ML20154P344

Abstracts for Publications in the NUREG-SERIES.Semiannual Compilation for January-June 1998

ML20154P344
Person / Time
Issue date:	09/30/1998
From:	NRC
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References
NUREG-0304, NUREG-0304-V23-N01, NUREG-304, NUREG-304-V23-N1, NUDOCS 9810220299
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NUREG-0304 Vol. 23, No.1 Abstracts for Publications in the NUREG-Series .

Semiannual Compilation for January - June 1998 U.S. Nuclear Regulatory Commission Office of the ChiefInformation Omcer

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AVAILABILITY NOTICE Availability of Reference Materials Cited in NRC Publications NRC publicahons in the NUREG series, NRC regu- NRC Public Document Room labons, and TMs 10, Energy, of the Code of Federal 2121 L Street, N.W., Lower Level Regudstions, may be purchased from one of the fol- Washington, DC 20555-0001 lowing sources: <http://www.nrc. gov /NRC/PDR/pdr1.htm>

1-800-397-4209 or locally 202-634-3273

1. The Superintendentof Documents U.S. Govemment Printing Office Microfiche of most NRC documents made public;y )

avaHable sinca huary 1981 may be M in the l RO. Box 37082 Local Public Document Rooms (LPDRs) located in  !

Washington, DC 20402-9328 the vicinity of nuclear power plants. The locahons

<http://wwwaccess.gpo. gov /su- docs > l of the LPDRs may be obtained from the PDR (see 202 -512-1800 ,

previous paragraph) or through:  :

2. The Nabonal Technical Informabon Service <http://www.nrc. gov /NRC/NUREGS/ l Sprig 3 VA 22161-0002 SR1350/V9/lpdr/html> l

<http://www.ntis. gov /ordomow> 1 703 -487 -4650 Publicly released documents include, to name a ,

few, NUREG-series reports; Federal Register no- 1 The NUREG series comprises (1) technical and ad- tices; applicant, licensee, and wnds documents ,

ministrative reports, including those prepared for and correspondence; NRC correspondence and ,

intomal mommanda; buHedns and infonnedon e intomational agreements, (2) brochures, (3) pro-condings of conferences and workshops, (4) adju- tices; inspechon and investigation reports; licens-  ;

dications and other issuances of the Commission se ownt repats; and Commssion papa and  !

and Atomic Safety and Uconsing Boards, and their attachments.

l (5) books. Documents available from public and special tech- l nical libraries include all open literature items, such l A single copy of each NRC draft report is available as books, joumal articles, and transachons, Feder-free, to the extent of supply, upon written request al Register nobces, Federal and State legislation, l as follows: and congressional reports. Such documents as theses, dissertations, foreign reports and transla-Address: Office of the Chief Informahon Officer tions, and non-NRC conference proceedings may Reproduction and Distribution be purchased from their sponsoring organization. ,

Sennces Secbon i U.S. Nuclear Regulatory Commission Copies of industry codes and standards used in a ,

Washington, DC 20555-0001 substantive manner in the NRC regulatory process  ;

E-mail: are maintained at the NRC Library, Two White Flint

<GRW1@NRC. GOV >

Facsimile: 301 -415 - 2289 North, 11545 Rockville Pike, Rockville, MD i 20852-2738. These standards are available in the  ?

library for reference use by the public. Codes and i A portion of NRC regulatory and technical informa-tion is available at NRC's World Wide Web site:

standards are usually copyrighted and may be purchased from the originating organization or, if

<http://www.nrc. gov >

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American National Standards Institute i

All NRC documents released to the public are avail- 11 West 42nd Street abic for inspection or copying for a fee, in paper, New York, NY 10036-8002 rmcrofiche, or, in some cases, diskette, from the <http://www.ansl.org>

Public Document Room (PDR): 212- 642-4900 l

A year's subscription of this report consists of two semiannualissues.  :

i NUREG-0304 Vol. 23, No.1 Abstracts for Publications in the l NUREG-Series 1

I Semiannual Compilation for January - June 1998

'l Date Published: September 1998 L. L. Stevenson, Project Manager Pchlishing Services Branch Office of the ChiefInformation Officer U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 f ~%,,

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i-CONTENTS i Preface........................................................ .. ............. v Index Tab Main Citations and Abstracts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 e- Staff Reports e Confererx:e Proceedings e Contractor Reports e Grant Reports i e international Agreement Reports I Secondary Report Number index . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 Personal Author index . . . . . . . . . . . . . . . . . . . .... .... ... . ..... ..... . . ...... 3 Subject index - . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... ....... .............. . 4 NRC Originating Organization Index (Staff Reports) . . . . . . . . ... ... .. . .... . ... .. 5

- NRC Originating Organization index (Intemational Agreements) .. ... .. ............ .. 6 .

NRC Contract Sponsor index (Contractor Reports) . . . . . . . , . . . . . .. .. . .... ... . . 7  ;

Contractor index . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... ..... ...... . 8 Intemational Organization Index . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ......... 9 Licensed Facility Index . . . . . . . . . . . . . . . . . .. ............ ...... .. ..... . ......... 10 4

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PREFACE The ll.S. Nuclear Regulatory Commission (NRC) compiles bibliographic data and abstracts for publications in the NUREG-series available to the public. The compilation is published semiannually.

In the first listing, the bibliographic data and abstracts for these publications are sequenced according to their NUREG-series number. publications including reports or brochures prepared by the staff designated (NUREG-XXXX) or (NUREG/BR-XXXX); conference .

proceedings designated (NUREG/CP-XXXX); reports prepared by an NRC contractor designated (NUREG/CR-XXXX); and publications resulting from intemational agreements designated (NUREG/lA-XXXX).

After the principal listing, nine other indexes list the reports by- i Secendary Report Number  ;

Personal Author l Subject  ;

~

NRC Originating Organization Index for Staff Reports NRC Originating Organization index for Intemational Agreement Reports  !

NRC Contractor Index for Contractor Reports i

Contractor Intemational Organization Licensed Facility Staff-Prepared Pub!ication i (1) NUREG-1552 (report number); (2) Fire Barrier Penetration Seals in Nuclear Power Plants (report title); (3) Bajwa, C. S., West, K. S. (report authors); (4) Office of Nuclear Reactor Regulation (organizational unit of authors); (5) July 1996 (publication date); (6) 55 pp. (number of pages); (7) 9608230207 (NRC Document Control System accession number-for NRC use); t (8) 89455:045 (the microfiche address-for NRC use).

Staff-Prepared Brochure (1) NUREG/BR-0164, Rev. 2 (report number); (2) NRC: Regulator of Nuclear Safety (report title); (3) None (report author); (4) Office of Public Affairs (organizational unit of author); (5)

April 1997 (publication date); (6) 24 pp (number of pages); (7) 9705020298 (NRC Document .

Control System accession number-for NRC use); (8) 92700:001-031 (the microfiche address- i for NRC use).

l Contractor-Prepared Publication (1) NUREG/CR-6279 (report number); (2) Application of Fracture Toughness Scaling Models to the Ductile-to-Brittle Transition (report title); (3) Joyce, J. A. (report author); (4) U.S. Naval v

. - - _ _ _ - ,- - . - -- .-.-. . , -_ . - = _ - -

Academy (organizational unit of author); (5) January 1996 (publication date); (6) 42 pp

(number of pages); (7) 9602220350 (NRC Document Control System accession number-for l NRC use); (8) 87234

102 (the microfiche address-for NRC use).

Conference Proceedinas

! (1) NUREG/CP-0149, V01 (report number); (2) Proceedings of the Twenty-Third Water l Reactor Safety information Meeting: Plenary Session, High Bumup Fuel Behavior, Thermal Hydraulic Research (report title); (3) Monteleone, S. (report author); (4) Brookhaven National Laboratory (organization that compiled the proceedings); (5) March 1996 (publication date); (6) l 278 pp. (number of pages); (7) 9604150352 (NRC Document Control System accession l number-for NRC use); (8) 87868:001 (the microfiche address-for NRC use).

Intemational Aareement Publication (1) NUREG/lA-0133 (report number); (2) Development, implementation and Assessment of Gpecific Closure Laws for Inverted-Annular Film-Boiling in a Two-Fluid Model (report title); (3)

DeCachard, F. (report author); (4) Paul Scherrer institute (organizational unit of author); (5)

October 1996 (publication date); (6) 103 pp (number of pages); (7) 9611190277 (NRC Document Control System accession number-for NRC use); (8) 90823:249 (the microfiche l address-for NRC use).

Some NRC reports in the NUREG-series are posted on NRC's World Wide Web site under the Reference Library icon on the home page: <http://www.nrc. gov >.

Availability of NRC Publications l

Copies of these publications may be purchased from one of the following sources:

l

! 1. The Superintendent of Documents l U.S. Govemment Printing Office i P.O. Box 37082 l Washington, DC 20402-9328 l < http://www.acce s s.g po.g ov/su_ docs >

202-512-1800 l

l

2. The National Technical Information Service Springfield, VA 22161-0002

<http://www.ntis. gov /ordemow>

703-487-4650 vi

W Main Citations and Abstracts i

I

, . The list of publications in this Compilation are arranged by number, where NUREG-XXXX is an i'

, NRC staff-criginated publication, NUREG/CP-XXXX is an NRC-sponsored Conference i

proceediregs, NUREG/CR XXXX is an NRC Contractor-prepared publication, NUREG/lA-XXXX b an iritornational agreement publication, and NUREG/BR-XXXX is a staff-originated publication The bibliographic information (see Preface for details) is followed by a brief i- abstract of this publication.

i NURE44040 V21 Ne4: UCENSEE CONTRACTOR AND active fuel fabrication facieltes possessing more then one effec-

VENDOR INSPECTION STATUS REPORT. Quarterty eve kilogram of special nuclear material. l Report, October December 1997.(White Book)

• Offbe of Nucio- l er Remotor Regulation (Post 941001). Apr# 1998. 81pp* NUREG0540 Vit N11: TITLE LIST OF DOCUMENTS MADE 9006100328. A3431:300. PUBLIOLY AVAILABLE. November 1-30, 1997.

• NRC - No De-

This pelodoel ooves #w resuhe W inspectons pufwmed by tailed A"iliation Given. January 1998. 284pp. 9002100158.

4 the NRC's Queuty Assuranos, Vendor inspecton and Mainte A207,8 022.

. nonce Branch that have been distributed to the inspected orge- Tre document is a metNy pubhceum omtaining decrig>

nkemone during the perkd from Octobw through Decembw tions of information received and generated by the U.S. Nucieer 1997* Reguistory Commission (NRC). This informaton includes (1) l docketed meterial a uasad with civHien nucieer power plants 4 NUREG4000 V30: REPORT TO CONGRESS ON ABNORMAL and other uses of redlonceve materials and (2) nondocketed

! OCCURRENCES. Fiscal Year 1997.

• Offlee for Analysis & Evel. meterial received and generated by NRC pertinent to its role as

, usuon of Operemonal Dete, Director AprH 1998. 23pp. a regulatory agency, The foHowing indexes are included: Per-eennnenna7. A3320:327. sonal Author, Corporate Source, Report Number, and Cross Seollon 208 of the Energy Reorganization Act of 1974 identi- Reference of Enclosures to Pnncipal Documents-Aes an occunonos (AO) as an unscheduled incident w ment M N Nuclear Regulemry Commissie (NRC) deteo NUREG4640 Vit N12: TITLE UST OF DOCUMENTS MADE PUBUCLY AVAILABLE. December 1-31, 1997.

• NRC - No De-mines b be signmcent h #w standpoint of pubuc heehh w teiled AfflNeton Given. February 1998. 315pp. 9803030348 safety. The Federal Reports Ellminston and Sunset Act of 1995 A2413:001 requires met AOs be reputed 2 Cegrees on an annual beeis. See NUlkEG4540,V19,N11 ebstract.

This report includes those events that NRC has determined to be AOs during fiscal year 1997. This report addresses two AOs NUREG0540 V30 N01: TITLE UST OF DOCUMENTS MADE et NRC-Econced faculties. One involved an event at a nucteer PUBLICLY AVAILABLE. January 1 31, 1998. MORRIS.E.B. NRC power plant, and one involved materials overexposure. The - No Detailed Afflheson Given. March 1998. 327pp.

report eleo addresses four Agreement State AOs. Two of theos 9803240332. A2883:001.

AOs involved overeuposures and two involved radopharmaceu. See NUREG-0540,V19,N11 abstract.

ilcel miesdministrellons. In addition, Appendix C of the report ire t cludes Sve events W loss W control W honed metwiels' NUREG 0540 V30 Not: TITLE UST OF DOCUMENTS MADE i PUBUCLY AVAILABLE. February 1-28, 1998.

• NRC - No De-  ;

NURE44004 V22 NOS: REGULATORY AND TECHNICAL RE. tailed AfRHenon Given. AprG 1998. 300pp. 9805050440  :

PORTS (ABSTRACT INDEX JOURNAL). Compunton For Third A3318:039.

Quarter 1997/$/ C.L.,.

• NRC - No Detailed Afflueton See NUREG 0540,V19,N11 abstract, i Given. January 1998. 41pp. 9802100108. A2079:175.

TNs joumal includes aN formal repons in the NUREG sortes NUREG4540 V30 NOS: TITLE UST' OF DOCUMENTS MADE  !

PUBLICLY AVAILABLE. March 1 31, 1998.

• NRC No Detailed -

4 prepared by me NRC staff and corWactors, proceedngs W con- Affibetion Given. May 1998. 390pp. 9808010321. A3571:044. l forem.as and workshape; as won as intomatonal a9reement m- See NUREG-0540,V19,N11 ebstract.

ports. The entries in this compMation are Irvlawad for access by  ;

INie end abstract, secondary report number, personal author, NUREG4640 V20 N04: TITLE UST OF DOCUMENTS MADE -

subject, NRC orgenhetion for staff and intemational agree- PUBUCLY AVAILABLE. April 1-30, 1998.

• NRC No Detailed 4 monts, contractor, intomatonal organizeton, and hooneso facs. Affleistion Given. June 1998. 352pp. 9807080350. A4010:001.

ty. See NUREG-0540,V19,N11 ebstract.

!' NUREG4004 V23 N04: REGULATORY AND TECHNICAL RE. NUREG 0713 Vie: OCCUPATIONAL RADIATION EXPOSURE AT  !

t PORTS (ABSTRACT INDEX JOURNAL). Annual Compilebon COMMERCIAL NUCLEAR POWER REACTORS AND OTHER

• FACILITIES.1998. Twenty-Ninth Annual Report. THOMAS,M.L '

For.1997.

• NRC No Deleued AfAlistion Given. Aprd 1998.

98pp. 9805180333. A3435:187. Division of Reguietory Apphcetions (Post 941217). 5 See NUREG-0304,V22,N03 abstract. HAGEMEYER,D. Science App 6cetions Intemational Corp. (foo -

merly Science Apphcetions, Inc.). February 1998. 300pp. i NURE44400 Vie: UCENSED FUEL FACluTY STATUS. 9803180118. A2009:001. l June 30, REPORT.ltwentory Difference Date. July 1,1995 TNs report summertres the occupational radiation exposure 1998.(Grey Book H) PHAM,T.N. Office of Nucieer Matsrlal information that has been reported to the NRC's Radiaton Ex-  ;

Selety & Seleguards. February 1998. 19pp. 9002250133. posure information Reporgng System (REIRS). The bulk of the A2282:178. data presented in the report was obtained from the 1998 annual NRC is committed to the periodic publicanon of Hoensed fuel radiation exposure reports submitted in accordance with the re-

. cycle faoluty irwentory difference date, foNowing Apency review quirements of 10 CFR 20.2208. The 1998 annual reports sub-  ;

of the informenon and completon of any related v.seongebons. mitted by about 284 hcensees indicated that approximately. '

informenon in this report includes inventory difference date for 138,310 individuals wore monitored,75,139 of whom were mun-l 1

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! 2 Main Citations and Abstracts itored by nuclear power facilities. They incurred an average indi- NUREG 0750 V47 N01: NUCLEAR REGUuTORY COMMISSION vidual dose of 0.1 rern (cSv) and an average measurable dose ISSUANCES FOR JANUARY 1998. Pages 1-12.

• NRC No of about 0.29 rem (cSv). Analyses of transient worker data indi- Detailed Affiliation Given. March 1998.18pp. 9803270335.

cate that 22,348 indNiduals completed work assignments at two A2755:148.

or more licensees during the ireisy year. The dose distribu- See NUREG-0750,V45 abstract.

NUREG-0750 V47 N02: NUCLEAR REGULATORY COMMISSION of transient work i by mutt n 996 -

ISSUANCES FOR FEBRUARY 1998. Pages 13-56.

• NRC - No age measurable dose calculated from reported data was 0.24 Detailed AMadon GNen. Ap1 M8. 51pp. 9805060 m cSV (rem). The corrected dose distnbution resulted in an aver- A33 age measurable dose of 0.29 cSv (rem). NUREG-0750,V45 abstract.

NUREG-0750 C104: INDEXES TO NUCLEAR REGUMTORY NUREG-0750 V47 N03: NUCLEAR REGULATORY COMM!SSION COMMISSION ISSUANCES. January 1,1991 through December ISSUANCES FOR MARCH 1998.Pages 57 75.

• NRC - No De.

31, 1995.

• NRC No Detailed Affiliation Given. November tailed Affiliation Given. April 1998. 25pp. 9805180293. i 1997. 452pp. 9803260270. A2725:001. A3428:328 Digests and indexes for issuances of the Commission, the See NUREG-0750,V45 abstract.

Atomic Safety and Licensing Appeal Panel, the Atomic Safety and LicenW: Board Panel, the Administrative Law Judge, the NUREG-0750 V47 N04: NUCLEAR REGULATORY COMMISSION Directors' Decisions, and the Decisions on Petitions for Rule- ISSUANCES FOR APRIL 1998.Pages 77 260.

• NRC No De-making are presented. tailed Affiliation Given. June 1998. 191pp. 9807060212.

A4009:044.

NUREG-0750 V45: NUCLEAR REGULATORY COMMISSION See NUREG-0750,V45 abstract.

ISSUANCES. Opinions And Decisions Of The Nuclear Regula-tory Cornmission Wrth Selected Orders. January June 1997.

• NUREG-0837 V17 N03: NRC TLD DIRECT RADIATION MONI-NRC - No Detailed Aftdiation Given. December 1997. 526pp. TORING NETWORK. Progress Report. July-September 1997. l 9802200041. A2245:001. STRUCKMEYER,R. Region 1 (Post 820201). January 199r.

Legalissuances of the Commission, the Atomic Safety and Li- 229pp. 9801260119. A1892:001.

censing Board Panel, the Administrative Law Judges, and NRC This report provides the status and results of the NRC Th v.

Program Offices are presented. moluminescent Dosimeter (TLD) Direct Radiation Monitorin?

Network. It presents the radiation levels measured in the vicinity NUREG 0750 V46101: INDEXES TO NUCLEAR REGULATORY of NRC licensed facilities throughout the country for the third l

COMMISSION ISSUANCES. July-September 1997.

• NRC - No quarter of 1997.

Detailed Affiliation Given. March 1998. 31pp. 9803270317.

A2767:305. NUREG-0910 R03: NRC COMPREHENSIVE RECORDS DISPOSI-D6 gests and indexes for issuances of the Commission, the TION SCHEDULE.

• NRC - No Detailed Affiliation Given. Febru-Atomic Safety and Ursensing Board Panel, the Administrative ary 1998. 380pp. 9803190155. A2629:090.

Law Judges, the Directors' Decisions, and the Decisions on Pe.

Title 44 United States Code, "Public Printing and Docu-titions for Rulemaking are presented. monts," regulations issued by the General Service Administra-tion (GSA) in 41 CFR Chapter 101, Subchapter B " Manage-NUREG-0750 V46102: INDEXES TO NUCLEAR REGULATORY ment and Use of Information and Records." and regulations COMMISSION ISSUANCES.Juty-December 1997.

• NRC - No issued by the National Archives and Records Administration Detailed Affiliation Given. April 1998. 49pp. 9805050382. (NARA) in 36 CFR Chapter Xil, Subchapter 8, " Records Man-A3320196. agement," require each agency to prepare and issue a compre-See NUREG-0750,V46,101 abstract. hensive records disposition schedule that contains the NARA approved records disposition schedules for records unique to NUREG-0750 V46 NO3: NUCLEAR REGULATORY COMMISSION the agency and contains the NARA's General Records Sched-ISSUANCES FOR SEPTEMBER 1997. Pages49-193.

• NRC - ules for records common to several or all agencies. The ap-No Detailed Affiliation Given. January 1998. 151pp. proved records disposition schedules specify the appropriate 9802180098. A2195S01. duration of retention and the final disposition for records cre-See NUREG-0750,V45 abstract. ated or maintained by the NRC. NUREG4910, Rev. 3, contains "NRC's Comprehensive Records Disposition Schedule," and NUREG 0750 V46 N04: NUCLEAR REGULATORY COMMISSION the onginal authonzed apped chabon numbers issued by ISSUANCES FOR OCTOBER 1997. Pages 195-256.

• NRC - NARA. Rev. 3 incorporates NARA approved changes and addi-No Detailed Affiliation Given. February 1998. 69pp. tions to the NRC schedules that have been implemented since l 9802180103. A2195:155. the last revision dated March,1992, reflects recent organiza-l See NUREG-0750,V45 abstract.

tional changes implemented at the NRC, and includes the latest NUREG-0750 V46 N06: NUCLEAR REGULATORY COMMISSION version of NARA's General Records Schedule (dated August ISSUANCEU. FOR NOVEMBER 1997. Pages 257-285.

• NRC . 1995).

No Detail ad Affiliation Given. February 1998. 35pp. NUREG 0933 S22: A PRIORITIZATION OF GENERIC SAFETY A ISSUES. EMRIT,R. Division of Engineering Technology (Post g.207 45 aMM 941217). March 1998. 398pp. 9804080010. A2923:001.

NUREGW50 V46 N06: NUCLEAR REGULATORY COMMISSION The report presents the safety priority ranking for generic ISSUANCES FOR DECEMBER 1997. Pages 287-319.

• NRC . safety issues related to nuclear power plants. The purpose of No Detailed Affiliaten Given. March 1998. 40pp. 9803270320. these rankings is to assist in the timely and efficient allocation of NRC resources for the resolution of those safety issues that A2755:195.

See NUREG-0750,V45 abstract have a significant potential for reducing risk. The safety priority rankings are HIGH, MEDIUM, LOW, and DROP, and have been NUREG-0750 V47101: INDEXES TO NUCLEAR REGULATORY assigned on the basis of risk significance estimates, the ratio of COMMISSION ISSUANCES. January-March 1998.

• NRC - No risk to costs and other impacts estimated to result if resolution Detailed Affiliation Given. June 1998. 17pp. 9806190291. of the safety issues were implemented, and the consideration of A3903:323. uncertainties and other quantitative or qualitative factors. To the See NUREG-0750,V48,101 abstract extent practical, estimates are quantiative.

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NUREG-0936 V16 N02: NRC REGUMTORY NUREG-0940 V02 N04: NUCLEAR REGUL'. TORY 1 l AGENDA. Semiannual Report. July-December 1997.

• Office of LEGISLATION.104th Congress.

• Office of the General Counsel l l Administration, Director (Post 940714). February 1998. 68pp. (Post 880701). December 1997. 523pp. 9804160185.

9803050116. A2424:115. A2991:001.

i The NRC Regulatory Agenda is a compilation of all rules on See NUREG-0980,V01,N04 abstract.

i which the NRC has recentty completed action, or has proposed action, or is Es,L;,,v action, and all petitions for rutemaking NUREG-1022 Rot: EVENT REPORTING GUIDELINES 10 CFR which have been received by the Cv,is,;w,;on and are pending 50.72 AND 50.73. ALLISON,0.P.; HARPER.M.R.; JONES W.R.;

dispositen by the Commission. The Regulatory Agenda is up. et al. Offee for Analysis & Evaluation of Operational Data. D6-dated and issued semiannually. rector. January 1invo.175pp. 9002100113. A2079:001.

Revision 1 to NUREG-1022 clarifies the immediate notifca-

, NUREG 0640 V16 N2 P1: ENFORCEMENT ACTIONS: SIGNIF1- tion requirements of Title 10 of the Code of Federal Regula-l CANT ACTIONS RESOLVED INDIVIDUAL tions, Part 50, Secton 50.72 (10 CFR 50.72), and the 30-day ACTIONS. Semiannual Progress Report, July-December 1997.

• written licensee event report (LER) requirements of 10 CFR Ofc of Enforcement (Post 870413). April 1998. 416pp. 50.73 for nuclear power plants. This revision was initiated to im-9805210430. A3499:001. prove the reporting guidelines relaied to 10 CFR 50.72 and '

This compilation summarizes signtfcant enforcement actions 50.73 and to consolidate these guidelines into a single refer.

I that have been resolved during the period (July - Decembw ence document. A frst draft of this document was noticed for 1997) and includes copies of Orders and Notices of Violations public comment in the Fedwal Registw on Ocbbw 7,1991 @6 sent by the Nuclear Regulatory Commission to individuals with FR 50598). A second draft was noticed for comment in the Fed-

)

respect to these enforcement acdons, it is anticipated that the oral Register on February 7,1994 (59 FR 5814). This document information in this publication will be widely disseminated to updates and supersedes NUREG-1022 and its Supplements 1 managers and employees engaged in activities licensed by the and 2 (published in September 1983, February 1984, and Sep-NRC. The Cviiiew,,on believes this information may be useful tomber 1985, respectively). It does not change the reporting re-to Econsees in malung wuivnan.nt dedsions. quirements of 10 CFR 50.72 and 50.73.

NUREG-0940 V16 N2 P2: ENFORCEMENT ACTIONS: SIGNIFI-CANT ACTIONS RESOLVED REACTOR NUREG-1100 V14: BUDGET ESTIMATES. Fiscal Year 1999.

• Di-LICENSEES. Semiannual Progress Report. July December 1997. vision of Budget & Analysis (Post 890205). February 1998.

• Ofc of Enforcement (Post 870413). April 1998. 320pp. 176pp. 9802250137. A2282:001, 9805180*09. A3433227. This report contains the fiscal year budget justifcation to Con.

This compilation summartzes signifcant enforcement actions gress. The budget provides estimates for salaries and expenses that have been resolved during the period (July December and for the Offee of the inspector General for fiscal year 1999.

1997) and includes copies of letters, Notices, and Orders sent NUREG-1125 V19: A COMPILATION OF REPORTS OF THE AD-by the Nuclear Regulatory Commission to reactor licensees with VISORY COMMITTEE ON REACTOR SAFEGUARDS.1997 respect to these enforcement actions. It is anticipated that the Annual.

• ACRS - Advisory Committee on Reactor Safeguards.

Informadon in this publication will be widely disseminated to April 1998. 222pp. 9806010317. A3572:070.

managers and employees engaged in activities licensed by the This compilation contains 67 ACRS reports submitted to the NRC, so that actions can be taken to improve safety by avoid- Commission, or to the Executive Director for Operations, during ing future violabons similar to those described in this publica- calendar year 1997. It also includes a report to the Congress on tion. the NRC Safety Research Program. All reports have been made NUREG-0940 V16 N2 P3: ENFORCEMENT ACTIONS: SIGNIFl. available to the public through the NRC Public Document CANT ACTIONS RESOLVED MATERIAL Room, the U. S. Library of Congress, and the Internet at http://

LICENSEES. Semiannual Progress Report. July-December 1997. www.nrc. gov /ACRSACNW. The reports are categorized by the

• Ofc of Enforcement (Post 870413). April 1998. 407pp. most appropriate generic subject area and by chronological 9806010324. A3570:001. order within the subject area.

This compilation summartzes signifcant enforcement actions NUREG-1187 V01: PERFORMANCE INDICATORS FOR OPER.

that have been resolved during the period (July - Decembet ATING COMMERCIAL NUCLEAR POWER REACTORS. Data 1997) and includes copies of letters, Notices, and Orders sent Through September 1997.

• Office for Analysis & Evaluation of by the Nuclear Regulatory Commission to material licensees Operational Data, Director. January 1998. 485pp. 9802110145.

with respect to these enforcement actions. It is anteipated that A2094201 the information in this publication will be widely disseminated to This Nuclear Regulatory Commission (NRC) report provides marmgers and employees engaged in activities licensed by the performance ;ndicator data, accounting for the different oper.

NRC, so that actions can be taken to improve safety by avoid- ational conditions, through September 1997 for 109 reactors.

Ing future violations similar to those described in this publica- There are eight NRC Performant'e Indicators for Operating Commercial Nuclear Power Plants. (1) automatic scrams while NUREG 0900 V01 N04: NUCLEAR REGULATORY critical, (2) safety system actuations, (3) signifcant events, (4)

LEGISLATION.104th Congress.

• Offee of the General Counsel safety system failures, (5) forced outage rate (6) equipment (Post 860701). December 1997. 594pp. 9804160178. forced outages per 1000 commercial entcal hours, (7) collective A2992:100. radiation exposure, and (8) cause codes. This report is based l This document is a compilation of nuclear regulatory le9ise on data extracted from Licensee Event 90 ports (LERs) submit.

l tion and other relevant material through the 104th Congress,2d ted in accordance with 10 CFR 50.73,9:nediate notifications to Session. This compilation has been prepared for use as a re- the NRC Operations Center in accore.1ce with 10 CFR 50.72, cource document, which the NRC intends to update at the end monthly operating reports in accordance with plant technical of every Congress. The contents of NUREG-0980 include The specifcatbns, and screening of operating experience by NRC Atomic Energy Act of 1954, as amended; Energy Reorganiza- staff. Radiation exposure data are obtained from the Institute of tion Act of 1974, as amended, Uranium Mill Tallings Radiation Nuclear Power Operations (INPO). Graphical presentations of Control Act of 1978; Low-Level Radioactive Waste Policy Act; each plant's data, including trends and deviations analyses are Nuclear Waste Policy Act of 1982; and NRC Authortzation and provided, as well as tabulated summaries of the data. The Appropriations Acts. Other materials included are statutes and trends and devistx)ns analyses and tabulated summaries have l treaties on export licensang, nuclear non-proliferation, and envi- been presented and calculated accounting for the plants oper-ronmental protection. ational conditions.

4 Mah Citations and Abstracts cially available portable field instruments being used to conduct NUREG-1272 V10 N01: OFFICE FOR ANALYSIS AND EVALUA-TION OF OPERATIONAL DATA.1996 Annual Report,

• Office radiological surveys in support of decommissioning. The U.S.

for Analysis & Evaluation of Operanonal Data, Director. Decem- Nuclear Regulatory Commission (NRC) has amended its regula-ber 1997,265pp. 9804080062. A2920:001. tions to establish residual radioactMty crtteria for decomrnis-This annual report of the U.S. Nuclear Regulatory Commis- sioning of licensed nuclear facilities. In support of that rulemak-sion's Office for Analysis and Evaluation of Operational Data ing, the Commission has prepared a Generic Environmental (AEOD) describes activities conducted during 1996. The report impact Statement (GEIS), consistent wtth the National Environ-is published in three parts. NUREG-1272, Vol. G, No.1, covers mental Policy Act (NEPA). The effects of this new ulemaking power reactors and presents an overview of tra operating expe-on the overall cost of decommissioning are among the many rience of the nuclear power industry from the NRC perspective, factors consir'ared in the GEIS. The overall cost includes the including comments about trends of some performance meas- costs of decontamination, waste disposal, and radiological sur-ures. The report also includes the principal findings and issues veys to demonstrate compliance with the applicable guidelines.

identified in AEOD studies over the past year and summertzes An important factor affecting the costs of such radiological sur.

Information from such sources as licensee event reports and re- voys is the minimum detectable concentration (MDC) of field ports to the NRC's Operations Center. NUREG-1272, Vol.10, survey instruments in relation to the residual radioactMty crite-No. 2, covers nuclear materials and presents a review of the ria. The purpose of this study was two-fold. First, the data were events and concems during 1996 associated wtth the use of 16 used to de' ermine the validity of the theoretical minimum de-consed material in nonreactor applications, such as personnel tectsble concentrations (MDCs) used in the GEIS. Second, the overexposures and medical misadministrations. Both reports results of the study, published herein, provide guidance to li-also contain a discussion of the incident investigation Team consees for (a) selection and proper use of portable survey in-program and summarize both the incident investigation Team struments and (b) understanding the field conditions and the and Augmented inspection Team reports. Each volume contains extent to which the capabilities of c 4 instruments can be hm-(

' a list of the AEOD reports issued from CY 1980 through 1996. Ited. The types of instruments co.1 H1 used in fieid radiologi-NUREG-1272, Vol 10, No. 3, covers technical training and pre- ca' surveys that were evaluated inctuuwd, in part, gas propor-sents the activities of the Technical Training Center in support tional, Geiger-Mueller (GM), zinc autfide (ZnS), and sodium of the NRC's mission in 1996. lodide (Nal) detectors.

NUREG-1272 V10 NO2: OFFICE FOR ANALYSIS AND EVALUA* NUREG 1542 V03: ACCOUNTABILITY REPORT FISCAL YEAR TlON OF OPERATIONAL DATA.1996 Annual Report.

• Office 1997. CONNELLY,S.R. Office of the Controller (Post 890205).

for Analysis & Evaluation of Operatonal Data, Director. Decem- March 1998. 92pp. 9804200258. A3031:011.

bor 1997.136pp. 9805050445. A3319:255- The U.S. Nuclear Regulatory Commission (NRC) is one of See NUREG-1272,V10,N01 abstract. several Federal agencies participating in a pilot project to streamhne financial management reporting. The goal of this pilot NUREG-1272 V10 N03: OFFICE FOR ANALYSIS AND EVALUA. is to consolidate performance-related reporting into a single ac-TION OF OPERATIONAL DATA.1996 Annual Report.

