ENFORCEMENT ACTONS. SIGNIFICAN1 NUREG-1656 V01: CONSOLIDATED GUIDANCE ABOUT MATERIALS LICENSES am Specific Guidarco About Portable Gauge ACTIONS RESOLVED REACTOR LICENSEES Somk.nnual Progresa g,n, ymni NURYG A E AS ESSW 4 HWN WW MS 2
ENFORCEMENT ACTONS: SIGNIFICANT 3
i ACTIONS RESOLVED MATERIAL LICENSEES Semiannual Progress NUREG/dR-6506 V01: THE POTENTIAL FOR CRITICAL Report.#y-December 1996-ING DISPOSAL OF URANIUM AT LOW LEVEL WASTE EDO. OFFICE OF THE CONTROLLER PRE 039410 & POST $90306)
FACILITIES Uranium B6eWed With Soit NU EG V
La E
T FISCAL YEAFI 1996.
VS. NUCLEAR REWM COMMitSON DIVISION 0" BUDGET 4 ANALYSim (POST 690205)
OFFICE OF THE SECRE fARY OF THE COMMISSION NUREG 1350 V09 NUCLEAR REGULATORY COMMISSON INFOR-NUREG 1610. CONTROLI!NG THF ATOM The Beginnings Of Nuctur MATION DOEST,1997 Edshort Regula% 194M962.
j EDO FICE FOR ANALYSIS & EVALUATION OF OPERAtl0NAL ED0 F OF GEAR E.
REgMCH(
6) g OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA. DI.
NUREG 1603 DRFT INDIVIDUAL PLAN EEAMINATION RECTOR DATABASE User's Guide NUREG4090 V19 REPORT TO CONGRESS ON ABNORMAL DIVISION OF SYSTEMS T&NOLOGY (POST 841217)
OCCURRENCES Fiscal Year 1996.
NUREG-1602 DRFT FC; THE USE OF PRA IN RISK INFORMED APPLICA10NS Draft Rept For Commm EDf) 0FFICE OF lleFOMAfl0N RESOURCES MANAG& MENT & ARM O!F EDO. OFFICE OF NUCLE AR RE ACToll REGULAT;0N POST 900434)
OF FORMATION RESOURCES MANAGEMENT (POST OF F
A CT HE
(
N EG y
gN P RT H LATED NUREG 0304 V21 N04: REGULATORY AND TECHNICAL REPORTS TO THE CERTIFICATON OF TH8' ADVANLEE' DOILING WATER (ABSTRACT INDEX JOURNAL) Annual steon For 1996 REACTOR DESIGN Supplement No.1 Docket No. 62401,(General Y AVA ABLE F 26 99 NUR 167 FE VALUATION FIEPORT RELA 1ED TO THE NUREG 0540 V19 No iTLE LIST OF DOCUMENTS MADE PUBLIC.
RENEWAL OF THE OPERATING LICENSE FOF THE RESEARCH LY AVAILABLE March 1-31 1997.
REACTOR AT NORTH CAROUNA STATE UNIVERSITY.
NUREG4540 V19 N04. TITLI LIST OF DOCUMENTS MADE PUBLIC.
hilhiG 1604 C6RCUMFERENTIAL CRACKING OF STEAM OENERA.
LY AVAILABLE. April 1 30,1997, 1J~ TUBES l
NURE G4750 V44102. INDCXES TO NUCLEAR FIEGULATORY COM.
NURK W8 DAFT FC: PROPOSED REGULATORY GUIDANCE RE.
MISSON ISSUANCES J December 1996 LAiED TO IMPLEMENTATON OF 10 CFR 60 69 (CHANGES.
NUREG4750 V45 NO2. N EAR REGULATORY COMMi$ SON IS.
TESTS, Od EXPERIMENTS) Draft Repor1 For Cw.mont SUANCFS FOR FEBRUARY 1997, Pages 49-93 NUREG 1607: SAFETY EVALUATION REPORT RELATED TO THE NUREG4750 V46 NO3 NUCLEAR REGULATORY COMMISSION IS.
