ML20199M052
| ML20199M052 | |
| Person / Time | |
|---|---|
| Issue date: | 01/31/1998 |
| From: | NRC |
| To: | |
| References | |
| NUREG-0304, NUREG-0304-V22-N03, NUREG-304, NUREG-304-V22-N3, NUDOCS 9802100108 | |
| Download: ML20199M052 (41) | |
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NUREG-0304 VoI. 22, No. 3 Regulatory and Technical Reports (Abstract Index Journal)
Compilation for
- Third Quarter 1997
, July - September v S. Nuclear Regulatory Commission Omce of the ChiefInformation Omccr
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l AVAILABILITY NOTICE ;
Availability of Reference Materials Cited in NRC Publications Most documents cited in NRC publications will be available from one of the following sourcet'.:
- 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 m:Jority of documents cited in NRC publica-tions, it is not intended to be exhaustive.
Referenced documents available for inspection and copying for a fee from the NRC Public Document Room include NRC correspondence and internal NRC memoranda; NRC bulletins, circulars, information notices, inspection and investigation notices; licensee event reports; vendor reports and correspondence; Commission papers; and applicant and licensee docu-ments and correspondence.
The followbg documents in the NUREG series are available for purchase from the Government Printing Office: formal NRC staff and contractor reports, NRC-sponsored conference pro-ceedings, international agreement reports, grantee reports, and NRC booklets and bro-chures. Also available are regulatory guides, NRC regulations in the Code of Federal Regula-tions, and Nuclear Regulatcry Commission issuances.
Documents available from the National Technical Information Service include NUREG-series reports and technical reports prepared by other Federal agencies and reports prepared by the Atomic Energy Commission, forerunner agency to the Nuclear Regulatory Commission, Documents available from public and special technical libraries include all open literature items, such as books, journal articles, and transactions. Federal Register notices, Federal and State legislation, and congressional reports emi usually be obtained from these libraries.
Documents such as theses, dissertations, foreigr. reports and translations, and non-NRC con-ference proceedings are available for purchase from the organization sponsoring the publica-tion cited.
Single copies of NRC draft reports are available free, to the extent of supply, upon written request to the Office of Administration, Distnoution and Mail Services Section, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.
Cop 4 industry codes and standards used in a substantive manner in the NRC regulatory prot ;43 are maintained at the NRC Library, Two White Flint North 11545 Rockville Pike, Rock-ville, MD 20852-2738, for t:se 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 quarterly issues.
NUREG-0304 Vol. 22, No. 3 Regulatory and Technical Reports (Abstract Index Journal)
Compilation for Third Quarter 1997 July - September t
D:te Published: Jar.uary 1998 L L. Stevenson, Project Manager Publications Brancl.
Omce of the ChiefInformation O.Ticer U.S. Nuclear Regulatory Commission Wcshington, DC 20555-0001 pa %y h
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t CONTENTS Preface........................................................................... V index
- Tab Main Citations and Abstracts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 e Staff Reports e Conference Proceedings '
e Contractor Reports -
e Grant Reports
- International Agreement Reports Secondary Report Nurnber index . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 i Personal Author Index . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 Subject Index . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 NRC Originating Organization Index (Staff Reports) . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . 5 .
NRC Originating Organization Index (International Agreemenis) . . . . . . . . . . . . . . . . . . . . . . . . 6 NRC Contract Sponsor index (Contractor Reports) . . . . . . . . . . . . . , , . . . . . . . . . . . . . . . . . . . . 7 Contractor index . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . , . . . . . . . . . . . . . . . . . 8 International Organization index . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 Ucensed Facility index . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10
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i PREFACE i ?
This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports ,
. . issued by the U.S. Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC's intention to ;
publish this compilation quarteny and to cumulate it annually. Your comments will be appreciated. Please send them to:
< +
Publications Branch l Office of information Resources Management T6 E7
. U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 The main citations and abstracts in this compilation are listed in NOREG number order: NUREG-)000(, NU-REG /CP1X)00(, NUREG/CR-)000(, and NUREG/lA-)000(. Tnese precede the following indexes: ,
Secondary Repod Number index
- Personal Author index l ' Susje::t Index ,
NRC Originating Organization Index (Staff Reports)
NRC Originatin0 Organization index (Inte national Agreements) .
!' NRC Contract Sponsor Index (Contractor Reports) j Contractor Index International Organization Index
[ Licensed Facility Index l
l A detailed explanation of the entries precedes each index.
i The bibliographic elements of the main citations are the following:
Staff Report 1 NUREG-0808: MARK 11 CONTAINMENT PROGRAM EVALUATION AND ACCEPTANCE CRITERIA. ANDER-
[- SON, C. J. Division of Safety Technology. August 1981. 90 0 8109140048 09570:200.
Where the entries are (1) report number, (2) report title, (3) report author, (4) organizational unit of author, (5)
.date report was published, (6) number of pages in the report, (7) the NRC Document Con rol 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-4-
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 proceedings, (5) date report was published, (6) number of pages in the report, (7) the NRC Document Con-4 trol System accession number, (8) the report number of the originating organization, (9) the microfiche ad-4
-- dress (for NRC Internal use).
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Contractor Report NUREG/CR 1556: STUDY OF ALTERNATE DECAY HEAT REMOVAL CONCEPTS FOR LIGHT WATER REACTORS-CURRENT SYSTEMS AND PROPOSED OPTIONS. BERRY, D.L.; BENNETT, RR. Sandia Labo-ratories. May 1981.100 pp. 8107010449. SAND 80-0929. 08912:242.
Where the entries are (1) report number, (2) report title, (3) report authors, (4) organizational unit of authore 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: APPLICATIONS OF A NEW MAGNETIC MONITORING TECHNIOUE TO IN SITU EVAL-UATION OF FATIQUE DAMAGE IN FERROUS COMPONENTS. JILES, D.C.; BINER, S.B.; GOVINDARA 'U, M.; et al. Iowr. State Univ., Ames, IA. June 1994. 41 pp. 9407250286. 80328:195.
Where the entries are(1) report number, (2) report title. (3) report authors, (4) organizational unit of authors or publisher, (5) date report was published, (6) number of pages in the report, (7) the NRC Document Con-trol System accession number, (8) the report number of the originating organization (if given), (9) the micro- ]
fiche address (for NRC intemal use).
international Agreement Report q 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 titi s, (3) report author, (4) organizational unit of author, (5) date report was published, (6) number of pages in tt e report, (7) the NRC Document Control System acces-sion number, (8) the report number of the originatin ; organization (if given), and (9) the microfiche address (for NRC intemal use).
The following abbreviations are used to identify the document status of a report:
ADD - addendum APP - appendix DRFT - draft ERR errata N - number R - revision S - supplement V volume Availability of NRC Publications Cc: es 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, to the followir,g 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 by International Postal Money Order, payable to the Superintendent of Documents, or by draft on a United States or Canadian bank, payable to the Superintendent of Documents. ,
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NRC Report Codes The NUREG designation, NUREG XXXX, indicates that the document is a formal NRC staffgenerated re-port. Contractor-prepared formal NRC reports carry the report code NUREG/CR XXXX. This type of identifi-cation replaces contractor-established codes such as ORNUNUREG/TM XXX and TREE-NUREG-XXXX, as well as various other numbers that could not be correlated with NRC sponsorship or the work being 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 NRO grant reports, and NUREG/lA is used for international agreement reports.
Allthese report codes are controlled and assigned bythe staff of the Publications Brar.:h of the NRC Office of Information Resources Management.
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1 e
i 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 conference report, NUREG/CR XXXX is an NRC contractor 9repared report, and NUREG/lA XXXX is an inter-national a0reement re> ort. The bibliographic information (see Preface for details) is followed by a brief abstract of tils report, NUREG4040 V21 N01: LICENSEE CONTRACTOR AND requ6rements. Informaton in the event descriptons was ob-VENDOR INSPECTION STATUS REPORT, Quarterty toined from offcia! NRC oources.
Report, January-March 1997.(White Book)
- Offce of Nuclear Reactor Regulaton (F osi 941001). July 1997, 69pp. NUREG-0540 Vit N05: TITLE UST OF DOCUMENTS MADE 9707240136. 93885 282. PUBLICLY AVAILABLE.May 1 31, 1997,
- Offee of informauon This periodcal covers the results of inspections performed by Resources Management (Post 890205). Jufy 1997, 385pp.
the NRC's Special inspecten Branch, Vendor Inspecten Sec. 9708080231. 94697:001.
.I bon, that have been distributed to the inspected organtzstons This document is a monthly pubhcaton r,ontaining desenp-dunng the period from January through March 1997, tons of informat+0n receeved and generated by the U.S. Nuclear NUMEG4304 V22 N01: REGULATORY AND TECHNICAL RE. Regulatmy Cmmmason (NRC). This infamaton includes N PORTS (ABSTRACT INDEX JOURNAL). Compila')on For First d cheted ma'ertal associated with civihan nuclear power plants Quarter 1997, January-March.
- Office of Informaton Resources and omer uses of radcacWe matedals, and (2) rondocketed Management (Post 890205). June 1997, 42pp. 9709030367, matedal received and generated by NRC pertnent to its mie as A0236:196 e regulatay agay. The following indexes are encluded: Per.
This journal includes all formal reports in the NUREG senes sonal Author, Corporate Source, Report Number and Cross Ref-prepared by the NRC staff and contractors; proceedings of con- erence of Enclosures to Pnncipal Documents.
forences and workshops; as well as intomahonal agreement re-ports. The entnes in this compilaton are indexed for access by NUMEG4540 Vit N06: TITLE LIST OF DOCUMENTS MADE htle and abstract, secondary report number, personal author, PUBLICLY AVAILABLE. June 1 30, 1997, ' Office of Information subect f NRC organtration for staff and intomational agree- Resources Management (Post 890205). August 1997, 324pp.
ments, contractor, intomational organizabon, and hcensed facili- 9709120056. A0355:001 See NUREG-0540,V19,N05 abstract.
NUREG4386 Doe: UNITED STATES NUCLEAR REGULATORY NUREG-0540 V19 N07: TITLE LIST OF DOCUMENT 'ADE COMMISSION STAFF PRACTICE AND PROCEDURE PUBUCLY AVAILABLE.Jufy 1 31, 1997.
- Offee of inft non DIGEST. Commission, Appeal Board And ucensing Board Resources Management (Post 890205). September 7.
Decisons. July 1972 June 1996.
- Office of the General Coun. 410pp. 9710060476. A0622:001, set (Post 860701). July 1997. 695pp. 9708080133. 94729:001, See NUREG-0540,V19,N05 abstract.
TNs tith editon of the NRC Practce and Procedure Digest contains a digest of a number of Commission, Atomic Safety NUREG-0750 V45101: INDEXES TO NUCLEAR REGULATORY and Ucensing Appeal Board, and the Atome Safety and Licens- COMMISSION ISSUANCES.Jarvary-March 1997.
- Offee of in-ing Board decisions issued dunng the period of Jufy 1,1972 to formation Resources Management (Post 890205). June 1997, June 30,1996, interpreting the NRC's Rules. 29pp. 9709020298. A0255:150.
NUREG-0300 VII: TOPI L REPORT REVIEW STATUS.
- Offee Degests and indexes for issuances of the Comc.iisson, the of Nuclear Reactor Regulatton (Post 941001). August 1997. Atomo Safety and Licensing Board Panel, the Administrative 36pp. 9708200111. A0141:127. Law Judges, the Directors Decisions, and the Decisions on Pe-TNs report provides industry wtth proceduras for submitting htens fm Nemaking am presented topcal reports, guidance on how the U.S. Nuclear Regulato y Commission (NRC) processes and responds to topical repat NUREG-0750 V45102: INDEXES TO NUCLEAR REGULATORY submittals, and an accounting, with review schedules, of all top 6- COMMISSION ISSUANCES.JanuaryJune 1997
- Offee of in-cal reprirts currently accepted for review by the NRC. TNs formation Resources Management (Post 890205). September mt k WM amuay 1997,47pp. 9710100233. A0701:313.
See NUREG.0750,V45,101 abstract.
NUREG4525 V02 R05: SAFEGUARDS
SUMMARY
EVENT LIST (SSEL). January 1,1990 Through December 31.1996. NUREG 0750 V45 N05: NUCLEAR REGULATORY COMMISSION FADDEN M.A. Operahons Branch, July 1997, 94pp. ISSUANCES FOR MAY 1997.Pages 355-435.
- Offee of Infor.
9707140081. 93738:158. maton Resources Management (Post 890205). July 1997,88pp.
The Safeguards Summary Event ust provides brief summa- 9707230346. 93857:239.
rios of hundreds of safeguards-related events irwolving nuclear Legalissuances of the Commisson, the Atomic Safety and U-matenal or facilities regulated ty the U.S. Nuclear Regulatory censing Board Panel, the Administrative Law Judges, and NRC Commissiort Events are desenbed under the categories: Borrb. Program Offces are presented.
related, intrusion, Messing / Allegedly Stolen, Transportation-relat-od, Tampering /Vandaham, Arson, Firearms-related Radological NUREG4750 V45 N06: NUCLEAR REGULATORY COMMISSION Sabotage, Nordradologmal Sabotage, and Miscellaneous. Be- ISSUANCES FOR JUNE 1997, Pages 437 495.
- Office of Infor-cause of the public interest, the Miscellaneous category also in- maton Resources Management (Post 890205). August 1997.
ciudes events reported involving source material, byproduct ma- 66pp. 9708200220. A0141061.
tonal, and natural uranium, whch are exempt from safeguards See NUREt -0750,V45,N05 abstract.
1
2 Main Citations and Abstracts NUREG 0837 V17 N02: NRC TLD DIRECT RADtATION MONI- its operaton. The reports wers submitted to the Chairman and TORING NETWORK Progress Report. April-June 1997. Commissioners of the U.S. Nuclear Regulatory Commission. All STRUCKMEYER,R. Reg 6on 1 (Post 820201). September 1997. reports prepared by the Commit!ee have been made available 229pp. 9710100236. A0703 069- to the pubic through the NRC Pulic Document Room, the U.S.
This report provides the status and results of the NRC Ther. Library of Congress, and the intecnet at http>/www.nre gov /
motorrunescent Dosimeter (TLD) Direct Radiabon Morwtonn9 ACRSACNW.
Network. It presents the radiation levels measured in the vcanity of NRC Icensed facilities throughout the country for the second NUREG-1462 S01: FINAL SAFETY EVALUATION REPORT RE-quarter of 1997. LATED TO THE CERTIFICATION OF THE SYSTEM 80+
NUREG-0936 V16 Not: NRC REGULATORY DESIGN. Docket No. 52 002.(Aves Brcwn Boveri-Combuston
- Offce of Nuclear Reactor Regulaton (Post AGENDA Semiannual Report. January June 1997.
- Offee of Engineenng)
Administraton, Dwector (Post 940714) August 1997. 70pp. 941001). May 1997. 32pp. 9709020345. A0234:112.
9709120059 A0354.287. This report supplements the final safety evaluaton report the NRC Regulatory Agenda is a compdaten of all rules on (FSER) for the System 80+ standard desgn. The FSER was w'aich the NRC has recently completed acton, or has proposed issued by the U.S. Nuclear Regulatory Comnission (NRC) staff scan, or is considenng action, and all petitons for rulemaking as NUREG-1482 in August 1994 to documen' the NRC staff's whch nave been received by the Commission and are pending techncal review of the System 80+ design. Tha appleation for dispositen by the Commisson. The Regulatory Agenda is up- the System 80+ desgn was submitted by Combustion Engi-dated and issued semiannualty. neenng, Inc., now Asea Brown Boveri Combusboo Engineenng (ABB-CE) pursuant to Subpart B of 10 CFR Part 52. This sup-NUREG 0940 V16 N1 P1: ENFORCEMENT ACTIONS: SIGNIFl.
ACTIONS RESOLVED INDIVIDUAL piement documents the NRC staff a review of the cnanges to CANT ACTTIONS Semiannual Progress Report. January 4une 1997,
- the System 80+ design documentaten since the issuance of Ofc of Enforcement (Post 870413). September 1997. 422pp. the FSER. ABB-CE made these changes as a result of its 9710070386. A0639 001. review of the System BO+ design details. The NRC staff con.
This compilaton summarizes signifcant enforcement actions cludes that the changes to the System 80 + design documento-that have been resolved dunng the penod (January June ton are acceptable, and that ABB-CE's appication for design 1997) and includes copies of Orders and Notees of Violaton certitcaton meets the requirements of Subpart B to 10 CFR sent by the Nuclear Regulatory Commission to individuals wtth Part 52 that are applicable and techncally relevant to it.e respect to these enforcement actions. It is anticipated that the System 80+ desgn.
informaton in this pubhcation will be widely disseminated to managers and employees engaged in activities licensed by the NUREG-1496 V01: FINAL GENERIC ENVIRONMENTAL IMPACT NRC. The Commission beheves this informaton may be useful STATEMENT IN SUPPORT OF RULEMAKING ON RADIOLOG-to licensees in making employment decisions. ICAL CRITERIA FOR LICENSE TERMINATION OF NHC-Ll-CENSED NUCLEAR FACILITIES. Main Report. Final Report.
- Di-NUREG-0940 V16 N1 P2: ENFORCEMENT ACTIONS: SIGNIFl.
RESOLVED REACTOR vison of Regulatory Apphcabons (Post 941217) July 1997.
CANT ACTIONS LICENSEES Semiannual Progress Report, January 4une 1997
- 124pp. 9707230337. 93857:115.