• Office countability report in accordance with the Govemment Manage-for Analysis & Evaluation of Operational Data Director. Decem.

ber 1997. 42pp. 9805060124. A3321:069.

ment Reform Act (GMRA) of 1994. The NRC's third account-abihty report consolidates the information previously reported in See NUREG-1272,V10,N01 abstract. the NRC's annual financial statement required by the Chief Fi-NUREG 1363 V07: ATOMIC SAFETY AND LICENSING BOARD nancial Officers Act of 1990, as amended; the chairman's BIENNIAL REPORT. Fiscal Years 1995 1996.* Atomic Safety annual report to the President and the Congress, required by

& Licensing Board Panel. June 1998. 51pp. 9806290363. the Federal Managers Financial integrity Act of 1982; and the A3958:240. Chairman's semiannual report to the Congress on management The Panel handled 33 cases in fiscal Year 1995 and 29 decisions and final actions on Office of Inspector General (OlG) cases in fiscal Year 1996. This report summarizes, highlights- audit recommendations, required by the Inspector General Act and anatyzes how the wide-ranging issues raised in these cases of 1978, as amended. This report also includes performance were addressed by the Panel's licensing boards and presiding measures, as required by the Chief Financial Officers Act, the officers during this period. This report also describes the Govemment Performance Results Act of 1993, and the Chair.

Panel's other responsibihties, addresses the status of Panel ac- man's statement on the compliance of the agency's financial tivities, and reports on present and projected future caseloads. management systems with the Federal Financial Management improvement Act of 1996, NUREG-1415 V10 N02: OFFICE OF THE INSPECTOR GENERALSemiannual Report To Congress.Octotw 1,1997 - NUREG-1560 V01 P1: INDIVIDUAL PLANT EXAMINATION PRO-March 31,1998.

• Office of the inspector General (Post GRAM: PERSPECTIVES ON REACTOR SAFETY AND PLANT 890417). June 1998. 36pp. 9807060272. A4009:318. PERFORMANCE. Summary Report.

• Division of Systems Tech.

The inspector General Act of 1978, as amended, requires nology (Post 941217). December 1997. 257pp. 9802200064.

that inspectors General submit a Semiannual Report to Con- A22R001 gress" summartzing program activities. The inspector General's This report provides perspectrves gained by reviewing 75 Indi-report is submitted to the Chairman of the haC not later than vdual Plant Examination (IPE) submittals pertaining to 108 nu-April 30 and October 31 for each reporting penod. The Chair- clear power plant units. IPEs are probabilistic analyses that esti-man comments on the report and prepares the NRC's Semian- mate the core damage frequency (CDF) and containment per-nual Report to Congress as required by the Act. The Chairman formance for accidents initiated by intemal events (including in-then submits the agency's report and the OlG s report to Con- temal floods, but excluding internal fire). The U.S. Nuclear Reg-gress no later than November 30 and Mey 31, respectively, ulatory Commission (NRC), Office of Nuclear Regulatory Re-search, reviewed the IPE submittals with the objeme of gain-NUREG-1507: MINIMUM DETECTABLE CONCENTRATIONS WITH TYPICAL RADIATION SURVEY INSTRUMENTS FOR ing perspectives in three major areas: (1) improvements made to individual plants as a result of their IPEs and the cohectrve VARIOUS CONTAMINANTS AND FIELD CONDITIONS. results of the IPt! program, (2) plant-specific design and oper.

ACLOUIST.E.W. Oak Ridge Associated Universities.

BROWN,W.S. Brookhaven National Laboratory. POWERS,G.E.; stsonal features and modeling assumptions that significantly et at Division of Regulatory Apphcations (Post 941217). June affect the estimates of CDF and containment performance, and 1998.194pp. 9806190288. A3903.157. (3) strengths and weaknesses of the models and methods used This document describes and quantitatively evaluates the ef- in the IPEs. These perspectives are gained by assessing the fects of various factors on the de*ection sensitivity of commer- core damage and containment performance resuits, including

l l

Main Citations and Abstracts 5 1 I

overall CDF, accident segue ices, dominant contributions to the i ment is applicable to enforcement matters invoMng radiological 1 design and operational cruracteristics of the various reactor health and safety of the public, including employees' health and and containment types, and by comparing the IPEs to probabi- safety, the common defense and security, and the scrA ,,,,ent.

listic risk assessment characteristics. Methods, data, boundary This staterr.snt of general policy and procedure is published as conditions, and assumptions used in the IPEs are considered in NUREG-1600, Rev.1 to provide wide spread dissemination of understanding the difference and similartties observed among the Commission's Enforcement Policy. However, this is a policy the various types of plants. statement and not a regulation. The Commiss6on may deviate NUREG-1500 V02 P2-5: INDIVIDUAL PLANT EXAMINATION #om a matement of pow W pmcehe as app @te PROGRAM: PERSPECTIVES ON REACTOR SAFETY AND under the Mmhnces d a @lar cast PLANT PERFORMANCE.

• Division of Systems Technology (Post 941217). December 1997. 546pp. 9802200072. NUREG-1622: NRC ENFORCEMENT POLICY REVIEW. July 1995 A2246:163. - July 1997. LIEBERMAN,J.; PEDERSEN,R.M. Ofc of Enforce.

See NUREG-1560,V01,P1 abstract. ment (Post 8'D413). April 1998. 66pp. 9805060112. A3321:001.

On June 30,1995, the Nuclear Regulatory Commission (NRC)

NUREG-1660 V03 P6: INDIVIDUAL PLANT EXAMINATION PRO. lasued a complete revision of its General Statement of Policy GRAM: PERSPECTIVES ON REACTOR SAFETY AND PLANT and Procedure for Enforcement Actions (Enforcement Policy)

PERFORMANCE. Appendices.

• Division of Systems Technology (60 FR 3481). In approving the 1995 revision to the Enforce.

(Post 941217). December 1997. 46pp. 9802200077 A2249:302. ment Policy, the Commission directed the staff to perform a See NUREG-1560,V01,P1 abstract. review of its implementation of the Policy after approximately 2 NUREG-1570: RISK ASSESSMENT OF SEVERE ACCIDENT-IN- fe* eprs DUCED STEAM GENERATOR TUBE RUPTURE.

• Office of the re of the evie Nuclear Reactor Regulation (Post 941001). March 1998. 218pp.

9803310390. A2839:001. NUREG-1624 DRFT FC: TECHNICAL BASIS AND IMPLEMENTA-This report describes the basis, results, and related risk impli- TION GUIDELINES FOR A TECHNIQUE FOR HUMAN EVENT ANALYSIS (ATHEANA). Draft Report For Comment.

• Probabilis-cations of an analysis performed by an ad hoc working group to assess the containment bypass potential attributable to steam tic Risk Analysis Branch (Post 941217). May 1998. 404pp.

9806080242. A3687:001.

generator tube rupture (SGTR) induced by severe accident con-This report introduces a next-generation HRA method called ditions. The SGTR Severe Accident Working Group, comprised "A Technique for Human Event Analysis," (ATHEANA). AT9-of staff members from the NRC's Offices of Nuclear Reactor EANA was developed to address limitations identified in current Regulation (NAR) and Nuclear Regulatory Research (RES), un-HRA approaches by: (1) addressing errors of commission and dertook the analysis beginning in December 1995 to support a dependencies; (2) more realistically representing the human-proposed steam generator integrity rule. The work drew upon system interactions that have played important roles in accident previous risk and thermal-hydraulic analyses of core damage response; and (3) integrating advances in psychology with engi-sequences, with a focus on the Surry plant as a representative neering, human factors, and PRA disciphnes. This report is the example. This anatysis yielded new results, however, derived by step-by-step guidebook foi applying the method. It describes predicting thermal hydraulic condit#ons of selected severe acc" how to: (1) select and organize the ATHEANA team, (2) perform dent scenarios using the SCDAP/RELAPS computer code, and control the structured search processes for human failure flawed tube failure modeling, and tube failure probability esti-events and unsafe acts, including a discussion of the reasons mates. These results, in terms of containment bypass probabili-that such events occur (i.e., the elements of error-forcing con-ty, form the basis for the findings presented in this report-text), (3) use the knowledge encoded in the PRA siong with the NUREG 1575: MULTI-AGENCY RADIATION SURVEY AND SITE specialized knowledge and experience of the ATHEANA team INVESTIGATION MANUAL (MARSSIM). Final Report.

• NRC . to focus the searches on those events and reasons that are No Detailed Affiliation Given.

• Defense, Dept. of. *; et af. most likely to affect the ri6k, and (4) quantify the error-forcing Energy, Dept. of. December 1997. 665pp. 9802200046. EPA. contexts and probability of each unsafe act, given its context.

402R-97-016. A224S:001 The MARSSIM p'ovides information on planning, conducting, NUREOC626: FINAL ENVIRONMENTAL IMPACT STATEMENT evaluating, and documenting building and surface son final FOR THE CONSTRUCTION AND OPERATION OF AN INDE-status rad 6ological surveys for demonstrating compliance with PENDENT SPENT FUEL STORAGE INSTALLATION TO dose or risk-based regulations or standards. The MARSSIM is a STORE THE THREE MILE ISLAND UNIT 2 SPENT FUEL AT multi-agency consensus document that was developed collabo- THE IDAHO NATIONAL ENGINEERING AND ENVIRONMEN-ratively by four Federal agencies having authority and control TAL.

• Office of Nuclear Material Safety & Safeguards. March over radioactive materials: Department of Defense (DOD), De. 1998. 219pp. 9803180129. A2611:303.

partment of Energy (DOE), Environmental Protection Agency This Final Environmental impact Statement (FEIS) was pre-(EPA), and Nuclear Regulatory Commission (NRC). The MARS- pared by the U.S. Nuclear Regulatory Commission in accord-SIM's ob}ective is to describe a consistent approach for building ance wtth the requirements of 10 CFR Part 51. The FEIS con-and surface snit final status surveys to meet established dose tains an assessment of the potential environmental impacts of or risk-based release criteria, while at the same time encourag- the construction and operation of an independent Spent Fuel ing an effective use of resources. Storage installation (ISFSI) for the Three Mile Island Unit 2 (TMI-2) fuel debris at the Idaho National Engineering and Envi-NUREG 1600 R01: GENERAL STATEMENT OF POLICY AND ronmental Laboratory (INEEL). The NRC proposes to issue a li-PROCEDURE FOR NRC ENFORCEMENT conse to the U.S. Department of Energy-Idaho Operations ACTIONS. Enforcement Policy.

• Ofc of Enforcement (Post Offee (DOE-ID) which will authorire DOE-ID to store the TMI-2 8704t3). May 1998. 32pp. 9806030386. A3636:272.

fuel debns in an ISFSt. DOE-ID is proposing to design, con-TNs document includes the U.S. Nuclear Regulatory Commis- struct, and operate at the Idaho Chemeal Processing Plant nion's (NRC's or Commission'6) revised General Statement of (ICPP). The TMI-2 fuel debris would be removed from wet stor-Policy and Procedure for Enforcement Actions (Enforcement age at the Test Area North pool, transported to the ISFSI at the Policy) as it was published in the Federal Register on May 13, ICPP, and placed in storage modules on a concrete basemat.

1998 (63 FR 26630). The Enforcement Policy is a general state-ment of policy explaining the NRC's policies and procedures in NUREG-1627 V01: PERFORMANCE PLAN FY 1909.

initiating enforcement actions, and of the presiding officers and FUNCHES,J.L NRC - No De: ailed Affiliation Given. February the Commission in reviewmg these actions. TNs policy state- 1998. 91pp. 9805200007. A3468:006.

l 6 Main Citations and Abstracts The NRC's performance plan complements the agency's stra. The public " Workshop on Review of Dose Modeing Methods i togic plan by setting annual goals wtth measurabl9 target levels for Demonstration of Compliance with the Radiological Crtteria l of performance for FY 1999, as required by the Goverrnment for License Termination" was held at the NRC Headquarters

! Performance and Results Act. Auditorium, Rockville, Ms yland, on November 13-14,1997. The l workshop was one in a series to support NRC staff develop-l NUREG-1629: THE CHARACTER!ZATION OF VICKER'S MICRO- ment of guidance for implementing the final rule on "Radiologi-HARDNESS INDENTATIONS AND PILE-UP PROFILES AS A cal Crtteria for Ucense Terminston." The workshop topics in.

STRAIN-HARDENING MICROPROBE. SANTOS,C. Division of ciuded discussion of: dose models used for decommissioning Engineering Technology (Post 941217). ODETTE,G.R.; reviews; identification of criteria for evaluating the acceptability LUCAS,G.E.; et al. Califomia, Univ. of, Santa Barbara, CA. April of dose models; and selection of parameter values for demon-1998.153pp. 9805180231. A3428:008. strating compliance with the final rule. The 2-day public work-Microhardness measurements have long been used to exar* shop was jointly organized by RES and NMSS staff responsible lne strength properties and changes in strength properties in for reviewing dose modeling methods used in decommissioning metals, for example, as induced by irradiation. Microhardness reviews. The workshop was noticed in the Federal Register (62 affords a relatively simple test that can be applied to very small FR 51706). The workshop presenters included: NMSS and RES volumes of natorial. Microhardness is nominally related to the staff, who discussed both dose modeling needs for licensing re-

, flow stress of the material at a fixed level of plastic strain. Fur- views, and development of guidance related to dose modeling

! ther, the geometry of the pile up of r. storial around the indenta- and parameter selection needs DOE national laboratory scien-l tion is related to the strain-hardenirg behavior of the material; tists, who provided responses to earlier NRC staff <leveloped l steeper pile-ups correspond to smaller strain hardening rates. In questions and discussed their vanous Federally-sponsored dose this study the relationship between pile-up profiles and strain models (i.e., DandD, RESRAD, and MEPAS codes); and an EPA harderung is examined using both experimental and analytical scientist, who presented details on the EPA dose assessment methods. Vicker's microhardness tests have been performed on model (i.e., PRESTO code). The workshop was formatted to i a variety of metal alloys including low alloy, high Cr and austen- provide opportunities for the attendees to observe computer l

Itic stainless steels. The pile-up topology around the indenta- demonstrations of the dose codes presented. More than 120 tions has been quantrfied using confocal microscopy tech' workshop attendees from NRC Headquarters and the Regions, niques. In addition, the indentation and pile-up geometry has Agreement States; as well as industry representatives and con.

been simulated using finite element method techniques. These sultants; scientists from EPA, DOD, DNFSB, DOE, and the na-results have been used to develop improved quantification of tional laboratories; and interested members of the public partici-the relationship between pile-up geometry and the strain hard- pated. A complete transcript of the workshop, including view-ening constitutive behavior of the test matenal. graphs and attendance lists, is available in the NRC Pubhc Doc-I ument Room. This NUREG/CP documents the formal presenta-NUREG/CP-0162 V01: PROCEEDINGS OF THE TWENTY-FiFTH WATER REACTOR SAFETY INFORMATION MEETING. Plenary tions made dunng the workshop, and provides a preface outlire Sessions, Pressure Vessel Research,BWR Strainer Blockage ing the workshop,a focus, objectives, background, topics and And Other Generic Safety issues. Environmentally Assisted Deg- questions provided to the invited speakers, and those raised during the panel discussion. NUREG/CP 0163 also provides radation Of LWR.... MONTELEONE.S. Brookhaven National Laboratory. March 1998. 370pp. 9805180401. A3427:001. technical bases supporting the development of decommissiord j This three-volume report contains papers presented at the ing guidance.

Twenty-Fifth Water Reactor Safety Information Meeting held at NUREG/CR-4564 VD1 R2: SCANS (SHIPPING CASK ANALYSIS the Bethesda Marriott Hotel, Bethesda, Maryland, October 20- SYSTEM) A MICROCOMPUTER BASED ANALYSIS SYSTEM 22,1997. The papers are printed in the order of their presenta* FOR SHIPPING CASK DESIGN REVIEW. User's Manual to Ver-tion in each session and describe progress and results of pro- sion 3a. MOK,G.C.; THOMAS.G.R.; GERHARD,M.A.; et al Law-grams in nuclear safety research conducted in this country and rence Livermore National Laboratory. March 1998. 219pp.

abroad. Foreign participation in the meeting included papers 9803260397. UCID-20674. A2727.001.

presented by researchers from France, Japan, Norway, and SCANS (Shipping Cask Analysis System) is a microcomputer Russia. The titles of the papers and the names of the authors based system of computer programs and databases developed have been updated and may differ from those that appeared in at the Lawrence Livermore National Laboratory (LLNL) for eval-the final program of the meeting. usting safety analysis reports on spent fuel shipping casks.

NUREG/CP-0162 V02: PROCEEDINGS OF THE TWENTY-F FTH SCANS is an easy-to-use system that calculates the global re-WATER REACTOR SAFETY INFORMATION MEETING. Human sponse to impact loads, pressure loads and thermal conditions, Reliability Analysis And Human Performance Evaluation, Techni- pr Mng rwiewws with an mdependent check m anaWs cal lasues Related To Rulemakings, Risk-informed, Perform- 8*"itted by licensees. SCANS is based on microcomputers ance-Based initiatives. MONTELEONE,S. Brookhaven National cmpatible with the IBM-PC family of computers. The system is Laboratory. March 1998. 235pp. 9805180394. A3425:048. composed of a series of menus, input programs, cask analysis See NUREG/CP-0162,V01 abstract. programs, and outpt display programs. All data is entered through fill-in-the ;,;ank input screens that contain descriptrve NUREG/CP 0162 V03: PROCEEDINGS OF THE TWENTY-FIFTH data requests. Analysis options are based on regulatory cases WATER REACTOR SAFETY INFORMATION described in the Code of Federal Regulations 10 CFR 71 and MEETING. Thermal-Hydraulic Research And Codes, Digital in- Regulatory Guides published by the U.S. Nuclear Regulatory strumentation And Control, Structural Performance. Commission in 1977 and 1978.

MONTELEONE.S. Brookhaven National Laboratory. April 1998.

358pp. 9805180351. A3423901. NUREG/CR-4667 V24: ENVIRONMENTALLY ASSISTED CRACK-See NUREG/CP-0162,V01 abstract. ING IN LIGHT WATER REACTORS. Semiannual Report, January-June 1997. CHOPRA,0.K.; CHUNG,H.M.;

NUREG/CP-0163: PROCEEDINGS OF THE WORKSHOP ON GRUBER E.E.; et al. Argonne National Laboratory. April 1998.

REVIEW OF DOSE MODELING METHODS FOR DEMON- 115po. 9805180239. ANL-98/6. A3428:161.

STRATION OF COMPLIANCE WITH THE RADIOLOGICAL CRI- This report summanzes work performed by Argonne National TERIA FOR LICENSE TERMINATION. NICHOLSON,T.J. Divi- Laboratory on fatigue and environmentally assisted cracking sion of Regulatory Applications (Post 941217). PARROTT J.D. (EAC) in hght water reactors from January 1997 to June 1997.

Division of Waste Management (NMSS 940403). May 1998. Topics that have been investigated include (a) fatigue of 123pp. 9806080229. A3688:041. carbon, low alloy, and austenitic stainless steels (SSa) used in

Main Citations and Abstracts 7 reactor pi@'s and pressure vessels, b) Irradiation-assisted NUREG/CR-5562: DATING AND EARTHOUAKES: REVIEW OF strees corrosion cracking of Types 304 and 304L SS, and (c) OUATERNARY GEOCHRONOLOGY AND ITS APPLICATION EAC of Alloys 600 and 600. Fatigue tests were conducted on TO PALEOSEISMOLOGY, SOWERS,J.M.; LETTC W.R. Affill- l ferrttic and austeninc SSa in water that contained various con- ation Not Assigned. NOLLER J.S. Vanderbilt Univ., Nashville, I contrations of dienoNed oxygen (DO) to determine whether a TN. March 1998. 850pp. 9807100109. A4103:001. I slew strain rate appleed during various portions of a tensile-load- Quatemary 96w,,dagy, or the dating of Quaternary de-Ing cycle is equally effective in decreaseng fatigue life. Slow. posits and landforms, is critical to palooseismo;0gy; it rrovides strandrate-tensile tests were conducted in simulated boiling the means of assessing rates of deformation and the timing of water reactor (BWR) water at 288 degrees C on SS specimens past displacements. This report provides: (1) reviews of twenty-Irradiated to a low fluence in the Halden reactor and the resutta two Quatemary geochronologic methods, each authored by an were compared with similar data from a control-blade sheath acthe researcher, (2) a discussion of the application of geoch-and neutron-absorbar tubes irradiated in BWRs to the same ronobgy to paleosesmology, including twelve separately au-fluence level. Crack-growttwate tests were conducted on com- thored case studies, and (3) the results of four original field and pact-tension specimens from several heats of Alloys 600 and laboratory studies. Quatemary geochronology is a growing field 690 in low-DO, simulated pressurized water reactor envirorw in which new methods are being devebped and existing meth-monts, ods are being improved, resulting in a large selection of meth-ods and greater accuracy and applicabHity for most methods, in NUREQ/CR 4474 Y25: PRECURSORS TO POTENTIAL SEVERE addition, most dating methods are undergoing continued testing l CORE DAMAGE ACCIDENTS: 1996. A Status Report. to better understand their limitations and applicability. This has BELLES.R.J.; CLETCHER,J.W.; COPINGER,D.A.; et al. Oak led to more effective application, and occasionally, decreased Ridge National Laboratory. December 1997. 271pp. use of sWie methods. Despite the many dating methods 9802200043. ORNL/NOAC 232. A2250:001. available and these new advances, obtaining accurate and pre.

TNs report describes the 14 operational events in 1996 that cise age estimates of Quatemary deposits and landforms re-affected 13 commercial light-water reactors and that are consid- a s a chaHenge. Best results are obtained when the pale ered to be precursors to potential severe core damage acci- seism I gist and geochronologist closety collaborate, when age dents. All these events had conditional probabilities of subse- estimates are venfied by the application of multple dating meth-quent severe core damage greater than or equal to 1.0 x 10(4).

8 m anaWs accwnts 6 aH swces of uncedainy, s a uWgo WhnM pw rwiew.

These events were identified by first computer-screening the 1996 licensee event reports from commercial light-water reac- NUREG/CR 5591 V04 N1: HEAVY-SECTION STEEL IRRADIA- ,

tors to identify those events that could potentially be precursors. TION PROGRAM. Semiannual Progress Report For October l Candglate precursors were selected and evaluated in a process 1992 Through March 1993. CORWIN.W.R. Oak Ridge National similar to that used in previous assessments. Selected events Laboratory. April 1998. 50pp. 6006180222. ORNL/TM-11568.

underwent engineering evaluation that identified, analyzed, and A3428;277.

documented the precursors. Other events designated by the The primary goal of the Heavy-Section Steel irradiation Pro-Nuclear Regulatory Commission (NRC) also underwent a similar gram is to provide a thorough, quantitatue assessment of ef-evaluation. Finally, documentsd precursors were submitted for facts of r:eutron irradiahon on material behavior, and in particu-review by licermees and NRC headquarters and regional offices far the fracture toughness properties, of typical pressure vessel to ensure the plant design and its response to the precursor steels as they relate to light-water reactor pressure-vessel integ-were correctfy characterized. This study is a continuation of ear- rity. Effects of specimen size, material chemistry, product form lier work, which evaluated 1969-1995 events. The report dis. and microstructure, irradiation fluence, flux, temperature and cusses the general rationale for this study, the selection and spectrum, and post-irradiation annealing are being examined on documentation of events as precursors, and the estimation of a wide range of fracture properties. Dunng this reporting period, conditional probabilities of subsequent severe core camage for irradiated crack-arrest specimens were tested; charpy V-notch the events. specimens of high-cooper weld metal were annealed and tested; a fracture mechanics evaluation of the unirradiated Mid-NUREG/CR-5361: SEISMIC ANALYSIS OF PIPING. Final Program land low upper-shelf weld was nearty completed; irradiation of Report. JAOUAY,K. June 1998. 400pp. 9807060324. the first large Midland capsule was completed; refined calcula-A4008:001. tions and detailed experimental measurements of the exposure This report provides a summary of the work conducted by the parameters in the High Flux Isotope Reactor were evaluated; in- ,

Energy Technology Engineering Center (ETEC) under the U.S. cavity irradiation of vessel support matenals were completed; Nuclear Regulatory Commission Seismic Analysis of Piping Pro- unirradiated microstructural characterizabon of a Russian reac-gram. ETEC was contracted by the NRC to review the technical for vessel steel was completed; collaborative investigations of bases for new rules in the ASME Boiler and Pressure Vessel in-cascade point-defect generat;on experiments and investiga-Code, Section ill related to seismic analysis of piping systems in tions of a very wide range of Hux Iwels m low 4empwature en nuclear power plants, and evaluate the cumulatue impact of brittlement were initated; baseline testing for an ASTM round these changes in design criteria on overall safety margins of robin on reconstituted Charpy V-notch specimens was complet-these piping systems. The ETEC effort is documented in this 4 inimnal agreement was reached on cohaborabe m pms-

,,pgg sure vessel material from the Japan Power Derronstration Re-actor; impact and tensile specimens of two U.S. reactor vessels NUREG/CR-5602: ENGINEERING DRAWINGS FOR 10 CFR matenals wwe scapsulated and irradiation begun in a Russian PART 71 PACKAGE APPROVALS. SHEAFFER.M.K.; reactor; and tensile and impact specimens were tested for three THOMAS,G.R.: DANN.R.K.; et al. Lawrence Livermore National stainless steel welds aged for up to 20.000 h.

Laboratory. May 1998. 20pp. 9806100427. URCL-ID-130438. NUREG/CR-5591 V08 N1: HEAVY-SECTION STEEL IRRADIA-A3728:158. TION PROGRAM. Semiannual Progresp Report For October This report provides information for preparing drawings of 1996 Through March 1997. ROSSEEL,T.M. Oak Ridge National transportation packages submitted in an applicabon for approval Laboratory. February 1998. 66pp. 9803180030. ORNL/TM-under 10 CFR Past 71. It discusses the purpose of these draw- 11568. A2812:158.

Ings and describes the recommended format and technical cun- Maintaining the integnty of the reactor pressure vessel (RPV) i tent appropriate for package applicabons. Examples of frequent- in a light-water-cooled nuclear power plant is crucial in prevent-l ly used drawing symbols are also provided. ing and controlling severe accidents that have the potential for l

8 Main Citations and Abstracts major contamination release. Because the RPV is the onty key transients and instability issues. Chapter 1 is an overview of the safety-related 00dpOnent of the piant for which a redundant code's capability and limitations; Chapter 2 discusses the neu-backup system does not exist, it is imperative to fully under- tron kinetics modeling and the implementation of reactivtty edas.

stand the degree of irradiation-induced degradation of the Chapter 3 is an overview of the heat conduction calculations.

RPV's fracture resistance that occurs during service. For this Chapter 4 presents modifications to the thermal hydraulics reason, the Heavy-Section Steel Irradiation (HSSI) Program has model of the vessel, recirculation loop, steam separators, boron been established. Its primary goal is to provide a thorough, transput and SBWR specific components. Chapter 5 describes quantitative assessment of the effects of neutron irradiation on modehng of the plant control and safety systems. Chapter 6 tne material behavior and, in particular, the fracture toughness presents the modeling of Balance of Plant (BOP). Chapter 7 de-properties of typical pressure-vessel steels as they relate to scribes the mechanistic containment rnodel in the code. The light-water RPV integrity. Effects of specimen size; material content of this report is complementary to the RAMONA-3B chemistry; product form and microstructure; irradiation fluence, code desenptron and assessment document.

flux, temperature, and spectrum; and postirradiation annealing are being examined on a wide range of fracture properties. The NUREG/CR4359 V02: RAMONA-4B: A COMPUTER CODE WITH HSSI Program is arranged into seven tasks: (1) program man- THREE-DIMENSIONAL NEUTRON KINETICS FOR BWR AND agement, (2) Irradiation effects in engineering materials, (3) an- SBWR SYSTEM TRANSIENTS. User's Manual. ROHATGI,U.S.;

nealing, (4) microstructural analysis of radiation effects, (S) in. CHENG,H.S.; KHAN,H.J.; et al. Brookhaven National Laborato-service irradiated and aged material evaluations, (6) fracture ry. March 1998. 350pp. 9803190151, BNL-NUREG-52471.

toughness curve shift method, (7) special technical assistance, and (8) foreign research interactions. The work is performed by the Oak Ridge National Laboratory. This document is the User's Manual for the Boiling Water Reactor (BWR), and Simplified Boiling Water Reactor (SBWR)

NUREQ/CR4119 V01 R1: MELCOR COMPUTER CODE systems transient code RAMONA-4B. The code uses a thres.

MANUALS. Primer And Users' Guides, Version 1.8.4, July 1997. dimensional neutron-kinetics model coupled with a multichannel GAUNTT,R.O.; COLE,R.K. Sandia National Laboratories. nonequilibrium, dnft-flux, two-phase flow model of the thermal HODGE.S.A.; et al. Oak Ridge National Laboratory. May 1998.

hydraulics of the reactor pressure vessel. The code is designed 615pp. 9806100430. SAND 97-2398. A3726:001.

to analyze a wide spectrum of BWR and SBWR core and MELCOR is a fully integrated, engineering-level computer system transients. Chapter 1 gives an overview of the code's code that models the progression of severe accidents in light water reactor nuclear power plants. MELCOR is being devel- 2 dMW N @'s oped at Sandia National Laboratories for the U.S. Nuclear Reg, structure, hsts major aubroutines, and discusses the computer ulatory Commission as a second-generation plant risk assess- requirements. Cha'ter 3 provides the instructions for installing ment tool a.id the successor to the Source Term Code Pack, and running the RAMONA-4B code on sun SPARC and IBM age. A broad spectrum of severe accident phenomena in both workstations. Chapter 4 contains component desenptions and boiling and pressurtzed water reactors is treated in MELCOR in detailed card-by-card input instructions. Chapter 5 gives sam-a unified framework. These include thermal-hydraulic response pies of the tabulated output for the steady-state and transient in the reactor coolant system, reactor cavity, containment, and calculations and discusses the plotting procedures for the confinement buildings; core heatup, degradation, and relocation; steady-state and transient results. Three appendices contain im-core. concrete attack; hydroren production, transport, and com- portant user and programmer information: lists of plot variables bustson; fission product rolease and transport behavior. Current (Appendix A), listings of input deck for sample problem (Appen-uses of MELCOR include estimation of severe accident source dix B), and a description of the plotting program PAD (Appendix wms and their sensitivities snd uncertainties in a variety of ap- C).

plications. This publication e/ the MELCOR computer code e&uals corresponds to MELCOR 1.8.4, released to users in NUREG/CR4364: HUMAN PERFORMANCE IN RADIOLOGICAL July 1997. Volume 1 contains a primer that describes MEL- SURVEY SCANNING. BROWN,W.S. Brookhaven National Lab-COR's phenomenological scope, organization (by package), and oratory. ABELOUIST,E.W. Oak Ridge Associated Universities.

documentation. The remainder of Volume 1 contains the March 1998. 54pp. 9803180087. BNL-NUREG-52474.

MELCOR User's Guides, which provide the input instructions A2609:303.

and guidelines for each package. Volume 2 contains the The probability of detecting residual contamination in the field MELCOR Reference Manuals, which describe the phenomeno- using portable radiological survey instruments depends not only logical models that have been implemented in each package. on the sensitivity of the instrumentation used in scanning, but NUREG/CR4119 V02 R1: MELCOR COMPUTER CODE also on the surveyor's performance. This report provides a MANUALS. Reference Manuals, Version 1.8.4, July 1ffd basis for taking human perfortnance into account in determining GAUNTT,R.O.; COLE.R.K. Sandia National Laborat'r6. of the minimum level of activity detectable by scanning. A theo-HODGE,S.A.; et al. Oak Ridge National Laboratory. May 1998. retical framewurk was developed (based on signal detection 800pp. 9806100437. SAND 97 2398. A3723:001. theory) which allows influences on surveyors to be anticipated See NUREG/CR-6119,V01,R01 abstract. and understood, and supports a quantitative assessment of per.

NUREG/CR4359 VC1: RAMONA-4B: A COMPUTER CODE WITH formance. The performance of surveyors under controlled yet THREE-DIMENSIONAL NEUTRON KINETICS FOR BWR AND realistic field conditions was examined to gain insight into the SBWR SYSTEM TRANSIENTS.Models And Correlations, task and to develop means of quantifying performance. Then, ROHATGl,U.S,; CHENG,H.S.; KHAN,H.J.; et al. Brookhaven Na- their performance was assessed under laboratory conditions to tional Laboratory. March 1998. 453pp. 9803190143. BNL- quantify more precisely their ability to make the required dis-NUREG-52471. A2628:001. criminations. The information was used to charactertze survey-Ramona-4B is a systems transient code for application to dif- ors' performance in the scanning task and to provide a basis for j ferent versions of Bolhng Water (BWR) such as the current predicting levels of radioactivity that are likely to be detectable BWR, the Advanced Boiling Water Reactor (ABWR), and the under vanous conditions by surveyors using portable survey in.

Simplified Boiling Water Reactor (SBWR). This code uses a struments.

three-dimensional neutron kinetics model coupled with a multi-channel, nonequihbrium, drtft-flux, two-phase flow formulation of NUREG/CR4377: EFFECTS ON RADIONUCLIDE CONCENTRA-the thermal hydraulics of the reactor vessel. The code is de- TiONS BY CEMENT / GROUND-WATER INTERACTIONS IN signed to analyze a wide spectrum of BWR core and system

i Main Citations and Abstracts 9 SUPPORT OF PERFORMANCE ASSESSMENT OF LOW. followed the aging. Connection functionality was monitored LEVEL RADIOACTIVE WASTE DISPOSAL FACILITIES. using insulation resistance measurements during the aging and KRUPKA,K.M.; SERNE,R.J. Battelle Memonal Institute, Pacific LOCA exposures. Because only 5 of the 10 connection types  !