DEPARTMENT OF ENERGY'S PROPOSAL FOR THE IRRADIATION SUANCES FOR MARCH 1997.Paget 95-263 OF LEAD TEST ASSEMBLIES CONTAINING TRITIUM.PF3CDUCING NUREG4750 V45 N04: NUCLEAR REGULATORY COMMISSION IS.
BURNABLE ABSORDER RODS IN COMMERCIAL LIGHT WATER SUANCES FOR APRIL 1997.Pages 265 353.
RiACTORS.
1 i
25 i
t
4 1
1 l
i f
1 i
)
l l
i
?
4 i
6 a
i Y
l s
l II
,1 I
h I
I i
l l
l 4
i l
---,-a w.
--ea-e-w-s-,,e-e-,ms.-ew-g-g.-
e,-+.,
a,,e.wev,-w,s.ew,ww,,,,em-y.,-
w.
ecm-wepe gymw_w-wm _egmewe gw
,e meyew www-
NRC Originating Organization Index (International Agreements)
This index lists those NHC 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 t NUREG number and ?itle of the report (s). If further information is needed refer to the main citation by NUREG number.
There were no NUREG/lA reports published this quarter.
I 4
1 i
t, k
i 4
27
,,r, m-y.
.,o.,
y
,,,,.--_,-vr-
i 1
4 l
4 A
i l
l l
P
[
t J
l l
o l
l I
l L
1 l
l
..-7,-.,,
y..-,
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 a.phabetically by major NRC organization (e.g., program office) cnd 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) are aared by that organi-zation. If further information is needed, refer to the main citation by tie 9UREG/CR number.
ELO OPPICE POR ANALYS48 & EVALUAT10N OF OPERATIONAL NUREG/CH-6691 V07 N1: HEAVY 4E(XION STEEL IRRADIATION DATA PROGRAM Semiennual Progress Report For October 1995 Through DivlSION OF SAFETY PROGRAMS (POST 070413)
March 1996 NUREG/CR 4674 Y23 PRECURSOR 9 TO POTENTIAL SFVERE NUREG/CR4233 V02. STABluTY OF CRACKED PtPE UNDER SEIS-CORE DAMAGE ACCIDENTS 1995 A Status Report-MC/ DYNAMIC DISPLACEMENT CONTROLLED NUREG/CR-4674 V24 PRECURSORS TO POTf NTIAL SEVERE STRE SSES Subtaal 12 rinal Report OORE DAMAGE ACCOENTS 1962-83.A Status Report NUREQ/CR4233 V03. CRACK ST ABlu1Y IN A REPRESENTATIVE PIPING SYSTEM UNDER COMBINED INERTIAL AND SEISMIC /DY.
n NUREG/CR 0200 R5V1P1: SCALE: A MODULAR CODE SYSTEM NUREG/N233 V04. INTERNATONAL PIPING INTEGRITY RE.
FOR PERFORMING STANDARDIZED COMPUTER ANALYSES FOR SE ARCH PROGRAM (IPIRG) PROGRAM Program Final Report LCENSING EVALUATON Control Modules C4 C6 NUREG/CR 6363 EFFECTS OF THERMAL AGING AND NEUTRON NUREG/CR4200 R5VtP2: SCALE: A MODULAR CODE SYSTEM IRRADIATION ON THE MECHANCAL PROPERTIES OF THREE.