Ofc of Et forcement (Post 870413). September 1997. 430pp. The action being considered in tNs Final Genenc Environ-9710070391. A0640 059. mental impact Statement (GEIS) is an amendment to the Nucie-This compitabon summarizes signifcant enforcement actons er Regulatory Commissioei s (NRC) regulations in 10 CFR Part that have been resolved dunng the penod (January June 20 to include raciologeal critena for decommissioning of lands 1997) and includes copies of letters, Nobces, and Orders sent and structures at nuclear facilities. Under the National Environ-by the Nuclear Regulatory Commission to reactor licensees with mental Pohey Act (NEPA), all Federal agenc%s must consider respect to these enforcement actions. It is anticipated that the the effect of their actons on the environment. To fulfill NRC's informabon in tNs pubhcabon will be widely disseminated to responsibilities under NEPA, the Commisson is preparing this managers ard employees engaged in activtties licensed by the GEIS which analyzes altamauve courses of action and the NRC, so that actions can be taken to improve safety by avoid- costs and impacts associated with those alternatives. In prepar-ing future violations similar to those described in tha pubica' ing the final GEIS, the following approach was taken: (1) a list-tsort ing was developed of regulatory attematives for establishing ra-NUREG 0940 V16 N1 P3: ENFORCEMENT ACTIONS: SIGNIFl- diological cntena for decommissioning, (2) for each attemative, CANT ACTIONS RESOLVED MATERIAL a detailed analysis and comparison of incremental impacts, both LICENSEES. Semiannual Progress Report,JanuaryYune 1997,
- radiological and nonradological, to workers, members of the Ofc of Enforcement (Post 870413). September 1997, 425pp. pubhc, and the environment, and costs were performed; and (3) 9710100100. A0702:001. based on the analysis of impacts and costs, conclusions on ra-Tiw t.ca pilaten summanzes signifcant enforcement actons diological critena for decommissioning were provided. Contained that lieve been resolved dunng the period (January June in the GEIS are results and conclusons related to achieving, as 1997) and includes copies of letters, Notees, and Orders sent an objective of decommissioning ALARI,, reduction to preexist-by the Nuclear Regulatory Commisson to matenal Icensees ing background, the radiological cnterion for unrestricted use, with respect to these enforcement actions. It is anticipated that decommissioning ALARA analysis for soils and structures con-the information in this pubhcaton will be widely disseminated to taining contaminabon, restncted use and attematrve analysis for managers and employees engaged in activities licensed by the special site-specife situabons and grounowater cleanup.
NRC, so hat actons can be taken to improve safety by avoid-ing future violations similar to those described in this pubhca' NUREG-1496 V02: FINAL GENERIC ENVIRONMENTAL IMPACT ton. STATEMENT IN SUPPORT OF RULEMAKING ON RADIOLOG-NUREG-1423 V07: A COMPILATION OF REPORTS OF THE AD- l CAL CRITERIA FOR LICENSE TERMINATION OF NRC-Lt.
VISORY COMMITTEE ON NUCLEAR WASTE. July 1996 June CENSED NUCLEAR FACILITIES. Appendices A And B. Final 1997.
- Advisoy Committee on Nuclear Wasr August 1997. Report.
- Divison of Regulatory Applications (Post 941217).
83pp. 9709120064. A0354:151. July 1997. 478pp. 9707230341. 93856:001.
This compelabon contams 11 reports issued by the Advisory See NUREG-1496,V01 abstract. j Committee on Nuclear Waste (ACNW) dunng the ninth year of )
Main Citations and Abstracts 3 NUREG 1496 V03: FINAL GENERIC ENVIRONMENTAL IMPAOT inservce irwpecton of containment structures. This rule amend-STATEMENT IN SUPPORT OF RULEMAKING ON RADIOLOG- ment incorporates by reference the 1992 Edition with the 1992 ICAL CRITERIA FOR LICENSE TERMINATION OF NRC-Ll- Addenda of Subsectons iWE and IWL of the ASME Code ad-CENSED NUCLEAR FACILITIES. Appendices C-H. Final Report. dressing the inservice inspecton of metal containments /hners
- Division of Regu!atory Apphcatons (Post 941217). July 1997. and concrete containtnents, respectively. The pvpose of tNs 651pp. 9707230343. 93854:001.
See NUREG-1496,V01 abstract report is to reconcile the techncal informaton and agreernents resulting from the NUMARC IR reviews wNch are generally de-NUREG-1656 V2 DRF FC: CONSOLIDATED GUIDANCE ADOUT scribed in NUREG-1557 and the inservce inspecton require.
MATERIALS LICENSES. Program Specifc Guidance About in. ments cd subsectons IWE and IWL as promulgated in.$50.55a dustnal Radiography Licenses. Draft Report For Use And Com. for t ise renewal considershon. TNs report concludes that ment. CARRICO.J.B.: COLLINS.D.; WHITE,0.: et al Division nf Subt. ctons lWE and rWL as endorsed in 9 50.55a are general-Industrial & Medcol Nuclear Safety (Post 870729). August 1997, ty consistent with the technical agreements reached dunng the 170pp. 9710150143. A0729:046. IR reviews. Specife exceptons are identified and additional This document is uftimately intended for use by appicants, h- evaluations and augmented inspections for renewal are recom-censees, and NRC staff and will also be available to Agreement mended.
States. TNs gu6 dance corresponds with the revision to 10 CFR Part 34 published in May 1997. TNs document combines and NUREG-1612: STATUS REPORT: REACTOR VESSEL INTEGRI.
supersedes the guidance previously found in draft Regulatory TY DATABASE. FAIRBANKS.C.J.: LEE.A.D.; MEDOFF.J.: et al.
Guide FC 4014, " Guide for the Preparation of Applications for Offee of Nuclear Reactor Regulaton (Post 941001). July 1997.
the Use of Sealed Sources and Devices for Performing industri- 65pp. 9707140087. 93738.255.
al Radiography," and in NMSS Policy and Guidance Directive The U.S. Nuclear Regulatory Commission (NRC) developed FC B415. " Standard Review Plan for Apphcatsons for the Use of Scaled Sources and Devees for Performing industrial Radi*
the Reactor Vessel Integnty Database (RVID) following the staff's review of heensse responses to Genenc Letter (GL) 92-ography." TNs draft report, where appleable, provides a tr. ore 01, Revison 1 (Ref.1). The database summarues the proper-risk 4nformed, performance-based approach to industnal radeog-raphy hcerr,ng consistent wtth the current regulatons. This ties of the reactor prossure vessel (RPV) beltline materials for draft NUREG Report is being distributed for comment to en- each operating commercial nuclear power plant. The RVID con-courage pubic partcipaten in its development. It represents the tains four tables for each plant: (1) background informaton current posetton of NRC staff, whch is rubject to change after g the review of pubhc comments. Commentc re~veo will be com P P' sidered in developing the final NUREG Report ti at represents table.' References and notes follow each table documenting the the official NRC staff positen. Until the final NUREG Report is source (s) of data and presenting supplementalinformabon. Ad-pubhshed, this draft NUREG Report represents the best avait. ditionally, the RVID has " sort" and " data search" capabilities.
able guidance, and may be used when preparing requests for The user can select a desired groupeng of plants and then kcensing actons. Once the hnal NUREG Report is published, specify informaton categones to search and hat The design of NRC staff will use it in its review of requests for hcensing ac- the RVID consohdates the industry's RPV data in a convenient tions. The draft and final NUREG Roorts may differ. If your h- and accessible manner. Some of the data categones contain conse was issued or amended based on recommendations in data inputs of " docketed" information; other data categories the draft NUREG Report and you feel that the final guidance is contain computed numencal values, which may or may not be more advantageous to you, you may choose to request an " docketed". The programming loge used for calculatons in the cmendment. RVID follows the methodology in Regulatory Guide (RG) 1.99, NUREG-1601: CHEMICAL PROCESS SAFETY AT FUEL CYCLE Revision 2 (Ref. 2). For the Palisades RPV, the data and infor.
FACH ITIES. AYRES.D.A. Divison of Fuel Cycle Safety & Safe. mation contained in the RVID, Version 1.1, are current through guards (Post 930207). August 1997. 26pp. 9708180186. April 12,1995; the data and information for the RPVs of all A0077:187. other operating commercial nuclear power plants are current TNs NUREG provides broad guidance en chemical safety through December 31,1994. The staff will update the RVID pe-lasues rekvant to fuel cycle facahties. It desenbes an approach rodically to reflect the latest information available, informabon acceptable to the NRC staff, with examples that are not ex- contained in the industry's responses to the closeout letters to haustive, for addressing chemical process safety in the safe GL 92-01, Revision 1, and in the industry's responses to GL 92-storage, handhng, and processing of heensed nuclear matenal. 01, Revison 1 Supplement 1 (Ref. 3), are not necessarily re-it e counds to bcense holders and apphcants a general philoso- flected in this version, but will appear in a future verson of the phy of the role of chemical process safety with respect to NRC- RVID.
hcensed materials; sets forth the basc information needed to property evaluate chemmal process safety; and describes plau- NUREG/CP-0153: PROCEEDINGS OF THE 24TH DOE /NRC NU-sible methods of idenufymg and evaluating chemical hazards CLEAR AIR CLEANING AND TREATMENT cnd assessing the adequacy of the chemical safety of the pro- CONFERENCE. Held in Portland, Oregon, July 15-18, 1996.
posed equipment and facihties. Examples of equipment and FIRST,M.W. Harvard School of Pubic Health, Boston, MA.
methods commonly used to prevent and/or mitigate the conse- August 1997,1,041pp. 9709120076. CONF 960715. A0347:001.
quences of chemical incidents are discussed in tfus document-This report contains the papers presented at the 24th DOE /
NUREG-1611: AGING MANAGEMENT OF NUCLEAR POWER NRC Nuclear Air Cleaning and Treatment Conference and the PLANT CONTAINMENTS FOR LICENSE MNEWAL LIU,W.C.; associated discussions Major topes are: (1) nuclear air clean-KUO,P.T,; LEE,S.S. Offee of Nuclear ReaN Regulabon (Post ing issues, (2) waste management, (3) instrumentation and 941001). September 1997,63pp. 971010015J A0703:297. measurement, (4) testing air and gas cleaning systems, (5) in 1990, the Nuclear Management and Resources Council progress and challenges in cleaning up Hanford, (6) internat:on-(NUMARC), now the Nuclear Energv institute (NEI), submitted al nuclear programs, (7) standardized test methods, (8) HVAC, for NRC review, the industry reports (irs), NUMARC Report 90- (9) decommissioning, (10) computer modeling applicatons, (11) 01 and NUMARC Report 90-10, addressing aging management iodine treatment, (12) fitters, and (13) codes and standards for issues associated with PWR containments and BWR contain- filters and adsorbers.
ments for hcense renewal, respect:vely. In 1996, the Commis-son amended 10 CFR 50.55a to promulgate requirements for
4 Main Citations and Abstracts NUREG/CP 0159: PROCEEDINGS OF THE OECD/CSNI WORK- such as change in fuel pnces, ; .nstruction and ritirement SHOP ON TRANSIENT THERMAL HYDRAULIC AND NEU- schedules, and system demand pro,ections.
TRONIC CODES REQUIREMENTS Held in Annapohs, Maryland, USA. November 5-8, 1996.
- Organization NUREG/CR-4219 V13 N1: HEAVY-SECTION STEE' TWNOL-for Econome Cooperston & Development.
- SCIENTECH, Inc. OGY PROGRAM.Semsannual Progress "~ ort For October July 1997. 842pp. 9708210006. NEA/CSNI/R(97)4. A0172:001. 1995. March 1996 PENNELL,W.E. Oak Rid 9 'shonal Labore-This is a report on the CSNI Workshop on Transeent Thermal- tory. September 1997. 95pp 9710100227. ORNL/TM-9593.
Hydraulc and Neutrone Codes Requirements held at Annapohs, A0705:126.
Marytand, USA, November 5-8, 1996. This experts' meebng The Heavy-Secten Steel Technology (HSST) Program is con.
consisted of 140 partcipants from 21 countnes; C5 invited ducted for the U.S. Nuclear Regulatory Comrnisson (NRC) by papers were presented. The meeting was divided into five the Oak Ridge National Laboratory (ORNL). The program focus areas: (t) current and prospective plans of thermal-hydraulc is on the development and vahdabon of technology for the as-codes development, (2) current and anticiputed uses of thermal. sessment of fracture-preventon margens in commercial nuclear hydraule codes; (3) advances in modehng of thermal-hydraule reactor pressure vessels. The HSST Program is organized in phenomena and associated additional expenmental needs; (4) seven tasks: (1) program management, (2) constraint effects numencal methods in multLphase flows; and (5) programming tonalytical development and vahdaton, (3) evaluation of cladding language, code architectures and user interfaces. The workshop effects, (4) ductile to cleavage fracture mode conversion, (5) consensus identified the following 6mportant action items to be fracture analysis methods development and apphcatons ,
addressed by the intomahonal community in order to maintain matenal property data and test methods, and (7) integratu of and improve the calculational capabihty: - preserve current code results into a state of-the-art methodology. The program Laks expertise and institutional memory; preserve the ability to use have been structured to place emphasis on the resolution frac-the existing investment in plant transient analysis codes; . main- ture issues with near term licensing signifcance. Resources to tain essenhal expenmental capabilities; develop advanced execute the research tasks are drawn from ORNL with subcore measurement capabilites to support future code vahdahon tract support from universtbes and other research labora4 ries.
work; Integrate existing analybcal capabilities so as to improve Close contact is maintained with the sister Heavy-Sechon Steel performance and reduce operating costs; exploit the proven Irradiation Program at ORNL with related research programs advances in code architecture, numerics, graphical user inter- both in the United States and abroad. This report provWe an faces, and modularization in order to improve code performance overview of pnncipal developments in each of the seven pro-and scrutabahty, and more effectrhely utshze user exponence in gram tasks from October 1995. March 1996.
modifying and improving the codes.
NUREG/CR-5229 V09: FIELD LYSIMETER INVESTIGATIONS:
NUREG/CP-0161: TRANSACTIONS OF THE TWENTY-FIFTH LOW LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM WATER REACTOR S/FETY INFORMATION MEETING. FOR FISCAL YEAR 1906. Annual Report. MCONNELL,1W.;
MONTELEONE,S. Brookhaven National Laboratory. September ROGERS,R.D. Idaho Natonal Engineenng & Environmental Laboratory. SANFORD,W.E.; et al. Oak Ridge National Labora-T a re c is ma f papers on reactor safety rest. arch to be presented at the 25th Water Reactor Safety in in August 1997. 55pp. 9709150098. INEL 94/0278.
formation Meehng at the Bethesda Marnott Hotel in Bethesd# A03 267.
pied Lysimeter investigatons: Low Level Waste Data Maryland, October 20-22, 1997. The summanes bnefly describe Base Development Program, funded by tea U.S. Nuclear Regu-latory Commisson, is (a) studying the degradaten eHects e e b the ce of N le R t R r h U S NR m-ganic ion-exchange resins caused by radiation, (b) examining manes of invited papers concerning nuclear safety issues frort the adequacy of test procedures recommended in the Branch U.S. govemment laboratones, tho electre utiht es, the nuclear Technical Position on Waste Form to meet the requirements of industry, and from foreign govemments and industry are also in.
cluded. The summanes have been compiled in one report to 10 CFR 61 using sohdified ion-exchange resins, (c) obtaining provide a basis for meaningful discussion of information ex- performance informaton on solidified ion exchange resins in a disposal environment, and (d) determining the condition of liners changed dunng the course of the meebng, and are given in order of their presentation in each sesson. used to dispose ;he ion-exchange resins. Dunng the field testing expenments, both portland type 1-11 cement and Dow vinyt ester-NUREG/CR 4012 V04: REPLACEMENT ENERGY COSTS FOR styrene waste form samples were tested in lysemeter arrays lo-NUCLEAR ELECTRICITY-GENERATING UNITS IN THE cated at Argonne National Laboratory East (ANL-E) in lilinois UNITED STATES: 1997-2001. VANKUlKEN.J.C.; GUZIEL,K.A.; and at Oak Ridge Natonal Laboratory (ORNL). The study was TOMNINS,M M.; et al. Argonne Nabonal Laboratory. Septem- designed to provide continuous data on nuchde release and ber 1997. 54pp. 9710100244. ANL AA-30. A0705:220. movement, as well as environmental conditions, over an ex-This report updates previous estimates of replacement energy tended period. Those expenments have been shut down and costs for potential short term shutdowns of 109 U.S. nuclear are to be exhumed. This report discusses the plans for removal, electricity units. This information was developed to assist the samphng. and analysis of waste form and soil cores from the U.S. Nuclear Regulatory Commession (NRC) in its regulatory lysimetets. Results of parttion coefficient determinations are impact analyses, specifically those that examine the impacts of presented, as well as applcation of a source term computer proposed regulations requenng retrofittng of or safety modifica- code using those coeffeients to predict the fysimeter results. A tions to nuclear reactors. Such actions might necessitate shut- study of radionuchde-containing collords associated with the downs of nuclear power plants while these changes are being leachate waters removed from these fysimeters is desenbed. An implemented. The change in energy cost represents one factor update of upward migration of radionuclides in the sand-filled ty-that the NRC must consider when deciding to require a partscu- simeter at ORNL is included.
lar modification. Cost estimates were dertved from probabihste producton cost simulations of pooled utlity system operations. NUREG/CR 5591 V07 N2: HEAVY-SECTION STEEL IRRADIA-Factors affecting replacement energy costs, such as rendem TION PROGRAM. Semiannual Progress Report For April unit faibres, maintenance and refuehng requirements, and load Through September 1996. CORWIN,W.R. Oak Ridge Natonal vanations, are treated in the analysis. This report desenbes an Laboratory. September 1997. 7tpp. 9710070369. ORNL/TM-abbreviated anatybcal approach at it was adopted to update the 11568. A0642:202.
( cost eshmates pubhshed in NUREG/CR-4012. Vol. 3. The up- The goal of the Heavy Section Steef irradiation Program is to i dates were made to extend the bme frame of cost eshmates provide a thorough, quant)tatrve assessment of effects of neu-and to account for recent changes in utihty system conditions, tron irradiahon on matenal behavior, and in particular the frac-l l
Main Citations and Abstracts 5 ture toughness properbes, of typical pressure vessel steels as the analysis of the PCA benchmark is described. Calculations they relate to hght-water reactor pressure-vessel integnty. Ef- with the computer code DORT, based on the escrete-ordinates fects of specimen stre, material chemstry, product form and rni- .nethod, were @i-d for three ENDF/B-VI-based multsgroup crostructure, irradiaton fluence, flux, temperature and spectrum, hbraries: BUGLE-93, SAILOR 95, and Bl>GLE 96. An excellent and post-irradiaton anneakng are bosng examined on a wide agreement of the calculated (C) and measures (M) equivalent range of fracture proportes. The HSSI Program is arranged into fisson fluxes was obtained. The artthmetsc average C/M for all 14 tasks: (1) program management, (2) fracture toughnee the dosameters (total of 31) was 0.93 t ' O.03 and 0.921. 0.03 (K(Ic)) curve sNft in Ngh-cogper welds, (3) crack-arrest tough- for the SAILOR-95 and BUGLE-96 libraries, respectivery. The ness (K(la)) curve sNft in high-copper welds, (4) irradiation ef- average C/M rato. obtained with the BUGLE 93 hbrary, for the facts on cladding (5) K(ic) and K(la) curve sNfts in low upper. 28 measurements was 0.93 t 0.03 (the neptunium measure-shelf welds, (6) anneakng effects in low upper shelf welds, (7) ments an the water and asr regens were overpredicted and ex.