NdJ.C National Laboratory. May 1998.154pp. 9806010310. passed a post-LOCA, submerged dielectric withstand test, fur- l PNNL-11408. A3572:292. ther detailed investigation of electncal w,o,edis4 and the ef. I The U.S. Nuclear Regulatory Comrnission is developing a facts of cable jacket integrity on the cable-connection system is l techncal position docunt that provides guidance regarding warranted.

the performance assessment of low-level radoactive waste dis-poeal facilities, This gudence consders the effects that the NUREG/CR4447: RESULTS OF CRACK-ARREST TESTS ON IR-chemistry of the vault disposal system may have on radionu- RADIATED A 508 CLASS 3 STEEL ISKANDER S.K.;

clide release. The geochemistry of pore waters buffered by co- MILELLA,P.P.; PINI,A. Oak Ridge National Laboratory. February mentrhous materials in the disposal system will be different from 1998. 97pp. 9802270188. ORNL-6894. A2342:122.

the local ground water. Therefore, the cement-buffered environ. Crack-arrest specimens of irradiated A 508 class 3 forging ment needs to be considered within the source term calcula. stoel were tested and evaluated according to the American So-tions if credit is taken for solubility limits and/or sorption of dis. ciety for Testing and Materials Standard Test Method for Deter- i solved radionuclides within disposal units. A literature review mining Plain-Strain Crack-Arrest Fracture Toughness, K(la), of )

was conducted on methods to model pore-water compositions Femte Steels, E 1221 88. The irradiation-induced shifts while resulting from reactions with cement, experimental studies of small, averaging only about 10 K, are approximately the same cement / water systems, natural analogue studies of cement and as the Charpy 41 J temperature shifts. The specimens were ir-concrete, and radionuclide solubilities experimentally determined radiated at temperatures ranging from 243 to 280 degrees C to in coment pore waters. Based on this review, geochemical mod. fluences varying from 1.7 to 2.7 x 10(19) neutrons /cm(2)(>l eling was used to calculate maximum concentrations for ameri. MeV).

cium, neptunium, nickel, plutonium, radium, strontium, thorium' and uranium for poro-water w,5,s, is buffered by cement NUREG/CR-6453: H. B. ROBINSON-2 PRESSURE VESSEL and local ground-water. Another literature review was complet- BENCHMARK. REMEC,l.; KAM.F.B. Oak Ridge National Labo-ed on radionuclide sorption behavior onto " fresh, cement / con. ratory. February 1998. 58pp. 9803050078. ORNL/TM-13204.

crete where the pore water pH will be " 10. Based on this A2424:056 review, a database was developed of preferred minimum distri-The HBb2 benchmark is specified and analyzed in this re ort. Analysis of the HBR-2 benchmark can be used as partial bution coefficient (K(d)) values for these radionuclides in fulfillment of the requirements for the qualifcation of the meth-i cementhete enmems, odology for calculating neutron fluence in pressure vessels, as NUREG/CR4410: NUCLEAR FUEL CYCLE FACILITY ACCIDENT required by the U.S. Nuclear Regulatory Commission Regulatory ANALYSIS HANDBOOK.

• Science Applications intemational Guide DG-1053, " Calculational and Dosimetry Methods for De-Corp. (formerty Science Applications, Inc.). March 1998.637pp. termining Pressure Vessel Neutron Fluence." Section 1 of this 9804060094. A2880:001, report provides all the dimensions, material compositions, and The purpose of this Handbook is to provide guidance on how neutron source data necessary for the analysis. The measured to calculate the characteristics of releases of radioactive maten- quantities, to be compared with the calculated values, are the als and/or hazardous chemcals from nonreactor nuclear facili- specifc activities of the neutron dosimeters, on both sides of ties. In addition, the Handbook provides guidance on how to the pressure vesset in the surveillance capsule attached to the calculate the consequences of those releases. There are four thermal Lid and in the reactor cavity. Section 2 describes the j major chapters: Hazard Ev6,luation and Scenario Development; anatysis of the HBR-2 benchmark with the computor code i Source Term Determination; Transport Within Containment / DORT and three ENDF/B VI based muttigroup libranes. The av- i Confinement; and Atmospheric Dispersion and Consequence erage ratio of the calculated-to-measured specific actrvities (C/

Modeling. These chapters are supported by Appendices, includ- M) for the six dosameters in the surveillance capsule was 0.90 Ing: a summary of chemical and nuclear information that con- xx 0.04 for all three libraries. The average C/Ms for the cavity tains descriptions of various fuel cycle facilities; details on how dosimeters (without neptunium dosimeter) were 0.89 xx 0.10, to calculate the characteristics of source terms for releases of 0.91 xx 0.10, and 0.90 xx 0.09 for the BUGLE-93, SAILOR-95, hazardous chemicals; a comparison on NRC, EPA, and OSHA and BUGLE-96 libraries, respectively.

programs that address chemical safety; a summary of the per-formance of HEPA and other filters; and a discussion of uncer. NUREG/CR4472: PRELIMINARY PHENOMENA IDENTIFICA-tainties. Several sample problems are presented: a free-fall spill TlON AND RANKING TABLES FOR SIMPLIFIED BOILING of powder; an explosion wtth radioactive releases; a fire with ra. WATER REACTOR LOSS-OF-COOLANT ACCIDENT SCENAR-dioactive releases; filter failurs; hydrogen fluoride relears from a lOS. KROGER,P.G.; ROHATGI,U.S.; JO,J.H.; et al. Brookhaven tankcar; a uranium hexafluoride cylinder rupture; a lig,.sd spill in National Laboratory. April 1998.162pp. 9805050390. BNL-a vitrification plant; and a criticality incident. Finally, this Hand. NUREG-52501. A3317:239.

book includes a computer model, LPF#1b, thel is intended for A set of Phenomena identifcation and Ranking Tables (PIRT) use in calculating leakpath factors. for three potential Loss-of-Coolant Accident (LOCA) scenarios in the General Electric Simplified Boiling Water Reactor is pre.

NUREG/CR4412: AGING AND LOSS &-COOLANT ACCIDENT sented. The selected LOCA scenarios are typical for the class (LOCA) TESTING OF ELECTRICAL CONNECTIONS. of small and large breaks generally considered in Safety Analy-NELSON.C.F. Sandia National Laboratories. January 1998. sis Reports. The method used to develop the PIRTs is de-109pp. 9803180097. SAND 97-3170. A2611:196. scribed. Following a discussion of the transient scenanos, the This report presents the results of an expenmental program PIRTs are presented and discussed in detailed and summartzed to determine the aging and loss-of-coolant accident (LOCA) be- form. A procedure for future valedation of the PIRTs, to enhance havior of electrical connections in order to obtain an initial scop- their value, is outlined.

ing of their performance. Ten types of connections commonly used in nuclear power plants were tested. These included 3 NUREG/CR4479: TECHNICAL BASIS FOR ENVIRONMENTAL types of condup w 2 types of cable-to-device connectors,3 OUALIFICATION OF MICROPROCESSOR-BASED SAFETY-types of cars 9 cuole connectors, and 2 types of in-line RELATED EQUIPMENT IN NUCLEAR POWER PLANTS.

splices. The e ructions were aged for 6 months under simulta- KORSAH,K. Oak Ridge National Laboratory. HASSAN,M. Brook-neous therth W9 degrees C) and radiation (46 Gy/hr) condi- haven National Laboratory. TANAKA,T.J.; et at Sandia National tions. A simulated LOCA consisting of sequential high dose-rate Laboratories. January 1998.128pp. 9803180022. ORNL/TM-irradiation (3 kGy/hr) and high-temperature steam exposures 13264. A2610:197,

10 Main Citations and Abstracts This document presents the results of studies sponsored by cility design, develop an improved understanding of the expect-the Nuclear Regulatory Cum,,a.bii (NRC) to provide the tech- ed rupture behavior of tubes with circumferential cracks, and nical basis for enu.n.n-ntal quellfication of computer-based predict the behavior of flawed and unflawed tubes under severe safety equipment in nuclear power plants. The studies were accident conditions. Task 4 is sic ri d with the acquisition of conducted by Ook Ridge National Laboratory (ORNL), Sandia tubes and tube sections from retired steam generators for use National Laboratories (SNL), and Brookhaven National Labora- in the other research tasks. Progress on the acquisition of tubes tory (BNL). The studies address the following: (1) adequacy of from the Salem and McGuire I nuclear plants is reported.

the present test methods for qualification of digital l&C systems; (2) preferred (i.e., Regulatory Guide-endorsed) standards, (3) NUREG/CR4534 V02: FRAPCON-3: A COMPUTER CODE FOR rin v,nu,&,ded stressors to be included in the qualification proc. THE CALCULATION OF STEADY-STATE. THERMAL-ME-ess during type testing: (4) resolution of need for accelerated CHANICAL BEHAVIOR OF OXIDE FUEL RODS FOR HIGH aging for equipment to be located in a benign environment; and BURNUP. BEYER,C.E.; LANNING D.D. Battelle Memorial Insth (5) determination of an appropriate approach for addressing the tute, Pacife Northwest National Laboratory. DAVIS,K.L; et al.

impact of smoke in digital equipment qualification programs. Idaho National Engineering & Erwironmental Laboratory. De-Significant findings from the studies form the technical basis for cember 1997,111pp. 6803050101. PNNL-11513. A2423:211.

a recommended approach to the environmental qualification of FRAPCON-3 is a FORTRAN IV computer code that calculates microprocessor-based safety-related equipment in nuclear the steady-state response of light water reactor fuel rods during power plants, long-term bumup. The code calculates the temperature, pres-sure, and deformabon of a fuel rod as functons of bme-& ped NUREG/CR4509: THE EFFECT OF INITIAL TEMPERATURE ON ent fuel rod poww and plant boundary Mons, %e >

FLAME ACCELERATION AND DEFIAGRATION-TO-DETONA- nomene modeled by the code include 1) heat conduction TION TRANSITON PHENOMENON. CICCARELL1,G.;

through the fuel and cladding,2) cladding elastic and plastic de-BOCCIO J.L; GINSBERG T.; et al. Brookhaven National Labora- formation, 3) fuel-cladding mechanical Interaction, 4) fission gas 1998, 75pp. 9806080235. BNL-NUREG-52515. release, 5) fuel rod intemal gas pressure,6) heat transfer be-tween fuel and cladding, 7) cladding oxidation, and 8) heat The Higt$-Temperature Combustion Facuity at BNL was used transfer from cladding to coolant. The code contains necessary to conduct deflagration-to-detonation transition (DDT) experi, material properties, water properties, and heat- transfer correla-ments. Periodic orifice plates were installed inside the entire tons. The codes' integral predictons of mechanical behavior length of the detonation tube in order to promote flame accep have not been assessed against a data base, e.g., cladding erstion. The orifice plates are 27.3-cm outer diameter, which is strain or failure data. Therefore, it is recommended that the l equivalent to the inner diameter of the tube, and 20.6 cm-inner diameter. The detonation tube length is 21.3 meters long, and code not be used for analyses of cladding stress or strain, FRAPCON-3 is programmed for use on both mainframe comput-the spacing of the orifece plates is one tube diameter. A stand.

ard automobile diesel engine glow plug was used to ignite the ers and UNIX-based workstations such as DEC 5000 or SUN test mixture at one end of the tube. Hydrogen-air steam mix. Sparcstation 10. It is also programmed for persoral computers tures were tested at a range of temperatures up to 650K and at with FORTRAN compiler software and at least 8 to 10 mega-an initial pressure of 0.1 MPa. It was also observed that the dis, bytes of random access memory (RAM).

tance required for the flame to accelerate to the point of deto-nation initiation, referred to as the run-up distance, was found t NUREG/CR4534 V03: FRAPCON-3: INTEGRAL ASSESSMENT.

LANNING,0.D.; BEYER.C.E. Battelle Memorial institute, Pacific be a function of both the hydrogen mole frrction and the mix- Northwest National Laboratory. BERNA G.A. Affittation Not As-ture initial temperature. Decreasing the hydrogen mole traction signed. December 1997. 210pp. 9803050091. PNNL-11513.

or increasing the initial mixture temperature resulted in longer run-up distances. The density ratio across the flame and the A2423 2 .

speed of sound in the unbumed mixture were found to be two Fuel rod material properties and performance models have been updated for the FRAPCON steady-state fuel rod perform-parameters which influence the run-up distance.

ance code to account for changes in behavior due to extended NUREG/CR4511 V02: STEAM GENERATOR TUBE INTEGRITY fuel bumup. The updated code is named FRAPCON-3 and is in.

PROGRAM. Annual Report. August 1995 September 1996. tended to replace the earlier codes FRAPCON 2 and GAPCON-DIERCKS D.R.; BAKHTIARI,S.; KASZAK.E.; et al. Argonne Na- THERMAL-2. The property and model updates are described in tional Laboratory. February 1998.193pp. 9803180028. ANL-97/ Volume 1 of this report. Volume 2 of this report constitutes the

3. A2611:001, code descrip.;on document and includes the input instructions.

This report summartzes work performed by Argonne National This document (Volume 3) provides the results of the asbess-Laboratory on tne Steam Generator Tube Integrity Program ment of the integral code predictions to measured data for vark from the inception of the prog tm in August 1995 through SeP- ous performance parameters. In the case of fuel temperature tomber 1996. The program is divided into five tasks: (1) Assess' and fission gas release (FGR) predictions, comparison is made j ment of inspection Reliability, (2) Research on ISI (inservice-in- to both benchmark data sets and independent benchmark data l

specton) Technology, (3) Research on Degradation Modes and sets. The benchmark data sets are described in Section 2.0.

[ Integrtty (4) Tube Removals from Steam Generators, and (5) Appendix A describes each individual set of benchmark data Program Management. Under Task 1, progress is reported on and gives the code input for each data comparison. The data the preparation of facilities and evaluation of nondestructive are drawn from a wide range of bumup levels and operating I evaluation techniques for inspecting a mock-up steam generator conditions for both PWR and BWR type rods.

for round-robin testing, the development of better ways to corre-late failure pressure and leak rate with eddy current (EC) sig. NUREG/CR4536: VERIFICATION OF THE LWRARC CODE FOR nals, the inspecten of sleeved tubes, workshop and training ac- LIGHT-WATER-REACTOR AFTERHEAT RATE CALCULA-tivities, and the evaluation of emerging NDE technology. Results TlONS. MURPHY,B.D. Oak Rehe National Laboratory. February are reported in Task 2 on closed-form solutions and finite-ele- 1998.15pp.9802270183. ORNL/TM-13396. A2342:107.

ment electromagnetic modeling of EC probe responses for varl- This report describes verification studies carried out on the ous probe designs and flaw characteristics. In Task 3, facilities LWRARC (Light-Water Reactor Afterhcat flata Calculations) are being designed and built for the production of cracked tubes computer code. The LWRARC code is proposed for automating under aggressive and near-prototypical conditions and for the the implementation of procedures specified in Draft Revision 1 testing of flawed and unflawed tubes under normal operating, of the U.S. Nuclear Regulatory Commission (NRC) Regulatory scendent, and severe-accident conditions. Crack behavior and Guide 3.54 " Spent-Fuel Heat Generation in an independent stabihty are also being modeled to provide guidance for test fa- Spent-Fuel Storage installation," which gives guidehnes on the

l l Main Citations and Abstracts 11 l

l calculation of decay heat for spent nuclear fuel. Draft Regula- going project, the Accident Sequence Precursor project, to ana-l tory Guide 3.54 allows one to estimate decay-heat values by lyze the safety Q-ifs in.6 of other types of accident procur-

! means of a table lookup procedure with interpolation p.ovin 4 sors, such as those arising from intemally-initiated transients l between tabie-entry values. The tabulated values of the relevant and pipe breaks, but earthquakes and fires are not within the l parameters span ran9ee that are appropriate for spent fuel from current scope. The roeutts of this protect are that (1) En overall i

a boiling.weter reactor (BWR) or a pressurtzed-water reactor step-by-step .TM,edvivvy has been dweloped for procursors to I (PWR), as the case may be, and decay-heat rates are obtained both fire-initiated and seismic-initiated potential accidents, (11) l l for spent fuel whose properties are within those parameter some stylized case-study examples are provided to demonstrate l l limits. In some instances, where these limits are olther exceed- how the fulty-developed methodology works in practice, and (iii) ed or where they approach critical regions, adjustments are in- a generic seismic-fragility data base for equipment is provided i

voked following table lookup. The LWRARC computer code is for use in seismic-precursor anatyees.

l Intended to replicate this manual process.

NUREG/CR4537: INFLUENCE OF LONG-TERM THERMAL NUREG/CR4645 V01: PROBABILISTIC ACCIDENT CONSE-AGING ON THE MICROSTRUCTURAL EVOLUTION OF NU. QUENCE UNCERTAINTY ANALYSIS. Earty Health Effects Un-

! CLEAR REACTOR PRESSURE VESSEL MATERIALS.An Atom cNtainty Assessment. Main Report. HASKIN.F.E. New Mexico, 1

Probe Study. PAREIGE,P. France. RUSSELL K.F.; U. iv. of, Albuquerque, NM. HARPER F.T. Sandia National Lab-STOLLER,R.E.; et al. Oak Ridge NaMonal Laboratory. March oratories. GOOSSENS,LH.J.; et al. Delft Urdvers!ty of Technolo-1998. 28pp. 9803180083. ORNL/TM-13406. A2610 324. gy. December 1997. 64pp. 9804240196. EUR 16775.

l Atom probe field ion rik,.v.cepy (APFIM) investigations of the A3158:001.

microstructure of unaged (as-fabricated) and long-term thermally The development of two new probabilistic accident conse-aged (xx100,000 h at 280 degrees C) surveillance materials quence codes, MACCS and COSYMA, was completed in 1990.

from w,i.usc; 1 reactor pressure vessel steels were per. These codes estimate the consequences from the accidental formed. This combination of materials and conditions permitted releases of radiological material from hypothesized accidents at the investigation of potential thermal-aging effects. This micros, nuclear installations. In 1991, the U.S. Nuclear Regulatory Com-tructural study focused on the quantification of the compositions mission and the CvsinJ.i40n of the European Communities of the matrix and carbidos. The APFIM results indicate that begt1 cG.ps,Wng a joint uncertainty analysis of the two there was no significant microstructural evolution after a long. codes. The ultimate objecttve of this joint effort was to system.

term thermal exposure in wold, plate, or forging materials. The stically develop credible and traceable uncertainty distributions matrix depletion of copper that was observed in weld materials for the respective code input variables. A formal expert judg-was consistent with the copper concentration in the matrix after ment elicitation and evaluation process was identified as the the stress-roisef heat treatment. The compositions of cementite best technology available for developing a library of uncertainty carbidos aged for 100,000 h were compared with the distributions for these consequence parameters. This report fo.

Thermocalc(TM) prediction. The APFIM comparisons of materi- cuses on the results of the study to develop distribution for vari-als under these conditions are consistent with the measured ables related to the MACCS and COSYMA earty health effects change in mechanical properties such as the Charpy transition models, temperature.

NUREG/CR4545 V02: PROBABILISTIC ACCIDENT CONSE-NUREG/CR4540: STATE-OF THE-ART REPORT ON PIPING QUENCE UNCERTAINTY ANALYSIS. Early Health Effects Un-FRACTURE MECHANICS. WILKOWSKI,G.M.; OLSON,R.J.; certainty Assessment. Appendices. HASKIN F.E. New Mexico, SCOTT,P.M. Battelle Memodal institute, Columbus Laboratories. Univ. of, Albuquerque, NM. HARPER,F.T. Sandia National Lab.

January 1996. 385pp. 9802100139. BMI-2196. A2077:001. oratories. GOOSSENS.LH.J.; et al. Delft University of Technolo-This report is an in-depth summary of the state-of-the-art in gy. December 1997. 350pp. 9804240244. EUR 16775.

nuclear piping fracture ir-ci- It represents the culmination A3158:068 of 20 years of work done primarily in the U.S., but also attempts to include important aspects from other intomational efforts. Al- See NUREG/CR-6545'V01 abstract

• though the focus of this work was for the nuclear industry, the NUMEG/CR-6546: A DAMAGE MECHANICS BASED APPROACH technology is also applicable in many cases to fossil plants, p* TO STRUCTURAL DETERIORATION AND RELIABILITY.

trochemical/ refinery plants, and the oil and gas industry. In BHATTACHARYA,B.; ELLINGWOOD B. Johns Hopkins Univ.,

compiling this detailed summary report, all of the equations and Baltimore, MD.

• Oak Ridge National Laboratory. February details of the analysis procedure or experimental resutts are not 1998. 200pp. 9803180018. ORNLSUB96-SP638. A2610:001.

necessarily included. Rather, the report describes the important Structural deterioration often occurs without perceptible mani-aspects and limitations, tells thw reader where he can go for fur.

ther information, and more importantly, describes the accuracy festation. Continuum damage mechanics defines structural of the rredels. Nevertheless, the report still contains over 150 damage in terms of the material microstructure, and relates the equations and over 400 references. The main sections of this damage variable to the macroscopic strength or stiffness of the structure. This enables one to predict the state of damage pnor report describe: (1) the evolution of piping fracture mechanics to the initiation of a macroscopic flaw, and allows one to esti-history relative to the developments of the nuclear industry, (2) mate residual strength / service life of an existing structure. The tem developmentsystress analyses, material property as- accumulation of damage is a dissipative process that is gov-pects, and fracture now-m analyses, (3) unresolved issues emed by the laws of thermodynamics. Partial differential equa-l and technically evolving areas, and (4) a summary of conclw sions of major www_6ts to date. tions for damage growth in terms of the Helmholtz free energy are derived from fundamental thermodynamical conditions.

l NUREG/CR4544: METHODOLOGY FOR ANALYZING PRECUR. Closed-form solutions to the equations are obtained under un-SORS TO EARTHOUAKE-INITIATED AND FIRE-INITIATED AC- laxial loading for ductile deformation damage as a function of CIDENT SEQUENCES. BUDNITZ,R.J.; LAMBERT,H.E. Future plastic strain, for creep damage as a function of time, and for Resources Associates, Inc. APOSTOLAKI,G.A.; et al. Massa- fatigue damage as function of number of cycles. The proposed chusetts institute of Tmtv,v;vw, Cambridge, MA. April 1998. damage growth model is extended into the stochastic domain 149pp. 9805050400. A3320:027. by considering fluctuations in the free energy, and closed-form This report covers work to develop a methodology for analyz. solutions of the resulting stochastic differential equation are ob-ing precursors to both earthquake-initiated and intomal fire-intti. tained in each of the three cases mentioned above. A rehability sted accidents at commercial nuclear power plants. Currently, analysis of a ring-stiffened cylindrical steel shell subjected to the U.S. Nuclear Regulatory Commission sponsors a large on. corrosion, accidental pressure, and temperature is pWum-d.

i l

l

12 Main Citations and Abstracts NUREG/CR GSee: FfNITE ELEMENT ANALYSES FOR SEISMIC Results from 27 previour studies were used to anahao strees SHEAR WALL INTERNATIONAL STANDARD PROBLEM. drop vs. magnitude in eastom North Amence. Strees drop was PARK,Y.J.; HOFMAYER,C.H. Brookhaven National Laboratory. not constant, but incrossed approximately with the aquero root AprH 1000. 278pp, amn* 13. BNL-NUREG-62530. of the seismic moment from 3 bars at 10(20) dyne cm to 600 A3318:343. bare at 10(25) dyne am. Q(lg) as a funcuan of frequency was Two idenunel reinforced concrets (RC) sheer wens, which anahzod in Sve regions of the coneguous UrWWd States. Simul-consist of web, flanges and massive top and bottom eiebe, were teneous inversions using Fourter amplitude spectra were com-tested up to unimets failure under earthquake monons at me puted to determine attenusson, site responses, and source Nuoleer Pcwor Engineering Corporation's (NUPEC) Tadotou E* epectra. UnNke some previous studies, Q(Ig) in the centrol and gineering Laboratory, Japan. NUPEC provided the dynamic test northeastom U.S. was found to be neerh identical from 2 to 10 results to the OECD (Organizagon for Economic Cooperemon Hr. Q(ig) in the southeastem U.S. is about 20% lower. Anelastic and Development), Nucieer Energy Agency (NEA) for use as an athnuaton of four regional phemes, and source pwwnews of intemenonal Sanderd Problem OSP). The sheer webs wm in- 27 earthquakes, including the 1995 West Texas earthquake tended 2 be part W a hpical reacW bunding. One W me maim (M(b) 5.6) were also esemated. L(g) attenuanon is in good oblocuver of the Seismic Sheer WaN ISP (SSWISP) wee to agreement with previous setmetes for the central and eastem

,arbus seienWc enehme memods for omaste stuc- U.S. Assuming a single comer frequency source model, strees tures W fw design and seienk margin aseeemment n also drope range from about 1 to 100 bars. The West Texas earth-a unique opputunNy 2 aseees me Wate.4me-m1 in quake has lower values of a few bars to a few tone of bars

• nonlineer dynamic analysis of reinforced concrete sheer well stuctures under severe earmquake loadings. As a pertoipant M NUREG/CR 6571 V01: PROBABluSTIC ACCIDENT CONSE-the SSWISP workshops, Brookhaven National Laboratory (BNL) QUENCE UNCERTAINTY ANALYSIS. Uncertainty Asessement porknned Anne element anehees under me sponewship W me For intemel Dosimetry. Main Report. GOOSSENS,LH.J.;

U.S. Nucieer Regulatory Commission (USNRC). Three types of - et al. Delft Univoretty of Technology anchels were perknned,14., monoenic stak W), KRAAN.B.C.P'b.

HARRISON,J. National Radiological Protecton Board. April

@ Webc and dynande enehesa N noncenic Wak 1996. 70pp. 9005180257. EUR 15773. A3425:279' analyses were performed by two consultants. F. Vecchio of the conse-University of Toronto (UT) and F. FNippou of the Univoretty of he W two new quence codes, MACCS and COSYMA, was -,- ed in 1990.

CalNomia at Berkeley (UCS). The analyele results by BNL and These codes asumate the consequenos from the accidental re-the consultants were presented during the escond wwkshop in Yokohama, Japan in 1996. A total of 55 analyses were present- h W radlobgical material #mn hypomesized accidents at nuclear installations, in 1991, the U.S. Nuclear Reguietory Com-ed during the workshop by 30 perucipants from 11 dNfwent countries. The mejor findings on the presented analyse rneth- mission and the Commission of the European Communitise ods, as wou as engineering insights regarding the applicabinty began componsoring a joint uncertainW anahois of me two and reliability of the FEM codes are osecribed in deteN in this codes. The ulumete objeceve of mis joint Wfort was to system-report, etcally develop credible and traeaaMa uncertainty distributions for the respective code input variables. A formal expert judg-NUREG/CR 4655 V01: PROBABluSTIC ACCIDENT CONSE- ment olicitation and evaluation process was identified as the QUENCE UNCERTAINTY ANALYSIS. Late Health Effects Un- best technology eveNeble for developmg a library of uncertainty certainty AsessemenLMain Report. UTTLE,M.P.: distribunons for these consequence parameters. This report fo.

MUIRHEAD,C.R. UrWted Kingdom. GOOSSENS.LH.J.; et al. cueos on the results of the study to develop distribution for veri-Delft Univoreny of Technology _ December 1997. 64pp. abies related to the MACCS and COSYMA intomal doeinwtry 9002230110. EUR 16774. A2257:293. models The dr. ' r. ,; of two new probabilistic accident conse-quence codes, MACCS and COSYMA, was dr;:':= i in 1990. NUREG/CR-4671 V02: PROBABILISTIC ACCIDENT CONSE-These codes estimate the consequence from the accidental re- QUENCE UNCERTAINTY ANALYSIS. Uncertainty Assessment leemos of radiological material from hypotheelzed accidents at For intamal Dosimetry. Appendices. GOOSSENS,LH.J.;

nuclear instabations. In 1991, the U.S. Nuclear Regulatory Com- KRAAN.B.C.P.: et al. Delft Univoretty of Technology.

miselon and the Commission of the European Commurities HARRISON,J.D. National Radiological Protect 6on Board. April began coeponsoring a joint uncertamty analysis of the two 1998. 317pp. 9805180287, EUR 16773. A3426:001.

codes. The uHimate objective of this joint effort was to system- See NUREG/CR.6571,V01 abstract.

stically develop credible and traceable uncertainty distributions for the roepective code input variables. A formal expert judg- NUREG/CR-4673: " INVESTIGATING SEISMOTECTONICS IN ment alloiteton and evalueton process was identNied as the THE EASTERN UNITED STATES USING A GEOGRAPHIC IN-best technology available for developing a library of uncertainty FORMATION SYSTEM." EBEL,J.E.; LAZAREWICZ,A.R,:

dletributons for theos consequence parameters. This report fo- KAFKA.A.L Boston College, Weston, MA. February 1996, cueos on me results of the study to develop distributon for vari- 109pp. 9803030332. A2379:209.

ables rotated to the MACCS and COSYMA late health effects A Geographic information System (GIS) database has been modeis assembled to use in regional analyses looking for seismotecton-NUREG/CR 4566 V02: PROBABluSTIC ACCIDENT CONSE- icah acWve features in me conval and esswn U.S. (CEUS). In-ciuded in me detaMaa fa me region are umwny, sa>

OUENCE UNCERTAINTY ANALYSIS. Late Health Effects Un- quakes, stress measurements, gravity residual fioid, magrW owlsinty UTTLE M.P.

MUIRHEAD,C.R. UnNed Kingdom. GOdSSENS LH.J.: et aj roeidual neid, maja h and regional geology, especiah Dent Univweny M Technology. Deewnbw 1997. 223pp. faults. Observables from this database were extracted for the seermcah actve areas d me nmmeastem, soumeastem and 9002230116. EUR 16774. A2257:070. central U.S. for use in multivariate statetical analyses. These See NUREG/CR-6555,V01 abstact.

analyses indicate that the earthquakes of the CEUS do tend to NOREG/CR 4884: ANALYSES OF SOURCE SPECTRA, ATTENU- assocate with faults and other deformation structures, but that ATION, AND SITE EFFECTS FROM CENTRAL AND EASTERN the geologic characteristics are not very similar between earth-UNITED STATES EARTHOUAKES. UNDLEY,G. Califomia, quakes in different regions. The discrirrenant function analysie 11 2 . 4 Santa Barbera, CA. February 1998. 100pp. shows some ability to differentate between seismic and non-9002250142. A2281:189. seesmic areas.

l

. - ~ - ~ . - _ _ - _ -

t Main Citations and Abstracts 13 i

! NURES/CR4875: FAILURE BEHAVIOR OF INTERNALLY PRES- tNo study can be used to focus activities relatng to the regule-l SURIZED RAWED AND UNFLAWED STEAM GENERATOR tory beels for digital l&C upgrades in NPPs, including identifice-TUBING AT HIGH TEMPERATURE -EXPERIMENTS AND tion of dominent streasors, "" g, ;,,, equipment quellflos-l COMPARISON WITH MODEL PREDICTIONS. MAJUMDAR.S.; tion, and requirements to limit the effects of environmental SHACK,W.J.; DIERCKS,0.R.; et al. Argonne Nellonel Laborato- stroesore ry. March 1998.10tpp 0003200301 ANL-97/17. A2730:221.

This report summertase experimental work performed at Ar- NURES/CR4588: EFFECTS OF LWR COOLANT ENVIRON- ,

gonne Neuonal Laboratory on the fenure of intemelly pressur. MENTS ON FATIGUE DESIGN CURVES OF CARBON AND l imod steem generator tubing at high temperatures (" 700 de- LOW ALLOY STEELS. CHOPRA,0.K.; SHACK.W.J. Argonne J grees C). A model was developed for prodloung feture of flowed National Laboratory. March 1996.128pp. 9003200364. ANL-97/ '

and unflowed steem generator tubes under intemel pressure 18. A2727:220.

and temperature histories postulated to occur during severe ac- The ASME Boner and Pressure Vessel Code provides rules aidents. The model was validated by feMure tests on specwnens for the construction of nucteer power plant components. Figures

! with part-th=_$ =" exial and circumferented flows of verlous I-9.1 through I-9.6 of Appendix 1 to Section lit of the Code l lengths and depths, conducted under various constant and specify fatigue design curves for structurd meterleis. WNie of-l- romped intemel preneure and temperature condluona. The feil facts of reactor coolant environments are not expHcitly ed-j , ure temperatures prodlcted by the model for two temperature dreened by the design curves, test date indicate that the Code j l end preneure histories, e=Ma*=d for severe accidents initleted fatigue curves me r not always be adequate in coolant environ-l' by a etstion Mar *mt, agree very won with tests performed on monts. This report summertzes work performed by Argonne Ne-both flowed and unflowed specimens. tional Laboratory on fatigue of carbon and low-alloy steels in NURES/CR4677: U.S. NUCLEAR POWER PLANT OPERATING Nght water reecer (LWR) erN. The exioung feggue S-l COST AND EXPERIENCE SUMMARIES. KOHN,W.E.; N date have boon evolusted to establish the effects of vertous l REID,R.L.; WHITE,V.S. Oak Ridge National Laboratory. Febru metenal and loedng vertebles such as steel type, dissolved oxygen level etsin range, etsin rate, temperatum, w6entaton, ery 1998. 433pp. 9002230118. ORNL/TM-13494. A2256 001.. - i l

TNs report has been pepered M provide Notorical opwenng and sulfur content on the fatigue life of these steels. Statistical 1 cost and experience informadon on U.S. commercial power rnodois have been d:;_':5+2 for estimating the fatigue S-N piants. Costs incurred ener ineel constuceon are cherectertred cunes as a funcWon of material, loading, and environmental j es annual production ocets, represeneng fuel and plant operet- verteles. The reeuns have been used to setmah the probabE. j ing and mainknence expenses, and capnel exoendnures reist- ty of fatigue cracking of reactor components The dNferent  ;

ed to fooNNy addeons/modmoeWons wNch are included in the methods for incorporating the effects of LWR cooient erwiron. '

pient capnel esset bees. As re e===d in the report, annual data monts on the ASME Com fengue design cunes are presented fu mese two cost were etsined h pubEW ad 2 repwm and rnuet be W es heWng N egren NUREG/CR4580: THE EFFECTS OF SURFACE CONDITION ON fso uracy and W. Desenent W m W AN ULTRASONIC INSPECTION: ENGINEERING STUDIES

' ^ USING VAUDATED COMPUTER MODEL GREENWOOD.M.S.

cost hiekrke Betteile Memorial Ins #tute, Pacific Northwoot National Laborato-

' summerke nuclew unN are provided. The iment of thoes summaries is to ry. April 1998,154pp. 9005200010. PNNL-11751. A3467:217, identNy impatent opwenng events; refusNng, major mainte- This report documents work performed at Pacific Northwest nonce, and oeur signmcent cumges, opwoung mussens and National Laboratory (PNNL) on the effects of surface roughness signmoent noensing or enforcement scuans. Infamenon used in on the rehet#ty of en unresonic inservice inspecuon. The prL the summertos is condensed from annual operating reports aut> nury objective of tNs resserch is to develop ASME Code rec-

' muted by the noensees, plant Notories contained in Nuclew ommendemons in order to lim t the adverse effects of a rough Power Expertonos, trade press articles, and the Nuclear Regule- surface and mereby increses em rehabHNy of unresonic inserv-

' tory Commiselon (NRC) web site (www.nrc. gov). los W in wder 2 ocNove Ns @)ome, M studies were conducted that included exportmental vahdetion of

NURES/CR4579

DIGITAL l&C SYSTEMS IN NUCLEAR POWER computer codes, d:;r:5 -$ et the Center for Nondestructive l PLANTS. Risk-Screenmg Of Environmental Streasors And A Evaluation (CNDE) et lows State University as a result of a co-Comporteon Of Hardware Unevailabety With An Existing Analog operative effort between the Electric Power Reneerch Insututo System. HASSAN,M. Brookhaven National Laporatory. (EPRI) and the Nuclear Regulatory Commission. The basic VESELY,W.E. Science Apphcotions intomational Corp. (formerly problem eseociated with a rough surfeos in en inservios inspec.