FOR PERFORMING STANDARDIZED COMPUTER ANALYSES FOR WIRE STAINLESS STEEL WELD OVERLAY CLADDING LCENSING EV ALUATION Control Modules St. H1-NUREGICR-6372 V01: RECOMMENDATONS FOR PROBABILISTC NUREG/C40200 RSV2P1: SCALE: A MODULAR CODE SYSTEM SEISMC HAZARD ANALYSIS GulDANCE ON UNCERTAINTY AND FOR PERFORMING STANDARDIZED COMPUTER ANALYSES FOR USE OF EXPERTS Main n LICENSING Eb,.UATION Functonal Modules F1. F8 NUREG/CR6372 V02, RE MENDATIONS FOR PCOBABluSTC NUREG/CR4200 R$V2P2. SCALE: A MODULAR CODE SYSTEM SEISMIC HA2ARD ANALYSIS' GUIDANCE ON UNCERTAINTY AND FOR PERFORMING STANDARDIZED COMPUTER ANALYSES FOR USE OF EXPERTS Appendices LICE NSING EVALUATION Functeunal Modules F 9. F11.
NUREG/CR4399 RESULTS OF CHARPY V NOTCH IMPACT TEST.
NUREG/CR4200 R5V2P3. SCALE: A MODULAR CODE SYSTEM ING OF STRUCTURAL STEEL SPECIMENS IMRADIATED AT 30 FOR PERFORMING STANDARDIZED COMPUTER ANALYSES FOR DEGREES C TO 1 X 10(16) NEUTRONS / CM(2) IN A COMMER LICENSING EVALUATION Functonal Modules F16. F17.
CIAL RE ACTOR CAVITY.
NUREG/CR0200 R$V3 SCALE A MODULAR CODE SYSTEM FOR NUREG/CR4511 YO1: STEAM GENERATOR TUBE INTEGRITY PERFORMING ST ANDARDtZED COMPUTER ANALYSES FOR Ll-PROGRAM Semaannual Hoport, August 1995. March 1998.
CENSING EVALUATION Mencoltaneous DIVISION OF REGULATORY APPLICATIONS (POST 941217)
NUREG/CR4661: RECOMMENDATIONS FOR PREPARING THE NUREG/CR6404 AN EXPERIMENTAL SCALE.MODEL STUDY OF CRITICAUTY SAFETV EVALUATION OF TRANSPORTATON SEISMC RESPONSE OF AN UNDERGROUND OPENING IN JOINT.
PACKAGES.
ED ROCK MASS NUREG/CR4361: CRITICAUTY BENCHMARK GUIDE FOR LIGHT.
NUREG/CR4504 V01; AN UPDATED NUCLEAR CRITICALITY SUDE WATER REACTOR FUEL IN TRANSPORTATION AND STORAGE ROLE.Techrucal Basis.
PACKAGES.
NUREG/CR4514. ANALYSIS OF POTENTIAL SELF GUARANTEE DIVISION OF INDUSTRIAL & MEDICAL NUCLEAR SAFETY (POST TESTS FOR DEMONSTRATh)G FINANCIAL ASSURANCE BY NON, 870729)
PROFIT COLLEGES, UNIVERSITIES, AND HOSPITALS AND BY NUREG/CR4074 V03: SEALED SOURCE AND DEVCE DESIGN BUSINESP FIRMS THAT DO NOT ISSUE BONDS.
SAFETY TESTING.Techrucal Report On The Firdngs Of Task 4 in.
NUREG/CR4515: BLT-EC (DRE.ACH, LEACH. AND TRANSPORT.
f vestegahon Of A Fa6 led Brachytherapy Needle Apphcator.
EQUluBRIUM CHEMISTRY) DATA INPUT GUIDE.A Computer DIVISION OF WA3TE MANAGEMENT (NMSS 940403)
Model For $4mulatmg Release And Coupled Geochemmal Transport NUREG/CR6505 V01: THE POTENTIAL FOR CRITICALITY FOLLOW-Of Contaminants From A Subsurface Disposal Facilitv.
ING DISPOSAL OF URANIUM AT LOW LEVEL WASTE NUREG/CR-6535: DEVELOPMENT OF CONFORMAL RESPIRATOR 6 ACluTIES Uranium Blended With S00.
MONITORING TECHNOLOGY.