Irradiaton effects in a commercial low upper shelf weld, (8) mi- ciuded from the average). No systemabc decrease in the C/M crostructural analysis of irradiation effects (9) in-service aged ratos with increasing destance from the core was observed for maternal evaluations, (10) correlaton monitor materials, (11) any of the librares used, special technscal assistance, (12) JPDR steel examnaton, (13) technical assistance for JCCCNRS Working Groups 3 and 12, NUREG/CR4469: FIELD STUDIES AT THE APACHE LEAP RE-and (14) additsonal requirements for matenals. TNs report pro. SEARCH SITE IN SUPPORT OF ALTERNATIVE CONCEPTUAL v6 des an overview of the activthes witNn each of these tasks MODELS. BASSETT.R.L; NEUMAN,S.P.; WlERENGA.P.J.; et from April Through September 1996. al. Artzona, Univ. of, Tucson, AZ. August 1997, 200pp.
9708290222. A0232:073.
NUREG/CR4437: FLOW AND TRANSPORT AT THE LAS TNs is a final technical report for a project of the U.S. Nucle-CRUCES TRENCH SITE: EXPERIMENT 11 8 . VINSON,J.;
HILLS,R.G.: et al. New Mexico State Univ., Las Cruces, NM at Regulatory Comtrussen (sponsored contract 04-090-051) with The University of Artzona The contract was an optional ex.
WlEREt4GA.P.J. Artrona, Univ. of Tucson, AZ. July 1997.
234pp. 9708210009. A0142:001, tension for the period July 12,1994 to May 31,1995. The Three water flow and solute transport expenments were per- project manager is Thomas J. Nicholson, Office of Nuclear Reg-utatory Research. The obf ecbves of this contract are to exarrune formed as part of a comprehensive feld trench study near las Cruces, New Mexico to test deterministic and stochasbc models hypotheses and test attemative conceptual models conceming of vedose zone flow and transport. This report presents partial unsaturated flow and transport through fractured rock and to results from the tNrd experiment (expenment lib). Expenments dessgn and execute confirmatory field and laboratory experi-lla and b were conducted e- 'he North side of the trench, on a ments to test these hypw.esis and conceptual models at the plot 1.22 m wide by 12 m long, perpendicular to the trench. The Apache Leap Research Site near Supenor, Anzona. Each chap.
area was drip imgated dunng two bme penods with water con- ter in this progress report summarizes research related to a taining a variety of tracers. The water front was measured with specific set of objectives and can be read and interpreted as a tensiometers and neutron probes. Solute fronts were deter. separate entity. The tasks include detecten and charactert:a-maned from soil solutens through suction samplers and from ton of historical rapid flow through fractured rock and the rela-tonship to perched water systems using environmental isotopic disturbed samples. Expenment lib resutta show predominantiy downward water movement through tiie layered unsaturated tracers of (3)H and (14)C, fluid are rock denved (234)U/(238)U soil. Tntium plumes were only half as deep and half as wide as measurements, and geophysical data. The water balance in a the water plumes at 310 days after the start of the expenment. small watershed at the ALRS demonstrates the methods of me-Chromium, apphed as Cr(VI), moved similar to tritium, but with a counting for ET, and eshmahng the quantity of water available for infiltraton through (racture networks. Grain density measure-loss of mass due to reduction of Cr(VI) to Cr(tit). Chloride and ments are now possible for core-sized samples using a newly nitrate, erwtially present at high concentrabons in the soil solu-tion, were displaced by the Imgabon water. The extensive data designed gas pycnometer. The distribution and magnitude of air permeabihty measurements have been done in a three-dimen-presented should serve well as a data base for model testing' sional setting and subsequent geostabstical analysis is present-
- NUREG/CR4451: A SAFETY AND REGULATORY ASSESS- ed. Electroruc data sets of the data presented here are avail-MENT OF GENERIC BWR AND PWR PERMANENTLY SHtn. able from the authors more detailed discussion and analyses DOWN NUCLEAR POWER PLANTS. TRAVIS,R.J.; DAVIS R.E.; are available in the referenced technical pubhcatons.
CROVE E.J.; et al. Brookhaven Nationa' Laboratoy August 1097,57pp.9708080190. BNL-NUREG-52498. 94731:089. NUREG/CR4464: AN EVALUATION OF METHODOLOGY FOR An entuahon of the nuclear power plant regulatory bases is SEISMIC QUALIFICATION OF EQUIPMENT, CABLE TRAYS, perfornied, as it pertains to those plants that are permanently AND DUCTS IN ALWR PLANTS BY USE OF EXPERIENCE shutdown (PSD) and awarting or undergoing decommissiorung. DATA. BANDYOPADHYAY,K; KANA,D.D.; KENNEDY,R.P.; et al.
t our spent fuel storage configurations are examined. Recom. Brookhaven Natonal Laboratory. July 1997, 140pp.
mandations are provided for those operationally based t.gula. 9708040210. BNL-NUREG 52500. 93995:001, tons that could be partally or totally removed for PSD plants Advanced Reactor Corporation (ARC) has developed a meth-without impacting pubhc health and safety. odology for setsnuc quahfication of equipment, cable trays, and ducts in Advaaced Light Water Reactor plants. A Panel (mem-NUREG/CR4454: POOL CRITICAL ASSEMBLY PRESSURE bers of which acted as individuals) supported by the Office of VE5SEL FACILITY BENCHMARK. REMEC,l.; KAM F.B.K. Oak Nuclear Regulatory Research of the Nuclear Regulatory Com-Ridge National Laboratory July 1997. 52pp. 9708210013.
mission has evaluated tNs methodology. The review approach ORNL/TM-13205. A0141274-and observatons are included in this report. In general, the The pool entical assembly (PCA) pressure vessel wall facihty Panel supports the ARC methodology with some exceptions 6-Js,erk (PCA benchmark) is described and analyzed in this and provides recommendations for further improvements.
report. Analysis of the PCA benchmark can be used for parbal fulfillment of the requirements for the quahtication of the meth-odo60gy for pressure vessel neutron fluence calculations, as re. NUREG/CR4478: MOTOROPERATED VALVE (MOV) ACTUA-TOR MOTOR AND GEARBOX TESTING. DEWALL,K.G.;
quired by the U.S Nuclear Regulatory Commission regulatory WATKINS,J.C.; BRAMWELL,D. Idaho Natonal Engineering a guide DG 1053. Sechon 1 of this report describes the PCA Environmental Laboratory. Jufy 1997. 54pp. 9708210034. INEL-benchmark and provides all data necessary for the benchmark 96/0219. A0141:217, analysis. The measured quantities, to be compared with the cal- Researchers at the Idaho Natonal Engineenng and Environ-culated values, are the equivalent fission fluxes. In Secten 2 mental Laboratory tested the performance of electric motors
6 Maln Citations and Abstracts and actuator gearboxes typcal of the equipn.ent installed on NUREG/CR4508: COMPONENT UNAVAILABILITY VERSUS IN.
moto'. operated valves used in nuclear power plants. Using a SERVICE TEST (IST) INTERVAL EVALUATIONS OF COMPO-test stand that simulates valve closure loads against flow and NENT AGING EFFECTS WITH APPLICATIONS TO CHECK pressure, we tested five electre motors (four ac and one de) VALVES. VESELY,W.E.; POOLE,A.D Oak Ridge National Labo-and three gearboxes at conditions a motor m6ght experience in ratory. July 1997,270pp. 9707280087. ORNL-6909. 93916.086.
a power plant, including such off normal conditions as operabon Methods are presented for calculating component unavailabi-at hsgh temperature and reduced vohage. We also morvtored hties when Inservice Test (IST) intervals are changed and when the efficiency of the actuator geartiox. All five motors operated component aging es exphcitty included. The methods extend at or above thest rated starting torque dunng tests at normal vol- usual approaches for calculating unavailabihty and nsk effects tages arid temperatures. For all frve motors, actual torque of changing IST Intervals which utilize Probabikste Risk Assess-losses due to voltage degradation were greater than the losses ment (PRA) methods that do not explcrtty include component calculated by methods typically used for predicting motor torque aging. Different IST charactenstics are handled including ISTs at degraded voltage condatons. For the de motor the actual wNch are not followed by corrective maintenances wNCh Com-torque losses due to elevated operating temperatures were pletely renew or parbally renew the component. ISTs wNch are greater than the losses calculated by the typical predictive not followed by maintenanco actrvities needed to renew the method. The actual effeciencies of the actuator gearboxes were component are also handled. Any downtsme associated with the generally lower than the running effciencies pubhthed by the IST, including the test downtime and the following maintenance manum.cturer and were generally nearer the pubhshed pull-ott downbme, is included in the unavailabihty evaluations. A range efficiencees Operaton of the gearbox at elevated temperatore of component aging behaviors is studied including both hnear did not effect the operahng effeiency. and nonhnear aging behaviors. Based upon evaluatons com-pleted to date, pooled failure data on check vatves show rela-NUREG/CR4497: DATA COLLECTION AND FIELD EXPERI- tively small aging (e.g, less than 7% per year). However, data MENTS AT THE APACHE LEAP RESEARCH SITE.May 1995 - from some plant systems could be evidence for larger aging 1996. BASSETT,R La NEUMAN.S P.; WiERENGA.P.1; et al. A'b rates occumng in time penods less than 5 years. The methods zona, Univ. of, Tucson, AZ August 1997,144pp. 9709150105. are utaltzed in tnis report to carry out a range of sensitety eval-A0363.18& uations to evaluate aging effects for different possible apphce-TNs report documents the research performed dunng the tions. Based on the sensitmty evaluations, summary tables are penod May 1995-May 1996 for a project of the U.S. Nuclear constructed showing how optimal IST intoival ranges for check Regulatory Commisson (sponsored contract NRC-0&O90-051) valves can vary relative to different aging behaviors which meght by the University of Atuona. The protect manager for this re- exist. The evaluations are also used to identify IST intervals for search is Thomas J Nicholson, Office of Nuclear Regulatory check valves which are robust to component aging effects.
Research. The objectives of this research were to examine hy' General insights on aging effects are also extracted. These sen-potheses end test alternative conceptual models concerning un- sitmty studies and extracted results provide useful informaton saturated flow and transport through fractured rock, and to whch can be supplemented or be updated with plant specific design and execute confirmatory field and laboratory expen- information. The models and results can also be input to PRAs ments to test these hypotheses and conceptual models at the to determine associated nsk imphcatens.
Apache Leap Research Site near Supenor. Anzona. Each chap-ter 6n tha report summanres research related to a specific set NUREG/CR-6519: SCREENING REACTOR STEAM / WATER of obtectives and can be read and interpreted as a separate PIPING SYSTEMS FOR WATER HAMMER. GRIFFITH.P. Mas-entity. Topics include: crosshole pneumatic and gaseous tracer sachusetts Institute of f achnology, Cambndge, MA. September field and modeling expenments designed to help vahdate the 1997. 52pp. 9709120067. A0354.234.
applicabihty of continuum geostatistical and stochastic con- A steam / water system possessing a certain combinabon of cepts, theones, models, and scahng relabons relevant to un- thermal, hydrauhc and operabonal states, can, in certain geome-saturated flow and transport, use of geoctiemistry and aquifer tnes lead to a steam bubble collapse induced water hammer.
testing to evaluate fracture flow and perching mechanisms; in- These states, operabons, and geometnes are identified. A pro-vestigabons of uranium isotopes to evaluate leaching selectmty; cedure that can be used for identifying whether an unbudt reac-and transport and modehng of both conservative and non-con- tor system is prone to water hammer is proposed. For the most servative tracers. common water hammer, steam bubbio collapse induced water hamme , six conditions must be met in ordor for one to occur.
NUREG/CR-6506: EMBRITTLEMENT DATA BASE, VERSION 1. These are: 1) the pipe must be almost honzontal, 2) the sub-WANG.J A. Oak Ridge Nabonal Laboratory. August 1997. coohng must be greater than 20 degrees C; 3) the L/D must be 220pp.9709120071. ORNL/TM 13327. A0413:068. Greater than 24; 4) the velocity must be low enough so that the Version 1 of the Embnttlement Data Base (EDB)is a compre' pipe does not run full, ie., the Froude number must be less hensive collection of data resulting from merging Verson 2 of than one; 5) there should be void nearby; 6) the pressure must the Power Reactor Embnttlement Data Base (PR EDB) and Ver' be hgh enough so that significant damage occurs, that is the son 1 of the Test Reactor Embnttlement Data Base (TR-EDB) pressure should be above 10 atmospheres. Recommendabons Fracture toeghness data were also integrated into Verson 1 of on how to avoid this kird of water hammer in both the design the EDB. For power reactor riata, the current EDB hsts 1,029 and the operation of the reactor system are made.
trarssition-temperature shift data points (321 from plates,125 from forgings,115 from correlation monitor matenals,246 from NUREG/CR-6523 V01: PROBABILISTIC ACCIDENT CONSE-welds, and 222 from heat-affected zone (HAZ) matenals) from OUENCE UNCERTAINTY ANALYSIS. Food Chain Uncertainty Charpy specmens that were Irradiated in 271 capsules from Assessment. Main Report. BROWN,J. United Kingdom.
101 commercial power reactors. For test reactor data, informa. GOOSSENS,LH.J4 KRAAN.B C.P.; et al. Delft University of ton is available for 1,308 different irradiated sets (352 from Technology. June 1997, 78pp. 9709020313. EUR 16771.
plates,186 from forgings,303 from correlation monitor maten. A0234.001, als,3% from welds, and 71 from HAZs) and 268 different irradi- The development of two new probabilishc accident conse-ated plus annoaled data sets (89 from plates,4 from forgings, quence codes, MACCS and COSYMA, was completed in 1990.
11 from correlaton monitor materials, and 164 from weld mate- These codes eshmate the consequence from the accid)ntal re-rials). The data files of EDB are given in dBASE format and can leases of radiological matenal from hypothesized accidents at be accessed with any perc.onal computer using the DOS or nuclear installatons. In 1991, the U.S. Nuclear Regulatory Com-WINDOWS operating system. A utihty program has been wntten mission and the Commission of the European Communities to invesbgate radiation embnttlement using this datt. base. began cosponsonng a joint uncertainty analysis of the two
l l
l Main Citations and Abstracts 7 codes. The ultimate ob)ective of this joint effort was to system- NUREG/CR-6531: EFFECTS OF RADIOACTIVE HOT PARTI-alcally develop credible and traceable uncertainty distnbutions CLES ON PlG SKIN. KAURIN,D.G.; BAUM.J W.; CARSTEN,A.L; for the respective code snput vanables A formal expert judg- et al. Brookhaven Natonal Laboratory. June 1997. 315pp.
ment elettaten and evaluabon process was identified as the 9710060475. BNL NUREG-52499. A0623:056.
best technology available for developing a library of uncertainty Tt e purpose of these studies was to determine the incidence distributions for these consequence parameters. This report to. and seventy of lesons resulting from very localized depositon cuses on the results of the study to develop distnbution for vark of dose to skin from small (< 0.5 mm) discrete radoactve par-ables related to the MACCS and COSYMA food chain models. teles as produced in the work environments of nuclear reactors.
Doth soil / plant transfer processes and radonuclide transport in Hanford mini-pags were exposed, both on and slightly off the animals were assessed. skin, to locahred repicate doses from 0.31 to 64 Gy (averaged over 1 CM(2) at 70 J' m depth unless noted otherwise) using NU'lEQ/CR-6523 V02: PROBABILISTIC ACCIDENT CONSE- Sc 46, Yb 175. Tm 170, and fissioned UC(2) isotopes having OUENCE UNCERTAINTY ANALYSIS, Food Chain Uncertainty maximum beta-partcle energies from about 0.3 to 3 MeV. Ery-Assessment.Appendees. DROWN.J. United Kingdom. thema and scabs (indicating ulceration) were scored for up to GOOSSENS,LHl; KRAAN.B C.P.; et al. Delft University of 71 days post irradiaton. The responses followed normal cumu-Technology. June 1997. 334pp. 9709020327. E8IR 16771. lative probability distributons, and therefore, no trus threshold A0233 001, could be defined. Hence.10 and 50% scab incidence rates See NUREG/CR-6523,V01 abstract. were deduced using probit analyses. The lowest dose which produced 10% incidence was about 1 Gy for Yb 175 (0.5 MeV NUREG/CR-6525: SECPOP90: SECTOR POPULATION, LAND maximum energy) beta partcle exposures, and about 3 to 9 Gy FRACTION, AND ECONOMIC ESTIMATION PROGRAM. for other isotopes. The histopathology of lesons was deter-HUMPHREYS S L. Sandia Nabonal Laboratones. mined at several doses. Single exposures to doses as large as ROLLSTIN.J.A. GRAM, Inc. RIDGELY,J.N. Divison of Systems 1,790 Gy were also given, and resutts were observed for up to Technology (Post 941217). September 1997. 441pp. 144 days post-exposure. Seventy of debiment was estimated by 9710070358. SAND 93-4032. A0641:125. analyzing the results in terms of leson diameter, persistence, in 1973 Mr. W. Athey of the Environmental Protechon Agency and infecton. Over 1,100 sites were exposed. Only two ex-wrote a computer program called SECPOP which calculated posed sites became infected after doses near 500 Gy; the le-population estimates. Since that time, two tNngs have changed sions healed quickly on treatmer t.
wNch suggested the need for updating the onginal program-more recent population censuses and the widespread use of NUREG/CR-6538: EVALUATION OF LOCA WITH DELAYED personal computers (PCs). The revised computer program uses LOOP AND LOOP WITH DELAYED LOCA ACCIDENT SCE-NARIOS. MARTINEZ GURIDl; SAMANTA.P.K.; CHU,T-L; et al.
the 1990 and 1992 Populabon Census informaton and runs on current PCs as "SECPOP90". SECPOP90 consists of two parts.