Science Appilostions, Inc.). January 1998.128pp. 9002130002. tion is that es the transducer rotates slightly to accommodste BNL-NUREG-52536. A2144:068, the rough surface, the beam direction in the metal changes and in tNs report, we present e screenng study to idenOfy envb the time-of-fNght of the scho changes as well. One problem is i ronmental streaeors for dlgital instrumentation and comrol (l&C) the excessive weld crown, where wold material protrudes above systems in a nucieer power plant (NPP) which can be potentiek the adjoinmg surfaces. In tNs reeeerch this condition is modeled i ly risk-signmcent, and compare the hardware uneveHebility of by considering a step thecontmulty on the top ourface. CNDE such a system with that of its extehng analog counterpart. The developed several models of increasing complexity in order to streasors evolusted are temperature, humidity, vibration, redi- model en ineonnoe inspecton. TNs report describes the vnHde-ston, electro magnetc interference (EMI), and smoke. The re- tion of four computer codes. These codes were used to symmic j ouNe of risk-screening for en exempio plant, subject to some en inservice inspecbon in order to understand effects =ht-bounding eseumphone and bened on reiseve changes in plant ed with rotation of the treneducer as it traverses e step dloconth i rlek (core damage frequency Impacts of the stroesore), indloste nuity. Studies resuhed in ASME Secton XI Code recommende-l that humidity, EMI from hghtning, and smoke can be poten8elly tions.

j . risk-eignllicant Risk from other sources of EMI could not be i evolusted for a lack of date. Risk from temperature appears to NUREG/CR 4000: AN INVESTIGATION OF TENDON SHEATH-be insignmcent es that from the assumed levels of vibrations. A ING FILLER MIGRATION INTO CONCRETE. NAUS D.J.;

componeon of the hardware unevellebety of the e,Nting analog OLAND,C.B. Ook Ridge National Laboratory. March 1998.81pp.

. Safety inlocton Actuation System (SIA3) in the escanpie plant 9807000348. ORNL/TM-13554. A4009:236.

wim that of en eseumed digital upgrade v the sys;m indicates During some of the inspectons et nuclear power plants with

! that system uneveliebHity may be more ses sitive to the level of prostressed concrete containments, it was observed that the t

r-^ _

.c ,w in elements of the dignal syste n men to the envh contamments had expwnnced leakage of the tendon eheathing

! ronmentaa and opwesonal vertemons invo#mL The findmos of few (Le., streeks). The objectwo of tNs activity was to provide l

l-l

14 Main Citations and Abstracts an indication of the extent of tendon sheathing filler leakage plementing practices already known to mitigate the effects of into the concrete and its affects on concrete properties. Utera- potentialty adverse aidhs.

tuna was reviewed and concrete core samples were obtained from the Trojan Nuclear Plant and tested. The literature pnmari. NUREG/CR 4606: INVESTIGATION OF TECHNIQUES FOR THE ly addressed effects of crude or lubricating oils that are known DEVELOPMENT OF SEISMIC DESIGN BASIS USING THE l to cause concrete damage. However, these materials have sig. PROBABILfSTIC SEISMIC HAZARD ANALYSIS. ,

BERNREUTER,0.L; BOISSONNADE,A.; SHORT,C.M. Lawrence nificantly different characteristics relative to the materials used l as tendon sheathing fillers Examination and testing of the con. Uvermore National Laboratory. April 1998.168pp.9805060107.  !

crete cores indicated that the appearance of tendon sheathing UCRL-ID-128920. A3321:113.

filler on the concrete surface was due to leakage from the con. The Nuclear Regulatory Commission asked Lawrence Uver-dults and its tubsequent migration through cracks that were more Laboratory to form a group of experts to assist them in ,

present. Migration of the tendon sheathing filler was confined to revising the seismic and geologic siting criteria for nuclear the cracks and there was no perceptible movement into the power plants, Appendix A to 10 CFR Part 100. This document concrete. Results of compressive strength testing indicated that describes a deterministic approach for determining a safe Shut-the concrete quality was consistent in the containment and that down Earthquake (SSE) Ground Motion for a nuclear power the strength had increased over 40% in 25.4 years relative to plant site. One disadvantage of this approach is the difficulty of )

the average compressive strength at 28 days age. Integrating differences of opinions and differing interpretations into seismic hazard characterization. In answer to this, probabi- 1 NUREG/CR-6604: RADTRAD: A SIMPLIFIED MODEL FOR RADI- listic seismic hazard assessment methodologies incorporate dif-ONUCLIDE TRANSPORT AND REMOVAL AND DOSE ESTi- ferences of opinions and interpretations among earth science MATION. HUMPHREYS,S.L; MILLER,LA.; et al. Sandia Nation- experts. For this reason, probabilistic hazard methods were se- l al Laboratories. HEAMES,T.J. . April 1998.408pp.9805180342. lected for determining SSEs for the revised regulation,10 CFR l SAND 96-0272. A3424 001, Part 100.23. However, because these methodologies provide a This report documents the RADTRAD computer code devel- composite analysis of all possible earthquakes that may occur, oped for the U.S. Nuclear Regulatory Commission, Office of Nu- they do not provide the familiar link between seismic design clear Reactor Regulation to estimate transport and removal of loading requirements and engineering design practice. There-radionuclides and dose at selected receptors. The document in- fore, approaches used to charactertze seismic events (magni-cLies a users' guide to the code, a desenption of the technical tude and distance) which best represent the ground motion basis for the code, the quality assurance and code acceptance level determined with the probabilistic hazard analysis were in-testing documentation, and a programmers' guide. The RAD- vestigated. This report summarizes investigations conducted at TRAD code can be used to estimate the containment release 69 nuclear reactor sites in the central and eastem U.S. for de-using either the TID 14844 or NUREG-1465 source terms, and termining SSEs using probabilistic analyses. Altemative tech-assumptions, or a user-specified table, in addition, the code can niques are presented along with justification for key choices.

account for the reduction in the quantity of radioactive material due to containment sprays, natural deposition, filters, and other NUREG/CR-6600:

SUMMARY

AND EVALUATION OF LOW-VE-natural and engineered safety features. The RADTRAD code LOCITY IMPACT TEST OF SOLID STEEL BILLET ONTO CON.

uses a combination of tables and/or numerical models of CRETE PADS. WITTE,M.C.; HOVINGH,J.; MOK,G.C.; et al. Law-source term reduction phenomena to determine the time de- rence Uvermore National Laboratory. February 1998, 184pp.

pendent dose at user specified heations for a given accident 9802250129. UCRL 129211. A2281:001.

scenarlo. The code also provides the inventory, decay chain, Spent fuel storage casks intended for use at independent and dose conversion factors needed for the dose calculation. spent fuel storage installations are evaluated during the applica-The RADTRAD code can be used for occupational radiation ex. tion and review process for low-velocity impacts representative posure assessments, typically in the control room, for site of possible handling accidents. In the past, the analyses in-boundary dose estimates, and for dose attenuation estimates volved in these evaluations have assumed that the casks due to facility or accident sequence modifications. dropped or tipped onto an unyielding surface-a conservative and simphfying assumption. Applicants are currently seeking a NUREG/CR-6605: AN EVALUATION OF HUMAN FACTORS RE- more realistic model for the analyses to predict the effect of a SEARCH FOR ULTRASONIC INSERVICE INSPECTION. cask dropping onto a reinforced concrete pad, including energy POND,D.J.; DONOHOO,0.T.; HARRIS,R.V. Battelle Memortal in- absorbing aspects such as cracking and flexure. To develop stitute, Pacific Northwest National Laboratory. March 1998, data suitable for benchmarking these analyses, the NRC has 41pp. 9803260380. PNNL 11797. A2726:291. conducted several series of drop. test studies of a solid steel This work was undertaken to determine if human factors re* billet and of a near-full-scale empty cask. This report contains a search has yielded infomiation apphcable to upgrading require- summery and evaluation of all steel billet testing conducted by ments in ASME Boiler and Pressure Vessel Code Section XI. Sandia National Laboratories and Lawrence Uvermore National improving methods and techniques in Section V, and/or sug- Laboratory. A series of finite element analyses of the billet test-gesting relevant research. A preference was established for in- ing is described and benchmarked against the test data. A formation and recommendations which have become accepted method to apply the beehmarked finite element model of the and standard practice. Manual Ultrasonic Testing / inservice in- soll and concrete pad to un analysis of a full-size storage cask spectson (UT/ISI) is a complex task subject to influence by is provided. In addition, an apphcation to a " generic" full-size dozens of variables. This review frequently revealed equivocal cask is presented for side and end drops, and tipover events.

findings regarding effects of environmental variables as well as repeated indications that insin.6 performance may be more, NUREG/CR-6611: RESULTS OF PRESSURE LOCKING AND and more rehability, influenced by the workers' social environ. THERMAL BINDING TESTS OF GATE VALVES. DEWALL K_G.;

ment, including 6e,agedel practices, than by other situational WATKINS J.C.; MCKELLAR,M.G.; et al. loaho National Engi-variables. Also of significance are each inspectors relevant neering & Environmental Laboratory. May 1998. 69pp.

knowledge, skills, and abilities, and determination of these is 9806080225. INEELEXT9800161. A3688:237.

seen as a necessary first step in upgrading requirements, meth. The U.S. Nuclear Regulatory Commission (NRC), Office of ods, and techniques as well as in focusing research in support Nuclear Regulatory Research, is funding the Idaho National En-of such programs. While understanding the effects and mediat- gineering and Environmental Laboratory (INEEL) in performing ing mechanisms of the variables impacting inspecton perform- research investigating the performance of gate valves subjected ance is a worthwhile pursuit for researchers, initial improve- to pressure locking and thermal binding conditions. Pressure monts in industrial UT/ISI performance may be achieved by im- locking and thermal binding are phenomena that make a closed

Main Citations and Abstracts 15 gate valve difficult to open. If the loads associated with pres. The Nuclear Regulatory Commission has initiated a program sure locking or thermal binding a o very high, the actuator might at the Oak Ridge National Laboratory to provide assistance in not have the capacity to open the valve. We tested a flexible- their assessment c 'he effects of potential degradation on the

)

wedge gate valve and a double-disc gate valve under pressure structural integrity and leaktightness of metal containment ves-locking and thermal binding cai46.. The results show that sets and steel liners of concrete containments in nuclear power these valves are susceptible to pressure locking; however, they plants. One of the program objectives is to identify repair prac-are not significantly affected by thermal binding. The results tices for restoring metallic containment pressure boundary com-also show that seat leakage affects the bonnet pressurtzation ponents that have been damaged or degraded in service. This rate when the valve is subjected to thermally induced pressure report presents issues associated with inservice condition as-locking W.idew. sessments and continued service evaluations and identifies the NUREG/CR-6613 V01: CODE MANUAL FOR MACCS2. User's mies and requirements fu the repair and replacement of nom Guide. CHANIN,D. Technadyne Engineering Consuttants. Inc. conforming containment pressure boundary components by YOUNG,M.L Sand 6a National Laboratories. May 1998. 300pp. weidjng or metal removal. Discussion topics include base and 9806150058. SAND 97-0594. A3823:001, welding materials, welding procedure and performance qualifica-This report desenbes the use of the MACCS2 code. The doc- tims,1,Wwii techniques, testing methods, acceptance crite-ument is primarity a user's guide, though some model descrip- ria, and documentation requirements necessary for making re-tion information is included. MACCS2 represents a ma}or en- pairs and replacements so that the plant can be retumed to a hancement of its predecessor MACCa, the MELCOR Accident safe operahg cedum.

Consequence Code System. MACCS2, distributed by govem. I ment code centers since 1990, was developed to evaluate the NUREG/GR-0016: THE ROLE OF TIME-DEPENDENT DEFOR.

impacts of severe accidents at nuclear power plants on the sur- MATION IN INTERGRANULAR CRACK INITIATION OF ALLOY 600 STEAM GENERATOR TUBING MATERIAL WAS,G.S.;

rou%ng pubEc. The pdncipal phenomena cmsidered are ab LIAN,K. Michigan, Univ. of, Ann Arbor, ML March 1998. 41pp.

mv=wouw transport and deposition under time-variant meteorol-9804200284. A3031:101 ogy, short and long-term mitigative actions and exposure path-ways, deterministic and stochastic health effects, and economs Intergranular stress corrosion cracking (IGSCC) of two com-mercial alloy 600 conditions and controlled-purity Ni-18Cr-9Fe costs. No other U.S. code that is publicly available at present alloys were investigated using constant extension rate tensile offers all these capabilities. MACCS2 was developed as a ge*

eral-purpose tool applicable to diverse reactor and nonreactor (CERT) tests in primary water with 1 bar hydrogen overpressure facilities licensed by the Nuclear Regulatory COrci. Moa or op-at 360 degrees C and 320 degrees C. Heat treatments pro-duced two types of microstructures in both commercial and con-ersted by the Department of Energy or the Department of De" trolled-purity alloys: one dominated by grain boundary carbides fense. The MACCS2 package includes three primary enhance

• and one dominated by intragranular cart *1es. CERT tests con-ments: (1) a more flexible emergency-response model, (2) an

, ducted over a range of strain rates and at two temperatures expanded library of radionuclides, and (3) a semidynamic food showed that in all samples, IGSCC was the dominant failure chain model Other ime,0isirsins are in the areas of phenome- 6 For both the mrcial alloy and the controlled-purity nological modeling and new output options. Initial installation of alloys, the microstnJcture with grain boundary carbides showed the code, written in FORTRAN 77, requires a 486 or higher IBM

• delayed crack initiation and shallower crack depths than did the compatible PC with 8 MB of RAM.

intragranular carbide microstructure under a!! experimental con-NUREG/CR-6613 V02: CODE MANUAL FOR ditions, indicating that a grain boundary cartSde microstructure MACCS2. Preprocessor Codes COMIDA2, FGRDCF, IDCF2. Is more resistant to IGSCC than an intragranular carbide micros-CHANIN,0. Technadyne Engineenng Consultants, Inc. tructure. Observations support both the film rupture / slip olasolu-YOUNG.M.L Sandia National Laboratories. May 1998.102pp. tion mechanism and enhanced localized plasticity. Crack growth 6906150062. SAND 97-0594. A3799:129, rates increased with increasing strain rate according to a power This report is a user's guide for the preprocessors developed law relation with a strain rate exponent between 0.40 and 0.64.

for the MACCS2 code. MACCS2 represents a major enhance- However, crack growth rate measured in m/ unit strain de-ment of its predecessor MACCS, the MELCOR Accident Conse- creased with increasing strain rate indicating an effect of either quence Code System. MACCS, distributed by govemment code the environment or creep. The temperature dependence of the centers since 1990, was developed to evaluate the impacts of crack growth rate was consistent with the literature, severe accidents at nuclear power plants on the surrounding public. The principal phenomena considered are atmospheric NUREG/IA-0024: APPLICATION OF RELAPS/ MOD 3.1 CODE TO transport and deposition under time-variant meteorology, short THE LOFT TEST L3-6. PY' EV,S.S.; ROGINSKAGA,V.L Russia.

i and long-term mitigative actions and exposure February 1998. 66pp. 9802100124. A2059:287.

pathways deterministic and stochastic health effects, and eco- A calculation of LOFT Experiment L3-6, a small-break equiva-nomic costs. MACCS2 was developed as a general-purpose lent to a 4-inch diameter rupture in the cold leg of a four-loop tool applicable to diverse reactor and nonreactor facilities li commercial pressurized water reactor, has been performed to censed by the Nuclear Regulatory Cummmean or operated by help validate RELAP5/ MOD 3.1 for this application. The version the Department of Energy or the Department of Defense. The of the code to be used is SCDAP/RELAP5/M%3.1.Bd0. Three prowivw.i-s available for use with the MACCS2 code are calculations were carried out in order to stud) ".e sensitMty to COMIDA2, DOSFAC2, FGRDCF, and IDCF2. The COMIDA2 change of the break nozzle superheated disenarge coeffbient.

code contains a semidynamic food chain model and generates Conducted comparative analysis of the LOFT L3-6 experiment a file of dose-to-source conversion factors that are used by shows on the whole a reasonable agreemet beten calculab MACCS2 in calculations of ingestion doses. DOSFAC2, ed and measured data. Some discrepancies in the system pres-FGRDCF, and IDCF2 generate a file of dose conversion factors sure do not distort a picture of the transient.

that are required for MACCS2 dose calculations. The pre.

processors, written in FORTRAN 77, require a 486 or higher NUREG/lA 0025: RELAPS/ MOD 3 SUBCOOLED BOILING MODEL ASSESSMENT. DEVKIN,A.S.; PODOSENOV,A.S. Rus-IB mpa h K sian Research Center (Kurchatov institute). May 1998. 83pp.

NUREG/CR-4615: A SURVEY OF REPAIR PRACTICES FOR NU- 9805200009. A3468:097.

CLEAR POWER PLANT CONTAINMENT METALLIC PRES- This report presents the assessment of the RELAP5/ Mod 3 SURE BOUNDARIES. OLAND C.B.; NAUS,D.J. Oak Ridge Na- (Sm5 wrsion) code subcooled boiling process model, which is tional Laboratory. May 1998.128pp. 9806080222. ORNL/TM- based on a variety of experiments. The accuracy of the model 13601. A3686:178. is confirmed for a wide range of regime parameters for the case

+ -r*~4* atA-4+ - - 8sM- A4,.4 W4 4 J c.-.J.A+%4,.w -,A,sese4e- -- A. ,, Ww...A2a,c.4,de ,imn_ a &A, ..M be-

• a n.~+4---_a'4.-n -sJa-I

- 16 ' hueln Citatkms and Abstracts of unNorm hoedng along #m channd. The condenention rete is void fracton behavior preschon in subcooled boEng rW

- remer underprodksed, which may lead to considerebie enors in for nonunnormly or unheeted channels.

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Main Citations and Abstracts 1SA  !

1 l NURE3tBR 0080: ADVISORY COMMITTEE ON NU- -

CLEAR WASTE - 1998 STRATEGIC PLAN AND PRI-ORITY ISSUES AND ACTIVITIES.

• ACNW- Advisory

. CommNice on Nuclear Weste. March 1998.12pp.

9004200219. A3031:001, The Advisory Committee on Nuclear Weste (ACNW) has dni;:f a strategic plan that establishes a frame

- work to guide it in providing independent and timely tech-nical advice to the Nuclear Regulatory Commission on  :

!' nuclear weste disposal and management issues. The plan  !

i

includes neer term priority issues the Committee will con- l l sider in 1998, as well as longer term issues the Committee i: plans to consider in 1999 and beyond. . The ACNWs strate-i gic plan is anchored to the NRC's Strategic Plan for Fiscal l~ yen 1997 - 2002 and supports the mission, vision, and

toisent goals, strategies, and substrategies identified by j' the egency.

I

' NUREGtBR 0117N97 4: NMSS LICENSEE NEWSLETTTER.

• Office of Nuclear Meterial Safety and Safe-lz guards. February 1998,12pp. 9804200291, A3031:143.'

( This newsletter contains articles that discuss recent re .

[- gulatory issues and provide administrative information. It

! includes descriptions of recent Federal Register notices, generic communications, significant enforcement actions, and significent operational events

_ NUREGtBR 0249: THE ATOMIC SAFETY AND LICEN.

_ SING BOARD PANEL

• Office of Public Affairs.

L February 1998. 6pp. 9803190405. A2670:015.

Through the Atomic Energy Act, Congress made it possible for the public to get a full and fair hearing on -

civilien nuclear matters. Individuals who are directly ,

l < affected by licensing action involving a facility producing i l or utilizing nuclear materials may participate in a formal heer-ing, on the record, before independent judges on the Atomic Safety and Licensing Board Penal. - Hearings, routinely involve -

difficult interrelated questions, often et the cutting edge of j science and technology, confronting highly technical and scientific theories, opinions, and research findings. In addition, NRC hearings air local concoms about the consequences of severe accidents and continue the notional debate over the role nuclear power should play in meeting the nation's energy noods.

i Y '

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d 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.

1 I

"A*Y MPORT NUM MPORT NUtWER **Y REPORT NURWER NUIMER ANL47/17 NUREG/CR4675 4 13264 NUREG/ 4479 ANL-07/18 NUREG/m4603 4 13306 NUREG/ 4 638 ANL47/3 NUREG/CR4611 V02 4 13408 NUREG/ M 7 ANL-06/6 BM6 2108 NUREG/CR-4087 V24 NUREG/CR4640 ORU j ONL4dUREG42471 ORNL/TM-13801 NUREG/CR4815

, NUREG/CR4369 V01 ORNLSUB06 SP838 NUREG/CR-0646 BNL-NUREG42471 NUREG/CR4369 V02 PNNL-11408 NUREG/CR4377 ONLJdUREG-62474 NUREG/CR4364 PNNL 11513 NUREG/CR4634 V03 i BNL-NUREG42601 NUREG/CR4472 PNNL 11513 NUREG/CR4634 V02 ONL48UREG42615 NUREG/CR4600 PNNL-11751 NUREG/CR4689 R MG/CR-6664 N E SNL NUREG42538 NUREG/CR4679 7 NUREG CR V01 4

EPA-402R-97416 8AND974604 NUREG/CR4013 V02 NUREG1675 SAND 07-2322 EUR 18773 NUREG/CR4671 V01 NUREG/CR4666 V01 SAND 97-2322 NUREG/CR4666 V02 EUR 18773 NUREG/CR4671 V02 SAN 007-2398 NUREG/CR4119 V01 R1 EUR 16774 NUREG/CR4666 VO1 SAND 97-2398 NUREG/CR4119 V02 R1 EUR 16774 NUREG/CR4666 V02 SAND 97-2000 NUREG/CR-8646 V01 EUR 16775 NUREG/CR4645 V01 SAN 007-2000 NUREG/CR4645 V02 EUR 16775 NUREG/CR4645 V02 SAND 07-3170 NUREG/CR4412 INrri FXT9000161 ORNL 0804 NUREG/CR4611 NUREG/CR4447 lh Ej ORNL/NOAC-232 NUREG/CR-4674 V25 SAND 96 0272 NUREG/CR4004 UCBD-20874 NUREG/CR-4664 VD1 R2 ORNL/TM-11688 NUREG/CR-6691 V06 N1 UCRL 129211 NUREG/CR4808 ORNL/TM 11688 NUREG/CR-6601 V04 N1 UCRL-ID 128920 NUREG/CR-8806 ORNL/TM-13204 NUREG/CR4463 URCL-lO 130438 NUREG/CR-6602 i

d 17

N- . .e. , _ m44+#i# .s .e 4 4 _a J4.adaaa.a .a ,y,s.t_.- 4,4.,. 4A.m.+_..AM_m.m 4,44 44m..msa ,_A_g me ,4 sma44-.m._....d4 a.,A .WA44- m. A4AW,p-.M_.A 4 Ji. .am..she.4s, i

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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-l tion by the NUREG number.

l l

AAmalAST.E.W. CNAIWUL NLNEG 1907: heNieduM DETECTABLE CONCENTRATIONS WITH TYP- NUREG/CR4813 Voi: CODE MANUAL FOR MACC82. User's Gulde.

! ICAL RADIATION SURVEY INSTRUbENTS FOR VARIOUS CONTAMI- NUREG/OR4813 Vot: CODE MANUAL FOR MAnn8k8 8veprocessor i NANTS Afm FELD ColemONS. Codsennuargg, FOROCF, IDCF2.

PAJREG/CR4004. HUMAN PERFOHMANCE N RADIOLOGICAL l SURVEY SCANNMG. C6EN,TE. I l NUREG/OR4000.

SUMMARY

AND EVALUATION OF LOW-VELOCITY

• R01: EVENT REPORTING GUIDEUNES 10 CFR 80.72 A T M SWD SMEl WRET NTO N N

[ AfG 80.73. 00EIIS,N A AP0gyns aars a a NUMEG/CR4300 V01: RAMONA48 A COMPUTER CODE WITH NUfEG/CR4644 METpnnt'u nGY FOR ANALYZING PREOURSORS mREE48dENOME NEUmm KNETICS FOR BWR APO SSWR TO EARTHQUAKE-INmATED MND FIRE-INmATED AnnansNT SE- '

- CR m,EE41E,MoNE ,EumON ia,ETCOMPUTE.R CSFOR WR CO,D.E A WITH S.WR GA, 4R, , Sv-M mA,EEmusere Manuel l ..

NUlWG/CR4611 VOE: STEAM GE9ERATOR TUBE INTEGRITY CfNe87 V34: ENVIRONMENTALLY ASSISTED CRACIONG IN 6 UGHT-WATER REACTOP.S. 'emiennual Report,JanuaryJune 1997.

NUfEG/CfMS74 V36: PRECURSORS TO POTENTIAL SEVERE CORE NLKIEG/m4583. EFFECTS Of LWR COOLANT ENVIRONMENTS ON DAMAGE aminnefTS: 1988. A Sleeue Report FATIGUE DESIGN CURVES OF CARBON AND LOW-ALLOY STEELS, i N Cetul08,KM.

I NufEG/CR4634 VUE: FRAPCOfW: A CObEUTER CODE FOR THE NUREG/GN087 V24: ENVIRONMENTALLY A301STED CRAC80NG IN CALCULATION OF STEADY 4 TATE. TtERMAL4ECHANICAL BE- LIGHT-WATER REACTORS. Semiennumi ReporU- ; M 1987.

HAVIOR OF OKIDE FUEL RODS FOR HIGH SURNUP

! NUf4G/CReste V0B: FRAPCON4 MTEGRAL.amasanusgT. caneassu a a a m NUREG/m4800: THE EFFECT OF INmAL TEMPERATURE ON NUf4G/CR4006. INVESTIGATION OF TECHpeQUES FOR TE DE- FLAME ACTLERATION AND DEFLAGRATIONTOCETONATION Mapl 8mm PHENOldENON VELOPtENT OF asannan DESIGN BASIS USING TE PROBA86US-TIC asannaf' HAZARD ANALYSIS. ,,

gEYWI,C2. NUREG/CfM874 V26: PRECURSORS TO POTENTIAL SEVERE CORE l

NUREG/CR4884 VOR: FRAPCON4. A COMPUTER CODE FOR THE DAMAGE ACCIDENTS: 1908. A Status Report.

CALCULATION OF STEADY 4 TATE. TEflMAL4ECHANICAL BE.

HAVIOR OF OlGDE PUEL FIOOS FOR HIGH BURNUP COSAfLK.

NUREG/m4884 WOS: FRAPOON4 INTEGRAL amasanusNT, NUREG/CR4119 V01 . R1: MELCOR COMPUTER CODE MANUALS. Primer And Users' Guidos, Version 1.8.4. July 1997.

WGATTACleaflYAA NUREG/m4119 V02 R1: MELCOR cot # UTER CODE NUREG/CfM640 A DAMAGE MECHANICS SA8ED APPROACH TO MANUALS. Reference Manuele, Version 1.8.4, July 1997.

STRUCTURAL DETERIORATION AND REUABIUTY COINELLY,SA NUREG-1542 V03: ACCOUNTASIUTY REPORT FISCAL YEAR 1997.

Fu ACC RAT A,. -FLAGRATo,.- - TI. ,E,,

TRANOfTION PSENOMENON- MUREG/CfM666 V01: PROSABILISTIC ACCIDENT CONSEQUENCE ansannssanans a UNCERTAINTY ANALYSIS. Late Hosah Efloose - Uncertainty NUflEG/CR4000. INVESTIGATION OF TEQ4NIQUES FOR THE DE* fGW666 V02 PROBAWUSTIC ACCIDENT COPEEOUENCE BAWS USMG mE PROBAWUS- ANALYSIS. Late Heellh Ellects Uncertainey g NUREKm/CR4671 V01: PROSA81USTIC ACCIDENT CONSEQUENCE NURES/CR4811: RESULTS OF PRESSURE LOCIGNG AND THERMAL UN2RTANTY ANALYMS. Uncerninly Aaessemore For inlernal NURE PROSA88UlmC ACCIDENT CONSEQUENCE ggpugt,WA UN2RTAINTY ANALYSIS. Uncertainty Aaessement For internal NUfEG.1807: heleMUM DETECTABLE CONCENTRATIONS WITH TYP- DoelmstryAppendose.

! ICAL RADIATION SURVEY MBTRUMENTS FOR VARoUS CONTAte-l seANT3 Age FIELD CONDmONS. COPueSER,DA

! NUfEG/CfWBO4-. HUMAN PERFORMANCE N RADIOLOGICAL NUFIEG/GM874 V26: PRECURSORS TO POTENTIAL SEVERE CORE SURVEY SCAf#GNG. DAMAGE ACCIDENTS: 190ll A Steaue Report BINIINTIAJ. CORWIII,WA NLNEG/GW844, AETHODOLOGY FOR ANALYZING PRECURSORS NUREG/CfM691 V04 N1: HEAVY 4ECTION STEEL IRRADIATION I TO EARTHQUAIE4dmATED AfC Fife 4NmATED AnninSNT SE- PROGRAM.Somiennual Proyese Report For Areahar 1982 Through OLENCES. March 1903.

l t'

19

l N Perteftel AUSMBr IftdSE i

e40suuc. e00esums uu.

NUfES/CR 8000: ENGDEERING DRAWINGS FOR to CFR PART 71 NUREG/m4646 Vot: PROBA81USTC ACOIDENT CONSEQUENCE PACKAGE APPRO'/ALS. UNCERTAINTY ANALYSIS. Early , HeeNh Efloole Uncertanty <

Assenementush Report RA1EKL NUREG/m4646 V08: Ppnaame leTIC AOCIDENT CONSEQUENCE NUREG/CR4884 V02: FRAPCON4: A COMPUTER CODE FOR THE UNCERTAINTY ANALYSIS. Early HeeNh EfIncts Uncertainly CALCULATION OF STEADY-STATE. THERMAL 4ECHANICAL BE- Asessement.AppemBoss.

HAVIOR OF OXIDE FUEL RODS FOR HIGH BURNUP. NUREG/CR4606 V01: PROBA88USTC FNNT CONSEQUENCE UNCERTAINTY ANALYSIS.Lete HeeNh Eflects Unoortainly DEVKNIAS. AssessmenLMain Report.

NMG/lA4086: RELAP6/MC'30 SUSCOOLED 80 lung MODEL AS. NUREG/m4566 vot: Ppnaame iaTIC ACCIDENT CONSEQUENCE SESEMENT, UNCERTAINTY ANALYSIS.Lete Heath Eflects Uncertainty AssessmenLAppeasses.

MWAEKO. NUREG/CR4671 V01: PROBASIUSTIC ACCIDENT CONSEQUENCE NUlWG/CR4011: RESULTS OF PRES 8URE LOCIONG Ale TERMAL UNCERTAINTY ANALYSIS. Uncertainly Assessment For intemel f eWDING TESTS OF GATE VALVES. . Main Report NUREG/ 71 V03: PROSA81USTC ACCIDENT CONSEQUENCE N W G/ 11 Vee: STEAM GENERATOR TUSE INTEGRITY PnOGRAMAnnual 1ee6 - Septoneer 19e6.

NUPEG/m4676: FAILURE VIOR OF INTERNALLY PRESSUR- m j IZED PLAWED Al@ UNFLAWED STEAM GEERATOR TUBMG AT NUptEG/CR4800: THE EFFECTS OF SURFACE CONDIN ON AN i HIGH TSM'ERATURE EXPEREMENTS AND COMPARISON WITH ULTRASONIC INSPECTION: ENGINEERNG STUDIES USING VAU- l MODEL PREDCMS. DATED COMPUTER MODEL DOLAllA W. annamma r r.

NUfEG/CfHe74 V36: PRECURSORS TO POTENTIAL SEVERE CORE NUREG/CfM867 V24: ENVIRONMENTALLY AS6lSTED CRACKING W

'maa8 ACCIDENTS: 1906. A Status Report UGHT-WATER REACTORS. Semiennual Report J=.= / '"" 1997. l amanana a T. ggypggg, 73/m4006: AN$mC EVALUAM NUREG/CR4646 V01: PROSA81USTC ACCIDENT CONSEQUENCE dR ULTRA MSENW HUMAN FACTm8 RESEARCH WSPECDM. UNCERTAINTY ANALYSIS. Early HeeNh Eflects Unce m g AsessemenLMain Report NUREG/CR4673: "INVESTIGATNG SEISMOTECTONICS W THE j

,,UMTED STATES USWG A N NM NUREG4713 V18: OOCUPATIONAL RADIATION EXPOSURE AT COM-MERCIAL NUCLEAR POWER REACTORS AND OTHER l FACluTIES,1006. Twenty-Mnth Annual Report m l NUREG/CR 0648: A DAMAGE MECHANICS BASED APPROACH TO  !

AND M N ,

/h4646 V01:PROSABluSTC ACCIDENT CONSEQUENCE gggy,gg, UNCERTAINTY ANALYSIS. Early HueNh Eflects Uncertainty NUREG 0003 822: A PRCRITIZATION OF GENERC SAFETY ISSUES.

Main sport US QU M PsyRDCK C. UNCERTAINTY ANALYSIS. Early HeeNh Effects uncertainty NUREG/CR4800 THE EFFECT OF WITIAL TEMPERATURE ON AsseeemenLAppemAces.