DIVISION OF SYSTEMS TECHNOLOGY (POST 941217)
EDO. OPPICE OF NUCLEAR REGULATORY RESEARCH (POST 820406)
NUREG/CR4tS3: A SIMPUFIED MODEL OF DECONTAMINATON OFFICE OF NUCLEAR HEGULATORY RESEARCH (960724941217)
BY BWR STEAM SUPPRESSON POOLS NUREG/CR4530. DEUBERATE IGNITION OF HYDROGEN-AIR
- NUREG/CR4167. LATE PHASE MELT PROGRES$10N EXPERIMENT STEAM MIXTURES IN CONDENSING STEAM ENVIRONMENTS.
MP 2.Results And Analysis.
DIVISION OF REGULATORY Ar?UCATIONS (870413-941217)
NUREG/CR4507; CRITICAL HEAT FLUX (CHF) PHENOMENON ON NUREG/CR4037. MEASUREMENT OF RESIDUAL RADIOACTIVE A DOWNWARD FACING CURVED SURFACE.
SURF ACE CONTAMINATION BY 2 D LASER HEATED TLD.
OlVtSON OF ENGINEERING TECHNOLOGY (POST 941217)
EDO. OFFICE OF NUCLEAR REACTOR REGULATION (POST 000420)
NUREG/CR-4667 V22: ENVIRONMENTALLY ASSISTED CRACKING OFFICE OF NUCLEAR REACTOR REGULATON (POST 941001)
IN LIGHT WATER REACTORS. Semiannual ReportJanuary 1996 NUREG/CR4331 R01: ATMOSPHERIC RELATIVE CONCENTRA.
June 1996 TlONS IN BUILDING WAKES L
29
Contractor Index This index lists, in alphabetical order, the contractors that prepared the NUREG/CR reports listod in this co mitation. Listed below each contractor are the NUREG/CR numbers and titles of their re/ orts, if further information is needed, refer to the main citation by the NUREG/CR nurnbor.
ARGONNE NATONAL LADORATORY LAWRENCE LIVERMORE NATIONAL LABORATORY NUREG/CR 4867 V22 ENVIRONMENTALLY ASSISTED CRACKING IN NUREG/CR-6372 V01: RECOMMENDATIONS FOR PROBABillSflC LIGHT WATER REACTORS. Sermannual Report, January 1996. June SEISMIC HAZARD ANALYSIS GUIDANCE ON UNCERTAINTY AND 1996.
USE OF EXPERTS Main Report NUREG/CR4511 V01: STEAM GENERATOR TUBE INTEGRITY NUREG/CR4372 V02. RHCOMMENDATONS FOR PRODABILISTC PROGRAM Serrmannual Report, August 1995. March 1996.
BEISMC HAZARD ANALYSIS: GUIDANCE ON UNCERTAINTY AND CATTELLE MEMORIAL INSTITUTE, COLUMBUS LADORATORIES l
NURfG/CR4F13 V02 STABILITY OF CRACKED PIPE UNDER SEIS-NORTH CAROLINA. STATE OF MIC/ DYNAMIC DISPLACEMENT CONTROLLED STRESSES Swtask NJREG 1556 V01: CONSOLIDATED GUIDANCE ADOUT MATERIALS l
1.2 Final Report LCENSE S Progtam Speede Guedance About Portable Gauge NUREG/CR4231 V03 CRACK STABILITY IN A REPRESENTAftvE Lcenses Finol Report PIPING SYSTEM UNDER COMBINED INERTIAL AND SEISMIC /DY.
NAMC DISPLACEMENT CONTROLLED STRESSES Subtash 1.3 Final OAK RlDGE N ATIONAL LABORATORY Report NUREG/CR4200 FiSVIP1: SCALE: A MODULAR CODE SYSTEM FOR NUREG/CR4233 V04 INTERNATONAL PIPING INTEGRITY RE.