Brookhaven Natonal Laboratory. July 1997. 231pp.
9708060249. BNL NUREG-52528. 94698:022.
site and regonal. The site analysis provides populat on and eco-Genenc Safety issue 171 (GSI 171), Engineered Safety Fea-nomic data estmates for any locabon within the continental United States. Siting analysis is relatively fast running. The re' tures (ESF) Failure from a Loss Of Offsrte Power (LOOP) subse-quent to a Loss Of Coolant Accident (LOCA), deals with an ac-g'onal pcmon assesses site availability for different siting poicy crdent sequence in whch a LOCA is followed by a LOOP. This decisions; i e., the impact of available sites grven specifc popu-issue was later broadened to include a LOOP followed by a laton density entena witNn the continental United States. Re-LOCA. Plants are designed to handle a simultaneous LOCA and gional analysis is slow. This report compares the SECPOP90 LOOP. In tNs report, we address the unique issues that are in-populaton estimates and the nuclear power reactor hcensee- volved in LOCA with delayed LOOP (LOCA/ LOOP) and LOOP provided information. Although the source, and therefore, the with delayed LOCA (LOOP /LOCA) accident sequences, and de-accuracy of the hcensee informaton is unknown, tNs Compari- termine that such sequences and the specife concems raised sen suggasts SECPOP90 makes reasonable eshmates. as parrt of GSI-171 are not fully addressed in indrvidual Plant Ex.
NUREG/CR-6527: FINAL RESULTS OF THE XR21 BWR ME- " ** '**'*# " * * "**
TALLIC MELT RELOCATION EXPERIMENT. GAUNTT.R.O addressed more fully by IPEs than aro LOCA/ LOOP ones.
Sandia National Laboratones. HUMPHRIES,LL Science Apph.'-
LOCA/ LOOP accidents are analyzed further in tNs report by de-cabons International Corp. (formerly Science Applications, Iric.).
August 1997.177pp. 9708210414. SAND 971039. A0156:112. veloping event tree / fault-tree models to gaantify their contnbu-tions to core-damage frequency (CDF) in a pressunzed water This report documents the final resutts of the %21 boshn9 reactor and a boihng water reactor (PWR and a BWR). Engi-water reactor (BWR) metalhc melt relocation expenment, con- neenng evaluabon and judgements are used dunng quantifca.
ducted at Sandia National Laboratones for the U.S. Nuclear tion to estimate the unique conditions that anse in a LOCA/
Regulatory Commission. The object:ye of tNs expenment was to LOOP accident. The resutts show that the CDF contnbuten of investigate the material relocation processes and re'ocaten such an accident can be a dominant contnbutor to plant risk, patiways in a dry BWR core following a severe nuclear reacto' although BWRs are less vulnerable than PWRs, accident such as an urrecovered staton blackout accident. The imposed test conditions (what therma: state and the melt gen- NUREG/CR 6539: EFFECTS G FLUORIDE AND OTHER HALO-eration rates) simulated the conditions for the pontulated acci. GEN IONS ON THE EXTERNAL STRESS CORROSION dent scenano and the prototype design of the lower core test CRACKING OF TYPE 304 AUSTENITIC STAINLESS STEEL.
sects,n (in compositen and in geometry) ensured that thermal WHORLOW,K.M.: HUTTO,F.B. Affiliation Not Assigned. July maues and physical flow bamers were modeled adequately. 1997. 50pp. 9707240126. 93886:153.
The expenment has shown that, under dry core conditons, the The dnp procedure from ASTM C 692 95a was used to re-metalkc core materials that melt and drain from the upper core search the effect of halogens and inNbitors on the External regens can drain from the core reg >on entirely without formation Stress Corrosion Cracking (ESCC) of Type 304 stainless steel of robust coherent blockages in the lower core. Temporary as it apphes to NRC RG 1.36. The solutions used in this re-blockages that suspended pools of molten metal later melted, search were prepared using pure chnical reagents to simulate allowing the metals to continue draining dawnward. The test fa- the halogens and inhibitors found in sulation extraction solu-cihty and instrumentation are desenbed in detail The test pro- tions. The results indicated that sodium sihcate compounds that gression and results are presented and compared to MERIS were higher in sodium were more effectrve for preventing chlo-code analyses, nde-induceri ESCC in type 304 austenite stainless steel, Potas-
l l
8 Main Citations and Abstracts sium sitcate (all sihcate inhabitor) was not as effectue as Fatque damage causes continuous, cumulatwo merostruc-sodium sitcate. Lirnated teshng with sodium hydroxde (all- tural changes in matonals and the magnete properbes of steels sodium inhibitor) indcated that it may be effectwo as an inNb6- are sensitwo to these merostructural changes. TNs work there-tor. Fluonde, bromide, and iodde caused minimal ESCC whch fore focused on the telatonsNps between fatigue damage and could be effectwety inNbited by modum salcate. The additon of the measured magnetic properties of different steels under a fluonde to the chloride / sodium sehcate systems at the threshold vanety of fatigue conditons. The project also investgated the of ESCC appeared to have no synergiste effect on ESCC. The E
feasibihty and appicabikty of magnetc inspecten techrnques for mass ratio of sodium + sitcate (mg/kg) to chloride (mg/kg) at non-destructue evaluation of fatigue damage. From the results the lower end of the NRC RG 1.36 Acceptatahty Curve was not of a senes of fabgue tests, conducted on different steels under suffcient to prevent ESCC using the methods of this research. both low cycle and Ngt> cycle fatque conditons, the magnetc NUREG/CR4541 R02: PHENOMENA IDENTIFICATION AND properbes, such as coercswty, remanence and Barkhausen RANKING TABLES FOR WESTINGHOUSE AP600 SMALL effect, were found to change systematcally with fatigue BREAK LOSS-OF COOLANT ACCIDENT, MAIN STEAM LINE damage. The magnetc properties showed agnifca :t changes, BREAK, AND STEAM GENERATOR TUBE RUPTURE SCE. especialty dunrg early stage of the fabgue and also at the end NARIOS. WILSON,0 E,; FLETCHER C.D.; DAVIS.C.B.; et al. of fatgue lifebme. An approximately knear relatonsNp between Idaho Natonal Engineenng & Environmental Laboratory. June the mechancal modulus and magnets romanence was ob-1997,260pp. 9709030400. INEL-94/OO61. A0235:298. served and was explained by a model developed in this study to This report documents the resutts of Phenomena identifca. describe the dynamic changes in the magnetic and mechanical l ton and Ranking Table (PIRT) efforts for the Weshnghouse properties. The results of this research demonstrated that mag-AP600 reactor. The purpose of tNs PIRT la to ident fy important netic measurements are suitable for non-destructwo evaluaton phenomena 30 that they may be addressed in both the experi- of fatigue damage in steets such as A5338 steel and Cr-Mo mental programs and the RELAPS/ MOD 3 systems analysis steels. These magnetc measurement techniques have been in-computer code, The responses of AP600 dunng small break corporated into instrumentaton for in-situ evaluaton of steel loss-of coolant accident, main steam kne break, and steam gerb structures and components.
erator tube rupture acc dent scenarcs were evaluated by a committee of thermal-hydrauhc experts. Committee membersNp NUREG/CR-6558: NRC ANTITRUST LICENSING ACTIONS, included idaho Nabonal Engineenng and Environmental Labora- 1978-1996. MAYER S.J.; SIMPSON,J.J. Oak Rdge National tory staff and recognized thermal-hydraubc experts from outsde Laboratory. September 1997.141pp. 9710070363. ORNL/TM-of the laboratory. Each of the accident scenanos was subdwid- 13452. A0642:273.
ed into separate, sequenbal penods or phases. Within each NUREG.0447 "Anttrust Review of Nuclear Power Plants,"
phase, the plant behavior is controlled by, at most, a few ther. was pubhshed in May 1978 and includes a compilaton and dis-mal.hydrauhc processes. The committee identified the phenonw cussion of U.S. Nuclear Regulatory Commission (NRC) proceed-ena influencing those processes, and ranked the influences as ings and actNity invchnng the NRC's competitwo review pro-being of high, medium, low, or insgnificant importance. The pri-mary product of tNs effort is a senes of tables, one for each gram through February 1978. NUREG-0447 is an update of an eartier discussion of the NRC's antitrust review of nuclear power phase of each accident scenano, desenbing the thermal-hydrau-bc phenomena judged by the committee to be important, and lants, NR AlG-001, "The US Nuclear Regulatory Commisson's the relative ranking of that importance. The ratonales for the Anttrust Review of Nuclear Power Plants: The Conditoning of phenomena selected and their rankings are provided. Licenses," which reviewed the Commisson's antitrust review functon from its incepton in December 1970 through Apnl NUREG/CR-6557: DEVELOPMENT OF THE MAGNESCOPE AS 1976. This report summanzes the support provided to NRC staff AN INSTRUMENT FOR IN SITU EVALUATION OF STEEL in updating the compilation of the NRC's antitrust licensing COMPONENTS OF NUCLEAR SYSTEMS. JILES,0 Ca Bl,Y4 review actuibes for commercial nuclear power plants that have BINER,S.B. Iowa State Unw., Ames, lA. August 1997. 64pp. occurred since February 1978.
9708290226. A0232:264.
Secondary Report Number index This index lists, in alphabetical order, the performing organization-issued report codes for the NRC contractor and international agreement reports in this compilation. Each code is cross-referenced to the NUREG number for the report and to the 10-digit NRC Document Control System accession number, MCONDARY MPORT NUteMR MPORT NUtsOER SECONDARY REPORT nut 00ER MPORT NUseMR ANL AA 30 NUREG/CR-4012 V04 NEA/CSNt/R(97)4 NUREG/CP4159 BNL NUREG42496 NUREG/CR4451 ORNL4909 NUREG/CR4506 BNL-NUREG42499 NUREG/CF44531 ORNL/TM 11566 NUREG/CA-5591 V07 N2 BNL.NUREG 52500 NUREG/CR4464 ORNL/TM-13205 NUREG/CR4454 BNL.NUREOr52526 NUREG/CR4536 ORNL/TM-13327 NUREG/C644506 CONF.960715 NUREG/CP.0153 OANL/TM 13452 NUREG/CR4658 EUR 16771 NUREG/CR4523 V01 ORNL/TM-9593 NUREG/CR4219 V13 N1 EUR 16771 NUREG/CR4523 V02 SAND 934032 NUREG/CR4525 INEL.94/0061 NUREG/CR4541 R02 SAND 97 0335 NUREG/CR4523 V01 INEL 94/0276 NUREG/CR-5229 V09 EANO97 0335 NUREG/CR 6523 V02 INEL-96/0219 NUREG/CR4476 SANO971039 NUREG/CR4527 i
9
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Personal Author Index This index lists the personal authors of NRC staff, contractor, and international agreement reports in alphabetical order. Each name is followed by the NUREG number and the title of the report (s) prepared by the author, if further information is needed, refer to the main cita-
, tion by the NUREG number, AmeOTT Mt sURTTJ.D.
NUREGICR4523 V01: PROBABlUSTIC ACCIDENT CONSEQUENCE NUREG/CR4541 R02: PHENOMENA IDENTIFICATON AND RANKING UNCERTAINTY ANALYSl3 Food Chaan Uncertamty Assessm nt. Main Tt.BLES FOR WESTINGHOUSE ape 00 SMALL BREAK LOSSCF.
Report COOLANT ACCIDENT, MAIN STEAM UNE BREAK, AND STEAM NURtG/CR4523 V02: PROBASILISTO ACCIDENT CONSEQUENCE GENERATOR TUBE RUPTURE SCENARIOS.
UNCERTAINTY ANALYSIS Food Chain Uncertainty AssessmentApperulices. CARRfCOJ.8.
NUREG-1556 V2 DRF FC: CONSOUDATED GUIDANCE ABOUT MATE-ARCHAMSEAUJ.O. RIALS UCENSES. Program Specmc Guidance About industnal Radio 0-NUREG/CR4531: EFFECTS OF RADCACTIVE HOT PARTICLES ON raphy Uconses. Draft Report For Use And Comment PlO SKIN 4 CARSTEN,A.L OYMES.D.A. NUREG/CR4531: EFFECTS OF RaDCACTIVE HOT PARTICLES ON NUREG.1601: CHEMICAL PROCESS SAFETY AT FUEL CYCLE FAClu. PlG SKIN CHEN,0.
AZARM.MA NUREG/CR.6497: DATA COLLECTION AND FIELD EXPERIMENTS AT NUREG/CR4451: A SAFETY AND REGULATORY ASSESSMENT OF THE APACHE LEAP RESEARCH SITE.May IFd5 1996, GENEHC BWR AND PWR PERMANENTLY SHUTDOWN NUCLEAR N R G/CR4538: EVALUATON OF LOCA WITH DELAYED LOOP AND BANDYOPADHYAY,K LOOP WITH DELAYED LOCA ACCIDENT SCENAROS.
NUREG/CR4464: AN EVALUATION OF METHODOLOGY FOR SEIS-U '556 V2 DAF FC: CONSOUDATED GUIDANCE ABOUT MATE-ALWR TS U E OF RENCE AT RIALS LICENSESProgram Specific Guidance About industnal Radiog-BASSETT RL raphy Ucenses. Draft Report For Use And Comment NUREG/CR4459: FIELD STUDIES AT THE APACHE LEAP RESEARCH URE /C'R4523 V01: PROBABluSTIC ACCIDENT CONSEQUENCE NU EG/ LLE A FE EX E E TS AT UNCERTAINTY ANALYSIS Food Chain Uncertamty Assessment. Main THE APACHE LEAP RESEARCH SITE.May 1995 1996 NUR CR4523 V02: PROBABluSTIC ACCIDENT CONSEQUENCE BAUM).W. ANALYSIS. Food Chain Uncertamty UNCERTAINTY NUREG/CR4531 EFFECTS OF RADIOACTIVE HOT PARTICLES ON AssessmentAppendices.
PIG SKIN-CORWIN,WA gg,y NUREG/CR.5591 V07 N2: HEAVY-SECTON STEEL IRRAD(ATION I NUREG/CR6557: DEVELOPMENT OF THE MAGNESCOPE AS AN IN- PROGRAM. Semiannual Progress Report For Apnl Through September STRUMENT FOR IN SITU EVALUATON OF STEEL COMPONENTS 18 "
OF NUCLEAR SYSTEMS.
' DAVOSON,G.R. J DINER,S.B'CR4557:
NUREG/ DEVELOPMENT OF THE MAGNESCOPE AS ANNUREG/CR4459 IN- FIELD STUDIES AT THE APACHE LEAP MLAHCH SHE IN SUPPORT OF ALTERNATIVE CONCEPTUAL MODELS STRUMENT FOR IN SITU EVALUATON OF STEEL COMPONENTS NUREG/CR4497: DATA COLLECTON AND FIELD EXPERIMENTS AT OF NUCLEAR SYSTEMS. THE APACHE LEAP RESEARCH SITE.May 1995 1996.
900CHER,T.J. DAVIS.C.B.
NUREG/CR4541 R02: PHENOMENA IDENTIFICATON AND RANKING NUREG/CR-6541 R02: PHENOMENA IDENTIFICATON AND RANKING TABLES FOR WESTINGHOUSE AP600 SMALL BREAK LOSS-OF. TABLES FOR WESTINGHOUSE AP600 SMALL BREAK LOSS-OF.
COOLANT ACCIDENT. MAIN STEAM UNE BREAK, AND STEAM COOLANT ACCIDENT, MAIN STEAM UNE BREAK, AND STEAU GENERATOR TUBE RUPTURE SCENARIOS- GENERATOR TUBE RUPTURE SCENARIOS.
BRAMWELL,0. DAVIS,R.E.
NUREG/CR4478-. MOTOR 4PERATED VALVE (MOV) ACTUATOR NUREG/CR4451: A SAFETY AND REGULATORY ASSESSMENT OF MOTOR AND GEARBOX TESTING- GENERIC BWR AND PWR PERMANENTLY SHUTDOWN NUCLEAR POWER FLANTS.
BROWNJ.
fGEG/CR4523 V01: PROBABluSTIC ACCIDENT CONSEQUENCE DEWALL.K.G.
UNCERTAINTY ANALYSIS. Food Cham Uncertamty AssessmentMain NUREG/CR4478: MOTOR OPERATED VALVE (MOV) ACTUATOR N CR-6523 V02' PROBAB4USTIC ACCOENT CONSEQUENCE UNCERTAINTY ANALYSIS. Food Cham Uncertamty ELLIOT,8.J.
AssesernentAppendices. NUREG-1612. STATUS REPORT: REACTOR VESSEL INTEGRITY DA.
TABASE.
NUREG/CR.4012 V04: REPLACEMENT ENERGY COSTS FOR NUCLE- FADOEN.M.A.
AR ELECTRICITY GENERATING UNITS IN THE UNITED STATES: NUREG4525 V02 R05: SAFEGUARDS
SUMMARY
EVENT LIST 1997 2001. (SSEL).Jarwary 1,1990 Through December 31,1996.
11
12 Personal Author index l i
l FAIRSANKS.CJ. HUMPHREYS.S.L NUREG 1612: STATUS REPORT: REACTOR VESSEL INTEGRITY DA- NUREG/CR4525: bECPOP90 SECTOR POPULATION. LAND FRAC.
l TABASE. TON, AND ECONOMC ESTIMATION PROGRAM.
FIRST,M.W. HUMPHRIES.LL l NUREG/CP4153. PROCEEDINGS OF THE 24TH DOE /NRC NUCLEAR NUREG/CR4527: FINAL RESULTS OF THE XR21 BWR METALLO Alk CLEANING AND TREATMENT CONFERENCE. Heed in PoMand- MELT RELOCATION EXPERIMENT.
j Ore 9eri, July 15-18,1996.
- '. ETCHER.C D NUREG/CRf539: EFFECTS OF FLUORIDE AND OTHER HALOGEN NUREG/CR4541 R02: PHENOMENA IDENTIFICATION AND RANKING TABLES FOR WESTINGHOUSE AP600 SMALL BREAK LOSS-OF-ONS ON THE MERNAL SMESS MOSON CRACM W COOLANT ACCOENT, MAIN STEAM LINE BREAK, AND STEAM TYPE 304 AUSTENfilC STAINLESS STEEL.
GENERA'OR TUBE RUPTURE SCENAROS- ILLMAN,W.A.