FLAME ACCELERATION AND DEFLAGRATION.TODETONATION NUREG/CR4666 V01: PROBA81USTC ACCIDENT CONSEQUENCE TRANSmON PHENOMENON UNCERTANTY ANALYSIS.Lete HenNh E locts Uncertakity AssenemenLMein Report Puseason s s NUREG/CR4666 V02 PROBASIUSTIC ACCIDENT CONSEQUENCE NUREG/CR4000.

SUMMARY

AND EVALUATCN OF LOW-VELOCITY UNCERTANTY ANALYSIS.Lete Health Effects Unoerisinty IMPACT TEST OF SOUD STEEL BILLET ONTO CONCRETE PADS. - A, i-NUREG/CR4671 V01: PROBA88USTIC AOCIDENT CONSEQUENCE FRAfgG.NI,J. UNCERTANTY ANALYSIS. Uncertanty Asessement For intemel NUREG/CR4676: FAILURE BEHAVIOR OF WTERNALLY PRESSUR- Dom' metry. Main Report i lZED FLAWED AND UNFLAWED STEAM GENERATOR TUSING AT NUREG/CR4671 V02: PROBA81USTC ACCIDENT CONSEQUENCE HIGH TEMPERATURE -EXPERIMENTS AND COMPARISON WITH UNCERTAWTY ANALYSIS. Uncertainty Asessement For Intemel MODEL PREDCTIONS, Dommety " -

PUNCIES,8L HARPERJd.fL NUREG 1627 V01: PERFORMANCE PLAN FY 1999. NUREG-1022 R01: EVENT REPORTING GUIDEUNES 10 CFR 60.72 j AND 60 73.

GAUNTT,RO.

NUREG/CR4119 V01 R1: MELCOR COMPUTER CODE HAftfils,fLV.

MANUALS.Petmar And UsersM== Version 1.8.4. July 1997. NUREG/CR4006: AN EVALUATION OF HUMAN FACTORS RESEARCH NUREG/CR4119 V02 R1: uFirY1R CX)MPUTER CODE FOR ULTRASONC INSERVCE INSPECTION.

MANUALS Retarence Manuele, Version 1.8.4, July 1997.

HARRIODet,J.D.

N NUREG/CR4671 V01: PROBA81USTIC ACCIDENT CONSEQUENCE NUREG/CfM664 V01 R2: SCANS (SHIPPNG CASK ANALYSIS UNCERTANTY ANALYSIS. Uncertanty Asessement For incomel SYSTEM) A MICROCOMPUTER BASED ANALYSIS SYSTEM FOR Dosimetry. Main Report SHIPPING CASK DESIGN REVIEWheer's Manuel to Version 3e. NUREG/CR4671 V02: PROBA81USTIC ACCIDENT CONSEQUENCE UNCERTANTY ANALYSIS. Uncertanty Asessement For intemeJ GERLACHA. Dosimsey? ~-

NUREG/CR4800: THE EFFECT OF INmAL TEMPERATURE ON FLAME ACCELERATION AND DEFLAGRATION.TODETONATION HASIGN,FA.

TRAN8 MON PHENOMENON. NUREG/CR4646 V01: PROBA81USTC ACCIDENT CONSEQUENCE UNCERTAINTY ANALYSIS. Early Health Effects Uncertenty

• """"""7. AsessementMain Report NUREG/CR460fr THE EFFECT OF WITIAL TEMPERATURE ON NUREG/CR4646 V02: PROBA81USTIC ACCIDENT CONSEQUENCE FLAME AONIFRATION AND DEFLAGRATION-TO-DETONATION UNCERTAINTY ANALYSIS. Earty Health Effects Unoortanty TRANSmON PMNORENON. AeoseemenLAppendose-

Personal Author index 21 passans na KASZA KE.

NUREG/CR4479: TECHNCAL BASIS FOR ENVIRONMENTAL QUAU- NUREG/CR4511 V02: STEAM GENERATOR TUBE INTEGRITY FOATION OF MOROPHOCESSOR-BASED SAFETY-RELATED PROGRAM. Annual Report August 1995. September 1996.

EQU6PMENT IN NUCLEAR POWER PLANTS.

NUREG/CR4579: DIGITAL I&C SYSTEMS IN NUCLEAR POWER KHAN,HA PLANTS. Risk-Screenin9 Of Environmental Streasore And A cow NUREG/CR4359 V01: RAMONA4B A COMPUTER CODE WITH son Of Hardware U.-- iWIth An Exionn9 Analog Systern-THREE-DIMENSIONAL NEUTRON KINETCS FOR BWR AND SBWR psanses y2 SYSTEM TRANSIENTS.Modele And Correlatione.

NUREG/CR 0004: RADTRAD A SIMPUFIED MODEL FOR RADONU- NUREG/CR4359 V02 RAMONA-48: A COMPUTER CODE WITH CUDE TRANSPORT AND REMOVAL AND DOSE ESTIMATION. THREE-DIMENSONAL NEUTRON KINETICS FOR BWR AND SBWR SYSTEM TRANSIENTS. User's Manuel pnnas e a NUREG/CR4119 V01 R1: MELCOR COMPUTER CODE KUN04NOMITH,D.

MANUALS. Primer And Users' Guedes Veralon 1.8 4 1997. NUREG-1629: THE CHARACTERIZATION OF VICKER'S MICROHARD.

NUREG/CR4119 V02 R1: MELCOR R CODE NESS INDENTATIONS AND PILE 41P PROFILES AS A STRAIN-HARD-MANUALS. Reference Manuele, Version 1.8.4 July 1997. ENING MICROPROBE.

HOPMAYER,C.H. KNOSUCH,L.

NUREG/CR4554: FINITE ELEMENT ANALYSES FOR SEISMIC SHEAR NUREG/CR4575: FAILURE BEHAVIOR OF INTEHNALLY PRESSUR-WALL INTERNATIONAL STANDARD PROBLEM.

IZED FLAWED AND UNFLAWED STEAM GENERATOR TUBING AT NC, HIGH TEMPERATURE -EXPERIMENTS AND COMPARISON WITH NUREG/CR4555 V01: PROBABluSTIC ACCIDENT CONSEQUENCE MODEL MEDOTONS.

UNCERTAINTY ANALYSIS.Lete Health Effecte Uncertainty KOHN,WL NU V02 PROBABluSTIC ACCIDENT CONSEQUENCE NUREG/CR4577: U.S. NUCLEAR POWER PLANT OPERATING COST UNCERTAINTY ANALYSIS. Late Health Effecte Uncertainty AND EXPERIENCE SUMMARIES.

AseeeementAppendices.

NUREG/CR4571 V01: PROBABILISTO ACCIDENT CONSEQUENCE KORSAH.K.

UNCERTAINTY ANALYSIS. Uncertainty Assosoment For internal NUREG/CR4479: TECHNOAL BASIS FOR ENVIRONMENTAL QUAU.

Doornetryy,ein Report. FICATION OF MICROPROCESSOR-BASED SAFETY RELATED NUREG/CR4571 vu2: PROBABluSTO ACCIDENT CONSEQUENCE EQUIPMENT IN NUCLEAR POWER PLANTS '

UNCERTAINTY ANALYSIS. Uncertisinty Aseeeement For Internei l

Dommetry Appendicoe KRAAN.B.C.P.

1 NUREG/CR4545 V01: PROBABluSTIC ACCIDENT CONSEQUENCE HOVINGH,J.

UNCERTAINTY ANALYSIS. Early Health Effects uncertainty NUREG/CR4006:

SUMMARY

AND EVALUATION OF LOW-VELOCITY AseeeemenLMein Report IMPACT TEST OF SOUD STEEL BILLET ONTO CONCRETE PADS. NUREG/CR4545 V02 PROBABluSTIC ACCIDENT CONSEQUENCE HUPPERT M UNCERTAINTY ANALYSIS. Early Health Effecte Uncertainty NUREG-1507: MINIMUM DETECTABLE CONCENTRATIONS WITH TYP-NU 4 555 PROBABILISTIC ACCIDENT' CONSEQUENCE ICAL RADIATION SURVEY INSTRUMENTS FOR VARIOUS CONTAMl-NANTS AND FIELD CONDITIONS.

UNCERTAINTY ANALYSIS.Lete Health Effecte Unoorteinty Mein W HUMPHREYS,SL NUREG/CR4555 V02 PROBABluSTO ACCIDENT CONSEQUENCE NUREG/CR4eO4: RADTRACt A SIMPUFIED MODEL FOR RADIONU. UNCERTAINTY ANALYSIS.Lete Health Effecte Uncertainty CUDE TRANSPORT AND REMOVAL AND DOSE ESTIMATION. Ameneemer.LAppendlces.

NUREG/CR4571 V01: PROBABluSTIC ACCIDENT CONSEQUENCE emeranensR.S.K. UNCERTAINTY ANALYSIS. Uncertainty Aseeeement For internal NUREG/CR4447: RESULTS OF CRACK-ARREST TESTS ON IRRADI- Doornetry. Mein Report ATED A 500 CLASS 3 STEEL NUREG/CR4571 V02 PROBABluSTIC ACCIDENT CONSEQUENCE UNCERTAINTY ANALYSIS. Uncerteenty Assosoment For Intemel EG CR 5361: SEISMIC' ANALYSIS OF PIPING. Final Program Report KROGER.P.G.

NUREG/CR4472: PREUMINARY PHENOMENA IDENTIFICATION AND EG/CR4472: PREUMINARY PHENOMENA DENTIFICATION AND RANKING TABLES FOR SIMPUFIED BOluNG WATER REACTOR RANKING TABLES FOR SIMPUFIED BOILING WATER REACTOR LOSSOF COOLANT ACCOENT SCENARIOS.

LOSS OF COOLANT ACCOENT SCENARIOS.

JOHN 00st,GL N'JREG/CR4377: EFFECTS ON RADIONUCUDE CONCENTRATIONS NUREG/CH-4554 V01 R2 SCANS (SH:PPING CASK ANALYSIS BY CEMENT / GROUND-WATER INTERACTIONS IN SUPPORT OF SYSTEM) A MICROCOMPUTER BASED ANALYSIS SYSTEM FOR PERFORMANCE ASSESSMENT OF LOW LEVEL RADIOACTIVE SHIPPtNG CASK DESIGN REVIEW. User's Manuel to Version Se. WASTE DISPOSAL FACluTIES.

JOtES,W.R. KUPPERMAN,D.S.

NUREG-1022 R01: EVENT REPORTING GUIDEUNES 10 CFR 50.72 NUREG/CR4511 V02: STEAM GENERATOR TUBE INTEGRITY AND 50.73. PROGRAM. Annual Report. August 1995 - September 1996.

KAPKA,AL LAMSERT,HL NUREG/CR4573: " INVESTIGATING SEISMOTECTONICS IN THE NUREG/CR4544: METHODOLOGY FOR ANALYZING PRECURSORS EASTERN UNITED STATES USING A GEOGRAPHIC INFORMATON TO EARTHOUAKE-4NITIATED AND FIRE-INITIATED ACCIDENT SE.

SYSTEM." QUENCES.

NURE CR4453: H. B. ROBINSON-2 PRESSURE VESSEL BENCH- N CR4534 V02: FRAPCON-3: A COMPUTER CODE FOR THE j CALCULATION OF STEADY-STATE, THERMAL-MECHANICAL BE. 1 KARLgEN.T at. HAVIOR OF OXIDE FUEL RODS FOR HIGH BURNUP.

NUREGICR-4067 V24: ENVIRONMENTALLY ASSISTED CRACKING IN NUREG/CR4534 V03: FRAPCON4 INTEGRAL ASSESSMENT.

UGHT-w ATER REACTORS. Semiennued RN 1997.  !

KASSIER,T.F. NUREG/CR4573: "lNVESTIGATING SEiSMOTECTONICS IN THE NUREG/CR.4067 V24: ENVIRONMENTALLY ASSISTED CRACKING IN EASTERN UNITED STATES USING A GEOGRAPHIC INFORMATON UGHT WATER REACTORS. Semiennual RepoN 1997. SYSTEM."

_ _ . - ~ _ _ . _ _

P P

l 22 M Author hdez  ;

LETFE WJL .

HDwysa anass a [

NUREG/CR4002: DATING AfD EARTHOUAKE8. REVIEW OF QUA. NUREG/CP4142 Vot: PROCEEDMGS OF TM TWENTY-FIFTH

• TERNARY GEOCHRONOLOGY AND ITS APPUCATION TO PALEO- WATER REACTOR SAFETY INFORMATION MEETING. Plenary i SEnanans ritaY. Semelone,Preenwe Vesemi Research,0WR Steiner Blochage And Opier  !

Generic Safety leause.Enwhenmenteer Aeolated L ^ 1 Of LWR UA8L8L NUREG/CP4182 Vot; FwinssnWGS OF TVI TWENTY-FIFTH '

NUREG/GR4014: THE ROLE Of TIME-DEPENDENT DEFORMATION WATER REACTOR SAFETY INFORMATION MEETING. Human Re6-IN MTERGRANULAR MACK INITIATION OF ALLOY 800 STEAM elsely Anelpole And Hwnen Portonnance Evaluston, Technioni teouse  !

GEDERATOR TUSING MATERIAL. i Related To RulemeMng,s, Risk-Inlonned Portonnance4esed inIte-CP4182 VOS: PROCEEDINGS OF THE TWENTY-FIFTH NUREG-1ett: NRC ENFORMMENT POUCY REVIEW.luly 1906 Ady WATER REACTOR SAFETY INFORMATION MEETING.ThenneH4y.

• • dreute Reeserch And Codme, Dighal Instumentaton And Control,

• LemmaVA Stuonnai Personnenom ,

NUREG/CR4884: ANALYSES OF SOURCE SPECTRA, ATTENUATION. , , , , , , , , ,

" '" " ^" "

NUREG4640 V20 N01: TITLE LIST OF DOCUMENTS MADE PUBUCLY TE p AVAILAnf F inquary 1-31,1908.

LarTLEALP 8L NUREG/CR4066 V01: PROSA81USTIC ArnnFNT CONSEQUENCE UNCERTAINTY ANALYSIS. Late Healti Eficate C _ .., ENUK'EG/CR4675:

NUR FAILURE BEHAVIOR OF INTERNALLY PRE 88UR-IZED FLAWED AND UNFLAWED STEAM GENERATOR TUBING AT WMain W HIGH TEMPERATURE -EXPERIMENTS AND COMPARISON WITH NUREG/CR4666 V02: PROSA81USTIC ACCOENT CONSEQUENCE UNCERTAINTY ANALYS68. tate HeeNh E#ects Uncertainly MODEL PREDICTIONS.  ;

MUNLNEAR,88.D. I LAfDAS GA. NUREG/CR-4674 V26: PRECURSORS TO POTENTIAL SEVERE CORE NUREG-itte: TM CHARACTERIZATION OF VICKER'S MICROHARD. DAMAGE ACCIDENTS 1908. A Stelue Report  ;

DESS INDENTATIONS AND PILE UP PROFILES A8 A STRAIN-HARD.  :

ENMG MimOPROSE. IAUWWEAEACJL i:

NUREG/CR4666 V01: PROBA81USTIC ArnnFNT CONSEQUENCE naammmanas .a a UNCERTAINTY ANALYSIS.Lete Heenh Efloose Uncertainty l NUREG-tott R01: EVENT REPORTING GUIDELINES 10 CFR 60.72 AsseemmenLMain Report  ;

ADO 80.73. NUREG/m4666 V02: PROBA81USTIC ArnnsNT CONSEQUENCE 'i UNCERTAINTY ANALYSIS. Late Hamlet Effects Uncertainty MN AsessementAppensose. i NUREG/CR4611 VOR: STEAM GENERATOR TUSE INTEGRITY i PROGRAM. Annual 1906. September 1908. IIURPNY,5.D.

NUREG/CR4676: F VIOR OF INTERNALLY PRESSUR- NUREG/CR4636, VERIFICATION OF THE LWRARC CODE FOR IZED PLAWED AND UNFLAWED STEAM GENERATOR TUSING AT LIGHT-WATER REACTOR AFTERHEAT RATE CALCULATIONS.

PeGH TEtN'ERATURE EXPERIMENTS AND CX)MPARISON WITH <

MODEL PREDICTIONS. ISURTY,S.S.

NUREG/CR4006:

SUMMARY

AND EVALUATION OF LOW-VELOCITY EAL888'A 8L IMPACT TEST OF SOUD STEEL BILLET ONTO CONCRETE PADS. I NUREG/CR4300 V02: RAMONA 48: A COMPUTER CODE WITH 1 TtWIEE-DIMENSIONAL NEUTRON 10NETICS FOR BWR AND 88WR MAUS,0.,1. l SYSTEM TRApeelENTS. User's Manuel NUREG/CR4608. AN INVESTIGATION OF TENDON SHEATHING

"''""" FILLER MIGRATION MTO CONCRETE. '

NUREG/CR4016: A SURVEY OF REPAIR PRACTINS FOR NUCLEAR NUMEG/CR4800 THE EFFECT OF INITIAL TEMPERATURE ON POWER PLANT CONTAMMENT METAU.lO PRES 8URE BOUND- l FLAME ACMLERATION AND DEFLAORATION-TO ETONATION ARIES.

TRANSITION PMNOMENON, P eWR Anal P F ,

11: RESULTS OF PRES 8URE LOCIONG AND THERMAL OF F ICA BipelNG TE8TS OF GATE VALVES. i IEVISOTIN,I.Y. l NE NUREG/CR4360 V01: RAMONA-48; A COMPUTER CODE WITH l NUREG/CR4447: RESULTS OF CRACK ARREST TESTS ON IRN THREE DIMENSIONAL NEUTRON KINETICS FOR BWR AND 88WR ATED A 808 CLAS8 3 STEEL- SYSTEM TRANSIENTS.theaan And Coneletone I ans, , ,, , , NUREG/CR4360 V02: RAMONA-48. A COMPUTER CODE WITH NUREG/CR4004 RADTRAD: A SIMPUFIED MODEL FOR 1ADIONU. NREN MRM M MR BWR M SMR i SYSTEM TRANSIENTS. User's Manuet CUDE TRANSPORT AND REMOVAL AND DOSE ESTIMATOft asulaR,es.K. 18CNDLSDN T.J. I NUlWG/m4637 MFLUENCE OF LONG-TERM THERMAL AGS G ON NUREG/CP4103: PROCEEDINGS OF THE WORKSHOP ON REVIEW l TIE hmCROSTRUCTURAL EVOLUTION OF NUCLEAR REASTOR OF DO8E MODEUNG METHOD 6 FOR DEMONSTRATION OF COM-PfESOURE VranFI MATER 6ALSAn Atom Protie Study. PUANCE WITH THE RADIOLOGICAL CRITERIA FOR UCENSE TER- ,

MINATION.

N W. IIDLLER,AS.  ;

NUIEG/m-4674 V26: PRECURSORS TO POTENTIAL SEVERE CORE DAMAGE AmansNTS: 1906. A 8eamas Report. NUREG/CR 6662: DATING AND EARTHOUAKES: REVIEW OF QUA-TERNARY GEOCHRONOLOGY AND ITS APPUCATION TO PALEO- l M DK A C. 8E18MOLOGY.

NufEG/OR-4664 V01 R2: SCANS (SHIPPING CASK ANALYSIS ,

SYSTEM) A MICROCOMPUTER BASED ANALYSIS SYSTEM FOR DDETTEAfL SHIPPING CASK OESIGN REVIEW. User's Manuel to Varelon Se. NUREG-1829: THE CHARACTERIZATION OF VICKER'S MICHOHARD- 1 NUREG/CR4000: SUMt4ARY AND EVALUATION OF LOW-VELOCITY NESS INDENTATIONS AND PILE UP PROFILES AS A STRAM-HARD- J IMPACT TEST OF SOUD STEEL BILLET ONTO CONCRETE PADS. ENING MICROPROSE.

amnasens n er na maan e a ,

NUfEG/CR4004. RADTRADt A SIMPUFIED MODEL FOR RADIONU- NUREG/CR4600. AN INVESTIGATION OF TENDON SHEATHING  ;

CUDE TRANSPORT AND REMOVAL AND DOWE EST54ATION. FILLER hmORATION MTO CONCRETE. 9 i

I J

2 Personal Author index 23 NUREG/CR4816: A SURVEY OF REPAIR PRACTICES FOR NUCLEAR ROHATSI,UA POWER PU4NT ODNT%iNMENT METALUC PRESSURE BOUND- NUREG/CR4369 Voi: RAMONA 48. A COMPUTER CODE WITH

, ARIES.

THREE-DIMENSIONAL NEUTRON KINETICS FOR BWR AND SBWR SYSTEM TRANSIENTS.Modele And Correisuono.

OLSONAJ. NUREG/CR4369 V02: RAMONA48. A CX)MPUTER CODE WITH NUREG/CR4640: STATE OF.THE-ART REPORT ON PIPING FRAC- THREE OIMENSIOhAL NEUTRON KINETICS FOR BWR AND SBWR TURE MECHANICS. SYSTEM TRANSIENTS. User's Manuel i

NUREG/m4472: PRELIMINARY PHENOMENA IDENTIFICATION AND PA8EIGE.P.

RANKING TABLES FOR SIMPUFIED BOIUNG WATER REACTOR NUREG/CR4637 lNFLUENCE OF LONG-TERM THERMAL ACING ON LOSS.OF COOLANT ACCIDENT SCENARIOS.

THE MICRO 8TRUCTURAL EVOLUTION OF NUCLEAR REACTOR PRES 8URE VESSEL MATERMLSAn Atom Probe Study. pnaaews TX 1

NUREG/CR4691 V08 N1: HEAVY-SECTION STEEL 1RRADIATION PARKJR PROGRAM.Somiennual Progreev Report For October 1996 Tivough 4

NUREG/CR-4887 V24 ENVIRONMENTALLY ASSISTED CRACKING IN March 1997.

UGHT WATER REACTORS. Semiennual Report, January. June 1997.

pimensii s W, PARKJ.Y. NUREG/GI-6602: ENGINEERING DRAWINGS FOR to CFR PART 71 NUREG/CR4611 V02: STEAM GENERATOR TUBE INTEGRITY PACKAGE APPROVALS.

PROGRAM Annual Report,Au9ust 1995. September 1996.

pasensi e ar s, PARK.YJ. NUREG/CR4637: INFLUENCE OF LONG. TERM THERMAL AGING ON NUREG/CR4664: FINITE ELEMENT ANALYSES FOR SEISMIC EHEAR THE MemOSTRUCTURAL EVOLUTION OF NUCLEAR REACTOR WALL INTERNATIONAL STANDARD PROBLEM. PRESSURE VESSEL MATERIALS.An Atom Probe Study.

PARROTT,JA RUTNER,WL NUREG/CP 0163: PROCEEDINGS OF THE WORKSHOP ON REVIEW NUREG/CR4867 V24: ENVIRONMENTALLY ASSISTED CRACKING IN

, OF DOSE MODEUNG METHODS FOR DEMONSTRATION OF Cold- UGHT-WATER REACTORS. Semiennual Report January Jur.e 1997.

PUANCE WITH THE RADIOLOGICAL CRITERM FOR UCENSE TER-l MINATION. pas ama air

, NUREG/CR4644: METH000 LOGY FOR ANALYZlNG PRECURSOR 3 PEDERSENAM. TO EARTHOUAKE-INITMTED AND FIRE-INITIATED ACCIDENT SE-NUREG-1622: NRC ENFORCEMENT POUCY REVIEW. July 1995 July OUENCES.

1997.

SANDERS,R.L PHAM,T.N. NUREG/CR4119 V01 R1: MELCOR COMPUTffl OODE i' NUREG 0430 V16: UCENSED FUEL FACILITY STATUS MANUALS. Primer And Users' Guideo, Version 1.8.4, July 1997.

REPORT. inventory DIMerence Date. July 1,1995 June 30,1996.(Grey NUREG/CR4119 V02 R1: MELCOR COMPUTER CODE Book ll) MANUALS.Relerence Manuals, Version 1.8.4 July 1997.

Pggit,A. mananans a a NUREG/CR4447: RESULTS OF CRACK-ARREST TESTS ON 1RRADI- HUREG-1022 Rot: EVENT REPORTING GUIDEUNES 10 CFR 60.72 i ATED A 508 CLASS 3 STEEL AND 50.73.

P"a**"nV.AA SAIECKI,JL NUREG/M4025: RELAPS/ MOD 3 SUBCOOLED BOLLING MODEL AS. NUREG/CR-4007 V24: ENVIRONMENTALLY ASSISTED CRACKING IN SESSMENT UGHT-WATER REACTORS. Semiennual Report, January. June 1997.

POND,DA SANTOS,C.

NUREG/CR-0806: AN EVALUATION OF HUMAN FACTORS RESEARCH NUREG-1629: THE CHARACTERIZATION OF VICKER'S MICROHARD-FOR ULTRASONIC INSERVICE INSPECTION. NESS INDENTATIONS AND PILE-UP PROFILES AS A STRAIN.HARD-l ENING MICROPROBE.

NUREG-1507: MINIMUM DETECTABLE CONCENTRATIONS WITH TYP- SCHRDE1 ERA ICAL RADIATION SURVEY INSTRUMENTS FOR VARIOUS CONTAMI- NUREG-1829: THE CHARACTERIZATION OF VICKER'S MICROHARD-NANTS AND FIELD CONDITIONS. NESS INDENTATIONS AND PILE-UP PROFILES AS A STRAllMMRD-ENING WICROPROBE.

PYLEVAS.

NUREG/lA.0024: APPUCATION OF RELAP5/ MOO 3.1 CODE TO THE SCOTT PR LOFT TEST L34. NUREG/CR4640: STATE OF-THE-ART TfPORT ON PIPING FRAC-TURE MECHANICS.

RAVIgElRA, ILK.

NUREG/CR4644 METHODOLOGY FOR ANALYZING PRECURSORS SERNE,RA TO EARTHOUAKE-INITIATED AND FIRE-INITIATED ACCIDENT SE- NUREG/CR4377: EFFECTS ON PADIONUCUDE CONCENTRATIONS QUENCES. BY CEMENT / GROUND-WATER INTERACTIONS IN SUPPORT OF PERFORMANCE ASSESSMENT OF LOW-LEVEL RADIOACTIVE REID A L WASTE DISPOSAL FACluTIES.

NUREG/GI-0677: U.S. NUCLEAR POWER PLANT OPERATING COST AND EXPERIENCE SUMMARIES. SHACK,WJ.

NUREG/CR 4867 V24: ENVIRONMENTALLY ASSISTED CRACKING IN RESIEC.I. UGHT-WATER REACTORS. Sermannual Report,Jonuary. June 1997.

NUREG/CR4463: H. S. ROBINSON.2 PRESSURE VESSEL BENCH. NUREG/CR4611 V02: STEAM GENERATOR TUBE INTEGRITY MARK. PROGRAM. Annual Report, August 1995. September 1996.

NUREG/CR4575: FAILURE BEHAVIOR OF INTERNALLY PRESSUR-RD0paasssy a a IZED FLAWED AND UNFLAWED STEAM GENERATOR TUBING AT NUREG/CR4119 V01 R1: MELCOR (X)MPUTER CODE HIGH TEMPERATURE -EXPERIMENTS AND COMPARISON WITH MANUALS.Prkner And Users' hi= Version 1.8.4. July 1997, MODEL PREDICTIONS.

NUREG/CR4119 V02 R1: MELCOR COMPUTER CODE NUREG/CR4683: EFFECTS OF LWR COOLANT ENVIRONMENTS ON MANUALS.Reeerence Manuals, Version 1.8.4, July 1997. FATIGUE DESIGN CURVES OF CARBON AND LOW-ALiGY STEELS.

mmmaarana V.L. SHEAPPEfLM.K.

NUREG/M4P24: APPUCATION OF RELAP5/ MOD 3.1 CODE TO THE NUREG/CR-6602: ENGINEERING DRAWINGS FOR 10 CFR PART 71 LOFT TEST L34. PACKAGE APPROVALS.

i l

24 Personal Author index SHORT,C.4L NUREG/CR-5502 ENGINEERING DRAWINGS FOR 10 CFR PART 71 l

NUREG/CR4008: INVESTIGATION OF TECHNIQUES FOR THE DE. PACKAGE APPROVALS.

VELOPMENT OF SEISMIC DESIGN BASIS USING THE PROBABluS-TIC SEISMIC HAZARD ANALYSIS. THOMany L 1 l

NUREG4)713 V18: OCCUPATIONAL RADIATION EXPOSURE AT COM-l SLOVfEAC. MERCIAL NUCLEAR POWER REACTORS AND OTHER NUREG/CR4472: PREUMINARY PHENOMENA IDENTIFICATION AND FACluTIES,1996. Twenty-Ninth Amuel Report.

I RANKING TABLES FOR SIMPUFIED BOfJNG WATER REACTOR I

LOSSOF-COOLANT ACCIDENT SCENARIOS. TRUMMER,DJ, NUREG/CR-4554 VD1 R2: SCANS (SHIPPING CASK ANALYSIS SMITH,J.L SYSTEM) A MICROCOMPUTER BASED ANALYSIS SYSTEM FOR

( NUREG/CR4867 V24: ENVIRONMENTALLY ASSISTED CRACKING IN SHIPPtNG CASK DESIGN REVIEW. user's Manual to Version 3a.

UGHT WATER REACTORS. Senuamuel Report. January-June 1997.

VESELY,W.E.

SMLTHAC. NUREG/CR4579 DIGITAL L&C SYSTEMS IN NUCLEAR POWER l NUREG/CR4119 V01 R1: MELCOR COMPUTER CODE PLANTS. Risk-Screening Of Environmental Stroseors And A Compart.

MANUALS. Primer And Users' Guides, Version 14.4 1997 non Of Hardware Unevallability Wtth An Existin9 Ana6og System.

NUREG/CR4119 V02 R1: MELCOR R CODE l MANUALS. Reference Manuals, Version 1.8.4, July 1097. WAS,G.S.

, NUREG/GR-0016: THE ROLE OF TIME-DEPENDENT D" FORMATION l SOPPET,WK. IN INTERGRANULAR CRACK INITIATION OF ALLOY 600 STEAM NUREG/CR4067 V24: ENVIRONMENTALLY ASSISTED CRACKING IN GENERATOR TUBING MATERIAL.

I UGHT WATER REACTORS. Senwennual Report. January June 1997.

WATKINS,J.C.

562: DATING AND EARTHQUAKES: REVIEW OF OUA- N NG TE GATE VES TERNARY GEOCHRONOLOGY AND ITS APPUCATION TO PALEO-SEISMOLOGY. WHi1E,V.S.

NUREG/CR4577: U.S. NUCLEAR POWER PLANT OPERATING COST STOLLERAE. AND EXPERIENCE SUMMARIES.

l NUREG/CR-8537: INFLUENCE OF LONG-TERM THERMAL AGING ON THE MICROSTRUCTURAL EVOLUTION OF NUCLEAR REACTOR WILKC'VSKI,G.M.

PRESSURE VESSEL MATERIALS.An Atom Probe Study. NUREG/CR4540: STATE OF-THE-ART REPORT ON PIPING FRAC-TURE MECHANICS.

STRAINAV.

NUREG/CR4667 V24: ENVIRONMCNTALLY ASSISTED CRACKING IN WITTE.M.C.

I UGHT-WATER REACTORS. Semiannual Report, January June 199/. NUREG/CR4600:

SUMMARY

AND EVALUATION OF LOW-VELOCITY IMPACT TEST OF SOUD STEEL BILLET ONTO CONCRE7E PADS.

STRUCKMEYERA NUREG4837 V17 NO3: NRC TLD DIRECT RADIATION MONITORING WOOOAT,  !

NETWORK.Progrees Report July-September 1997. NUREG/CR4479: TECHNICAL BASIS FOR ENVIRONMENTAL QUAU- 1 FICATION OF MICROPROCESSOR-BASED SAFETY-RELATED i SWARTAS. EOUiPMENT IN NUCLEAR POWER PLANTS.

NUREG/CR4119 V01 R1: MELCOR COMPUTER CODE i

MANUALS. Primer And Users' Guides. Version 1.8 4, July 1997 WU,J.S.

l NUREG/CR4119 V02 R1: MELCOR COntPt/TER CODE NUREG/CR4544: METHODOLOGY FOR ANALYZING PRECURSORS

[

MANUALS. Reference Manuals, Version 1.8.4, July 1997. TO EARTHOUAKE-INITIATED AND FIRE-INITIATED ACCIDENT SE-1 OUENCES.

NUREG/CR4119 V01 R1; MELCOR COMPUTER CODE YAMAMOTO.T.

. MANUALS. Primer And Users' th, Version 1.8 4 1997. NUREG-1629: THE CHARACTERIZATION OF VICKER'S MICROHARD-l NUREG/CR4119 V02 R1: MELCOR COM R CODE NESS INDENTATIONS AND PILE-UP PROFILES AS A STRAIN-HARD- l l MANUALS. Reference Manuals, Version 1.8.4, July 1997 ENING MICROPROBE.

TAGAWAA YOUNG,M.F.

NUREG/CR4509: THE EFFECT OF INITIAL TEMPERATURE ON NUREG/CR4119 V01 R1: MELCOR COMPLITER CODE  !

( FLAME ACCELERATION AND DEFLAGRATION-TO-DETONATION MANUALS. Primer And Users' Guides. Version 1.8.4. July 1997.

l TRANSITION PHENOMENON. NUREG/CR4119 V02 R1: MELCOR COMPLITER CODE MAfvUALS. Reference Manuals, Version 1.8.4, July 1997.

TMM NUREG/CR4479- TECHNICAL BASIS FOR ENVIRONMENTAL QUAU- YOUNA M I .  !

l FICATION OF MICROPROCESSOR-BASED SAFETY-RELATED NUREG/CR4613 V01: CODE MANUAL FOR MACCS2. user's Guide. i EQUIPMENT IN NUCLEAR POWER PLANTS. NUREG/CR4613 V02: CODE MANUAL FOR MACCS2. Preprocessor '

Codes COMIDA2, FGRDCF, IDCF2.

NUREG/CR4554 V01 R2: SCANS (SHIPPINd CASK ANALYSIS ZALUZEC,NJ- i l

i SYSTEM) A MICROCOMPUTER BASED ANALYSIS SYSTEM FOR NUREG/CR-4667 V24: ENVIRONMENTALLY ASSISTED CRACKING IN i l SHIPPING CASK DESIGN REVIEW. User's Manual to Version Sa. UGHT-WATER REACTORS. Senuannual Report, January-June 1997.