PERrORMWG STANDARDtIED COMPUTER ANAtVSES FOR Ll-SEARCH PROGRAM (IPIRG) PROGRAM Program Final Report CENS!NG EVALUATON Control Modules C4. C4 CATTELLE MEMORIAL INSTITUTE, PACIFIC NORTHWEST NATIONAL NUREG/CR4200 R5 VIP 2 SCALE: A MODULAR CODE SYS1EM FOR LADORATORY PERFORMING STANDARD 17ED COMPUTER ANALYSES FOR Lb CENSING EVALUATION Control Modules 81. H1.
NUREG/CR-6331 Rot: ATMOSPHERIC RELATIVE CONCENTRATIONS IN BUILDING WAKES NUREG/CR 0200 R5V2P1: SCALE: A MODULAR CODE SYSTEM FOR PFRFORMING STANDARDIZED COMPUTER ANALYSES FOR Lb CROOKHAVEN N ATIONAL LABORATORY CENSING EVALUATION Functional Modules F1. F8.
NUREG/CR4200 RSV2P2. SCALE: A MODULAR CODE SYSTEM FOR NUREG-1603 DAFT; INDIVIDUAL PLANT EXAMINATON DATABASE User's Gude.
PERFORMING STANDARDIZED COMPUTER ANALYSES FOR Lb NUREG/CR4515 BLT EC (BREACH. LEACH, AND TRANSPORT EQUl*
CENS1NG EVALUATION Functional Modules F 9. F11.
LIBRIUM CHEMISTRY) DATA INPUT GUIDE.A Computer Model Fo' NUREG/CR-0200 R5V2P3 SCAUE: A MODULAR CODE SYSTEM FOR
$4mulebng Rulease And CoutJed Geocherrucal Transport Of Contamb PERFORMING STANDARDlI6D COMPUTER ANALYSES FOR Lb nar,te From A Subouriace Disposal FactHy CENSING EV ALUATION F unctional Modules F 16. F 17.
NUREG/CR-0200 RSV3 SCALE: A MODULAR CODE SYSTEM FOR CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES fALU
^
S G N
NUREG/CR4404: AN EXPERIMENTAL SCALE-MODEL STUDY OF SEISMIC FiESPONSE OF AH UNDERGROUND OPENING IN JOINTED NUREG/CR 4674 V23 PRECURSORS TO POTENTIAL SEVERE CORE ROCK MASS.
DAMAGE ACCIDENTS 1995 A Status Report NUREG/CR 5591 V07 N1: HEAVY SECTION STEEL IRRADIATON ECODYNAMICS RESEARCH ASSOCIATES,INC, PROGRAM Semiannual Progress Report For October 1995 Through M
NUREG/CR4515 BLT EC (BREACH, LEACH, AND TRANSPORT EQUI' NURh0/
LIDRIUM CHEMISTRY) DATA INPUT GUIDE.A Computer Model For 5661: RECOMMENCATONS FOR PREPARING THE CRITb Samulating Release And Coupied Geochemical Transport Of Contarru.
CALITY SAFETY EVALUATION OF TRANSPORT ATION PACKAGES.
nants From A Subsurface Disposal Facddy NUREG/CR4361: CRITICALITY BENCHMARK GUIDE FOR LIGHT.
WATER REACTOR FUEL IN TRANSPORTATION AND STORAGE N RE CN4 IDERA E GN T OF HYDROGEN AIR-STEAM NUREG R 363 EFFECTS OF THERMAL AGING AND NEUTRON IR-MIXTURES IN CONDENSING bTEAM ENVIRONMENTS RADIATON ON THE MECHANCAL PROPERTIES OF THREE WIRE STAINLESS STEEL WELD OVERLAY CLADDING FRAMATOME NUREG/CR4399 RESULTS OF CHARPY V-NOTCH IMPACT TESTING NUREG/CP-0155: PROCEEDINGS OF THE SEMINAR ON LEAK OF STRUCTURAL STEEL SPECIMENS tRRADIA1ED AT 30 DE.