FUHRMANKM. NUREG/CR4497: DATA COLLECTION AND FIELD EXPERIMENTS AT NUREG/CR 5229 V09. FIELD LYSIMETER INVESTIGATONS: LOW. THE APACHE LEAP RESEARCH SITE.May 1995 1996.
LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR U G/CR 5229 V09- FIELD LYSIMETER INVESTKiATONS: LOW.
GAUNTT R.O. LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR NUREG/CR4527: FINAL RESULTS OF THE XR21 BWR METALLC FISCAL YEAR 1996 Annual Report MELT RELOCATON EXPERIMENT, JtLES,0.C.
OEDOtSAM. NUREG/CR4557: DEVELOPMENT OF THE MAGNESCOPE AS /.N IN-NUREG/C,+4459 FIELD STUDIES AT THE APACHE LEAP RESEARCH STRUMENT FOR IN SITU EVALUATION OF STEEL COMPONENTS SITE IN SUPPORT OF ALTERNATIVE CONCEPTUAL MODELS- OF NUCLEAR SYSTEMS.
GOOSSENS.LH.J. JONES,J.A.
NUREG/CR4523. V01: PROBABluSTIC ACCIDENT CONSEQUENCE NUREG/CR4523 V01: PROBADIUSTC ACCOENT CONSEQUENCE UNCERTAINTY ANALYSISFood Cham Uncertamty Assessment.Mam UNCERTAINTY ANALYSIS. Food Cham Uncertamty AssessmentMem N RAN ANAL S S cod m Unc NUR CR4523 V01 PROBABluSTIC ACCOENT CONSEQUENCE Assessment Appendees. UNCERTAINTY ANALYSIS. vood Cham Uncertamty Assessment.Appsmicas.
ORIFFITH,P.
NUREG/CR4519. SCREENING REACTOR S7c.AM/ WATER PIPING KAM,F.S.K.
SYSTEMS FOR WATER HAMMER. NUREG/CR4454: POOL CRITICAL ASSEMBLY PRESSURE VESSEL FACIL'TY BENCHMARK.
OROVE.E.J.
NUREG/CR4451: A SAFETY AND REGULATORY ASSESSMENT OF KANA.D.D.
GENERC BWR AND PWR PERMANENTLY SHUTDOWN NUCLEAR NUREG/CR4464 AN EVALUATION OF METHODOLOGY FOR SEIS-POWER PLANTS. MC QUAUFICATON OF EQUIPMENT. CABLE T3AYS, AND DUCTS IN ALWR PLANTS BY USE OF EXPERIENCE D/1A.
NUREG/CR-4012 V04. REPLACEMENT ENERGY COSTS FOR NUCLF. KAURIN,D.G.
AR ELECTRICITY. GENERATING UNITS IN THE UNITED STATES- NUREG/CR.6531: EFFECTS OF RADCACTI' E HOT PARTOLES ON 1997-2001. PIG SKIN.
OU2 MAN,A.G.
KENNEDY.R.P.
t"JREG/CR4459: FIELD STUDIES AT THE APACHE LEAP HESEARCH NUREG/CR4464. AN EVALVATON OF METHODOLOGY FOR SEIS-SITE IN SUPPORT OF ALTERNATIVE CONCEfrTUAL a4ODELS' MIC OUAUFICATION OF EOutPMENT, CABLE TRAYS, AND DUCTS HARDIRE.L IN ALWR PLANTS BY USE OF EXPERIENCE DATA.
NUREG/CR4459: FIELD STUOIES AT THE APACHE LEAP RESEARCH SITE IN SUPPORT OF ALTERNATIVE CONCEPTUAL i,ODELS K R AAN,5.C.P.
NUREG/CR4497: DATA COLLECTION AND FIELD EXPERIMENTS AT NUREG/CR4523 V01: PROBABluSTIC ACCIDENT CONSEQUENCE THE APACHE LEAP RESEARCH SITE.May 1995 1996. UNCERTAINTY ANALYSISFood Chain Ureertamty AssessmentMam Report HARPEM,F.T. NUREG/CR4523 V02. PROBABluSTIC ACCIDENT CONSECUENCE NUREG/CR4523 V01: PROBABluSTIC ACCIDENT CONSEQUENCE UNCERTAINTY ANALYSIS. Food Cham Uncertamty UNCERTAINTY ANALYSISFood Cham Uncertamty AssessmentMam Assessment.Appendees.
NUR CP 6523 V02: PROBABluSTIC ACCIDENT CONSEQUENCE KUO,P.T.
UNCEF . AINTY ANALYSIS. Food Cham Uncertamty NUREG-1611: AGING MANAGEMENT OF NUCLEAR POWER PLANT Asse mentAppendcas- CONTAINMENTS FOR LICENSE RENEWAL HASKIN F.E. Lgg,p.D.
NUREG/CR4523 V01. PROBABluSTIC ACCIDENT CONSEQUENCE NUREG.1612. STATUS REPORT: REACTOR VESSEL INTEGRITY DA-UNCERTAINTY ANALYSISFood Cham Uncertamty AssessmentMem TABASC.
NUR CR4523 V02: POOBABiUSTIC ACCIDENT CONSEQUENCE
- UNCERTAINTY LEE.S.S.
ANALYSIS. Food Chain Uncertamty
- "' ** NUREG 1611: AGING MANAGEMENT OF NUCLEAR POWER PLANT CONTAINMENTS FOR UCENSE RENEWAL HILLS R.O.
NUREG/CA-6437: FLOW AND TRANSPORT AT THE LAS CRUCES UU,W.C.
TRENCH SITE: EXPERIMENT 11B. NUREG.1611: AGING MANAGEMENT OF NUCt. EAR POWER PLANT CONTAINMENTS FOR UCENSE RENEWAL HOMA.S.C.
NUREG/CR4523 V01: PROBABluSTIC ACCIDENT CONSEQUENCE MARTINET GURIDI UNCERTAINTY ANALYSIS Food Cham Uncertamty AssessmentMan NUREG/CR4538. EVALUATION OF LOCA WITH DELAYED LOOP AND Report LOOP WITH DELAYED LOCA ACCIDENT SCENARIOS.
NURtG/CR4523 V02: PROBABluSTC ACCIDENT CONSEQUENCE UNCERTAINTY ANALYSIS. Food Chem Uncertamty MAYER,SJ.
AseessmentAppendcas. NUREG/CR4558. NRC ANTITRUST LICENSING ACTIONS, 1970-1996
- - +..n.. c+-. s. + .-.c. ..w. ws -=a.,- -tu. au _ .ma.-w. . - a. a n s + - . .au. e ~. .. .
1 l
i l
l l
Personal Author Index 13 HCCONNELLJ.W. SCHIFF,AJ. -
NUREG/CR4229 V09: FIELD LYSIMETER INVESTIGATIONS: LOW. NUREG/CR4464: AN EVALUATON OF METHODOLOGY FC41 SEIS-LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR MO QUALIFICATON OF EQUIPMENT, CABLE TRAYS, AND DUCTS FISCAL YEAR 1996.Arn.at Report . AN ALWR PLANTS P USE OF EXPERIENCE DATA.
MEDOFFJ. .
SCHWARTZ,M.
NUREG-1612. STATUS REPORT: REACTOR VESSEL INTEGRITY DA- NUREG-1556 V2 DRF FC- CONSOLIDATED GUIDANCE ABOUT MATE. ;
TABASE. RIALS LICENSES Pro 9 ram Specrhc (Juldence About industnal Radog.
raphylicenses. Draft Report For Use And Commer4.
I NUREGICP.0161: TRANSACTIONS OF THE TWENTY FIFTH WATER 88MP90NJJ.
REACTOR SAFETY INFORMATION MEETING. NUREG/CR4558. NRC ANTITRUST LICENSING ACilONS, 1976 1996.
MURRELL.M.T. STEPHENS,D.M.
NUREG/CR4497: DATA COLLECTION AND FIELD EXPERIMENTS AT NUREG/CR4497: DATA COLLECTION AND FIELD EXPERIMENTS AT
- . THE APACHE LEAP RESEARCH SITE.May 1995 1996. THE APACHE LEAP RESEARCH SITE.May 1995 9996. I NELL88,0. STROSNIDERJ.R.
, NUREG-1556 V2 DRF FC CONSOLIDATED GUIDANCE ABOUT MATE. NUREG-1612 STATUS REPORT: REACTOR VESSEL INTEGRITY CA-
- RIALS LICENSES. Program Specife Gudence About 'rdust6al Radiog- TABASE.
rephy Licensee. Dratt Report For Use And Comment STRUCKWEYER R.
NEUMAN,S.P. NUREG-0637 V17 NO2- NRC TLD DIRECT RADIATION MONITORING NUREG/CR4459: FIELD STUDIES AT THE APACHE LEAP RESEARCH NETWORK. Progress Report April June 1997.
SITE IN SUPPORT OF ALTERNATIVE CONCEPTUAL MODELS.
NUREG/CR4407: DATA COLLECTION AND FIELD EXPEHIMENTS AT SULLIVAN,T.M.
. THE APACHE LLAP REoEARCH SITE.May 1995 + 1996. NU91EG/CR4229 V09: FIELD LYSIMETER INVESTIGATONS. LOW-LEVEL WASTE DATA BASE DEVELOPMENT PROCRAM FOR PENNELL,W.E. FISCAL YEAR 1996 Annual Report NUREG/CR.4219 V13 N1: HEAVY SECTION STEEL TECHNOLOGY PROGRAM. Semiannual Progress Report For October 1995 - March THOMASSON,MJ.
1996, NUREG/CR4497: DATA COLLECTON AND FIELD EXPER:MENTS AT
- THE APACHE LEAP RESEARCH SITE May 1995 1996.
PISKURA,D.
NUREG.1556 V2 DRF FC: CONSOLIDATED GUIDANCE ABOUT MATE- THOMPSON.DL RIALS LICENSES Program Specific Gukience About Indus'nal Radiog NUREG/CR44S9: FIELD STUDIES AT THE , ' ACHE LEAP RESEARCH raphy Ucanoes. Draft Report For Use And Comment SITE IN SUPPORT OF ALTERNATIVE C MPTUAL MODELS.
NUREG/CR-6497: DATA COLLECTON Al 0
- iLD EXPERIMENTS AT
$ POOLE,A.S. THE APACHE LEAP RESEARCH SITE.May Iv95 1996.
NUREG/CR4508. COMPONENT UNAVAILABILITY VERSUS INSERV.
ICE TEST UST) INTERVAL.EVALUATONS OF COMPONENT AGING TOMPKINS.M.M.
EFFECTS WITH APPUCATIONS TO CHECK VALVES. NUREG/CR 4012 V04: REPLACEMENT ENEPGY COSTS FOR NUCLE.
AA ELECTRICITV. GENERATING UNITS IN THE (fNITED STATES:
PRENDERGAST,K. 1997 200t, NUREG-1556 V2 DRF FC CONSOLIDATED GUIDNICE ABOUT MATE-RIALS UCENSES Program Specthe Guidance About industnal Ramg. TRAVIS,RJ.
raphy Licenses. Draft Repurt For Use And Comment NUREG/CR4451: A SAFETY AND REGULATORY ASSESSMENT OF GENERIC BWR AND PWR PERMANENTLY SHUTDOWN NUCLEAR REMEC,L POWER PLANTS.
NUREG/CR 6454. POOL CRITICAL ASSEMBLY PRESSURE VESSEL FACILITY BENCHMARK. VANKUlKENJ.C.
NUREG/CR-4012 V04: REPLACfMENT ENERGY COSTS FOR NUCLE.
RIDGELYJ.N. AR ELECTRICITY./3ENERATING UN;TS IN THE UN:TED STATES:
y NUREG/CR4525: SECPOP90 SECTOR POPULATON, LAND FRAC. 1997 2001.
TION AND ECONOMIC ESTIMATON PROGRNA.
VESELY.W.E.
ROGERS.R.D. NUREG/CR4508: COMDONENT UNAVAILABlUTY VERSUS INSERV.
NUREG/CR-5229 V09 F: ELD LYSIMETER INVESTIGATONS: LOW. ICE TEST UST) INTERVAL:EVALUATONS OF COMPONENT AGING 1EVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR EFFECTS WITH APPUCATONS TO CHECK VALVES.
HSCAL YEAR 1996 Annual Report.
VINSON,J.
2 ROLLSTINJA NUREG/CR4437: FLOW AND TRANSPORT AT THE LAS CRUCES
' NUREG/CR6525: SECPOP90- SECTOR POAULATON, LAND FRAC- TRENCH SITE: EXPERIMENT 118.
TION, AND ECONOMIC ESTIMATON PROGRAM.
WANO,J.A.
ROODA NUREG/CR.6506: EMBRITTLEMENT DATA BASE. VERSION 1.
NUREG/CR4523 V01: PROBADIUSTIC ACCIDENT CONSEQUENCE UNCERTAINTY ANALYSISFood Chain Uncerterty AssessmentMaen WATKINSJ.C.
Report NUREG/CR4478: MOTOROPERATED VALVE (MOV) ACTUATOR NUREG/CR4523 V02: PROBABluSTIC ACCOENT CONSEOUENCE MOTOR AND GEARBOX TESTING. .
UNCERTAINTY ANALYSIS. Food Cham- Oncertamty AsseemmentAppendices. WHITE,D.
NUREG-1556 V2 DRF FC: CONSOUDATED GUIDANCE ABOUT MATE.
SAMANTA,P.K. .
RfALS UCENSESProgrem Spoofic Guidance About industnal Radio 9-NUREGIC46538 EVALUAT'r1N OF LOCA WITH DELAYED LOOP AND raphy Ocenses. Draft Report For Use And Comment.
LOOP WtTH DELAYED LOCA ACCIDENT SCENAROS.
- WHITTENJ.
SANFORD W.E. .
NUREG.15FS V2 DAF FC' CONSOUDATED GUIDANCE ABOUT MATE.
i NUREG/CR 5229 V09: FIELD LYSIMETER INVFSTIGATONS: LOW. R!ALS UCENGES. Program Spec % Guidance About industrial Radog-4 LEVEL WASTE ' DATA BASE DEVELOPMENT PROGRAM FOR raphy Ucenses. Draft Report Fr Use And Comment
- FISCAL YEAR 1996. Annual Report WHORLOW,K.M.
SCNAEPER.C.W. NUREG/CR4539: FFFECTS OF FLUORIDE AND OTHER HALOGEN NUREG/CR.6531: EFFECTS OF RADIOACTIVE HOT PARTICLES ON ONS ON THE EXTERNAL STRESS CORROSION CRACKING OF PC SKIN. TYPE 304 AUSTENITIC STAINLGG STEEL
~ ,-
\
l i
14 Personal Author Index WICHMAN,KA NUREG/CR4407: DATA COLLEJrlON AND FIELD EXPERIMENTS AT NUREG-161P STATUS REPORT: REACTOR VESSEL INTEGRITY DA- THE APACHE LEAP RESEARCH SITE May 1995 1996.
TADASE.
Y ANG.J.W.
N E CR4437: FLOW AND TRANSPORT AT THE LAS CRUCES NUREG/CR4538: EVALUATION OF LOCA W"TH DELAYED LOOP AND TRENCH SITE EXPERIMENT 118. LOOP WITH DELAYED LOCA ACCIDENT SCENARIOS.
NUREG/CR4459 flEL9 STUDIES AT THE APACHE LEAP RESEARCH SITE IN SUPPORT OF ALTERNATIVE CONCEPTUAL MODELS. YOUNG,MR HUREG/CH4407: DATA COLLECTION AND FIELD EXPERIMENTS AT NUREG/CR 6437: FLOW AND TRANSPORT AT THE LAS CRUCES THE APACHE LEAP RESEARCH SITE.May 1995 1996. TRENCH SITE- EXPERIMENT 168.
WILSON,G.L NUREG/CR4541 402: PHENOMENA IDENTIFICATION AND RANKING D b TABLES FOR WESTINGHOUSE AP600 SMALL BREAK LOSSOF. NUREG/CR4573 V01: PPOOASIUSTIC ACCIDENT CONSEQUENCE COOLANT ACCIDENT, MAIN STEAL 1 LINE DREAK, AND STEAM UNCERTAINW ANALYCIS. Foot Crwn Uncertartty AssessmenLMan GENERATOR TUBE RUPTURE SCEN ARIOS. Report NUREG/CR4523 V02: PROF JluSTIC ACCIDENT CONSEQUENCE
^ '
/ 9. FIELD STUDIES AT THE APACHE LEAP RESEARCH SITE IN SUPPORT OF ALTERNATIVE CONCEPTUAL WJOELS.
l
Subject index This index was developed from keywords and word strings in titles and abstracts. During this development period, there will be solne redundsney, which will be removed later when a rea-sonable thesaurus has been developed through experience. Suggestions for improvements Ore welcome.
ALWR Che A Uvo i NUREGIC34446*; AN EVALUATION C* METHODO!OGY FOft SEIS. NUREG/CR4608 OOMPONENT UNAVAltABILITY VERSUS INSERV.
MC QUALIFICATION OF Et,UIPMENT. CABLE TRAYS, /,ND DUCTS CE TEST (IST) INTERVAL EVALUATIONS OF COMPONENT AGING IN ALWR PLANTS BY USE OF EXPERIENCE DATA [FFECTS WITH APPLCATCNS TO CHECK VALVES.
Aceteent Soonerlo Chem 4 eel Procese Setety NUREG/CR4538 EVALUATION OF LOCA WITH DELAYED LOOP AND NUREG 1601: CHU81 CAL PROCESS SAFETY AT FUEL CYCLE FACILL LOOP WITH DELAYED LOCA ACC"Of NT SCENARIOS TIE 3 Actuotor Goerbos Cmle Architeetwo NURE G/CR4478 MOTOR-OPERATED YALVE (MOV) ACTUATOR NUREG/CP-0169. PROCEEDINGS OF THE OECD/CSNI WORKSHOP MOfDR AND GEARBOX TESTING ON TRANSIENT THERMAL HYDRAULC AND NEUTRONC CODES REQUIREMENT $ He6d in Annapoles,Meryle% USA.Novemter 64.
Adv6uy Commettee On Nuoteer Weste 1996.