, l l

l l

Subject index This index was developed from keywords and word strings in titles and abstracts. During this development period, there will be some redundancy, which will be removed later when a rea-sonable thesaurus has been developed through experience. Suggestions for improvements are welcome.

10 CPR Part 71 BWR NUREG/CR 6802 ENGINEERING DRAWINGS FOR 10 CFR PART 71 NUREG/CR4472: PRELIMINARY PHENOMENA IDENTIFICATION AND PACKAGE APPROVALS. RANIONG TABLES FOR SIMPUFIED BOluNG WATER REACTOR

, LOSS OF COOLANT ACCIDENT 8CENARIOS-

!' NUREG/CR4447: RESULTS OF CRACK-ARREST TESTS ON IRRADI- Behowtor Pressenen

[ ATED A 508 CLASS S STEEL NUREG/lA4021L RELAP6/ MODS SU8 COOLED $0 lung MODEL AS-i SES8 MENT l

ACRS Report NUREG-1126 V10 A COMPILATION OF REPORTS OF THE ADVISORY 8enelunerk i therTTEE ON REACTOR SAFEGUARDS.1997 Annust. NUREG/CR4463, H. B. ROSIN 80N-2 PRESSURE VESSEL BENCH.

Aggo i NUREG-1272 V10 N01: OFFICE FOR ANALYSIS AND EVALUATION OF BoAng Water Reester i OPERATIONAL DATA.1998 Annual Report NUREG/CR4472: PREUMINARY PHENOMENA IDENTIFICATION AND l NUREG-1272 V10 N02: OFFICE FOR ANALYSIS AND EVALUATION OF l RANKING TA8LES FOR SIMPUFIED 800UNG WATER REACTOR  !

) OPERATIONAL DATA 1986 Annual Report LOSSCF-COOLANT ACCIDENT SCENARIOS. p NUREG-1272 V10 NOS: OFFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA.1996 Annual Report Budget NUREG 1100 V14: SUDGET ESTIMATES. Fiscal Year 1900.

Ahneneel Oseurvenes NUREG-0000 V20: REPORT TO CONGRESS ON A8 NORMAL COSVIAA 000URRENCES.Flecal Year 1997. NUREG/CR4666 V01: PROSASIWSTIC ACCIDENT CONSEQUENCE Assedent Seguenos Peuourser UNCERTAINTY ANALYSIS.Lete HooNh Eflects Uncertainly AsseeementMain Report i

NUREG/CR-4874 V26: PRECURSORS TO POTENTIAL SEVERE CORE NUREG/CR4666 V02: PROSABluSTIC ACCIDENT CONSEOUENCE i DAMAGE ACCIDENTS:190ll A Sletus Report UNCERTAlmY ANALYSIS. Late Heellh Effecle Uncertainly NUREG/CR4544 MUHODOLOGY FOR ANALYZING PRECURSORS _"

TO EARTHQUAKE-INITIATED AND FIRE-INITIATED ACCID ~;NT CE4 QUENCES. Cook Storego ,

NUREG/CR4008

SUMMARY

AND EVALUATION OF LOW-VELOCITY Aeoeunte85ty Report .

IMPACT TEST OF SOLIO STEEL BILLET ONTO CONCRETE PADS.

NUREG-1642 VOS: ACCOUNTA84UTY REPORT FISCAL YEAR 1997.

Ceed Leg Anortiest Rete Nd=an='I NUREG/lA-0024: APPUCATION OF RELAP6/ MOD 3.1 CODE TO THE NUREG/CR4631L VERIFICATION OF THE LWRARC CODE FOR LOFT TEST L34.

LIGHT-WATER 4tEACTOR AFTERHEAT RATE CALCULATIONS.

Comprehenelve Roseed Agne NUREG4010 R03: NRC COMPRIEHENSIVE RECORDS DISPOSITION

l. NUREG/CR4412: AGING AND LOSSCF CnOLANT ACCIDENT (LOCA) SCHEDULE.

l TESTING OF ELECTRICAL CONNECTIONS.

NUREG/CR4646. A DAMAGE MECHANICS BASED APPROACH TO Computer Code STRUCTURAL DETERIORATION AND REUABlUTY. NUREG/CR4360 V01: RAMONA 48. A COMPUTER CODE WITH THREE-DIMENSIONAL NEUTRON KINETICS FOR BWR AND 88WR Agey 800 SYSTEM TRANSIENTS.na~eaan And Corretellona.

NUREG/GR-0016: T'tE r ROLE OF TIME-DEPENDENT DEFORMATION NUREG/CR4360 V02: RAMONA-48. A COMPUTER CODE WITH a IN IMERGRANULAR CRACK INITIATION OF ALLOY 800 STEAM THREE-DIMENSIONAL NEUTRON KINETICS FOR SWR AND 88WR GENERATOR TUSING MATERIAL SYSTEM TRANSIENTS. User's Manuel NUREG/CR4634 V02: FRAPCON-3: A COMPUTER CODE FOR THE Anseeg System CALCULATION OF STEADY-STATE, THERMAL-MECHANICAL BE-NUREG/CR4679 DIGITAL l&C SYSTEMS IN NUCLEAR POWER HAVIOR OF OXIDE FUEL RODS FOR HIGH SURNUP.

PLANTS. Risk-Screening Of Environmental Sweesore And A Compart- NUREG/CR4634 V03: FRAPCON-3: INTEGRAL ASSESSMENT.

son Of Herdeere Unsuetehdlly With An Exieling Analog Syalem.

l. Annuef fesport NUREG/CR4608: AN INVESTIGATION OF TENDON SHEATHING I

' NUREG-1272 V10 Not: OFFICE FOR ANALYSIS AND EVALUATION OF FILLER MIGRATION INTO CONCRETE.

OPERATIONAL DATA.1986 Annual Report i

NUREG 1272 V10 NOS: OFFICE FOR ANALYSIS AND EVALUATION OF Cenerete Pad OPERATIONAL DATA 1996 Annual Report NUREG/CR4008.

SUMMARY

AND EVALUATION OF LOW VELOCITY IMPACT TEST OF SOUD STEEL 81LLET ONTO CONCRETE PADS.

Atom Preto NUREG/CR4637: INFLUENCE OF LONG-YJIM THERMAL AGING ON Conleest IBeressepy l

THE 94CROSTRUCTURAL EVOLUTION OF NUCLEAR REACTOR NUREG1629 THE CHARACTERIZATION OF VICKER'S MICROHARD-PRESOURE VESSEL MATERIALS.An Atom Probe Study. NESS INDENTATIONS AND PILE-UP PROFILES AS A STRAIN-HARD-ENING MICROPROBE.

Atomes Sassey And uneneens Board l NUREG-1308 VO7: ATOMIC SAFETY AND UCENSING BOARD SIENNI. Ceneoguence Anefyele j AL REPORTflacal Years 1996 1908. NUREG/CR4613 V01: CODE MANUAL FOR MACC82. User's Guide.

4 W

4 26 l-

. - . - ~ , .-. .. --~.-,- - - - . - , --- - -- . - _ - . _. ~.- - .-

i 1

l 28 SdsjectItulex

- Es teuske NUREG/CR4640: A DAMAGE MECHANICS BASED APPROAQ4 TO NUREG/CR-6682 DATING AND EARTHQUAKES: REVIEW OF QUA- l STRUCTURAL DETE7tlORATION AND RELIA 81UTY TERNARY GEOCHRONOLOGY AND ITS APPUCATION TO PALEO- j NUREG/m4815: A SURVEY OF REPAIR PRACTICES FOR NUCLEAR SEISMOLOGY. I POWER PLANT CONTAIMNT hETALLIC PRES 8URE BOUND- NUREG/CR4644. METHOOOLOGY FOR ANALYZING PRECURSORS 1 ARIES. TO EARTHQUAKE-INITMTED AND FIRE-INITIATED ACCIDENT SE- l OUENCES.

CentedRoom NUREG/CR4664: ANALYSES OF SOURCE SPETHRA, ATTENUATION, WREWCR 8004 N. A M M M N I CUDE TRANSPORT AND REMOVAL AND DOSE ESTIMATION.

AND SITE EFFECTS FROM CENTRAL AND EASTERN UNITED l STATES EARTHQUAKES. l Coolant Enviremment  !

Elastrismi Conneogen NUREG/CR4883: EFFECTS OF LWR COOLANT ENVIRONMENTS ON ]

FATIGUE DESIGN CURVES OF CARSON AND LOW ALLOY STEELjL WREWCRM12: AGNG AND LOSS.OFN ACCOEM A TESTNG OF ELECTR6 CAL CONNECTIONS. I Consolen Pellgue

. NUREG/CR-4007 V24: ENVIRONMENTALLY ASSISTED CRAQUNG IN Enitellesment i UGHT-WATER REACTORS. Semiennual T , ^Or, J:.m.1997. NUREG/CR4447: RESULTS OF CRACK ARREST TESTS ON 1RRADL ATED A 508 CLASS 3 STEEL Crash Anset Test NUREG/CR4637: INFLUENCE OF LONG-TERM THERMAL AGING ON NUREG/CR4447: RESULTS OF CRACK ARREST TESTS ON 1RRADL THE MICROSTRUCTURAL EVOLUTION OF NUCEAR REACTOR  !

ATED A SOS CLASS 3 STEEL PRESSURE VESSEL MATERMLS.An Atom Probe Study. j G CR4640: A DAMAGE MECHANICS BASED APPROACH TO NUREG-1022 R01: EVENT REPORTNG GUIDEUNES 10 CFR 60.72 STRUCTURR DETERORATON AND MUA8luTY. AND 80.73.

Date Quegly Ch$setvo NUREG-1676: MULTLAGENCY RADIATION SURVEY AND SITE INVES. EsWorsement W l TIGATION MANUR M. Final Repg NUREG-0040 V16 N2 P1: ENFORCEMENT ACTIONS: SIGNIFICANT AC-  !

TIONS RESOLVED INDIVIDUAL ACTIONS.Serrmannual Proyese l Desenenteniening 1997. I NUREG-1807: MINIMUM DETECTABLE CONCENTRATIONS WITH TYP. V16 N2 P2: ENFORCEMENT ACTIONS: SIGNIFICANT AC.

ICAL RADMTON SURVEY INSTRUMENTS FOR VARIOUS CONTAML TIONS RESOLVED REACTOR UCENSEES.Somiennual Progress NANTS AND FIELD CONDITIONS. 1997.

NUREG 1676: MULTLAGENCY RADMTION SURVEY AND SITE INVES- G4040 V16 N2 P3: ENFORCEMENT ACTIONS: SIGNIFICANT AC.

TIGATION MANUAL . Final Report TIONS RESOLVED MATERML UCENSEES.Semiennual Progreso NUREG/CP4103: OF THE WORKSHOP ON REVIEW g ggy, OF DOSE MODEUNG METHODS FOR DEMONSTRATION OF COM-PUANCE WITH THE RADIOLOG4 CAL CRITERM FOR UCENSE TER- Engineering Drawing , )

MINATION. NUREG/CR-6602: ENGNEERING DRAWINGf! (CR 10 CFR PART 71 NUREG/CR4364: HUMAN PERFORMANCE N RADIOLOGICAL PACKAGE APPROVALS.  !

SURVEY SCANNHG Envirmenentes m- {

_ y _ y. .

NUAEG/CR4500: THE EFFECT OF INITML TEMPERATURE ON WREWCRM79: TECHNICAL BASIS M NMR WAU-FLAME ACCEERATION AND DEFLAGRATON-TO-DETONATION FICATON OF h4CROPRCCESSOR-8ASED SAFETY-RELATED EQUIPMENT IN NUCLEAR POWER PLANTS.

N PHENOMENON.

Datenemen Environmental Stresser NUREG/CR4500 THE EFFECT OF NITML TEMPERATURE ON NUREG/CR4679: DIGITAL l&C SYSTEMS N NUCLEAR POWER FLAME ACCEfERATION AND DEFLAGRATION-TO-DETONATION PLANTS. Risk-Screenho Of Envirtnmental Streasore And A Comperk 1 TRANSITION PHENOMENON. son Of Hardware Unevetability WIti An Emiellng Analo9 Systern.

lac Environmentasy Analsted CreeMns

/ 79: DIGITAL EC SYSTEMS IN NUCEAR POWER NUREG/CR-4067 V24: ENVIRONMEdTALLY ASSISTED CRACKING IN )

PLANTS. Risk Screening Of Environmental Streaeore And A Congserk UGHT-WATER REACTORS. Semierwel Report, January. June 1907, son Of Hanheere Unevensbety With An Emisung Analog System.

Event Reporting Guldeanos M And Control NUREG-1022 R01: EVENT REPORTNG GUOEUNES 10 CFR 60.72 i

/CP4162 VOS: PROCEEDINGS OF THE TWENTY-FIFTH AND 60.73.

WATER REACTOR SAFETY INFORMATION MEETING.ThermeLHy.

draubc Research And Codes, Digital instrumerneuen And Consol, Esternet Espesure Structwel Performanos. NUREG/CR4613 V02: CODE MANUAL FOR MACCS2 Prepraa===ar cadam COtmDA2 FGRDCF,IOCF2.

NUREG4010 ROS NRC COMPREHENSIVE RECORDS DISPOSITION FRAPC006 3 SCHEDUE- NUREG/CR4634 V02: FRAPCON-3: A COMPUTER CODE FOR THE Does ConverMan CALCULATION OF STEADY-STATE. THERMAL-MECHANICAL BE-

"^ " P NUREG/CR4813 V02 CODE MANUAL FOR MAOCS2.Propraa===ar Codoo COMIDA2, FGRD&, IDCF2.

WRE CR G A8SES MENT. l i

Penalty Aeeident Does NUREG/CP 183: PROCEEDINGS OF THE WORKSHOP ON REVIEW NUREG/CR4410: NUCLEAR FUEL CYCLE FACluTY ACCOENT ANAL- l OF DOSE MODEUNG METHODS FOR DEMONSTRATION OF COM. YSIS HANDBOOK. j WITH THE RADIOLOGICAL CRITERM FOR UCENSE TER- g,,,,, g NUREG/CR4683: EFFECTS OF LWR COOUNT ENVIRONMENTS ON Deshootry FATIGUE DESIGN CURVES OF CARBON AND LOW-ALLOY STEELS.

NUMG/CR4671 V01: PROBA80USTIC ACCOENT CONSEQUENCE M N Impoot Statement UNC,ERTAINTY p., ,,,y.u,gn ANALYSIS. y Uncertainty Asessement For incomed NUREG-1826: FINAL ENVIRONMENTAL IMPACT STATEMENT FOR THE CONSTRUCTION AND OPERATION OF AN INDEPENDENT EISP/SNI SPENT FUEL STORAGE NSTALLATION TO STORE THE THREE NUMEG/CR4463: H. B. ROnlN80N-2 PRESSURE VESSEL BENCH- MIE ISLAND UNIT 2 IIPENT FUEL AT THE IDAHO NATIONAL ENGk MARK. NEERING AND ENVIRM1 ENTAL

. m __ . __ . _ _ . . - _ _ _ _ _ _ _ _ . . _ _ _ _ - _ . _ _ _ _ _ - . _ _ . _ _ . _ ._

l Subject index 27 Rennedal Statement NUREG/CR-6601 VOS N1: HEAVY 4ECTION STEEL 1RRADIATON NUREG-1542 Vos: AOCOUNTABlUTY REPORT FISCAL YEAR 1997, e ROGRAM.8emiennual Propees Report For October 1906 Through 8

March 1997.

NUfEG/CR4864: FMITE p1 FeaFNT ANALYSES FOR SEISMC SHEAR 988h Burn Up Puol Reesereh WALL WTERNATIONAL STANDARD PROBLEM.

NUREG/CP-0162 V02- PROCEEDINGS OF THE TWENTY-FIFTH j pg,,g,, g,, WATER REACTOR SAFETY INFORMATION MEETING. Human Rot-NUREG/CR4884 V02: FRAPCON4: A COMPUTER CODE FOR THE ab8W Analyse And Human Performance Evolueton, Technical leeues CALCULATION OF STEADY-STATE, THERMAL MECHANICAL BE- Related To RulemelWge, Risk-Intormed, h inle&

i- HAVIOR OF OXIDE FUEL RODS FOR HIGH SURNUP #ves t NUREG/CR4884 VOS: FRAPCON4 INTEGRAL ASSESSMENT l

le p Burnup .

Ptems Anselere8en NUREG/OR4634 Vom FRAPCON4: A COMPUTER CODE FOR THE NUREG/m4809: THE EFFECT OF INITIAL TEMPERATURE ON l CALCULATION OF STEADY-STATE THERMAL-MECHANCAL BE. '

FLAME ACELERATION AND DEFLAGRATION TO.OETONATION HAVIOR OF OXIDE FUEL RODS FOR HIGH BURNUP TRANSITION PHENOMENON. NUREG/CR4634 V03: FRAPCON-3: INTEGRAL ASSESSMENT.

)

Preature Meehentes leSh Temperature 1 NUREG/CR4640 STATE OF-THE-ART REPORT ON PIPING FRAC- NUREG/CR4675: FAILURE BEHAVIOR OF INTERNALLY PRESSUR. I TURE MECHANM  !

IZED FLAWED AND UNFLAWED STEAM GENERATOR TUBMG AT

y,,,,,,e veuthnese HIGH TEMPERATURE -EXPERIMENTS AND COMPARISON WITH I NUREG/CR4447

RESULTS OF CHACK ARREST TESTS ON 1RRADI. MODEL PREDCTONS.

ATED A See CLASS 3 STEEL Numan Event Analyste ,

i Py m NUREG-1624 DRFT FC: TECHNCAL BASIS AND IMPLEMENTATION ]

l NUREG/CR4361: SEISMIC ANALYSIS OF PIPING. Final Program GUIDEUNES FOR A TEOINIOUE FOR HUMAN EVENT ANALYSIS l Report (ATHEANA).Drelt Report For Comment

! PustRes Numan Peeter

! NUREG/CR4634 V02 FRAPCON4: A COMPUTER CODE FOR THE NUREG/CR4005: AN EVALUATION OF HUMAN FACTORS RESEARCH l CALCULATION OF STEADY-STATE. THERMAL-MECHANCAL BE- FOR ULTRA 80NC MSERVCE M8PECTION.

HAVIOR OF OX4DE FUEL RODS FOR HIGH BURNUP NUREG/CR4634 VOS

FRAPCON4: INTEGRAL ASSESSMENT Numan Portermanos Gate Volvo NUREG/CR4354: HUMAN PERFORMANCE IN RADIOLOGCAL NUREG/CR4611: RESULTS OF PRESSURE LOCKING AND THERMAL SURVEY SCANNNG BMDMG TESTS OF GATE VALVES.

Generte Sately leeues NUREG/CP4162 V02 PROCEEDINGS OF THE TWEN1Y FIFTH I i NUREG Oe33 822 A PRIORITIZATION OF GENERIC SAFETY ISSUES. WATER REACTOR SAFETY INFORMATION MEETNG. Human Re5-

_ _ abSer Analyste And Human Perlormance Evaluodon, Techniosileause )

g,',,, ""'*" "U ' '

l NUREG/CR'4882 DATING AND EARTHOUAKES. REVIEW OF QUA.

l TERNARY GEOCHRONOLOGY AND ITS APPUCATION TO PALEO- ,

r. SEISMOLOGY. Hygrouge i l NUREG/CR4472: PRELIMINARY PHENOMENA IDENTIFICATION AND

( CR 45 TNG SB8MOTECTOpWCS W THE RANKING TABLES FOR SIMPUFIED BOILNG WATER REACTOR EASTERN UNITED STATES USMG A GEOGRAPHIC INFORMATION

1. 8 #N l

( SYSTEM " g,g,gg,,, pg,,, ,,,_ p,,,,,,

NUREG 1980 V01 P1: INDMOUAL PLANT EXAMMATION PROGRAM.

G/CR4673: " INVESTIGATING SEISMOTECTONICS IN THE PERSPECTIVES ON REACTOR SAFETY AND PLANT EASTERN UNITED STATES USING A GEOGRAPHIC MFORMATION PERFORMANCE. Summary Report 8YSTEM " NUREG-1500 V02 P24: INDMOUAL PLANT EXAMWATION PROGRAM.

PERSPECTIVES ON REACTOR SAFETY AND PLANT PERFORM-

, Ground Water interne8en ANCE.

j NUREG/CR4377: EFFECTS ON RADONUCUDE CONCENTRATIONS NUREG-1500 V03 P6: INDMDUAL PLANT EXAMMATION PROGRAM.

8Y MMENT/ GROUND-WATER ll(TERACTIONS N TUPPORT OF PERSPECTIVES ON REACTOR SAFETY AND PLANT l

PERFORMANCE ASSESSMENT OF LOW LEVEL RADIOACTIVE PERFC^.".". W "_ "

WASTE DISPOSAL FACIUTIES.

InSection Does M Snest NUREG/CR4613 V02: CODE MANUAL FOR MACCS2-W NUREG/CR4646 Vot: PROBASIUSTC ACCIDENT CONSEQUENCE Codes OOMIDA2, FORDCF, DCF2.

UNCERTAINTY ANALY888. Early Heellh Eflects 1,noortainly l AsessemenLMain Report inI8el Temperature NUREG/m 8546 V0E. PROBASILISTIC ACCOENT CONSEQUENCE NUREG/CR4509 THE EFFECT OF WITIAL TEMPERATURE ON '

UNCERTAMTY ANALYSIS. Early M E#ects Uncertiny FLAME ACCELERATION AND DEFLAGRATION-TO.OETONATON NUREG/CR 88K V01: PROBA81USTC ACCIDENT CONSEQUENCE  ;

UNCERTAINTY ANALYSIS.Lete Heenh - Eflects Uncertaintf M And Centrol l NUREG CR 0066"'"V0"2P 'L PROSA8luSTC ACCIDENT N NUREG/CR4479: TECHNICAL BASIS FOR ENVIRONinENTAL QUAU.

FICATION OF MICROPROCESSOR-BASED SAFETY RELATED 1

UllCERTAINTY ANALYSISM Hoenh Bham W EQUIPMENT IN NUCLEAR POWER PLANTS.-

I Noet hometer intergranular Creek NUREG/CR4472: PRELIMINARY PHENOMENA IDENTIFICATION AND NUREG/GR-0016: THE ROLE OF TIME-DEPENDENT DEFORMATION i RANKING TABLES FOR SIMPUFIED SOluNG WATER REACTOR IN INTERGRANULAR CRACK INITIATION OF ALLOY 800 STEAM f LOSS OF COOLANT ACCCENT SCENAfuOS. GENERATOR TUBING MATERIAL 2

E - -^ SteelIrvedm8en PreBram Internal Deelmstry NUIIEG/CR8891 V04 N1: W.AVY-SECTION STEEL IRRADIATION NUREG/CR4671 V02: PROSA84USTC ACCIDENT CONSEQUENCE i . PROGRAase-Nennual ProSmas Report For Octoter 1992 Through UNCERTA8rTY ANALYSIS. Uncertainly Aaessement For Inlemel l neemh 1ses. DoelmeeyAppemsces.

. . . - . m_ _ _ _ _ . . _ _-_m ..m_.__ _ - _ _ , . _ - _ _ . _ _ _ _ _ .. _ _ _. . _ _ __ _ _

i M St%004kHOSI tutssmal stre ' . -

Laer Lasel ResAmessee Weste 4 NUfEG/OR4644. IETHODOLOGY FOR ANALYZWG PREQJRSORS NUREG/CR4377. EFFECTS ON RADIONUCUDE CONCENTRATIONS j TO EARTHOUAME41tilATED Afe PIRE4dlTIATED AOCE)ENT SE- BY CEMENT / GROUND-WATER WTERACTIONS M SUPPORT OF i QUENCES- PERFORMANCE AmaramusgT OF LOW LEVEL RADIOCTIVE ,

i

! WASTE DEPOSAL FAClWTIES.

yyg

NURES/lA4004. APPUCATION OF RELAP6/unne1 CODE TO THE gm,.aggy gg,,g ,

LOFT TEST LA4 NUREG/CR4003 EFFECTS OF LWR COOuMT ENVIRONMENTS ON FATIGUE DESIGN CURVES OF CARBON AND LOW-ALLOY STEELA.

, Lyn l

NUfEG/G44087 V84

MNVIRONhENTALLY ASSISTED CRACIGNG M 4

M -WA

[qg twpugqd M pIOR AFTER> EAT RATE CALCULATIONS.

NUREG/CR4008.

SUMMARY

AND EVALUATION OF LOW-VELOCITY IMPACT TEST OF SOUD STEEL BILLET ONTO CONCRETE PADS.

OF LWR OOOLANT ENVIROSAENTS ON ,

j FATIGUE DESIGN CURVES OF CARRON AND LOW ALLOY STEELS. MACCS j j NUREG/CR4866 Voi: PROBABIUSTIC ACCIDENT CONSEQUENCE LWRAltC Code UNCERTANTY ANALYSIS. tate Heellh Ellecle Uncertehty 1 NUREG/CR4830 VERIFICATION OF THE LWRARC CODE FOR AnoesemenLMein Report. ,

UGHT-WATER-REACTOR AFTERHEAT RATE CALCULATIONS. NUREG/CR 0666 VOR: PROSAbduSTIC ArnnsNT CONSEQUENCE UNCERTAINTY . ANALYSIS. Late Heellh Effects Uncertainly

NUREG/CR4640

STATE-OF-TEART REPORT ON PrlNG FRAC-4 TURE MECHANICS. MACCSS j

^

LagelIssuenses NUREG/CR-0813 V01: CODE MANUAL FOR MACCS2. User's Guide. ,

NUFIEG-0700 C104: MDEXES TO NUCLEAR REGUuTORY rysman. NUREG/CR4813 V02: CODE MANUAL FOR MAQ:S2. Preprocessor 4

31 Codoo COMIDA2, FGROCF, IDCF2-i ION 1 i ISSUANCES. Opinions And Decisione Of The Nuclear Regulatory Com. HARE 8E8 NUREG-1507: MINIMUM DETECTABLE CONCENTRATIONS WITH TYP .

miselon Wilh Selected Orders.Jonuary June 1997.

NUREG4750 V46101: INDEXES TO NUCLEAR REGULATORY COM. ICAL RADIATION SURVEY INSTRUMENTS FOR VARIOUS CONTAMI- 1 MISSION IS8UANCES'" ^ __ 1997. NANTS AND FIELD CONDtTIONS.

NUREG 0700 V48102: INikXEB_TO NUCLEAR REGUMTORY COM- NUREG-1676: MULTI-AGENCY RADIATION SURVEY AND SITE INVES-  ;

MISSION ISSUANCES M E . 1- 1907.

TIGATION MANUAu (MAR 881M). Final Report.

NUREG4700 V46 NOS: NUCLEAR REGULATORY COMMISSION IS-SUANCES FOR SEPTEMBER 1997. 46 198. RELCOfl Computer Code NUREG4700 V48 N04: NUCLEAR TORY COMME 810N IS- NUREG/CR4119 V01 R1: MELCOR COMPUTER CODE SUANCES FOR OCTOBER 1997. 196-256. MANUALS. Primer And Users' Guideo. Verolon 1.8.4. July 1997.

NUREG4700 V46 N06: NUCLEAR TORY COhndl8810N IS. NUREG/CR4119 V02 R1- MELCOR COMPUTER CODE M T46 SUANCES FOR DErsumpR 1997. 387-319.

rvummamang 18 MANUALS Reference Manuais, Version 1.8.4, July 1997.

R REGUMTORY COM. Measurement Manning NUREG 0700 V47101: INDEXES TO 1908. NUREG-1676: MULTI-AGENCY RADIATION SURVEY AND SITE INVES-amensrug V47 NURt:G4790 g8UANCESN01: N "N~REJULATORY nnunmananN & TIGATION MANUAL MRS81M). Final Report SUANCES FOR JANUARY 1908. 1 12.

NUREG4700 V47 NOR: NUCLEAR TORY evummamang 18 08erehardnese SUANCES FOR FEBRUARY 1000. 13 66. NUMEG-1829: THE CHARACTERIZATION OF VICKER'S MICROHARD.

NUREG4700 V47 NOS: NUCLEAR TORY ryummamang IS- NESS INDENTATIONS AND PILE-UP PROFILES AS A STRAM HARD.

TORY nnunmaanng 18 N

7 SUANCES FOR APRIL 1998.Peges 77 300. gAerspressener NUREG/CR4479 TECHNICAL BASIS FOR ENVIRONMENTAL QUAU-Usense Tm FICATION OF MICROPROCESSOR 4ASED SAFETY RELATED NUREG/CP4193: PROCEEDINGS OF THE WORKSHOP ON REVIEW ,

OF DOSE unnpa afG METHODS FOR DEMONSTRATION OF COM- EQUIPhENT IN NUCLEAR POWER PLANTS. t PUANCE WITH THE RADIOLOGICAL CRfTERIA FOR UCENSE TER- y,g,,

UEA N NUREG/CR4811: RESULTS OF PRES 8URE LOCKWG AND THERMAL l

Usensed Fusi PeeWIy Stolus floperg geNDING TESTS OF GATE VALVES.

NUREG4430 V16: UCENBED FUEL FACluTY STATU8 E Jrwentory Dillerence Date. July 1,1906 - June 30,1908.(Grey NURE Roi NERAL STATEMENT OF POUCY AND PROCE.

DURE FOR NRC ENFORr5MFNT ACTIONS. Enforcement Poucy.

unenese Svent Report NUREG-1032 RO1: EVENT REPORTING GUIDEUNES 10 CFR 50.72 IWIC Entereement Peger AfC 60.73. NUREG-1800 R01: GENERAL STATEMENT OF POUCY AND PROCE.

NUREG 1187 V01: PERFORMANCE INDICATORS FOR OPERATING DURE FOR NRC ENFORCEMENT ACTION 8.Enforooment Potoy. .

nnuusstCIAL NUCLEAR POWER REACTORS.Dete Tteou@ 8eptem- NUREG 1822: NRC ENFORCEMENT POUCY REVIEW. July 1996 - July I her 1987. 1997.

NUREG/CR 4874 Vt6: PRECURSORS TO POTENTIAL SEVERE CORE DAMAGE AOCIDENTS: 1988. A 8true Report IIeutron Doobnetry NUREG CR4463' H. 8. RO91N80N-2 PRESSURE VESSEL BENCH- l CR-4057 V34: ENVIRONMENTALLY ASSISTED CRACIONG IN l

^f-- ggeutron IQnego UGHT-WATER NUREG/CR4SSS: REACTORS. Semiennual- 7NDON CLE FOR OF M LM_- MS 1997. VO1: RAMONA-48: A COMPUTER CODE WITH NUREG/CR.8369 l

• ^ THREE-OlMENSIONAL NEUTRON KINETICS FOR SWR AND 88WR l "CR4883 EFFECTS T,.

FATIGUE DE8IGN CURVES OF CARBON AND WW-ALLOY STEF ) SYSTEM TRANSIENTS.Modelo And Correlellone. l NUREG/CR4360 V02: RAMONA-48. A COMPUTER CODE WITH l s - Aseldent ' THREE-DII4EN810NAL NEUTRON KINETICS FOR BWR AND 88WR NUREG/CR4412: AGING AfC LOSSOF-COOLANT AOCIDENT (LOCA) SYSTEM TRANSIENTS. User *e Manuel TESTING OF ELECTRICAL CONNECTIONS-NUfEG/CR4472: PREUMINARY PHENORENA IDENTIFICATION AfC Blendestrususe Evolustion RANIONG TABLES FOR SIMPUFIED BOIUNG WATER REACTOR NUREG/CR4611 V02: STEAM GENERATOR TU8E INTEGRITY LOSS OF COOLANT ArnnsNT SCENARIOS. PROGRAM. Annual Report, August 1996 - September 1996.

l l

l I

l

-- -.--~.. .. ._ _ -_.

SutIloct ifWiox 29 leendestrustee Testas Portonnense Phn NUREG/CR4Eas: TDE EFFECTS OF SURFACE CONDITION ON AN NUREG-1827 V01: PERFORMANCE PLAN FY 1990.

ULTRASONIC INSPECTION: ENGWEERING STUDIES UglNG VAU-DATED COMPUTER MODEL Poemone Per Rideenshhg NUREG4036 V16 Not: NRC REGULATORY AGENDA 8emiennual Ituateer Aseident Analpelo Report.Juh-Decondier 1997.

NUREG/m4646 V01: PROSAtluSTIC ACCIDENT CONSEQUENCE i UNCERTAINTY ANALYSIS. Early Heenh Effects Uncertainty pping l A8P8't NURE CR4301: SEleMIC ANALYSIS OF PIPING. Final Program pm UNCERTAMTY ANALYWE Ear $ HeeNh Ensolo Uncertinty NUREG/CR4640: STATE.OF-THE ART REPORT ON PIPING PRAC.

6 TURE MECHANICS.

NURES 1 P1: INDMOUAL PLANT EXAMINATION PROGRAM.

PERSPECTNES ON REACTOR SAFETY AND PLANT 81uelser Pues PERFORMANCE. Summary ReporL .

MUREG/CR4410 NUCLEAR FUEL CYCLE FACluTY ACCIDENT ANAL. NURE41600 V02 P24: INDIVIDUAL PLANT EXAMINATION PROGRAM yg8HANDOOOK. PERSPECTNES ON REACTOR SAFETY AND PLANT PERFORM-ANCE.

Ituelser Power plant NURE41600 V03 P6: INDMDUAL PLANT EXAMINATION PROGRAM:

NUREG/CR46T7: U.S. NUCLEAR POWER PLANT OPERATING COST PERSPECTIVES ON REACTOR SAFETY AND PLANT AND EXPERIENCE SUMMARIES. PERFORMANCEAppendoes.

Bluelser Reester GesetF Post-Tensioning System l

NUREG/CR4119 V01 R1: MEL40R COMPUTER CODE NUREG/CR4608. AN INVESTIGATION OF TENDON SHEATHING MANUALS. And Usere etelon 1.8 7. FILL ER 64GRATION INTO CONCRETE.