BEFORE DREAK IN REACTOR PlPING AND VESSELS.
GREES C TO 1 X 10(16) NEUTRONS / CM(2)IN A COMMERCIAL RE.
ACTOR CAVITY.
l'RANCE NUREG/CR4504 V01: AN UPDATED NUCLEAR CRITICALIT) SLIDE NOREG/CP 0155-PROCEEDtNGS OF THE SEMINAR ON LEAK RULE Technical Basa BEFORE BREAK IN REACTOR PIPING AND VESSEL *L NUREG/CR4505 VOI: THE POTENTIAL FOR CRITICALITY FOLLOW.
ING DISPOSAL OF URANIUM AT LOW 4EVEL WASTE ICF, INC.
FACILITIES Uraruum Blended With Soil NUREG/CR4514 ANALYSIS OF POTENTIAL SELF. GUARANTEE TESTS FOR DEMONSTRATING FINANCIAL ASSURANCE BY NON.
ORGANIZATION FOR ECONOMIC COOPERATION A DEVELOPMENT PROFlf COLLEGES UNfVERSITIES, AND HO$PITALS AND BY BUST.
NUREG/CP-0158 iCOCEEDINGS OF THE OECD/CSNI SPECIALISTS NESS FIRMS THAT DO NOT ISSUE DONDS.
MEETING ON DORON DILUTION REACTIVITY TRANSIENTS Held in State College. PennsyNarna. USA. October 18 20,1995 ILUNOIS, STATE OF NUREG-1516. MANAGEMENT OF RADIOACTIVE MATERIAL SAFETV PENNSYLVANIA STATE UNIV., UNIVERSITY PARK, PA PROGRAMS AT MEDICAL FACILITIES Final Report.
NUREG/CP 0158 PROCEEDINGS OF THE OECD/CSNI SPECIALISTS MEETING ON BORON DILUTON REACTIVITY TRANSIENTS Held in KEITHLE Y INSTRUMENTS, INC.
State College. PennsyNa wa. USA.Oct3ber 18-20.1995 NUREG/CR 6037; MEASUREMENT OF RESIDUAL RADIOACTIVE SUR-NUREG/CR4507: CRITCAL HEAT FL UX (CHF) PHENOMENON ON A FACE CONTAMINATON BY 2-0 LASER HEATED TLD.
DOWPNARD FACING CURVED SURF ACE.
I 31
32 Contractor Index SANDIA NATIONAL LADOR ATORIES NUREQ/CR-4674 V24 PRECURSORS TO POTENTIAL SEVERE CORE NUREG/CR 4674 V24 PRECURSORS TO POTENTIAL SEVERE CORE DAMAGE AOCIDENTS 1982 83 A Status Report DAMAGE ACCIDENTS 198243 A Statut Report NUREG/CR4167. L ATE. PHASE MEL1 PROGRESSION EXPERIMENT NUREG/CR 6153 A SIMPLIFIED MODEL OF DECONT AMINAT60N DY MP-2 Results And AnaYsis BWR STE AM SUPPRESS 60N POOLS NURFG/CR-6167-LATE-PHASE MELT PROGRESSION EXPERIMENT SOUTHWEST RESEARCH INSTITUTE MP 2 Results And Analyses NUREG/CR4074 V03 SEALED SOURCE AND DEVICE DESIGN NUREG/CR45}0 DEllDERATE IGNITION OF HYDROGEN AIR-STEAM SAFETY TESTING Techncal Report On ite Frongs Of Task 4 trwes.