NUREG 1423 V07: A COMPILATION Or REPORTS OF THE ADVISORY d COMMITTEE ON NUCLE AR WASTE. July 1996. June 1997. Construction Permit N'JREG/CR4SL8 NRC ANTITRUST LICENSING ACTIONS, 1978 1906 Ag6ng NUREG 1611' AGING MANAGEMENT r> NUCLEAR POWER PLANT Conteenment Structure CONTAINMENTS FOR LCENSE FtENEWAL NUREG.1611: AGING MANAGEMENT OF NUCLEAR POWER PLANT NUREG/CR4506- COMPONENT UNAVAll ABILITY VERBUS INSERV- CONTAINMENTS FOR LCENSE RENEWAL.
ICE TEST (IST) INTERVAL EVALUATIONS OF COMPONENT AGING EFFECTL WITH APPLICATIONS TO CHECK VALVE 5 Core Degreestlen NUREG/CR4627 FINAL RESULTS OF THE XR21 BWR METALLIC Air Permesholety MELT RELOCATION EXPERIMENT.
NURf G/CR-6459 FIELD STUDIEli AT THE APACHE LEAP RESEARCH SITE IN SUPPO'IT OF ALTERNATIVE CONCEPTUAL MODELS. Mte Collection NURLG/CR449't. DATA COLLECTION AND FIELD EXPERIMENTS AT I4UREG/CR4497: DATA COLLECTKA AND FIELD EXPERIENTS AT THE APACHE LEAP F4ESEARCH SITE May 1996 1996 THE APACHE LEAP RESEARCH SITE May 1995 1996.
Antitruet E-. ..: L.,
NUREG/C54 6558. NRC ANTITRUST LICENSING ACTIONS, 1978 1996. NUREG.1496 V01: FINAL GENERC ENVIRONMENTAL IMPACT ST ATE-f MENT sN SUPPORT OF RULEMAKING ON RADtOLOGCAL CFilTE.
APeche EteP HlA FOR LICENSE TERMINATION OF NRC-LICENSED NUCLEA'1 NUREG/CR4459 FIELD STUDIES AT THE APACHE LEAP FIESEARCH F ACIUTIES Mem ReportFinal Report SITE IN SUPPORT OF ALTE RNATIVE CONCEPTUAL MODELS. NUREG 1496 V02 FINAL GENERC ENVIRONMENT AL IMPACT STATE-NUREG/CR4u?. DATA COLLECTION ANE' Fl[LD EXPERIMENTS AT MENT IN SUPPORT OF RULEMAKING ON RADIOLOGICAL CRITE-k THE APACHE LEAP RESEARCH DITE May 1995 1966 HLA FOR LCENSE TERMINATION OF NRC LCENSED NUCLEAR F ACILITIES Appendices A And B Final Report Austentt6e Steintees Stool NUREG-1496 V03 FINAL GENERC ENVIRONMENTAL IMPACT STATE.
NUREG/CR4639 EFFECTS OF FLUORIDE AND OTHEF4 HALOGEN MENT IN SUPPORT OF RULEMAKING ON RADIOLOGICAL CRITE-IONS ON THE EXTERNAL STRESS CORROSION CRACKING OF Rin FOR LCENSE TERMINATION OF NRC-L%ENSED NUCLEAR TYPE 304 AUSTENITC STAINLESS STEEL. FACILITIEC Appen(ces C.H Fnal Report NUREG/CP 0163. PROCEEDINGS OF THE 24TH DOE /NRC NUCLEAR SWR AIR CLEANING AND TREATMENT CONFERENCE Held in Portland, NUREG/CR4461: A SAFETY AN'1 REGULATORY ASSESSMENT OF Oregm, My 16-18,1996.
GENERC BWR AND PWR PERMANENTLY SHUTDOWN NVOLEAR NUREC/CR4451: A SAFETY AND REGULATORY ASSESSMENT OF SCWER PLANTS. GENERIC BWR AND PWR PERMANENTLY SHUTC'MN NUCLEAR HUREG/CR4527: FINAL RESULTS OF THE AR24 BWR METALLIC POWER PLANTS.
MELT RELOCATION EXPERIMENT.
Decontamineteo9 Soli 6ng Water Reestor NUREG/CP 0t$3. PROCEEDINGS OF THE 24TH DOE /NRC NUCLEAR NUREG/CR44$1: A SAFETY AND REGULATORY ASSESSMENT OF AIR CLEANING AND TREATMENT CONFER 6NCE. Held in Portland.
GENERC BWR AND PWR PERMANENTLY SHUTDOWN NUCLEAR Oregon, July 16 18,1996.
POWER PLANTS.
NUREG/CR4S27. FINAL RESULTS OF THE XR21 BWR METALLC Deee Limit MELT RELOCATION EXPEPIMENT. NUREG/CR4531: EFFECTS OF RADIOACTIVE HOT PARTICLES ON PIG SKIN.
CahoeTroy NUREQ/CRf t64, AN EVALUATCid OF METHODOLOGY FOR SEIS. Doelme.ty MC OUALIFICATION OF EQUlPMENT,OABLE TRAYS, AND DUCTS NUREG/CR 4531: EFFECTS OF RADIOACTIVE HOT PARTCLES ON IN ALWR PLANTS BY USE OF EXPERIENCE DATA. PIG SKIN.
Corteneetten Duct NUREG 1462 Soi: FINAL CAFETY EVALUATION REPORT RELATED NUREG/CR4464; AN EVALUATION OF MSHOCOLOGY FOR SEIS.
TO THE CERTIFICATION OF THE SYSTEM 80 + DESIGN.Dockel No. MIC OUALIFICATION OF EQUIPMENT,CAME THAYS, AND DUCTS 62 0024Asee Drown Boven Combustion Enyncering) IN ALWR PLANTS BY USE OF EXPERIENCE Mi A.
15 l
1
16 Subject index
- EPICOR41 Geostettetic NUREG/OR f*229 V09 FIELD LYSIMETER INVESilGATONS LOW- NUREG/CR6459 FIELD STUDIES AT THE APACHE LEAP F1ESEARCH L EVE L WASTE DATA BASE DE VELOPMENT PFtOGRAM FOR SITE IN SUPPORT OF AL1ERNAffvE CONCEPTUAL 1tODELS F ISCAL YE AR 1996 Annual Report NUREGICR4497. DATA COLLECTON AND Fi[LD EXPERIMENTS AT THE APACHE LEAP RESEAFICH Sif E MeF 1995 1996.
Economic NUREG/CR45?S SECPOP90 SECTOR POPULATION. LAND F RAC- HEPA Fitter flON, AND E CONOMC ESTIMATION PROGRAM NORIG/CP 0153 PROCE EDINGS OF THE 24TH DOE /NRC NLCLEAR AIR CLEANING AND TREATMENT CONFERENCE Held in Portland, Electric Power industry Or@ M 1618* 1996 HUREG/CR 4012 VD4 REPLACE MENT EVRGY COSTS FOR NUCLE-AR ELICTRICITY.GENL FLATING UNITb IN THE UNITED STATLS Relogentone 199 M 101. NUREG/CR4539 EF F ECTS Or FLOOROE AND OTHER HALOGEN ONS ON YHE EXTERNAL STRESS CORROSON CRACKING OF N REG F 6506. EMDRITf Lt MENT DAT A BASE, VERSON 1. TYPE 304 AUSTENITIC STAINLESS STEEL Haterd Evenushon Enfortement Action NUREG 1601: CHEMCAL PROCESS SAFETY AT FUEL CYCLE FACill-NUREG-0940 V16 N1 Pt ENFORCt MENT ACTIONS SIGNIF CANT AC-TIONS RESOLVfD INDfVOUAL ACTONS $emanrv11 Progress DIS N G 4 N P2 ENTORCEMENT ACTIONS SIGNIFICANT AC-8*I I" ***"*" P'08*
TioNS RESOLVED REACTOR LICENSE ES Semannual Progress H"'Y *8"'".5591V07 N2 HEAVY SEC160N STEEL IRRADIATION NUREG/CR PROGRAM Semiennual Progress Report or Atall Through Septemter Report, January June 1997 NURL G0940 V16 N1 PJ ENFORCEMINT AC110NS SIGNIFICANT AC- 1996.
ON R VED MATEFilAL tiCENSE E S Semiennual Prog ess NUREG/CR 4219 Vt3 Nt: HEAVY SECTION STEC. TECHNOLOGY Engineered $efety Dystem PROGRAM Semannual Progress Raport For Octoter 1995 . March NUlliG/CR4538 EVALUATON OF LOCA W11H DELAYED LOOP A.40 1996.
LOOP wtTH DELAYED LOCA AOCIDE NT s 1.NAHOS.
m Situ Evaluation Environmentalimpact Statement NUREG/CF4 6557: DEVELOPMENT OF THE "AGNESCOPE AS AN IN.
NURLG 1496 VOI FINAL GENERC ENVIRONMENTAL IMPACT STATE- STFIUMENT FOR IN SITU EVALVATK STEEL COMPONENTS MENT IN BUPPORT OF RULEMAKING ON RADIOLOGICAL CRITE- OF NWLEAR SYSTEMS RIA FOR LICENSE TEF1MINATON Or NRC LICENSED NUCLEAR F ACILITIE S Mem Report F~enal Report industrial Re$ography NUREG 1496 V02 FINAL GENEUIC ENVIRONMENT AL IMPACT ST ATE- NUREG 1556 V2 ORF FC: CONSOLIDATED GUCANCE ABOUT MATE-MLNT IN SUPPORT OF RULEMAKING ON FIADIOLOGCAL CFilTE- RIALS LICENSES Program Specific Guidance About Industral Radiog-FMA FOR LICINSF TERMINATON OF NRC-LICEdSED NUCLEAR rephy Ocenses DraN Report For Use And Comment F ACIL files Appendices A And B Ferval Report NUREG 1496 Vua F INAL otNE RIC f.NVIRJNME NT AL IMPACT ST ATE- IngeeHon Pathway M[NT IN SUPPORT Os RU'iMAKING ON RADIOLOGICAL CRITE- NUREG/CR4523 V01: PROBABluSTIC ACCIDENT CONSE'OVENCE UNCERT AINTY ANALYSIS f ood Cham Uncertamty Assessment Man
- HlA FOR LICENSE TERMINATION OF NRC-LICENSED NUCLEAR F ACILITIES.Appereces C.H F inal Report. Floport NUREG/CR4523 V02 PROBABluSTIC ACCIDLNT CONSEQUENCE Esternal Strees Corroe6on Cracking UNCE AT AINTY ANALYSIS. Food Cham Uncertamty NUREG/CR 6539 LFF ECTS OF FLOOROE AND OTHER HALOGEN Assessment Appendices lONS ON THE EXTERNAL STRESS CORROSON CRACKING OF TYPE 304 AUSTENITC ST AINLE SS STEEL inservice Test Intervel NUREGICR 6508 COMPONENT UNAVAILADIUTY VERSUS INSERV.
Fougue ICE TEST (IST) INTERVALEVALUATIONS OF COMPONLNT AGING NUREG/CP4557 DEVELOPMENT OF THE MAGNESCOPE AS AN IN' EF FECTS WITH APOLICATONS TO GlECK VALVCS-STRUMENT FOR IN SITU EVALUATION OF STEEL COMPONENTS OF NUCLE AR SYSTEMS Integrity Dotat ese NUREG-1612. STATUS FIEPORT: RE ACTOR VESSEL INTEGRITY DA-pg gygg TARASL NUREG/CR t229 V00 FIELD LYSIMETER INVESTIGATONS LOW-LEVEL WASTE DATA BASE DEVELOPMLNT PROGRAM FOR lon Eschenge FISCAL YE AR 1996 Annual neport' NUREG/CR S229 VM FIELD LYSIMETER INVESTIGATONS. LOW-LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR Final tetety tvaluation Report FISCAL YEAR 1996 Annual Report NUREG 1462 S01: FINAL SAFETY EVALUATON REPORT RELATED TO THE CERTIFICATION OF THE SYSTEM 80+ DESIGN Docket No. LOCA 52402 (Aeoa Brown DoveroCombust<m E r gineenng) NUREG/CR-6538 EVALUATION OF LOCA WITH DELAYED LOOP AND Fluoride LOOP WITH DELAYED LOCA ACCIDENT SCEN AROS NUREG/CR4539 EFTECTS OF FLOOFilDr AND OTHER HALOGEN REG /CR4538 EVALUATION OF LOCA WITH DELAYED LOOP AND 3 A STENI IC ST INLE TE LOOP WITH DELAYED LOCA ACCIDENT SCENARIOS Food Chain NUREG/CR4523 V01: PROBADILISTIC ACCIMNT CONSEQUENCE 3 "d ICU'"
UNCER1 AINTY ANALYSIS Food Cham Uncertamty Ascasment Man NUREG/CR4525 SECPOP90 SECTOR POPULATION, LAND FRAC-n.po,g TION. AND ECONOMC ESTIMATION PROGRAM NUREG/CR4523 V02' PROBABillSTC AOCIDENT CONSEQUENCE ANALYSIS. Food Cham Uncerta nty Las Cruces Trench SHe UNCERTAINTY NUREGICR4437; FLOW AND TRANSPORT AT THE LAS CRUCES Assessment Appendicos TRENCH SITE EXPERIMENT 118 Fracture foughnese NUREG'CFt 6506 EMORITTLEMENT DATA BASE, VERSON 1. L*9alissuances NUREG4750 V45 601: INDEXES TO NUCLEAR REGULATORY COM-Fuel Cycle Facility M:SSION ISSUANCE 3 January-March 1997.
NUREG-1601 CHEMCAL PROCESS SAFETY AT FUEL CYCLE FACill- NUREG4750 V45102: INDEXES TO NUCLEAR REGULATORY COM-TIES. MISSON ISSUANCES JaouarrJune 1997.
___________._.______________________m___
Subject index 17 NUREG4760 V46 N06: NUCLEAR REGULATORY COMMISSION IS. Nuclear telety ReeeerWi SUANCES FOR MAY 1907 Pages 366-436 NUREG/CP4161: TRANSACTONS OF THE TWENTY firth WATER NUREG4760 V46 N06 NUCLEAR REGULATORY COMMISSION IS- REACTOR SAF ETY INFORMATION MEETING BUANCES FOR JUNE 1997. Pages 437 496 Nuclear Weste h condimen NUREG/CR4469 FIELD STUDIES AT THE APACHE LEAP RESEARCH NUREG/CR45be NRC ANTITRUST LICENSING ACTONS, 1976-199A.
SITE IN SUPPORT OF ALTERNAf tVE CONCEPTUAL MODELS-Lloonee Renewal . .
" ^ " EG/ 553 IOC EDINGS OF THE 24TH DOE /NRC NUCLEAR T EN FOR NSE R NE AS CLEANING AND TREATMENT CONFERENCE Hand in Portiend.
LAsense Tt 'minet6en Oregori. July 16-18,1996 NUREG-; 396 V01 f%AL GENERC ENVmON64ENT AL IMPACT ST ATE.
Operoung LJoonee 64ENT IN SUPPORT OF RULEMAKfNG ON RADOLOGCAL CRITE.
NUREG/CR4556. NRC ANTITRUST UCENSING ACTIONS, 1976 1996.
R6A FOR LCENSE TERMINATON OF NRCUCENSED NUCLEAR t ACIUTIES Man Report Final Report NUREG 1496 V07 F INAL GENERC ENVIRONMENT AL IMPACT STATE- PWR MENT IN SUPPORT OF RULEMAKING ON RADOLOGCAL CRITE. NUREG/CR4#61: A SAFETY AND REGULATORY ASSESSMENT OF P". FOR LCENSE TERMINATION OF NRC UCENSED NUCLEAR GENERC BWR AND PWR PERMANENTLY SHUTDOWN NUCLEAR FACILITIES Apperwtices A And B Final wt POWER PLANTS.
NUREG 1496 vb). FINAL GENERC ENVif ' ENTAL IMPACT STATE- Powene For Rulemaking MENT IN SUPPORT OF RULEMAKING ON RADOLOGCAL CRITE-RlA FOR LCENSE TERMINATON OF NRC LCENSED NUCLEAR NUREG4936 vt6 N01: NRC REGULATORY AGENDA $enuannual F ACluTIE S Appendices C H Final Report ReportJanuary June 1997 LeseOf Coelant Aceident Phenomene identWooetton NUHEG/CR4541 R02. PHENOMENA OENTirCATION AND RANKING NUREG/CR4541 R02. PHENOMENA DENTIFCATON AND RANKING TABLES FOR WESTINGHOUSE AP600 SMALL BREAK LOSSOF- TABLES FOR WESTINGHOUSE AP600 SMALL BREAM LOSSOF-COOLANT ACCIDENT, MAIN STEAM LINE BREAK, AND STEAM COOLANT ACCIDENT, MAIN STEAM UNE BREAK, AND STEAM GENLr1ATOR TUDE RUPTURE SCENAROS. GENERATOR TUBE RUPTURE SCENAROS.
Low-Level Weste Per
- kin NUREG/CR 6229 V09 FIELD LYSIMETER INVEST 60ATIONS LOW- L - 3/CR4531: EFFECTS OF RADIOACTIVE HOT PARTOLES ON LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR = i . SKIN FISCAL YEAR 1996. Annual Report Magneecepe NUREG/CR4519. SCREENING REACTOR STEAM / WATER PIPING NUREG/CR4557, DEVELOPMENT OF THE MAGNESCOPE AS AN IN- SYSTEMS FOR WATER HAMMER.
STFIUMENT IOR IN Situ EVALUATION OF STEEL COMPONENTS OF NUCLEAR SYSTEMS PeelCrtueel AseemMy NUREG/CR44SA: POOL CRITICAL ASSEMBLY PRESSURE VESSEL Mann Steam Line Rreek FACIUTY BENCHMARK.
NUREG/CR4541 R02; PHENOMENA IDENTIFICATION AND RANKING TABLES FOR WESTINGHOUSE AP600 SMALL BREAK LOSSOF- Power Reector COOLANT ACCIDENT, MAIN STEAM LINE BREAK, AND STEAM NUREG/CR4506 EMBRITTLEMENT DATA BASE, VERSION 1.