CODE MANUALS. Reference Manuais, Version 1.8.4. July 1967. Pressure Boundary NUREG/CR4816: A SURVEY OF REPAIR PRACTICES FOR NUCLEAR teusteer Regidatory Legialemen POWER PLANT CONTAINMENT METALLC PRESSURE 80VN4 NUREG40e0 V01 N04: HUCLEAR REGULATORY LEGISLATION.104th V02 N04: NlJCLEAR REGULATORY LEGISLATION.104th Prosesse Leeldng Congrees.

NUREG/CR4811: RESULTS OF PRESSURE LOCKING AND THERMAL P Redemon Espesure BINDING TESTS OF GATE VALVES.

NUREG4713 Vie: OCCUPATIONAL RADIATION EXPO 8URE AT COM-hERCIAL NUCLEAR POWER REACTORS AND OTHER Pressure Weasel FACIUTIES,1008. Twenty 4dnth Annual Report. NUREG/CR4463. H. B. RO8tNSON-2 PRESSURE VESSEL BENCH-MARK.

OIIIso Of The Insposter emneral NUREG/CR4637: INFLUENCE OF LONG-TERM THERMAL AGING ON NURE41416 V10 Not: OFFICE OF THE INSPECTOR THE MICROSTRUCTURAL EVOLUTION OF NUCLEAR REACTOR GENERAL.Semiennual Report To Congrees, October 1,1997. March PRES 8URE VESSEL MATERIALS.An Atom Probe Shady.

31,1988.

Preneuro Vessel Roemereh Opereung Cost NUREG/CP-0162 V01: PROCEEDINGS OF THE TWENTY-FIFTH l

NUREG/CR4677: U.S. NUCLEAR POWER PLANT OPERATING COST WATER REACTOR SAFETY INFORMATION MEETING.Planery  ;

AND EXPERIENCE e -mES. Sessions. Pressure Vessel Research.BWR Streiner h*=Pa And Olhar Generic Safety i==C.u._r; AseiLeod Degradellon Of LWR Opereeng Espertones NUREG/CR4677: U.S. NUCLEAR POWER PLANT OPERATING COST hm AND N N & NUREG/lA4024: APPUCATION OF RELAP6/ MODS.1 CODE TO THE Operemonal Event LOFT TEST L34.

NUREG/CR 4674 V26: PRECURSORS TO POTENTIAL SEVERE CORE Probahmenc AccidentCeneoguance DAMAGE ACCIDENTS: 1996. A Steaus Report NUREG/CR-6666 V01: PROBAS4USTIC ACCIDENT CONSEQUENCE PWR UNCERTAINTY ANALYSIS.Lele Health Effects Uncertainly ,

NUREG/lA4024. APPUCATION OF RELAP5/ MOD 3.1 CODE TO THE AseseemenLMein Report l NUREG/CR-0665 V02: PROBA81USTIC ACCIDENT CONSEQUENCE j LOFT TEST L34.

UNCERTAINTY ANALYSIS.Lete HeeNh Effects Uncertainly l Peakege Appresel AsessementAppendoes.

NUREG/CR4802 ENGINEERING DRAWINGS FOR 10 CFR PART 71 NUREG/CR4671 V01: PROSA81USTIC ACCIDENT CONSEQUENCE PACKAGE APPROVALS. UNCERTANTY ANALYSIS. Uncertainty Aseeemment For intemel Doelmstry. Main Report Petesestumetegy NUREG/CR4671 V02: PROSA81USTIC ACCIDENT CONSEQUENE NUREG/CR4682: DATING AND EARTHOUAKES: REVIEW OF OUA. UNCERTAltfrY ANALYSIS. Uncertainty Asseeement For intemel GEOCHRONOLOGY AND ITS APPUCATON TO PALEO- WAppensees.

Prohannene Risk Assessment

% a,,,,,,,,,g NUREG.1624 DRFT FC: TECHNICAL BASS AND IMPLEMENTATION NUREG/CR4377: EFFECTS ON RADIONUCUDE CONCENTRATIONS GUIDEUNES FOR A TECHNIOUE FOR HUMAN EVENT ANALYSIS BY CEMENT /GROUDOWATER INTERACTIONS IN SUPPORT OF MM. Draft Report For Comment PERFORMANCE A88E88 MENT OF LOW 4.EVEL RADIOACTIVE NUREG/CR4119 V01 R1: MELCOR CX)MPUTER CODE WASTE DISPOSAL FACIUTIES. MANUALS. Primer And Users' twas Version 1.8.4. July 1997.

Portonnenes Incester NUREG/CR4119 V02 R1: MELCOR COMPUTER CODE MANUALS.Referenos Manuais,Vemion 1.8.4 July 1997.

NUREG-1187 vot: PERFORMANCE INDICATORS FOR OPERATING rNWRCIAL NUCLEAR POWER REACTORS.Dete Through Septem-Quaternary Geology ber 1997.

NUREG/CR4662: DATING AND EARTHOUAKES: REVIEW OF OUA-Pertensense Measure TERNARY GEOCHRONOLOGY AND ITS APPUCATION TO PALEO-NURE41642 VOS: ACCOUNTAttluTY REPORT FISCAL YEAR 1997. SEDSMOLOGY.

-. . - _ . . . - - . - ~ . - - _ ~ _ - . - - - . _ . - . . - - . - . . - . - - _ _ . _ _ - _ _ . . -

a I

N W ,

RAgntAs Regelstery And Teeledeel RepoR  !

NURSS/GW004. RADTRAct A SedPUPIED MODEL POR MAN NUREG4304 Vat NOS: REGULATORY AND TECHNCAL REPORTS '

CUDE TRANSPORT AND REMOVAL AfC DOSE ESTIMATION. (ABSTRACT NWEX JOURNAQ CorrpAseen For Thini Quener 1997, July September. 4 RSMSRS 40 NUREG4004 VSE N04: REGULATORY AND TECHNCAL REPORTS 4 NURES/CR4eIS VD1: RAMONA48 A COMPUTER CODE WITH NCEX JOURNAQ. W W For 1997*

THREE DesENSONAL NEUTRON IGNETES POR BWR AND SSWR Oonerets j CODE WITH NUREG/CR4064: FINITE ELEMENT ANALYSES FOR SElBMIC SHEAR TDEMN WUTRON 90PIETES FOR OWR MD SSWR WEL MTERNATONE STMDARD PROSLEnd l

SYSTRA TRANSENTS.usere Manuel  ;

i Im,Ap0/M000 Repelr Pressee ,

NUfEG/lA00AS: RELAPS/ MODS enannru sn SOluNG MODEL AS- NUREG/CR4818: A SURVEY OF REPAIR PRACTICES FOR NUCLEAR POWER PLANT CONTAMMENT METALUC PRES 8URE SOUND- -

. APPUCATION OF RELAPS/ MODO.1 OODE TO THE ARIES.

LOPT TEST LS4. t RePert To Conyees i l

! ResenenAgenere NUREG4000 V30: REPORT TO CONGRESS ON ABNORMAL l NURBS11e7 V01: PERPORMANCE INDICATORS FOR OPERATING OCCURRENCES.Fional Year 1997 l COtMR0lAL NUCLEAR POWER REACTORS.Dete Through Septem- NUREG-1416 V10 Not: OFFICE OF THE INSPECTOR i j, her 1997, GENERALSemiennual Report To Conyees, October 1,1997 March  !

g,g,,,g,, ,,gg,gg 31,1900. [

NURSS/CR 4054 V01 RE: SCANS (SHIPPNG CASK ANALYWS  !

mek h  ;

i SYSTEnd) A MICROOOMPUTER BASED ANALYSIS SYSTEM FOR NUREG 1670: RISK ASSESSMENT OF SEVERE ACCIDENT-IPQUCED l OHD; ING CASK DEWGN REVIEW.Usere Manuel to Verolon Se. [

' STEAM GENERATOR TUSE RUPTURE.

Ornerle NUREG/CR4879: DIGITAL 68C SYSTEMS W NUCLEAR POWER >

W4105: ppnrissruNGS OF THE WORKSHOP ON REVIEW PLANTS.Riek-Screening Of Erwironmental Smassare And A Comperb OF DORE Mrm8HNG METHODS FOR DEMONSTRATION OF COM- son Of Henfware Unewedsbety WIm An Edseng AnaioO Syelem.  :

PUANCE WITH THE RADOLOGCAL CRfTERIA POR UOENSE TER-  !

MMATION. fhdas l NUREG4038 Vie NOR: NRC REGULATORY AGENDA.Somiennual

! E/CRN4s sV01: CODE MANUAL POR MAOCSt.Ueste Gums. I SCANS 007 DETECTAGE NTONS WITH TYP- NUREG/CR-4664 V01 R2: SCANS (SHIPPNG CASK ANALYSl8 CE RAMATC0d SURVEY pdSTRUENTS FOR VAROUS CONTAW- SYSTEM) A MICROCOMPUTER SAGED ANALYSIS SYSTEM FOR j mgpago .

SHIPPNG CASK DESIGN REVIEW.Usere Manuel to Version Se.  ;

/CR4eed HUMAN W RADIOLOGCAL =

SURVEY SCANNMG. Soloty Anelpelo Report  !

NUREG/CR 4664 V01 R2: SCANS (SHIPPNG CASK ANALYS18 RodenesAde SYSTEM) A MOROCOMPUTER SABED ANALYSIS SYSTEM FOR  !'

NURES/CR4877: EFFECTS ON RADIONUCUDE CONCENTRATIONS SHIPPING CASK DESIGN REVIEW.Usere Manuel to Version Se.

SY (MBENT/ GROUND WATER MTERACTIONS M SUPPORT OF i PERPORMANCE amassausefT OF LOW LEVEL RADICACTivE Solente Analysie  ;

WASTE DISPOSAL FACIUTIES. NUREG/CR-6301: SEISMIC ANALYSIS OF PlPING. Final Program i Reester Assident CR-0664: FNfTE ELEMENT ANALYSES FOR SEtBMIC SHEAR  !

MURBG/CR4004 MADTRAD: A SIMPUFIED MODEL FOR RADIONU- WALL WTERNATIONAL STANDARD PROSLEM. i CUDE TRANSPORT AND REMOVAL AND TION. }

NUREG/CR4813 vot: CODE MANUAL FOR Unore Guide-Sciende DeWen Sede fireeter protesten NUREG/CR4808: WVESTIGATION OF TECHNIOUES FON THE DE- 5 NUREG/OR4478: SASIS FOR ENVIRONMENTAL QUALI. VELOPMENT OF SElBMC DESIGN SASIS USNG THE PRMABlUS. ,

PICATION OF MICROPROCESSOR SAGED SAFETY-flELATED TC SEISMC HAZARD ANALYSIS. t SQUIPhENT M NUCLEAR POWER PLANTS

. Reester Safety NUREG/CR4006: INVESTIGATON OF TECHNIOUES FOR THE DE. t NUF301 esp V01 P1: INDIVIDUAL PLANT EXAMINATION PROGRAM. VELOPMENT OF SEIBMIC DESIGN BASIS USNG THE PROSAStuS- l l

PERSPECTIVES ON REACTOR SAFETY AND PLANT TC SEISMC HAZARD ANALYSIS. }

NUESFD 4: PLANT EXAMMATION PROGRAM Setemte RBoment PERAPECTIVES ON REACTOR SAFETY AND PLANT PERFORM- NUREG/CR4884: ANALYSES OF SOURCE SPECTRA, ATTENUATION, 1000 V00 PS: INDIVIDUAL PLANT EXAMINATION PROGRAM. TE S' PERSPECTIVES ON REACTOR SAFETY AND PLANT }

W1: PROLEEDINGS OF THE TWENTY FIFTH CR4673: "lNVESTIGATNG SEISMOTECTONiCS W THE

• SA W ORMATON EMG TE UNITED STATES USING A GEOGRAPHC WFORMATION y,,,g nd [

TWE i WATER REACTOR SAFETY INPORMATION MEETING. Human Ren-abMy AndyWe And Hurnen Portormanos Emn, Technlod h NUMEG-1500 V01 P1: INDIVIDUAL PLANT EXAMINATION PROGRAM. [

Asisted To flulemeMnge, Risk-informed PersonienceSesed inne. PERSPECTIVES ON REACTOR SAFETY AND PLANT j

' PERFORMANCE. Summary Report ,

CP4108 - VOS: PRO MEDMGS OF THI TWENTY FIFTH NUREG 1500 Vot P2-6: MDIVIDUAL PLANT EXAMINATION PROGRAM:

WATER REACTOR SAFETY INFORMATION hEETNG.ThermeLHy. PERSPECTIVES ON REACTOR SAFETY AND PLANT PERFORM- ,

dreute Research And Codes, Dignal Instrumenteen And Consol ANCE. l StuolurW Performance. NUREG 1600 V03 PS: INDIVIDUAL PLANT EXAMINATION PROGRAM:  ;

-7 PERSPECTIVES ON REACTOR SAFETY AND PLANT i PERFORMANCE.Appendoes i Vill Not: NRC REGULATORY AGENDA.Somiennual NUREG 1670: RISK ASSESSMENT OF SEVERE ACCIDENT-lNDUCED .

RePerLJutrDemander 1997. STEAM GENERATOR TUSE RUPTURE.  !

Subject Index 31 NUREG-1824 DAFT FC: TECHNICAL BAS!S AND IMPLEMENTATION Stroes Drop GUOELINES FOR A TECHNIOUE FOR HUMAN EVENT ANALYSIS NUREG/CR4564: ANALYSES OF SOURCE SPECTRA, ATTENJATION, (ATHEANA). Draft Repor1 For Comment AND SITE EFFECTS FROM CENTRAL AND EASTERN UNITED NUREG/CP 0162 V01: PROCEEDINGS OF THE TWENTY-FIFTH STATES EARTHOUAKES.

WATER REACTOR SAFETY INFORMATION MEETING. Plenary Seesions. Pressure veseel Reneerch,BWR Strainer Blockso.r And Other Structural Engineering Generle Safety leaues.E Ameisted edemon Of LWR. .

NUREG/CR4119 VD1 R1: COR R CODE NUREG/CR4546: A DAMAGE MECHANICS BASED APPROACH TO MANUALS. Primer And Users' Guides, Version 1.8.4 1997 STRUCTURAL DETERIORATION AND RELIABluTY.

NUREG/CR4119 V02 R1: MELCOR R CODE Structural h NUR G/ 45 LUR E' VIOR ERNALLY PRESSUR- NUREG/CP 0162 V03: PROCEEDINGS OF THE TWENTY #lFTH IZED FLAWED AND UNFLAWED STEAM GENERATOR TUBING AT WATER REACTOR SAFETY INFORMATION MEETING.Thermel-Hy-HIGH TEMPERATURE -EXPERIMENTS AND COMPARISON WITH draulle Research And Codes, Dghal instrumente80n And Control, MODEL PREDICTIONS. Structural Performance.

NUREG/CR4604: RADTRAD: A SIMPLIFIED MODEL FOR RADIONU-CLOE TRANSPORT AND REMOVAL AND DOSE ESTIMATION. Sulmied Somns M*0ime NUREG/lA 0025: RELAPS/ MOO 3 SUBCOOLED B0 lung MODEL AS-Severe Core Damage SESSMENT.

NUREG/CR-4674 V25: PRECURSORS TO POTENTIAL SEVERE CORE DAMAGE ACCIDENTS: 1996. A Status Report. Surfeos Condition Sheer Wall NUREG/CR4589: THE EFFECTS OF SURFACE CONDITION ON AN ULTRASONIC INSPECTION: ENGINEERING STUDIES USING VALi-NUREG/CR4554: FIN!TE ELEMENT ANALYSES FOR !MMIC SHEAR DATED COMPUTER MODEL WALL INTERNATIONAL STANDARD PROBLEM.

Surface Creek G 4 V01 R2: SCANS (SHIPPING CASK ANALYSIS NUREG/CR4540: STATE OF THE ART REPORT ON PIPING FRAC-SYSTEM) A MICROCOMPUTER BASED ANALYSIS SYSTEM FOR RE MECHAM SHIPPING CASK DESIGN REVIEW User's Manuel to Version 3a. g%

Source Spectre NUREG 1507: MINIMUM DETECTABLE CONCENTRATIONS WITH TYP-NUREG/CR4564: ANALYSES OF SOURCE SPECTRA, ATTENUATION. ICAL RADIATION SURVEY INSTRUMENTS FOR VARIOUS CONTAMi-AND SITE EFFECTd FROM CENTRAL AND EASTERN UNITED NANTS AND FIELD CONDITIONS.

STATES EARTHOUAKES. NUREG/CR4364: HUMAN PERFORMANCE IN RADIOLOGICAL SURVEY SCANNING.

Source Term NUREG/CR4410 NUCLEAR FUEL CYCLE FACluTY ACCIDENT ANAL. System Transient YSIS HANDBOOK. NUREG/CR4359 V01: RAMONA-49: A COMPUTER CODE WITH THREE-DIMENSIONAL NEUTRON KINETICS FOR BWR AWD SBWR Spent Nucieer Fuel SYSTEM TRANSIENTS.Models And Correlations.

NUREG-1626: FINAL ENVIRONMENTAL IMPACT STATEMENT FOR NUREG/CR4359 V02: RAMONA-4B: A COMPUTER CODE WITH THE CONSTRUCTION AND OPERATION OF AN INDEPENDENT THREE DIMENSIONAL NEUTRON KINETICS FOR BWR AND SBWR SPENT FUEL STORAGE INSTALLATION TO STORE THE THREE SYSTEM TRANSIENTS. User *e Manual.

MILE ISLAND UNIT 2 SPENT FUEL AT THE IDAHO NATONAL ENGi-NEERING AND ENVIRONMENTAL. TLD Sputeng Tenene Strength NUREG-0637 V17 NO3: NRC TLD DIRECT RADIATION MONITORING NUREG/CR4596: AN INVESTIGATION OF TENDON SHEATHING N Knees Report. MW N FILLER MiGRATON INTO CONCRETE- TMI-2 Steem Generator NUREG 1626: FINAL ENVIRONMENTAL IMPACT STATEMENT FOR NUREG-1570: RISK ASSESSMENT OF SEVERE ACCIDENT-INDUCED THE CONSTRUCTON AND OPERATION OF AN INDEPENDENT STEAM GENERATOR TUBE RUPTURE. SPENT FUEL STORAGE INSTALLATON TO STORE THE THREE NUREG/CR4511 V02: STEAM GENERATOR TUBE INTEGRITY MILE ISLAND UNIT 2 SPENT FUEL AT THE IDAHO NATONAL ENGi-PROGRAM, Annual R t 1995 - September 1996. NEERING AND ENVIRONMENTAL-.

NUREG/CR4575: Fall RE B HAVIOR OF INTERNALLY PREGSUR-IZED FLAWED AND UNFLAWED STEAM GENERATOR TUBING AT Tomson Sheathing HIGH TEMPERATURE -EXPERIMENTS AND COMPARISON WITH NUREG/CR4596: AN INVESTIGATION OF TENDON SHEATHING MODEL PREDICTIONS. FILLER MIGRATION INTO CONCRETE.

NUREG/GR 0016: THE ROLE OF TIME-DEPENDENT DEFORMATION IN INTERGRANULAR CRACK INITIATICH OF ALLOY 600 STEAM Thermal Aging GENERATOR TUBING MATERIAL NUREG/CR4537: INFLUENCE OF LONG TERM THERMAL AGING ON THE MICROSTRUCTURAL EVOLUTION OF NUCLEAR REACTOR Steel Smet PRESSURE VESSEL MATERIALS.An Atom Probe Study.

NUREG/CR4606:

SUMMARY

AND EVALUATION OF LOW VELOCITY IMPACT TEST OF SOUD STEEL BILLET ONTO CONCRETE PADS. Thermal Sinding NUREG/CR4611: RESULTS OF PRESSURE LOCKING AND THERMAL THE Cr4ARACTER1ZATION OF VICKER'S MICROHARD-

'" " ^ '

NESS INDENTATIONS AND PILE-UP PROFILES AS A STRAIN-HARD- Thermal Hydraunc h ENING MICROPROBE.

NUREG/CP 0162 V03: PROCEEDINGS OF THE TWENTY #lFTH Strainerana9 WATER REACTOR SAFETY INFORMATON MEETING.Thermel-Hy NUREG/CP 0162 V01: PROCEEDINGS OF THE TWENTY FIFTH draulic Research And Oldes Dgital Instrumentation And Control, WATER REACTOR SAFETY INFORMATION MEETING. Plenary Structural Performance Sessions,Presouro Vessel Research,BWR Strainer Blockage And Other Genanc Safety leeues E.W-,wy Assisted Degradetlan Of LWR. ,Y CR43 9 V02: RAMONA-48: A COMPUTEH CODE WITH Stroes Corroelon Creoldng THREE-DIMENSIONAL NEUTRON KINETICS FOR BWR AND SBWR NUREG/CR4511 V02- STEAM GENERATOR TUBE INTEGRITY SYSTEM TRANSIENTS. User's Manual.

PROGRAM. Annual Report. August 1995. September 1996.

NUREG/GR-0016: THE ROLE OF TIME DEPENDENT DEFORMATION Thermolumineecent Doelmeter IN INTERGRANULAR CRACK INITIATION OF ALLOY 600 STEAM NUREG-0837 Vl7 NO3: NRC TLD DIRECT RADIATION MONITORING GENERATOR TUBING MATERIAL NETWORK. Progress Report. July-September 1997.

32 Subject index Tnie uel uncertainty Anseyste l NUREG4540 V19 N11: TITLE UST OF DOCUMENTS MADE PUBUCLY NUREG/CR4545 V01: PROBABILISTIC ACCIDENT CONSEQUENCE AVAILABLE. November 1-30 1997. UNCERTAINTY ANALYSIS. Early Health Effects Uncertainty  !

NUREG4540 V19 N12 TITLE! UST OF DOCUMENTS MADE PUBUCLY Assessment. Main Report. l AVAILABLE. December 1-31 1997. NUREG/CR4545 V02 PROBABluSTIC AOCIDENT CONSEQUENCE NUREG4540 V20 NO1:T!'iLd LIST OF DOCUMEff7S MADE PUBUCLY UNCERTAINTY ANALYSIS. Earty Health Effects Uncertainty l NU E 2- ST OF DOCUMENTS MADE PUBUCLY NU 1 PROBAB:USTIC ACCIDENT CONSEQUENCE N E T E T OF DOCUMENTS MADE PUBUCLY UNCERTAINTY ANALYSIS. Late Health Effects Uncertamty AVAILABLE. March 1-31,1998. Assessment. Main Report. i NUREG-0540 V20 N04: TITLE UST OF DOCUMENTS MADE PUBUCLY NUREG/CR4555 V02: PROBABILISTIC ACCIDENT CONSEOUENCE I AVAILABLE.Apr0130,1996. UNCERTAINTY ANALYSIS. Late Health Effects Uncertainty 1 Assessment.Apperdoes.

Tube NUREG/CR4571 V01: PROBABILISTIC ACCIDENT CONSEOUENCE l NUREG/CR4511 V02: STEAM GENERATOR TUBE INTEGRITY UNCERTAINTY ANALYSIS. Uncertainty Assessment For internal PROGRAM.Annuti Report AupJet 1995 - September 1996. Dosimetry. Main Fkport.

NUREG/CR4571 V02: PROBABluSTIC ACCIDENT CONSEQUENCE NURE 0 RISK ASSESSMENT OF SEVERE ACCIDENT-INDUCED

# ^**** '

STEAM GENERATOR TUBE RUPTURE.

Tubing V# l NUREG-0040 V21 N04: UCENSEE CONTRACTOR AND VENDOR IN- '

NUREG/CR4575: FAILURE BEHAVIOR Of' INTERNALLY PRESSUR. SPECTION STATUS REPORT. Quartery Report. October-December (ZED FLAWED AND UNFLAWED STEAM GENERATOR TUBING AT HIGH TEMPERATURE -EXPERIMENTS AND COMPARISON WITH 1887N' M MODEL PREDICTIONS. g Ultrasonic innervice inspection NUREG-1829: THE CHARACTERIZATION OF VICKER'S MICROHARD.

NUREG/CR4605: AN EVALUATION OF HUMAN FACTORS RESEARCH NESS INDENTATIONS AND PILE-UP PROFILES AS A STRAIN HARD.

FOR ULTRASONIC INSERVICE INSPECTION. ENING MICROPROBE, Ultrasonic inspection Welding NUREG/CR4589- THE EFFECTS OF SURFACE CONDITION ON AN NUREG/CR4615: A SURVEY OF REPAIR PRACTICES FOR NUCLEAR ULTRASONIC INSPECTION: ENGINEERING STUDIES USING VAU- POWER PLANT CONTAINMENT METALUC PRESSURE BOUND-DATED COMPUTtER MODEL ARIES.

l I

i NRC Originating Organization index (Staff Reports)

This index lists those NRC organization 3 that have published staff reports. The index is ar-ranged alphabetically by mafor 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 COMMff f'EE(8) DIVISION OF WASTE MANAGEMENT (NMSS 940403)

ACRS - ADVISORY COMMITTEE ON REACTOR SAFEGUARDS NUREG/CP-0163: PROCEEDINGS OF THE WORKSHOP ON REVIEW NURE41125 V19- A COMPILATION OF REPORTS OF THE ADVISO- OF DOSE MODEUNG METHODS FOR DEMONSTRATION OF RY COMMITTEE ON REACTOR SAFEGUARDS.1997 Annual COMPLIANCE WITH THE RADIOLOGICAL CRITERIA FOR U-ATOMIC SAFETY BOARD (S) & PANEL (S)

ATOMIC SAFETY & UCENSING BOARD PANEL U.S. NUCLEAR REGULATORY COtiful4840N NUREG-1363 V07: ATOMIC SAFETY AND UCENSING BOARD BIEN-NIAL REPORTFacal Years 1995 1996. OFFICE OF THE GENERAL COUNSEL (POST 860701)

NUREG-0980 V01 N04: NUCLEAR REGULATORY OFFICE OF EXECUTfvE DIRECTOR FOR OPERATIONS (EDO) NU E V02  : NUCLEAR REGULATORY NU 1 i NRC TLD DIRECT RADIATION MONITORING

• P 't 8' OFFICE TH IN CT G RR M 890417)

OFC OF NT POST NUREG 1415 V10 NO2- OFFICE OF THE INSPECTOR NUREG.0940 V16 N2 P1: ENFORCEMENT ACTIONS SIGNIFICANT GENERALSomlannual Report To Congrees,0ctober 1,1997 - March

^

, NRC NO DETAILED AFFILIATION GIVEN NUREG4940 V16 N2 P2: EhFORCEMENT ACTIONS: SIGNIFICANT NUREG 0304 V22 NO3: REGULATORY AND TECHNICAL REPORTS ACTIONS RESOLVED REACTOR UCENSEES.Sermannual Progress (ABSTRACT INDEX JOURNAQ. Compilation For Third Ouerter Report,JuleDecember 1997 1997)uleSeptember.

NUREG4940 V16 N2 P3: E5FORCEMENT ACTIONS: SIGNIFICANT NUREG 0304 V22 N04: REGULATORY AND TECHNICAL REPORTS ACTIONS RESOLVED InATERIAL UCENSEES.Serrmannual Progrees (ABSTRACT INDEX JOURNAL). Annual Compilation For 1997.

Reportdulyh 1997. NUREG 0540 Vf D N11: TITLE UST OF DOCUMENTS MADE PUBUC-NUREG-1600 R01: GENERAL STATEMENT OF POUCY AND PROCE. LY AVAILABd. November 130,1997.

DURE FOR NRC ENFORCEMENT ACTIONS. Enforcement Policy. NUREG4540 V19 N12: TITLE UST OF DOCUMENTS MADE PUBUC-NUR 1622 NRC ENFORCEMENT POUCY REVIEW #y 1995. July L AV LABLE -3 99 DOCUMENTS MADE PUBUC-LY AVAILABLEJanuary 131,1998.

EDO . OFFICE OF ADM6MISTRATION (PRE 870413 & POST 990206) NOREG4540 V20 NO2 TITLE UST OF DOCUMENTS MADE PUBUC.

OFFICE OF ADMINISTRATION, DIRECTOR (POST 940714) LY AVAILABLE. February 1-28,1998.

NUREG-0936 V16 NO2: NRC REGULATORY AGENDA.Sermannual NUREG-0540 V20 NO3: TITLE UST OF DOCUMENTS MADE PUBUC-Report. July-December 1997. LY AVAILABLE. March 1 31,1998.

NUREG4540 V20 N04: TITLE UST OF DOCUMENTS MADE PUBUC-EDO OFFICE OF THE CONTROLLER (PRE 820418 & POST 890205) LY AVAILABLE. April 1-30,1998.

OFFICE OF THE CONTROLLER (POST 890205) NUREG4750 C104: INDEXES TO NUCLEAR REGULATORY COMMIS-NUREG-1542 V03: ACCOUNTABluTY REPORT RSCAL YEAR 1997. C!ON ISSUANCES. January 1,1991 through December 31,1995.

DIVISION OF BUDGET & ANALYSIS (POST 890205) NUREG4750 V45: NUCLEAR REGULATORY COMMISSION NUREG-1100 V14: BUDGET ESTIMATES.Flecal Year 1999.

ISSUANCES. Opinions AM Dom Of The Nuclear Regulatory EDO FICE FOR ANALYSIS & EVALUATION OF OPERATIONAL NUR V4610 d UCLEAR RE TORY COM-OFF FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA, Dl-NU G-0 REGULATORY COM-

^

NCE F ear 1 . NU G-0 50 4 NO3 UCLEAR G TORY COMMISSION IS-NUREG-1022 R01: EVENT REPORTING GUIDEUNES 10 CFR 50.72 SUANCES FOR SEPTEMBER 1997. Pages49-193.

AND 50.73. NUREG4750 V46 N04: NUCLEAR REGULATORY COMMISSION IS-NUREG 1187 V01: PERFORMANCE INDICATORS FOR OPERATING SUANCES FOR OCTOBER 1997. Pages 195-256.

COMMERCIAL NUCLEAR POWER REACTORS.Dcts Through Sep. NUREG 0750 V46 Nob: NUCEAR REGULATORY COMMISSION IS-tomber 1997 SUANCES FOR NOVEMEER 1997. Pages 257-285.

NUREG-1272 V10 N01: OFFICE FOR ANALYSIS AND EVALUATION NUREG-0750 V46 N06: NUCLEAR REGULATORY COMMISSION IS-OF OPERATIONAL DATA 1996 Annual Report SUANCES FOR DECEMBER 1997. Pages 287-319.

NUREG 1272 V10 NO2 OFFICE FOR ANALYSIS AND EVALUATION NUREG-0750 V47101: INDEXES TO NUCLEAR REGULATORY COM-OF OPERATIONAL DATA.1996 Annual Report. MIS 3 ION ISSUANCES. January 44 arch 1996.

NUREG 1272 V10 NO3: OFFICE FOR ANALYSIS AND EVALUATION NUREG.0750 V47 N01: NUCLEAR REGULATORY COMMISSION IS-OF OPERATIONAL DATA.1996 Annual Report SUANCES FOR JANUARY 1998. Pages 1 12.

NUREG4750 V47 N02: NUCLEAR REGULATORY COMMISSION IS-EDO. OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS SUANCES FOR FEBRUARY 1996. Pages 13-56.

OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS NUREG 0750 V47 NO3: NUCLEAR REGULATORY COMMISSION IS-NUREG-0430 V16: UCENSED FUEL FACluTY STATUS SUANCES FOR MARCH 1998.Pages 57 75.

REPORT.irwentory Difference DataJuly 1, 1995 - June 30 NUREG4750 V47 N04: NUCLEAR REGULATORY COMMISSION IS-1996.(Gray Book 11) SUANCES FOR APRIL 1998.Pages77-260.

NUREG 1626: FINAL ENVIRONMENTAL IMPACT STATEMENT FOR NUREG 0910 R03: NRC COMPREHENSIVE RECORDS DISPOSITION 1HE CONSTRUCTION AND OPERATION OF AN INDEPENDENT SCHEDULE.

SPENT FUEL STORAGE INSTALLATION TO STORE THE THREE NUREG 1575: MULTI-AGENCY RADIATION SURVEY AND SITE IN-MILE ISLAND UNIT 2 SPENT FUEL AT THE IDAHO NATIONAL EN- VESTIGATION MANUAL (MARSSIM). Final Report GINEERING AND ENVIRONMENTAL NUREG 1627 Voi: PERFORMANCE PLAN FY 1999.

33

34 NRC Originating Organisation index (Staff Reports)

WO . 0PPICE OP ISfot.SAR MAULATORY pWMARON POST OSMOS) NUREG-1500 V02 P24: INDMDUAL PLANT EXAMINATION PRO.

DMSION OF ENGNGERING TECHNOLOGY (POST M1217) ORAM: PERSPECTNES ON REACTOR SAFETY AND PLANT PER-NUREG.csss 082: A l AIORfTIZATION OF GENERIC SAFETY FORMANCE.

ISSUES. NUREG 1980 VOS PS: INDMDUAL PLANT EXAMINATION PRO-NUREG 1000: THE 04ARACTERIZATION OF VICIER'S N GRAM: PERSPECTNES ON REACTOR SAFETY AND PLANT HARONEOS INDENTATIONS AND MLE UP PROFILES AS A PERFORMANCE.Appendoes.

STRAIN HARDENING MsCROPROSE. NUREG/CR4000: THE EFFECT OF INITIAL TEMPERATURE ON DMOION OF REGULATORY APPUCATIONS POST M1217) FLAME ACCELERATION AND DEFLAGRATON-TO DETONATION NUREG4713 V18: OOCUPATIONAL RADIATION EXPOSURE AT TRANSITION PHENOMENON.

OOhmERCIAL NUCLEAR POWER REACTORS AND OTHER PROSA84USTIC RISK ANALYSIS BRANCH (POST M1217)

FACIUTIES,1000.TwenipNinst Annual Repost. NUREG-18N DRFT FC: TECHNICAL BASIS AND IMPLEMENTATION NUREG 1907: MINIMUM DETECTABLE CONCENTRATIONS WITH GUIDEUNES FOR A TECHNIQUE FOR HUMAN EVENT ANALYSIS l TYPICAL RADIATION SURVEY INSTRUMENTS FOR VAROUS STHEANA). Draft Report For Comenent.

CONTAMINANTS AND FIELD CONDITIONS.