MIXTURE S IN CONDENSING S1EAM ENVIRONMENTS bgation Of A Fat;d Bischytherapy Nee $e Appicator-SCIENCE APPLICATIONS INTERNATlONAL CORP. (FORMERLY TRANSPORT ATSON. DEPT. OF SCIENCE APPLICATIONS, NUREG-1000 DRFT FC. CATEGORtllNG AND TRANSPORTING LOW f4UREG/CR 4674 V23 PRECURSORS TO POTENTIAL SEVERE CORE SPECIFIC ACTIVITY MATERIALS AND SURFACE CONTAMINATED DAMAGi ACCIDENTS 1995 A Status Report OBJECTS Draft Rept For Cornment I
international Organization Ind6x This index lists, in alphabetical order, the countries and performing organizations that pre-1:ered the NUREG/lA reports listed in this compliation. Listed below each country and per.
"orming 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 NUREGAA reports published this quarter.
33
mei 1
l
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 Cnd followed by the report number, if further information is needed, refer to the main citation by the NUREG number.
M *' E M % w ee m co f S IE an
"("*"****"S*"*"*'
"'* $'8 I
36
I
NRCpome3s0 u.s.lAACLEAR RaOULATORY COMM*4 eon t, REPORY NUMBEQ 04 (Amegned C MC, didd Vel supp4Rev.
"d:E BIBUOGRAPHIC DATA SHEET
- ***"*"""*"**''"8 4
i rs* *=*=auas ea re w NUREG-0304
- 2. TITu AND SUSTriu Vol. 22, No. 2 Cogulatory and Techreal Reports (Atstract index Journaf) 3.
DATE REPORT PUaLISHED ComNebon for Second Quarter 1997 "3N*
I
" ^
- 5. AUTHOR ($)
- 8. TYPE OF REPORT
- 7. PERIOD COVERED thcheeveDeses)
Apri. June 1997 s PERFcwomeo ORGANEATION. NWE Af D ADORESS (rMc. me them omoe w Ampm u 8 h*w Asy*try cw= neem W am*v edews. #owewer.
me none enn meen edesse)
Pubbestons Branch Ofhet of informabon Resources Management i
U.S. Nudear Regulatory CommecJon Washington, DC 20555-0001
- s. sPONoose40 ORGANEAtl0N. nae 4 AND ADDRESS fr me W %== es etovei a ow*wer. me Mc Chem CmW w mopm u a Nween Asymary Cwwneem enn meks edeese)
Same as 8, above.
- 10. $UPPLEIM.NT ARY NOTES L L Stevenson, Project Manager
- 11. Aa6 TRACT (suo owse w ines)
This joumalincludes aR formal reports in the NUREG series prepared by the NRC staff and contractors; proceedings of conferences and workshops; as wel as intomabonal agreement reports. The entries 6n this compilabon are indexed for access by trtle and abstract, secondary report number, personal author, subject, NRC organizabon for e*aff and intomabonal agreements, I
contractor, in'emational organizabon, and Econsed facility.
I
- 12. KEY WORDS/DESCRIPTORS Amt sures e pwonee mer ed usat aseeercAns ei nze6ne ee rspet) 13 AvALAstav s1 ATLh4LNT compaabon
""h*"*d abstract boex
" SEcuR"Yc'*SS'c^"o" (Tha Peee) unclassined crhe neoes unclassified
- 16. NUMBER OF PAGES
- 16. PRICE NRC FOmd 32 pg TNs tonn was they produced by EMe Federal Forms, Inc
i l
i i
i i
l Printed on recycled paper Federal Recycling Program
E E
f Main Citations and Abstracts y
gg M
F-0 B
SecondaryReport E
Numberindex g4 f.<d>
m, i
@8 s
g Personal AuthorIndex E
E bo E
Subject index 5
N EW5~
k NRC Originating Organization NkY h h
g Index (Staff Reports)
R$gpg g
5"$8*
6
- ?E$
0 NRC Originating Organization 9
Index(International Agreements)
~
5
~
5 5
E 3
h NRC Contractor SponsorIndex g
g a
5 E
.m 5
g f
Contractorindex h=
International Organization index g
h Ucensed Facility l
Index gg n
.