GENERATOR TUDE RUp(URE SCENARIOS Proctece And Precedure D6 poet Meternate Lloonees NUREG4386 006- UNITED STATES NUCLEAR REGULATORY COM-NUREG 1656 V2 DNF FC: CONSOLIDATED GUIDANCE ABOUT MATE- MISSON STAFF PRACTICE AND PROCEDURE D GEST.Conmasson, RIALS LCENSES Program Speerhc Guidance About industnal Radiog- Appeet Board And ucensmg Board DecesionsJuly 1972 June 1996.
rephy Utennes. Draft Report For Use And Comment Pressure Veseel EG R AL RESULTS OF THE XR2-1 BWR METALLC F AC LIT CH K' MELT RELOr ATION EXPERIMENT.
Preesortaed Thermal Shock NURE 612. STATUS REPORT: REACTOR VESSEL INTEGRITY DA-VE 456 VELOPMENT OF THE MAGNESCOPE AS AN IN- '
STRUMENT FOR IN SITU EVALUATION OF STEEL COMPONENTS OF NUCLEAR SYSTEMS. pre .m wage, p,,eg ,
hUREG/CR4451: A SAFETY AND REGULATORY ASSESSMENT OF Motor Opermed Yh GENERC BWR AND PWR PERMANENTLY SHUTDOWN NUCLEAR NUREG/CR 4478 MOTOROPERATED VALVE (MOV) ACTUATOR POWER PLANTS.
MOTOR AND GEARBOX TESTING.
m pg., Prebehinette Accident Conseguence NUREG/CP,0169 PROCEEDINGS OF THE OECD/CSNI WORKSHOP NUREG/CR4523 V01: PROBABluSTC ACCOENT CONSEOUENCE UNCERTAINTY ANALYSIS Food Cham Uncertamty AssessmentMem ON TRAW1NT THERMAL-HYDRAUUC AND NEUTRONC CODES REOUIREMENTS Held in Annapolis.Marytand, USA, November 6-4, A ggRWCR-6523 V02: PROBABluSTC ACCIDENT CONSEOUENCE Uncertanty UNCERTAINTY ANA'.YSIS. Food Cham Neutron Deetmetry AssessmentAppendices NUREG/CR4464 POOL CRITCAL ASSEMBLY PRESSURE VESSEL FACluTY BENCHMARK, Prebehehene R6ek Ateeeement NURE G/CR4508 COMPONENT UNAVAILABILITY VERSUS INSERV-16eutrente CE TEST (IST) INTERVALEYALUATONS OF COMPONENT AGING NUREG/CP 0169 PROCEEDINGS OF THE OECD/CSNI WORKSHOP EFFECTS WITH APPLICATONS TO CHECK VALVES ON TRANS6ENT THERMAL.HYDRAULO APs N W C CODES REOUIREMENTS Hold in Anrmpolia, Maryland,Uw- . ember 64, Redletten Embrtttlement 1996 NUREG 1612: STATUS REPORT: REACTOR VESSEL INTEGRfiY DA.
TABASE.
Nuoteer Air Cteening NUREG/CP4163 PROCEEDINGS OF THE 24TH DOE /NRC NUCLEAR Redlauen injury AIR CLEANING AND TREATMENT CONFERENCE. Held in Portland NUREG/CR4531: EFFECTS OF RADOACTIVE HOT PARTICLES ON Oregen July 16 18,1996. PIG SKIN.
y m . _ . . _ . . . . . . . . . . . . . .
j 18 Subject !ndex Redlomettve Hot Partic4e RlA FOR LCENSE TERMINATION OF NRC LICENSED NUCLEAR NURE G/CR4531 ElIECTS OF RADOACTIVE HOT PARTCLES ON F ACILITIE S Appen$ces C44 F inal Floport f4G SKIN Rules Mcs60 cartoon NUREG4936 V16 Not: f4RC FtEGULATORY AGE NDA $enmenrwal NUREG/CR4459 FIELD STUDIES AT THE APACH2 LE AP RESE ARCH ReportJanuary June 1997.
SITE IN SUPPORT OF Al Tt RNATIVE CONCEPTUAL MODE LS NURE GrCR4497 DAT A COLLECTION AND 7 IE LD EXPERIME NTS AT Ru6es Of Practice THE APACHE LE AP HESE ARCH SITE May 19W5 1996 NUREG43h6 D06 UNITED STATES NUCLE AR F4EGULATORY COM-MISSON STAFF PRACTICE AND PROCEDURE DIGEST.Commisson, Appeal Board And Licenwng Board Doctnons JJy 1972. June 1996 U 1 FINAL GENE RIC ENVIRONMENV IMPACT STATE.
MENT IN BUPPORT OF RULEMAkING ON RADOLOGICAL CFIITE' SECPOP90 RLA FOR L0ENSE TE RMINAllON OF NRC-LCENSED NUCLEAR HUREG/GR45M SECPOP90 SECTOR POPULATON. LAND FRAC-TION. AND ENNOMC (SilMATON PROGRAM Pf Ie 02 FI EE E 4VIRONMENTAL IMPACT STATE.
DENT IN SUPPORT or AULEMA< LNG ON RADIOLOGICAL CRITE. Safeguards Summary Event Wet RIA FOR LICENSE TE RMINATION OF NRC LICENSED NUCLEAR NUREG4525 V02 ROS SAF EGUARDS
SUMMARY
EVENT LIST NUF E V FI L GE N RIC Vf MENTAL IMPACT STATE-( """' # W * '" '
MENT IN SUPPORT OF HULEMAKING ON RADOLOGCAL CRITE. Sector PoPuMon RtA FOR LICENSE TERM 6NATON OF HRC.LCENSED NUCLE AR NURE3/CR4525 SECFOPin SECTOR POPULATION, LAND FRAC.
F ACILITlE S Append.cce C-H Final Report iION. AND ECONOMIC ESTLMATON PROGRAM Radeonuchde Transport Selem6c Queltfication NURE G/CR4523 V01: PROBABiUSTIC ACCIDENT CONSEQUENCE NUREG/CR4464 AN EVALUATON OF METHODOLOGY FOR SEIS.
UNCE RT AINTY ANALYSib Food Cham Urgertamty Assentmore Main MIC OVALIFCATION OF EQUIPMENT. CABLE TRAYS, AND DUCTS IN ALWR PLANTS BY USE OF EXPERIENCE DATA NL GR4523 V02 PROBABILISTIC ACCIDENT CONSEQUENCE UNCE 4i AINT Y ANALYblS F ood Chain Uncertanty g,,y g,,g Atomennent Appenho NUREG/CR4541 R02 PHEf OMENA IDENTIFCATION AND RANKING
' .eector Acc6deng T ABLES FOR WESTINGHOUSE AP600 SMALL BREAK LOSS-OF.
NUREG/CR4527; FINAL RESULTS OF THE XR2-1 BWR MET ALLIC COOLANT ACCIDENT, MAIN STEAM LINE BREAK, AND STEAM MFLT HILOCATON LAPERIMENT. GENERATOR TUBE RUPTURE SCENARol NURLG/CR4530 EVALUATION OF LOCA WITH DELAYED LOOP AND 8
LOOP WITH DELAYED LOCA ACCIDENT SCENARIOS
- }* 7 g g g Reactor &efety fWooerch TRENCH SITE. EXPERIMENT 110 NUREG/CP-0161: TilANSACTONS OF THE TWENTY FIFTH WATER RE ACTOR SAFETY INFORMAflON MEETING Station i schoot NUREQ/CR4527. FINAL RESULTS OF THE XR21 BWR METALLIC Reactor Shutdown MELT FtELOCATION EXPERIMENT, NUREG/CR 4012 V04 RE PLACEMENT ENERGY COSTS FOR NUCLE-AR ELECTRCITY GENERATING UNITS IN THE UNITED STATES Steam Bubble 1997 2001. NUREG/CR4519 SCREENING FIEACTOR me.AurWATER PIPING SYSTEMS FOR WATEFI HAMMER NUREG/CR4$25 SECPOP90. SECTOR POPULATION, LAND FRAC- Steam Generator TON, AND ECONOMC E STIMATON PROGRAM NURF"6/CR4541 A02 PHE NOMENA IDENTIFCATION AND RANKING TW LES FOR WESTINGHOUSE AP600 SMALL BREAK LOSS OA N '** Y ****I COOLANT ACCIDENT, MAIN STEAM LINE BREAK, AND STEAM NUREG-1612: STATUS REPORT: REACTOR VESSEL INTEGRITY DA' GENERATOR TUBE RUPTURE SCENAROS TABASE.
SteenWater System Regulatory Agende NUREG/CR4519 SCREENING REACTOR STEAM / WATER PIPING NUREG4936 V16 No t: NRC REGULATORY AGENDA Senuannual SYSTEMS FOR WATER HAMME R.
ReportJanuary June 1997.
Steel Component Retrutatory And Techn6 cal Report NUREGICR4557: DEVELOPMENT OF THE MAGNESCOPE AS AN IN-NUREG4304 V22 NOI: REGULATORY AND TECHNCAL REPORTS STRUMENT FOR IN SITU EVALUATION OF STEEL COMPONENTS (ABSTHACT INDE X JOURNAL) Comp 61ation f or First Quarte, OF NUCLEAR SYSTEMS.
1997, January-March System to + Deo6pn Regulatory weesament NURE G/CR 6451: A SAf ETY AND REGULATORY ASSESSMENT OF NUREG 1462 801: FINAL SAFETY EVALUATION REPOF1T RELATED GENERC BWR AND PWR PERMANENTLY SHUTDOWN NUCLEAR TO THE CERTIFICATION OF THE SYSTEM 80+ OESIGN Docket f4o.
52 002 (Asee Brown Boven-Combustion Engmeenng)
POWER PLANTS Replacement Energy Coat TLD NUREG/CR-4012 V04 HEPLACEMENT ENEFIGY COSTD FOR NUCLE. NUREG 0837 V17 NO2. NRC TLD DIRECT RADIATION MONITORING AR ELECTRCITY GENERATING UNITS IN THE UNITED STATES: NETWORK. Progress Report Aprtl. June 1997, 1997 2001 Test Reactor NUREG/CR4506 EMDRITTLEMENT DAT A BASE, VERSON 1.
Rulemaktnt NUREG 1496 V01: FINAL GENERC ENVIRONMENTAL IMPACT St ATE-MENT IN SUPPORT OF RULEMAKING ON RADOLOGCAL CRITE. ThermaWydraunc RIA FOR LICENSE TERMINATON OF NRCLCENSED NUCLEAR NUREG/CP4159 PROCrEDINGS OF THE OECD/CSNI WORKSHOP F ACILITIE S Mam Repor1 Fsnel Report ON TRANSIENT THERMAL. HYDRAULIC AND NEUTRONC CODES NUREG 1496 V02 FINAL GENERIC ENVIRONMENTAL IMPACT ST ATE. REQUIRE MENTS Held in Annapohs. Maryland. USA,Novemter fr6, MENT IN SUPPORT OF FIULEMAKING ON RAD'OLOGCAL CRfTE- 1996 RlA FOR LICENSE TERMINATION OF NRC LCENSED NUCLEAR F ACILITIES Appenreces A Aruf B Fina! Report Thermoluminescent Doelmeter NURE G 1496 V03 FINAL bENERC ENVIRONMENT AL IMPACT ST ATE. NUREG4637 V17 NO2: NRC TLD DIRECT RADiAtlON MONITORING ~
MENT IN SUPPORT OF RULEMAKING ON RADIOLOGICAL CRITE- NETWORK Progress Report April June 1997.
Subject index 19 Titw List Veridor Irepecton F80HEG4640 Vit NDS' TITLf. LIST OF DOCUME NTS MADE PUDLCLY NUREG4040 V21 N0t' ECENSE E CONTRACTOR AND VENDOR IN.
SPECTION STATUS REPORT. Chaarterty Report. January March N E 17 t 11 LIST OF DOCUMENf 6 MADE PUBLCLY AVAILADtt h 1 30 1997. 1997 We M NUHE GM40 vie t407. Yif tt LIST Or DOCUMENTS MADE PUBLCLY AV AILABL E#r 1 31,1997. Water Flow NUREG/CR4437. FLOW AND TRANSPORT AT THE LAS CRUCES REG Vt1: TOPCAL RE PORT REYilW ST ATUS.
- b E *8 Water Hammer Uncertaanty Analyog NURL A/CR4573 V01. PROBABILISTC ACCIDENT CONSEQUENCE NUREG/CR4519 BCREENING REACTOR STEAM /W ATER OPING UNCERTAINTY ANALYSIS Food Oom Uncertamty Asses
- ment Man SYSTEMS FOR WATER HAMMER Report NUREG/UR4523 V07. PROBAEllLISTC ACCIDENT CONSEQUENCE Westem AP600 UNCE RT AINTY ANALYSIS Food Osm Uncertamty NUREG/CR4641 R02. PHENOMENA IDENTIFCATION AND RANKING A"'**# #P8**** TABLES FOR WESTINGHOUSE AP600 SMALL BREAK LOSSOF-YadoseFone COOLANT ACCIDENT. MAIN STEAM LINE BREAK. AND STEAM NUREG/CR4437. FLOW AND TRANSPORT AT THE LAS CRUCES GENERATOR TUBE RUPTURE SCENAROS.
1RE NCH Si1E: EXPERIMENT 11B k
O 1
1
-..w-.
NRC Originating Organization Index (Staff Reports)
This index lists those NRC organizations that have published staff reports. The index is ar.
ranged alphabetically by ma,or NRC organizations (e.g., program offices) and then by sub-sections of these (e.g., divis 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 COMMITTEE (S) EDO . OFFICE OF ^ ' CLEAR MATERIAL SAFETY & SAFEQUARDS ADVISORY COMMITTEE ON NUCLEAR WASTE DIVISION OF INDUSTRIAL & MEDCAL NUCLLAR SAFFTY (POST NUREG 1423 V07: A COMPitATON OF REPORTS OF THE ADVISO. 070729)
RY COMMITTEE ON NUCLEAR WASTE. July 1996. June 1997. t4UREG-1556 42 DRF FC: CONSOLIDATED GUIDANCE ADOUT MA.
TERIALS LICENSES Program Specffic Guulance About industnal Re-OF CE FE V DIRECTOR FOR OPERATIONS (EDO) gpg5 ['l AgF NU EG 1601; CHEMCAL PROCESS SAFETY AT FULL CYCLE FA-NUREGee37 V17 NO2 NRC TLD DIRECT RADIATON MONITORING NETWORK Piogress Report AprdJune 1997- OPERATIONS BRANCn OFC OF E NFORCEMLNT (POST B70413) NUREG4525 V02 A05: SAFEGUARDS
SUMMARY
EVENT LIST NUREGM40 V16 N1 P1; ENFORCEMENT ACTONS SIGNIFICANT (SSEL) January 1.1990 Through Decernber 31,1996 ACTIONS REDOLVED INDIVIDUAL ACTONS Sermannual Progress Repritt.JanuaryJune 1997. U.S. NUCLE AR REOULATORY COMMIS$10N NOREG4940 V16 N1 P2. ENFORCEMENT ACTONS. SIGNIFICANT OF E OF T E NR N5 POST 1 ACTIONS RESOLVED REACTOR LICENSEES Sermannual Progress MISSION STAFF PRACTICE AND PROCEDURE NUR 4 V6 P3 E NFORCEMENT ACTONS SIGNIFICANT DIGEST Comrmessori, Appeal Board And Licensing Board ACTIONS FIISOLVI D MATERIAL LICENSEES Sermannual Progress De nsM 972. June m Report.Januarydune 1997. EDO . OFFICE OF NUCLEAR REGULATORY ! ? SE ARCN (POST 820405)
DIVISION OF REGULATORY APPLICATION (POST 941217)
EDO . OFIICE OF ADMINISTRATION (PRE 070413 & POST Sk1206) NUREG-1496 V01: FINAL GENERIC ENVIRONMENTAL IMPACT OF FICE OF ADMINISTRATION. DIRECTOR (POST 940714) STATEMENT IN SUPPORT OF RULEMAKING ON RADtOLOGCAL NUREG4036 V16 N01. NRC REGULATORY AGENDASermannual CRITERIA FOR LICENSE TERMINATON OF NRC. LICENSED NU-Report JanuaryJune 1997. CLE AR F ACluTIES Main Report Final Report NUREG 1496 V02: FINAL GENERIC ENVIRONMENTAL IMPACT EDO . OFFICE OF INFOFiMATION RESOURCES MANAGEMENT & ARM STATEMENT IN SUPPORI OF RULEMAKING ON RADIOLOGICAL
{ POST 661109) CRITERIA FOR LICENSE TERMINATION OF NRC-LICENSED NU-OFFICE OF INFORMATION RESOURCES MANAGEMENT (POST CLE AR F ACILITIES Apperdcas A And B Final Report.
890205) NURLG-1496 V03 FINAL GF.NERIC ENVIRONMENTAL IMPACT NUREG4304 V22 NOI: REGULATORY AND TECHNICAL REPORTS STATEMENT IN SUPPORT OF RULEMAKING ON RADIOLOGICAL (ADSTRACT INDEX JOURNAL) Cornpilation for Frst Quarte, CRITERIA FOR LICENSE TERMINATON OF NRC-LICENSED NU.
1997, January March CLEAR F ACILITIES es C-H Final Report.
NUREG4540 V19 N05 TITLE LIST OF DOCUMENTS MADE PUBLIC. $
D%A$fCR 65 ECPOP90 S TO UL T . LAND FRAC.
N EG4 0V 9 TIT'LE ST OF DOCUMENTS MADE PUBLIC.
LV AVAILADLE. June 1-30,1997. E00. OFFICE OF NUCLEAR REACTOR REGULATION (POST 000428)
NUREG4540 V10 N07: TITLE LIST OF DOCUMENTS MADE PUBLIC. OFFICE OF NUCLEAR REACTOR REGULATION (POST 941001)
LY AVAILABLE Juty 1-31,1997. NUREG4040 V21 N01: LICENSEE CONTRACTOR AND YENDOR IN-NUREG4750 V45101: INDEXES TO NUCLEAR REGULATORY COM. SPECTON STATUS REPORT. Quarterly Report. January-March MIS $10N ISSUANCES January-March 1997. 1997.(Wruta Book NUREG.0750 V45102 INDEXES TO NUC' EAR REGULATORY COM. $N@{ ph N gp( %RV W T U A ekel NUF V4 NOS N A RE ULATORY COMMlSSION IS-SUANCES FOR MAY 19w7 Pages 355-435 NUREG-1611: AGING MANAGEMENT OF NU WER PLANT NUREG4750 V45 N06 NUCLEAR REGULATORY COMMISSON IS- CONTAINMENTS FOR LICENSE RENEWAL SUANCES FOR JUNE 1997. Pages 437-495 NUREG-1612. STATUS REPORT: REACTOR VESSEL INTEGRITY DA.
TABASE.
c 21
B
NRC Originating Organization Index (International Agreementa)
This index lists those NRC organizations that have published international agreement re-ports. The index is arranged alphabetically by major NRC organizations (e.g., program of-fices) and then by subsectior i of these (e.g., divisions, branches) v,here appropriate. Each cotry is followed by a NUREG number and title of the r6gort(s), il further information is needed, refer to the main citation by NUREG number.
There were no NUREG/lA reports published this quarter.
P m
k 23
l l
l 1
l 1
NRC Contract Sponsor Index (Contractor Reports)
This index lists the NRC organizations that sponsored the contractor reports listed in this compilation. It is arranged alphabetically by major NRC organization (e.g., prograrn office) and then by subsections of these (e.g., divisions) where appropriate. The sponsor organiza-tion is followed by the NUREG/CR number and title of the report (s) areaared by that organi-zation.11 further information is needed, refer to the main citation by tio MUREG/CR number.
EDO . OFFICE OF NUCLE AR REGL".ATORT Ri&E ARCH (POST 820406) N'.' REG /CR 6437 FLOW AND TRANSPORT AT THE LAS CRUCES OlVIS% of INGINL1HING f E CHNOLOGY (POST 941217) THE NCH SITE EKPE RtMENT llB NUhl G/GR 4219 V13 N1 HE AVY S(ClON STLEL TECHNOLOGY NUHEG/CR 6451. A SAFETY AND REGULATORY ASSESSMENT OF PitOGRAM Semienriuol Prcyess Hepori For Octotier 1995 March GENERIC BWR AND PWR PERMANENTLY SHUTDOWN NUCLEAft 1996 POWE R PLANTS NUHE G/CH M91 V07 N2 HEAVY SECilON STEE L IHRADIATION NURE G/CR 4459 FIELD STUDIES AT THE APACHE LEAP Rt.
PROGHAM Semeanrwal Puyess Repor1 For April Through $epte*~ BEAF4CH Si1E IN SUPPORT OF ALTERNATIVE CONCEPTUAL tar 19% MOofLS NUHt G/CH 64S4 POOL ChillCAL AS$t MOLY PRE SSURE VESSEL NUHEG/CR 6497. DATA COLLECTION AND FIELD EXPERIMENTS F ACILITY u( NCHMARk AT THE APACHE LE AP RESE ARCH SITI May 1995 1996 NUHIG/CF46464 AN iVALUATION OF ME THODOLOGY FOR SEIS' NUniG/CH 6531_ EFf ECTS OF RADIOAC11Vt' HO1 PARTICLES ON MtC OVALIF ICAtlON Of (OulPMI NT.CADLF TRAYS. AND DUCTS PIG SKIN IN At WH PLAN 1B HY USE OF I XPt RIENCE DAT A DIVISION OF SYST[MS TECHNOLOGY (POST 941217)
NUHI G/CH4478 MOTOH OPERATtD VALVE (MOV) ACTUATOR NUREG/CH 6519 SCRf(NING HEAC10R STE AM/ WATER PIPING M010H AND Gi ARHOx lt STING SYSTEMS FOR W ATE FI HAMMER NUHI G/CR 6506 i MHHlTTL t ME NT DAT A DASF , Vt HSION 1 NURFG/CR 6523 YOI: PROBAHILtSTIC ACCIDENT CONSEQUENCE NUHf G/ Cit 6508 COMPONE NT UNAV AILABILITY Yi RSUS INSERV' UNCE RT AINTY ANALYSIS Food Chain Uncertaenty ICf 1[ S1 (IST) INT E HV AL i V AL U AflONS OF COMPONE NT Assessment Main tieport AGING I f f E C15 WITH APPLICATONS TO CHECK VALVE S NUREG/CR 65?3 b12 PHOBABillSitC ACCIDENT EONSEQUENCE NUitl G /CH 6538 ( V ALU AllON OF L OCA WITH DL L AYE D LOOP UNCERT AINTY ANALYSIS Food Chaw. Uncertainty AND L OOP Wi1H DL L AYE D LOCA ACCIDENT SCF N AR60s A .es.mont Appendices NUHi G/CH 6539 iii EC1B OF F LUOHIDE AND OTHER HALOGEN NUREG/CH 6525 SECPOP90 StCTOR POPULATION LAND FRAC-IONS ON THE [x1EHNAL STRE SS COHROSON CHACKING OF TON. ANDiCONOMIC ESTIMATION PROGRAM T YPl: 304 AUSit N116C ST AINtiSS STE E L NUREG/CR 6527. FINAL RESULTS OF THE XR2-1 DWR MET ALLIC NUHI G/CH 6M7 DlVELOPMENT OF ThE MAGNE SCOPE AS AN ME LT RELOCATION E XPE RIME NT.
INS 1HUMI NT FOH IN SITU IVALUATION OF STELL COMPO- NUHEG/CH 6541 R02 PHENOMENA IDENTIFICATON AND RANK.
NINTS Of NUCll A4 SYSTE MS ING 1 AHLES FOR WESTINGHOUSE AP600 SMALL BREAK LOSS-(31VISON OF REGUL ATOHY APPtl CATIONS (POST 941217) OF COOLANT ACCIDENT. MAIN STE AM LINE ORLAK. AND NUHE G/CR 4012 VO4 Hf PLAC( MINT ENERGY COS15 i WU- STEAM GENERATOR TUBE RUPTURE SCENARIOS Cll AR [ L E C1841CliY GL NI HAllNG UNIT S IN THE UNIT E D STATES 1997 ?001 EDO . Of FICE OF NUCLEAR RE ACTOR REGULATION (POST 0004281 NUHt G/CR 5229 V09 FIELD LYSIMETER INVE STIGAtlONS LOW- OF FICE OF NUCtt AR RE ACTOH HE GULAflON (POST 941001)
NURE GICR 6%8 NRC ANitTRUST LICENSING ACTIONS, 1978-L E Vi t W ASTE DAT A BASE DEVELOPME NT PROGRAM FOR F ISCAL YE AH 19% Annual Report 1996 2s
E
Contractor Index This index lists, in alphabetical order, the contractors that prepared the NUREG/CR reports 161ed in this compilation. Listed bolow each contractor are the NUREG/CR numbers and titles of their reports. If further information is needed, refer to the main citation by the NUREG/CR number.
ARGONNE NATIONAL LABORATORY NUREG/CR-6541 R02 PHENOMENA IDENTIFICATON AND RANKING NUREQ/CR 4012 VO4 REPLACEMENT ENERGY COSTS FOR NOCLE- TABLES FOR WESTINGHOUSE ape 00 SMALL BREAK LOSS-OF.
AN ELECTRICITY. GENERATING UNITS IN THE UNITED STATES COOLANT ACCIDENT, MAIN STEAM LINE BREAK, AND STEAM 1997 2001 GENERATOR TUBE RUPTURE SCENAROS NUREG/CR.5229 V09 FIELD LYSIMETER INVESTIGATIONS LOW.
LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR lOWA STATE UNIV AMES,lA FISCAL YE AR 1996 Annual Report NUREG/CR4557. DEVELOPMENT OF THE VAGNESCOPE AS AN IN-ORI2ON A, UNIV. OF, TUCSON, AZ STRUMENT FOR IN SITU EVALUATON OF STEEL COMPONENTS NURE G/CR 4437: FLOW AND TRANSPORT AT THE LAS CRUCES OF NUCLEAR SYSTEMS TRENCH SITE EXPERIMENT llB LOMA LINDA UNIV., LOM A LINDA, CA NURE G/CR4459 FIELD STUDIES' AT THE APACHE LEAP RESEARCH Sf1E IN RUPPORT OF ALTERNATIVE CONCEPTUAL MODELS NUREG/CR4531: EFFECTS OF RADIOACTIVE HOT PARTICLES ON NUHLG/CR4497. DATA COLLECTION AND FIELD EXPERIMENTS AT PIG SKIN THE APACHE iEAP RESEARCH SITE May 1995 1996 MASSACHUSETTS INSLTUTE OF TECHNOLOGY. CAMBRIDGE, MA DROOKHAVEN NATIONAL LABORATORY NURE G/CR4519 SCREENING REACTOR STEAM / WATER PIPING NUREG/CI' 0161: TRANSACTONS OF THE TWENTY-FIFTH WATER SYSTEMS FOR WATER HAMMER.
RE ACTOR SAF ETY INFORMATION MEETING NUREG/CR-5229 V09 FIELD LYSIMETER INVESTIGATIONS LOW- NEW MEXICO STATE UNIV., LAS CRUCES, NM LEVfL W AST E DATA BASE DEVELOPMENT PROGRAM FOR FISCAL YE AR 1996 Annual Reoort NUREG/CR4437: FLOW AND TRANSPORT AT THE LAS CRUCES NUREG'OR4451: A SAFETY AND REGULATORY ASSESSMENT OF TRENCH SITE EXPERIMENT llB G ERC W AND PWR PERMANENTLY SHUTDOWN NUCLEAR NEW MEKICO, UNIV. OF, ALBUQUEROUE, NM NURE G/CR4464 AN EVALUATON OF METHODOLOGY FOR SEIS- NUREG/CR4523 V01: PRORABILISTIC ACCIDENT CONSEOVENCE MC QUALIFCATON OF COUIPMENT CABLE TRAYS, AND DUCTS UNCERTAINTY AFA.YSIS Food Cham Uncertamty Assesammt Man IN ALWR PLANTS BY USE OF EXPER;ENCE DAT A Report NUREG/CR4531: EFFECTS OF RADIOACilVE HOT PARTCLES ON NUREG/CR4523 V02. rHOBADILISTIC ACCIDENT CONSEQUENCE PIO SKIN UNCERTAINTY ANALYSIS Food Cham Uncertamty NUREG/CR4538 EVALUATION OF LOCA WITH DELAYED LOOP AND Assessment Appendices LOOP WITH DELAYED LOCA ACCIDENT SCE N AROS DELFT UNIVERSITY OF TECHNOLOGY NUREG/CR4523 V01: PROBABILISTIC ACCIDENT CONSEQUENCE NUREG/CR-4219 V13 N1: HEAVY SECTION STEEL TECHNOLOGY UNCERTAINTY ANALYSIS Food Cham Uncertamty Assessment Mam PnOGRAM Semiannual Progress Report For October 1995 March Report 1996 NUREGICR 6523 V02. PROBABluSTIC ACCIDENT CONSEQUENCE NUREG/CR 5229 V09 FIELD LYSIMETER INVESTIGATIONS. LOW-UNCERTAINTY ANALYSIS Food Chain Uncertainty (EVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR Assessment Appendices FISCAL YEAR 1996 Annual Report NUREGICR-5591 V07 N2. HE AVY SECTION STEEL IRRADtATION OR AM, INC. PROGRAM Semiannual Progress Report For April Through September NUREG/CR4525 SECPOP90. SECTOR POPULATON LAND FRAC
- 1996 TION. AND ECONOMIC ESTIMATON PROGRAM NUREG/CR4454 POOL CRITCAL ASSEMBLY PRESSURE VESSEL HARVARD SCHOOL OF PUBLIC HEALTH, BOSTON, MA
^ 0 "
NUREG/CR4506 EMBRITTLEMENT DATA BASE, VERSON 1.
NUREG/CP4153. PROCEEDINGS OF THE 24TH DOE /NRC NUCLEAR AIR CLEANING AND TREATMENT CONFERENCE Held in Portland' NUREG/CR4508 COMPONENT UNAVAILABlUTY VERSUS INSERV.
Oregon, My 4 18'1996 CE TEST (IST) INTERVAL. EVALUATIONS OF COMPONENT AGING EFFECTS WITH APPLCATIONS TO CHECK VALVES HAW All, UNIV. OF. HILO, HI NUREG/CR4558 NRC ANTITRUST LICENSING ACTONS, 1978-1996.
NURE3/CR4523 V01: PROBABILISTIC ACCIDENT CONSEQUENCE y UNCERTAINTY ANALYSIS Food Cham Uncertamty Assessment Main ORGANIZATION FOR ECONOMIC COOPERATION & DEVELOPMENT Re. port. NUREG/CP 0150 PROCEEDINGS OF THE OECD/CSNI WORKSHOP NURt.G/CR4523 V02. PP.OBABluSTIC ACCIDENT CONSECUENCE ON TRANSIENT THERMAL HYDRAUUC AND NEUTRONC CODES UNCERTAINTY ANALYSIS Food Cham Uncertamty REQUIREMENTS Held in Annapobs, Maryland, USA. November 5-8 Assessment Appendices- 1996 IDAHO NATIONAL ENGINEERINO & ENYlRONMENTAL LABORATORY SANDIA NATIONAL LABORATORIES NUREG/CR 5222 V09 FIELD LYSIMETER INVESTIGATONS LOW- NUREG/CR4523 V01: PROBABIUSTIC ACCOENT CONSEQUENCE I PN VNCERTAINTY ANALYSIS Food Cham Uncertanty AssessmentMam LYEAR 996 NU G CR 7 T TED VALVE (MOV) ACTUATOR NUR CR 6523 V02: PROBABluSTIC ACCIDENT CONSEQUENCE NUREQ/CR4523 VOI: PROBABILISTIC ACCIDENT CONSEQUENCE UNCERTAINTY ANALYSIS Food Cham Uncertamty UNCERTAINTY ANALYSIS Food Cham Uncertamty AssessmentMem AssessmentAppende a Report NUPEG/CR4525: EECPOP90^ SECTOR POPULATON LAND FRAC.
NUREG/CR4523 VU2 PROBABluSTIC ACCOENT CONSEQUENCE TION AND ECONOMIC ESTIMATION PROGRAM.
UNCERTAINTY ANALYSIS Food Cham Uncertamty NUREG/CR4527. FINAL RESULTS OF THE XR2-1 DWR METALUC Assessment Appendices MELT RELOCATON EXPERIMENT.
27
28 Oontractor index
&CIENCE APPLICATIONS INTERNATIONAL CORP. (FORME RLY REQUIREMENT S Hekt in Annapoks Marriend. USA.Novernbar $4, SCIENCE APPLICATIONS, 19'A NUREG/CR-6521. FINAL RESULTS OF THE XR21 BWR METALLC UNrTED KINGDOW MELT RELOCATION EXPERIMENT. NUr4EG/CR4623 V01: PROBABILISTC ACCIDENT CONSEQUENCE UNCERTAINTY ANALYSIS. Food Cham Uncertanty AssessmentMan
&OfMEM IC NUREG/CP4159 PROCEEDINGS OF THE OECO/CSNI WORKSHOP NURWCRef,23 V02 PROBABILISTC ACCIDENT CONSEQUENCE ON TRANSIENT THERMAL HYDRAULC AND NEUTRONC CODES UNCERTAINTY ANALYST $. Food Cham Uncertanty A6sessment Appereces
\
international Organization Index This index lists, in alphabetical order, the countries and performing organizations that pre-pared the NUREG/lA reports listed in this compilation. Listed below each country and per-forming organization are the NUREG/lA numbers and titles of their reports. if further infor-mation s needed, refer to the main citation by the NUREG/lA number.
There were no NUREG/LA reports published this quarter.
C 29
1 Licensed Facility Index This index lists the facilities that were the subject of NRC staff or contractor reports. The facility names are arranged in alphabetical order. They are proceded by their Docket number and followed by the report number. If further information is needed, refer to the main citation by the NUREG number, um man ww s w maam nn um ugsog w p u w w . van orns un sos 31
6eRC Pome sM U s. NUOLEAR REoVLATORY COMMi&stON 1. RE PORT FAaeER ose nee .ee erwac. Ass voi, sum, nov,
- $3E BIBUOGRAPHIC DATA SHEET *"*"*""***'**'*"'8 (sa ****ne = **
- w=> NUREG4304
- TrrEE mo sUnirrEE Vol. 22, No. 3 Regulatory and Technical Reports (Abstract inder Journal) 3 DATE REPORT PUBLISHED Comptabon for Third Quarter 1997 Makm vtAR l
July September January 1998 4 FIN OR GRANT NUMBER s AtITHOR(s) e. TYPE OF REPORT
- 7. PERIOD COVE RED thun,ame teams)
Juty. September 1997
- 4. PERF ORMING ORGAP4ZATION . NAM NC ADDRESS (r NRC, pere teveen, (Ao e Raym U S Nwcase Reyes:ry Commeem e4 nedag emosa. # sw*ecer pane none e4 medmp enoes)
Puticabons Branch Informaton Management Division U S Nuclear Regulatory Commission Wechington, DC 20$55-0M1
- s. sPON$0 RING ORGANIZATlON . NAME MC ADOREst (r NRC. type 'sene es e6ove*, t ocvesckr. mm NRC t>vem (noe e Room u 8 kane Amewary Commesm end meene enveen1 Same as 8, above.
- 10. SUPPLEMLNT ARY NOTES L. L Stevenson, Project Manager
- 11. ABSTRACT (No een e ases)
The journalincludes all formal reports in the NUREG series prepared by the NRC staff and contractors; proceedings of conferences and workshope' as wel as internabonal agreement reports. The entries in this compitabon are indexed for access by btle and abstract, secondary report number, personal author, subject, NRC organizabon for staff and internabonal agreements, contractor, internabonal organization, and licensed facility.
- 13. KE V WORDS!OESCRIPTORs (Last eues er p&ues met ed went mesecners m tre6ng ye espet) 13 AVALAD'LIIY 81LMENT compAabon unlimited c.bstract index M sECURW CLAsMICATm tw Peee) unclassthed t% Roews unclassified 15 NUMDER OF PAGE8
- 16. PRICE W 'O'"' W 9 M N kwm was emit produced t my Eine Federer Forms. Inc L
4
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Main Citations and Abstracts f Q
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.z5@ 11 Secondary Report gl# bkh
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f NumberIndex g j @
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-N Personal AuthorIndex I !
umen y Subject Index Q$ g b!h$ #
NRC Originating Organization I$E #;Ig h
p Index (Staff Reports)
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NRC Originating Organization b k Index(International Agreements) R N j
!JRC Contractcr C 3 Sponsor Index g i@
ContractorIndex Intemational Organization Index Licensed Facility g$h g Index bgd E 8
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