NUREG/OP-01ee: PROCEEDINGS OF THE WORKSHOP ON REVIEW EDO OPPICE OF 'ar' *** REACTOR REGULATION (POST 000430)

OF 000E -WG METHOOS FOR DEMONSTRATION OF OFFICE OF NUCLEAR REACTOR REGULATION (POST 941001)

COMPUANCE WITH THE RADIOLOGICAL CRITERIA FOR U- NUREG-0040 V21 N04: UCENSEE CONTRACTOR AND VENDOR IN.

CENSE TERMINATION. SPECTION STATUS REPORT. Quarterty Report,0ctober December DMSION OF SYSTEMS TECHNOLOGY (POST 941217) ige 7.(WNie gook)

NUREG1000 Vo1 P1: INOMDUAL PLANT EXAMINATION PRO- NUREG-1570: RISK ASSESSMENT OF SEVERE ACC4 DENT INDUCED GRAM: PERSPECTNES ON REACTOR SAFETY AND PLANT STEAM GENERATOR TUSE RUPTURE.

PERFORMANCE. Summary Report

NRC Originating Organization Inslez (StaN Reports) 34A ADWISORY COMMITTEE (s) I ACNW ADVISORY Coned 4TTEE ON NUCLEAR WASTE NUREG4R4000: ADVISORY COMMITTEE ON NUCLEAR WASTE 1998 STRATEGC PLAN AND PRIORITY ISSUES AND ACTMTIES.

EDO OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEOUARDS OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS NUREG4R 0117NU7-4: NMSS LICENSEE NEWSLETTER.

U.S. NUCLEAR NEGULATORY COMMISSION OFFICE OF PUSUC AFFAIRS NUREGSR4M9:THE ATOMIC SAFETY AND LICENSING BOARD PANEL l

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1 NRC Originating Organization Index (International Agreements)

This index lists those NRC organizations that have published international agreement re-ports. The index is arranged alphabetically by major NRC organizations (e.g., m of-fices) and then by subsections of these (e.g., divisions, brancws) where .Each entry is followed by a NUREG number and title of the report (s), if further nformation is needed, refer to the main citation by NUREG number.

NUREG RELM5/ MODS SUS 000 LED 806UNG WXE &

soo agogr= g TORY POST 839405)

APPUCATION OF MOOS. CODE TO THE s5

- i

NRC Contract Sponsor Index (Contractor Reports)

This index lists the NRC organizations that sponsored the contractor reports listed in this compilation. It is arranged alphabetically by major NRC organization (e.g., program office) and then by subsections of these (e.g., divisions) where appropriate. The sponsor organiza-tion is followed by the NUREG/CR number and title of the report (s) pre aared by that organi-zation. If further information is needed, refer to the main citation by the NUREG/CR number.

EDO OFFICE FOR ANALYSl3 & EVALUATION OF OPERATIONAL NUREG/CR4583 EFFECTS OF LWR COOLANT ENVIRONMENTS DATA ON FATIGUE DESON CURVES OF CARBON AND LOW-ALLOY DIVISION OF SAFETY PROGRAMS (POST 870413) STEELS.

NUREG/CR4874 V25: PRECURSORS TO POTENTIAL SEVERE NUREG/CR4589- THE EFFECTS OF SURFACE CONDITON ON AN CORE DAMAGE ACCCENTS: 1996. A Status Report ULTRASONC INSPECTION: ENGINEERING STUDIES USING VAU.

DATED COMPUTER MODEL EDO OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS NUREG/CR4598: AN INVESTIGATION OF TENDON SHEATHING OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS FILLER MIGRATION INTO CONCRETE.

NUREG/CR4554 V01 R2: SCANS (SHIPPING CASK ANALYSIS SYSTEM) A MICROCOMPUTER BASED ANALYSIS SYSTEM FOR NUREG/CR4605: AN EVALUATION OF HUMAN FACTORS RE-SEARCH FOR ULTRASONC INSERVCE INSPECTION.

SHIPPING CASK DESIGN REVIEW. User's Manual to Verseon Sa.

NUREG/CR4502 ENGINEERING DRAWINGS FOR 10 CFR PART 71 NUREG/CR4606: INVESTIGATION OF TECHNIQUES FOR THE DE-VELOPMENT OF SEISMC DESIGN BASIS USING THE PROBABl.

NUR S WM RY AND EVALUATION OF LOW VELOCITY IMPACT TEST (? SOLID STEEL BILLET ONTO CONCRETE PADS.

NUREG 1R S ESSURE LOCKING AND THER-MAL BINDING TESTS OF GATE VALVES.

DIVISION OF FUd CYCLE SAFETY & SAFEGUARDS (POST P30207)

NUREG/CR4410 NUCLEAR FUEL CYCLE FACluTY ACCIDENT NUREG/CR4615: A SURVEY OF REPAIR PRACTCES FOR NUCLE.

ANALYSIS HANM AR POWER PLANT CONTAINMENT METALUC PRESSURE DiVISON OF WASTE MANAGEMENT (NMSS 940403) BOUNDARIES.

NUREG/CR4377: EFFECTS ON RADONUCUDE CONCENTRA. DIVISION OF REGULATORY APPUCATIONS (POST 941217)

TIONS BY CEMENT / GROUND-WATER INTERACTIONS IN SUP- NUREG/CR4364: HUMAN PERFORMANCE IN RADIOLOGICAL PORT OF PERFORMANCE ASSESSMENT OF LOW-LEVEL RADIO. SURVEY SCANNING.

ACTIVE WASTE DISPOSAL FACluTIES. NUREG/CR4536: VERIFICATION OF THE LWRARC CODE FOR LIGHT WATER REACTOR AFTERHEAT RATE CALCULATONS.

EDO OFFICE OF NUCLEAR REGULATORY RESEARCH (POST 820406) DIVISON OF SYSTEMS TECHNOLOGY (POST 941217)

D!VISON OF ENGINEERING TECHNOLOGY (POST 941217) NUREG/CR4119 V01 R1: MELCOR COMPUTER CODE NUREG/CR-4667 V24: ENVIRONMENTALLY ASSISTED CRACKING MANUALS. Primer And Users' Guides. Version 1.8.4. July 1997.

IN UGHT WATER REACTORS. Semiannual Report. January-June NUREG/CR4119 V02 R1: MELCOR COMPUTER CODE 1997. MANUALS. Reference Manuais. Version 1.8.4. July 1997.

NUREG/CR4361: SEISMC ANALYSIS OF PIPINGFrml Program NUREG/CR4359 V01: RAMONA48: A COMPUTER CODE WITH Report.

THREE-DIMENSONAL NEUTRON KINETICS FOR BWR AND NUREG/CR-5562 DATING AND EARTHOUAKES: REVIEW OF QUA- SDWR SYSTEM TRANSIENTS.Models And Correlations.

TERNARY GEOCHRONOLOGY AND (TS APPUCATION TO PALEO- NUREG/CR4359 V02: RAMONA4B: A COMPUTER CODE WITH SEISMOLOGY. THREE-DIMENSIONAL NEUTRON KINETICS FOR BWR AND NUREG/CR4591 V04 N1: HEAVY SECTON STEEL IRRADIATON SBWR SYSTEM TRANSIENTS. User's Manual.

PROGRAM. Semiannual Progress Report For October 1992 Through NUREG/CR4472: PREUMINARY PHENOMENA IDENTIFICATON March 1993.

AND RANKING TABLES FOR SIMPUFIED BoluNG WATER REAC-NUREG/CR 5591 V06 N1: HEAVY-SECTON STEEL IRRADIATION TOR LOSS-OF COOLANT ACCOENT SCENAROS.

PROGRAM. Semiannual Progress Report For October 1996 Through NUREG/CR4479: TECHNCAL BASIS FOR ENVIRONMENTAL QUAL-March 1997.

IFCATON OF MICROPROCESSOR-BASED SAFETY RELATED NUHEG/CR4412 AGING AND LOSS OF COOLANT ACCCENT EQUIPMENT IN NUCLLAR POWER PLANTS.

(LOCA) TESTING OF ELECTRCAL CONNECTONS.

NUREG/CR4509: THE EFFECT OF INITIAL TEMPERATURE ON NUREG/CR4447: RESULTS OF CRACK ARREST TESTS ON IRRA-OMTED A 506 CLASS 3 STEEL. FLAME ACCELERATION AND DEFLAGRATION-TO-DETONATON NUREG/CR4453: H. B. ROBINSON-2 PRESSURE VESSEL BENCH- TRANSITON PHENOMENON NUREG/CR4534 V02: FRAPCON.3: A OOMPUTER CODE FOR THE CALCULATION OF STEADY. STATE, THERMAL-MECHANICAL BE-NUR G CR4511 V02 STEAM GENERATOR TUBE INTEGRITY PROGRAM. Annual Report, August 1995 September 1996 HAVIOR OF OXCE FUEL RODS FOR HIGH BURNUP.

NUREG/CR4537; INFLUENCE OF LONG TERM THERM'AL AGING NUREG/CR4534 V03: FRAPCON-3: INTEGRAL ASSESSMENT.

ON THE MCROSTRUCTURAL EVOLUTION OF NUCLEAR REAC- NUREG/CR4544: METHODOLOGY FOR ANALYZING PRECURSORS TOR PRESSURE VESSEL MATERIALS.An Atom Probe SNdy. TO EARTHQUAKE-INITIATED AND FIRE-INITIATED ACCIDENT SE-NU EG/ STATE-OF-THE ART REPORT ON PIPING FRAC- E S PRMME @N NWM NUREG/CR4546: A DAMAGE MECHANCS BASED APPROACH TO UNCERTAINTY ANALYSIS. Early Health Effects Uncertainty

! STRUCTURAL DETERORATON AND REUABluTY. Assessment. Main Report j NUREG/CR4554: FINITE ELEMENT ANALYSES FOR SElSMIC NUREG/CR4545 V02: PROBABlUSTIC ACCIDENT CONSEQUENCE SHEAR WALL INTERNATONAL STANDARD PROBLEM. UNCERTAINTY ANALYSIS. Earty Health Effects Uncertainty f NUREG/CR4564; ANALYSES OF SOURCE SPECTRA, ATTENU- AssessmentAppendices.

ATON, AND SITE EFFECTS FROM CENTRAL AND EASTERN NUREG/CR4555 V01: PROBABluSTC ACCOENT CONSEQUENCE UN!TED STATES EARTHOUAKES. UNCERTAINTY ANALYSIS. Late Health Effects Uncertainty 3 NUREG/CR4573: "lNVESTIGATING SEISMOTECTONCS IN THE Assessment. Main Report EASTERN UNITED STATES USING A GEOGRAPHC INFORMA- NUREG/CR4555 V02 PROBABluSTC ACCOENT CONSEQUENCE TON SYSTEM." UNCERTAINTY ANALYSIS. Late Health Effects Uncertainty NUREG/CR4575: FAILURE BEHAVIOR OF INTERNALLY PRESSUR- Assessment. Appendices.

IZED FLAWED AND UNFLAWED STEAM GENERATOR TUBING AT NUREG/CR4571 VO1: PROBABluSTIC ACCOENT CONSEQUENCE HOH TEMPERATURE -EXPERIMENTS AND COMPAR100N WTTH UNCERTAINTY ANALYSIS. Uncertainty Assessment For Intemal MODEL PREDICTIONS. Dooimetry. Main Report.

I 37

38 NRC Contract Sponsor index NUREG/CR4671 V02: PROBABluSTIC ACCIDENT CONSEOUENCE NUREG/CR4613 V02: CODE MANUAL FOR MACCS2. Preprocessor UNCERTAINTY ANALYSIS. Unoortainty Asseeement For Intemel Codes COMIDA2, FGRDCF, IDCF2.

~

Doelmstryf_

NUREG/CR46E9: DIGITAL l&C SYSTEMS IN NUCLEAR POWER Ng[OF N N G 00 8}

PLANTS. Risk-Saoening Of Environmental Stroesors And A W NUREG/CR4577: U.S. NUCLEAR POWER PLANT OPEbTING eon Of Hardware U.2 - 'miWith An Ezioling Analog System. COST AND EXPERIENCE SUMMARIES.

NUREG/CR4613 V01: CODE MANUAL FOR MACCS2. User's Guide. NUREG/CR4004: RADTRAD: A SIMPUFIED MODEL FOR RADIONU-CUDE TRANSPORT AND REMOVAL AND DOSE ESTIMAflON.

I Contractor index This index lists, in alphabetical order, the contractors that prepared the NUREG/CR reports listed in this compilation. Listed below each contractor are the NUREG/CR numbers and titles of their reports. If further information is needed, refer to the main citation by the NUREG/CR number.

ADVANCEO SYSTERN CONCEPTS ASSOC:ATES NUREG/CR4479 TECHNCAL BASIS FOR ENVIRONMENTAL QUAll-NUREG/CR-0644 METHODOLOGY FOR ANALYZING PRECURSORS FICATION OF MOROPROCESSOR-BASED SAFETY-RELATED TO EARTHQUAKE-INITIATED AND FIRE-INITIATED ACCCENT SE- EQUIPMENT IN NUCLEAR POWER PLANTS.

QUENCES.

NUREG/CR4600: THE EFFECT OF WITIAL TEMPERATURE ON

- gg g g g ACCE RATION AND DEFLAGRATION-TO-DETONATION

^

- TER ORS . NUREG/CR4664: FINITE ELEMENT ANALYSES FOR SEISMC SHEAR NUREG/CR4611 vot: STEAM GENERA WTEGRITY WALL WTERNATIONAL STANDARD PRO 8 TEM.

PROGRAM. Annual 1996 September 1906. NUREG/CR4679: DIGITAL l&C SYSTEMS IN NUCLEAR POWER NUREG/CR4675: F HAVIOR OF WTERNALLY PRESSUR. PLANTS.Riek-Screening Of Environmental Sweesore And A Cornperi-IZED FLAWED AND UNFLAWED STEAM GENERATOR TUSING AT son Of Heresere UnevellebBty With An Exieeng Analo9 System.

HIGH TEMPERATURE EXPERIMENTS AND COMPARISON WITH MODEL PREDICTIONS. CALIFORNIA, UNIV. OF, SANTA SAMARA, CA NUREG/CR4683: EFFECTS OF LWR COOLANT ENVIRONMENTS ON FATIGUE DESIGN CURVES OF CARBON AND LOW-ALLOY STEELS. NUREG 1829 THE CHARACTERIZATM OF VCKER'S MICROHARD.

NESS INDENTATIONS AND PILE-UP PROFILES AS A STRAIN-HARD-BATTELig amenarm gugTmlTE, COLUMBUS LABORATORES ENWG MICROPROBE.

NUREG/CR-0640 STATE-OF-THE-ART REPORT ON PIPtNG FRAC. NUREG/CR4664: ANALYSES OF SOURCE SPECTRA, ATTENUATION, TURE MECHANICS AND SITE EFFECTS FROM CENTRAL AND EASTERN UNITED STATES EARTHQUAKES.

54TTELig maarm INSTmlTE, PACIFIC NORTHWEST NATIONAL LABORATORY DEFENBE, DEPT.OF NUREG/CR4377: EFFECTS ON RADIONUCUOE CONCENTRATIONS NUREG 1575: MULTI-AGENCY RADIATION SURVEY AND SITE INVES-BY CEMENT /GROUNO WATER INTERACTIONS IN SUPPORT OF TIGATION MANUAL (MARSSIM). Final Report PERFORMANCE ASSESSMENT OF LOW-LEVEL RADIOACTIVE CR VD  : A COMPUTER CODE FOR THE Y CALCULATION OF STEADY-STATE. THERMAL MECHANICAL BE- NUREG/CR4645 V01: PROSABluSTIC ACCIDENT CONSEQUENCE HAVIOR OF OXCE FUEL RODS FOR HIGH BURNUP. UNCERTAINTY ANALYSIS. Earty Health Effecte Uncertainty NUREG/CR4634 V03: FRAPCON-3: INTEGRAL ASSESSMENT. AaessemenLMain Report.

NUREG/CR4680: THE EFFECTS OF SURFACE CONDITION ON AN NUREG/CR4646 V02 PROSABluSTIC ACCIDENT CONSEQUENCE ULTRA 80NC INSPECTION: ENGINEERING STUDIES USING VAU- UNCERTAINTY ANALYSIS. Early Health Effects Uncertainty DATED COMPUTER MODEL

• _ ff.mdlces.

NUREG/CR4006: AN EVALUATION OF HUMAN FACTORS RESEARCH FOR ULTRASONC WSERVCE WSPECTON. NUREG/CR46Ei VO1: MOBA81USTC ACCIDENT CONSEQUENCE UNCERTANTY APuALYSIS.Lete Health Effecte Uncertamty SOSTON ens a ses WESTON, MA AsessemenLMain Report a NUREG/CR4673: "lNVESTIGATING SEISMOTECTONCS IN THE NUREG/CR4656 V02: PROBA8tuSTIC ACCIDENT CONSEQUENCE EASTERN UNITED STATES USING A GEOGRAPHC WFORMATION UNCERTANTY ANALYSIS.Lete Health Effecte Uncertainty SYSTEM? - - Appendices NUREG/CR4671 V01: PROSA81USTC ACCOENT CONSEQUENCE BR00KNAVEN NATIONAL LASORATORY UNCERTANTY ANALYSIS. Uncertainty Assosement For Internel NUREG-1507: MMIMUM DEITECTABLE CONCENTRATIONS WITH TYP- Doewnetry. Main Report ICAL RADIATION SURVEY WSTRUMENTS FOR VARIOUS CONTAMI-NUREG/CR4671 V02: PROBABiUSTC ACCIDENT CONSEQUENCr NUREG/CP 82 VO "

OF THE TWENTY FIFTH p WAMR REACTOR SAFETY INFORMATION MEETWG. Plenary Seselone. Pressure Vessel Research,8WR Strainer mu* ape And Other EMRGY, DEPT. OF NURE CP V02:' FIFjy NUREG-1575: MULTI-AGENCY RADIATION SURVEY AND SITE lb /ES-WATER REACTOR SAFETY INFORMATION MEETING. Human Reg. TIGATON MANUAL (MARSSIM). Final Report abbey Analysie And Human Performance Evolustion, Technical lemuse Related To Ruhemeldnge, Risk-informed, PerformanceBened initie- arTAL PROMCTION AGENCY swee. NUREG 1575: WULTI-AGENCY RADIATION SURVEY AND SITF INVES-NUREG/CP-0162 V03: PROCEEDINGS OF THE TWENTY-FIFTH TIGATION MANUAL (MARSSIM). Final Report WATER REACTOR SAFETY INFORMATION MEETING.Thermel-Hy-drause Research And Codes, Diglial instrumentaton And Control, 50E INTERNATIONAL Structural Performanos.

NUREG/CR4644: METHODOLOGY FOR ANALYZING PRECURSORS NUREG/CR4350 VD1: RAMONA 48. A COMPUTER CODE WITH TO EARTHQUAKE-lNITIATED AND FIRE-WITIATED ACCIDENT SE-THREE-DIMENSIONAL NEUTRON KINETICS FOR BWR AND 88WR QUENCES.

SYSTEM TRANSIENTS.Modele And Correlatone NUREG/CR4360 V02 RAMONA-48: A COMPUTER CODE WITH EUROPEAN enaanaumaryggS, enaamanom 0F YSTEM NTS. User" W NUREG/CR4671 V01: PROBABluSTC ACCOENT CONSEQUENCE NUREG/CR4364. HUMAN PERFORMANCE N RADIOLOGICAL UNCERTAWTY ANALYSIS. Uncertainty Aseseement For intemet SURVEY SCANNING. Doesmetry. Main Report NUREG/CR4472: PREUMINARY PHENOMENA IDENTIFICATION AND NUREG/CR4671 V02: PROSABluSTIC ACCIDENT CONSEQUENCE RANIONG TABLES FOR SIMPUFIED 80 lung WATER REACTOR UNCERTAINTY ANALYSIS. Uncertainty Asessement For Intemel LOSS OF COOLANT ACCOENT SCENARIOS. Doornstry. Appendices.

39

~. . - - - _. _. - - ~, -.

4 I

40 Coettractor trxlex PRANCE OAK RIDGE A000CIATED UNIVERSITIES NUREG/CR4637: INFLUENCE OF LONG TERM THERMAL AGING ON NUREG 1507: MINIMUM DETECTABLE CONCENTRATIONS WITH TYP-THE MCROSTRUCTURAL EVOLUTION OF NUCLEAR REACTOR CAL RADIATION SURVEY INSTRUMENTS FOR VARIOUS CONTAMk PRESSURE VESSEL MATERIALS.An Atom Probe Study. NANTS AND FIELD CONDITIONS.

NUREG/CR4364: HUMAN PERFORMANCE IN RADIOLOGICAL N RESOURCES ASSOCIAM INC. SURVEY SCANNING.  ;

NUREG/CR4644: METHOOOLOGY FOR ANALYZING PRECURSORS T EARTHOUAKE-INITIATED AND FIRE-lNITIATED ACCIDENT SE-RIOGE NATION MTORY l NUREG/CR-4674 V25: PRECURSORS TO POTENTIAL SEVERE CORE HAWAlt, UNIV. OF, HILO, HI DAMAGE ACCIDENTS: 199tk A Status Report NUREG/CR4666 V01: PROBABluSTC ACCIDENT CONSEQUENCE NUREG/CR4591 V04 N1: HEAVY-SECTION STEEL IRRADIATION UNCERTAINTY ANALYSIS.Lete Health Effecte uncertainty PROGRAM.Somiennual Progrees Report For October 1992 Through Assessment. Main Report. March 1993.

NUREG/CR-8666 V02: PROBABluSTIC ACCIDENT CONSEOUENCE NUREG/CR-5591 V08 N1: HEAVY SECTION STEEL IRRADIATION UNCERTAINTY ANALYSIS. Late Health Effects Uncertainty PROGRAM.Semiennual Progrees Report For October 1996 Through PROBABluSTC ACCIDENT CONSEQUENCE M*'Ch 1887-NUREG/CENi6 UNCERTAINTY ANALYSIS. Uncertainty Asessement For internal NUREG/CR4119 V01 R1: MELCOR COMPUTER CODE MANUALS. Primer And Users' Guides, Version 1.8.4)uly 1997.

. Main Report.

NUREG/ 71 W2 PROBAB!USTC ACCIDENT CONSEQUENCE NUREG/CR-6119 V02 R1: MELCOR COMPUTER CODE ,

UNCERTAINTY ANALYSIS. Uncertainty Aseseement For Internal MANUALS. Reference Manuals, Version 1.8.4, July 1997.

J Doelmstry.Appendlces. NUREG/CR4447: RESULTS OF CRACK-ARREST TESTS ON IRRADI- 4 ATED A 508 CLASS 3 STEEL IDAHO NATIONAL EleGINEERING & ENVgpenrTAL LASORATORY NUREG/CR4453: H. B. ROBINSON-2 PRESSURE VESSEL BENCH-  !

NUREG/CR4634 V02: FRAPCON-3: A COMPUTER CODE FOR THE MARK. l CALCULATION OF STFADY-STATE THERMAL-MECHANICAL BE' NUREG/CR4479: TECHNICAL BASIS FOR ENVIRONMENTAL QUALI-l N O CR461 ES L S OF PRESS EL I AND THERMAL FICATION 00 MOROPROCESSOR-BASED SAFETY RELATED BINDING TESTS OF GATE VALVES. EQUIPMENT IN i'ICLEAR POWER PLANTS.

NUREG/CR4536: VERIFICATION OF THE LWRARC CODE FOR l INSTITUTE POR MATERIALS M8e8 ARCH UGHT.WATE9-REACTOR AFTERHEAT RATE CALCULATIONS. )

NUREG-1829- THE CHARACTERIZATION OF VCKER'S MICROHARD- NUREG/CR4537: INFLUENCE OF LONG-TERM THERMAL AGING ON )

NESS INDENTATIONS AND PILE-UP PROFILES AS A STRAIN-HARD- THE MICROSTRUCTURAL EVOLUTION OF NUCLEAR REACTOR ENING MOROPROBE. PRESSURE VESSEL MATERIALS.An Atom Probe Study. l NUREG/CR4546: A DAMAGE MECHANICS BASED APPROACH TO STRUCTURAL DETERIORATION AND REUABILITY.

E A ICS BASED APPROACH TO NUREG/CR4577: U.S. NUCLEAR POWER PLANT OPERATING COST STRUCTURAL DETERIORATION AND REUABluTY.

AND EXPERIENCE SUMMARIES. <

l LAWRENCE UVERMORE NATIONAL LADORATORY NUREG/CR4598: AN INVESTIGAYlON OF TENDON SHEATHING NUREG/CR-4554 V01 R2: SCANS (SHIPPING CASK ANALYSIS FILLER MIGRATION INTO CONCRETE.

SYSTEM) A MOROCOMPUTER BASED ANALYSIS SYSTEM FOR NUREG/CR-6615: A SURVEY OF REPAIR PRACTCES FOR NUCLEAR SHIPPING CASK DESIGN REVIEW. User's Manuel to Version Sa. POWER PLANT CONTAINMENT METALUC PRESSURE BOUND-NUREG/CR-5602 ENGINEERING DRAWINGS FOR 10 CFR PART 71 ARIES.

PACKAGE APPROVALS.

NUREG/CR-8006: INVESTIGATION OF TECHNIQUES FOR THE DE- ORGANIZATION FOR ECONOMIC COOPERATION & DEVELOPMENT VE NT ISMIC SIGN BASIS USING THE PROBABluS-NUREG/CR-4667 V24: ENVIRONMENTALLY ASSISTED CRACKING IN NUREG/CR-ee08:

SUMMARY

AND' EVALUATION OF LOW-VELOCITY LIGHT-WATER REACTORS. Senuannual Report, January-June 199T.

IMPACT TEST OF SOUD STEEL BILLET ONTO CONCRETE PADS.

MASSACHUGETTS INSTITUTE OF TECHNOLOGY, CAMORfDGE. MA NUREG/CR4119 V01 R1: MELCOR COMPUTER CODE NUREG/CR4644: METHODOLOGY FOR ANALYZING PRECURSORS MANUALS.Prtmer And Users' Guides. Version 1.8.4, July 1997, I TO EARTHOUAKE-INITIATED AND FIRE-INfTIATED ACCIDENT SE- NUREG/CR4119 V02 R1: MELCOR COMPUTER CODE QUENCES. MANUALS. Reference Manuals, Version 1.8.4 July 1997.

MICHIGAN, UINV. OF. ANDI ARDOR, MI NUREG/CR4412: AGING AND LOSS OF COOLANT ACCIDENT (LOCA)

NUREG/GR-0016: THE ROLE OF TIME-DEPENDENT DEFORMATION TESTING OF ELECTRCAL CONNECTIONS.

IN INTERGRANULAR CRACK INITIATION OF ALLOY 600 STEAM NUREG/CR4479 TECHNICAL BASIS FOR ENVIRONMENTAL QUAU-GENERATOR TUBING MATERIAL FICATION O" MICROPROCESSOR-BASED SAFETY-RELATED EQUIPMENT th i'UCLEAR POWER PLANTS. l NATIONAL RA000 LOGICAL PROTECTION DOARO NUREG/CR4545 V01: PROBABluSTIC ACCIDENT CONSEQUENCE NUREG/CR4571 V01: PROBABluSTIC ACCIDENT CONSEQUENCE UNCERTAINTY ANALYSIS. Early Health Effects Uncertainty I UNCERTAINTY ANALYSIS. Uncertainty Aseeeement For intomal Asseeement.Me n Report l DosimetryMein Report NUREG/CR4545 V02: PROBABluSTC ACCIDENT CONSEQUENCE NUREG/CH4571 W2 PROBABluSTIC ACCIDENT CONSEQUENCE UNCERTAINTY ANALYSIS. Earty Health Effects Uncertainty UNCERTAINTY ANALYSIS. Uncertainty Aseessment For intomal f_ _. ,

NUREG/CR4555 V01: PROBABluSTIC ACCIDENT CONSEQUENCE i

NETHERLANOS ENERGY RE9EARCH FOUNDATION ECN UNCERTAINTY ANALYSIS. Late Health Effects Uncerts' .

NUREG/CR4545 VO1: PROBABluSTIC ACCIDENT CONSEQUENCE Assessment. Main Report l UNCERTAINW ANALYSIS. Earty Health Effects Uncertainty NUREG/CR4555 V02: PROBABluSTC ACCIDENT CONSEQUENCE i Asseeement. Main Report. UNCERTAINTY ANALYSIS. Late Health Effects Urcertainty j

? _ _ _ _ _ ,ea;.Appendcas.

NEW MEXICO, UINV. OF ALSUQUEROUE. NM NUREG/CR4571 V01: PROBABluSTIC ACCIDENT CONSEQUENCE j NUREG/CR4645 V01: PROBABIUSTIC ACCIDENT CONSEQUENCE UNCERTAINTY ANALYSIS. Uncertainty Assessment For Intemal ,

UNCERTAINTY ANALYSIS. Earty Health Effects Uncertainty Dosimetry. Main Report NUREG/CR4571 V02: PROBABILISTC ACCIDENT CONSEQUENCE NUR 54 V02 PROBABluSTC ACCIDENT CONSEQUENCE UNCERTAINTY ANALYSIS. Uncertainty Assessment For intamal U,NCERTAIN. TY ANALYSIS. Earty Health Effects Uncertainty

_ __ Dosimetry. Appendices.

NUREG/CR4604: RADTRAD: A SIMPLIFIED MODEL FOR RADIONU-00UCLEAR POWER ENGINEERipeG CORP. CUDE TRANSPORT AND REMOVAL AND DOSE ESTIMATION.

NUREG/CR4500: THE EFFECT OF INITIAL TEMPERATURE ON NUREG/CR-6613 V01: CODE MANUAL FOR MACCS2. User's Guide.

FLAME ACCELERATION AND DEFLAGRATION-TO-DETONATION NUREG/CR4613 V02: CODE MANUAL FOR MACCS2.Proprocessor TRANSITION PHENOMENON. Codes COMIDA2, FGRDCF, IDCF2.

I

4 6

i Contractor index 41 00 MIN AppuCATIces urTWWIATIONAL C0lW. pY NUREG/GW813 Vot: CODE MANUAL POR MAOC82.Prepecesser 90W00E APPUCATICIS, Codes COMIDAR. PGRDCF,10CFt.

NURBG4713 Vie: OCCUPATIONAL RADIATION EXPOGURE AT COM-IWICIAL NUCLAAR POWER REACTORS AND OTHER UINTED 1W00D001 FACIUTES.180s.T. _ .L. Annung NUREG/CIWees W1: pamm g ACCIDENT CONSEQUENCE Nul45G/CfMs74 Vas: PROGURAORS TO SEVERE CORE UNCERTAINTY ANALYSIS. Late Hoelm Effects Uncertainer

-! DAMAGE AOCWENTS: 1988. A SIsha Report Acessement. Main Report NUREG/OfM410: NUCLEAR PUEL CYCLE FACIUTY AOCIDENT ANAL. NUREG/OfMOS6 V00: PROBASIUSTIC ACCIDENT CONSEQUENM yeIBHAND000gL UNCERTAINTY ANALYSIS. Late HeeNh Eleonte Uncertainly NUREG/OfWSM DIGrTAL 18C SYSTEMS IN NUCLEAR POWER AssessmenLAppensees.

PLANT 3. Risk 4eeening Of Environmental Streasore And A Comperl.

een Of Henleere UnovatebERy Wilh An Edsene Ansing Systent VAIIDWWILT UIIIV,IIAANVIuA TN NUREG/CIM002: DATING AND EARTHQUAKES. REVIEW OF QUA-TECISIADVIS - 00NSULTAlfft, IIIC. TERNARY GEOCHRONOLDGY AND ITS APPUCATION TO PALEO-NUREG/CR4813 V01: CODE MANUAL POR MACC82. User's Gulde. 8EleMOU30Y.

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l International Organization index This index lists, in alphabetical order, the countries and performing organizations that pre-

! pared the NUREG/lA reports listed in this compilation. Usted below each country and per-forming organization are the NUREG/lA numbers and titles of their reports. If further infor-l mation is needed, refer to the main citation by the NUREG/lA number.

L l

I RUSSIA NUREG/ WOO 25: RELAP5/ MOO 3 SUSCOOLED BOluNG MODEL AS-

"NiE$/E APPUCATION OF RELAP5/ MODS.1 CODE TO THE torr 1E r ta j

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Licensed Facility Index

' This index lists the facilities that were the subject of NRC staff or contractor reports. The facility names are arranged in alphabetical order. They are preceded by their Docket number and followed by the report number. If further information is needed, refer to the main citation by the NUREG number.

1. N1 HA MW, Ud f, Code Pouw & MGQM nm N E M t p g,- M Sigg i

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45

NRC FORM 3a5 U.S. MJcLEAR REGULATOFly manaane" 1. REPORT NLMIER QM (Assioned by mRc, And yet., supp., Rev.,

EsE. BIBUOGRAPHIC DATA SHEET *"**"""""""***U*"8 (s= merucen.one. w; NUREG-0304

2. TITLE AND SU8 TITLE Vol. 23, No.1 Abstracts for Publications in the NUREG-Series

3. DATE REPORT PusUSHED Semiannual Compilation for January - June 1998 Mo*H YEAR l

September 1998 in Vol. 23, No.1 of NUREG-0304,the16e was changed from " Regulatory and Technical Reports 4. FIN OR GRANT NUMBER

. (Abstract index Joumal)."

5. AUTHOR (S) s. TYPE OF REPORT

7. PERIOD COVERED (incsusive cesee)

January- June 1998

8. PERFORMNG ORGANIZATION . NAME AND ADDRESS (a AMC, pam omisen, omes cr Asem u.S. Nucasar Ampuimary commesert and memy emana; acontecer, povano nome and meihng eness)

Publishing Services Branch Of5ce of the Chief information Officer U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

9. SPONSORING ORGANIZATION . NAME AND ADDRESS (ahRC, fype 'Some es e6erei scontecAr. ppm AMC Dwamn. once a Aspen. U.S Nuclear AmpuAstry Comnweaan, and mehw emene)

Same as 8, above.

10. SUPPLEnENTARY NOTES L L Stevenson, Project Manager

11. ABSTRACT (Joo werde a Ases)

This journalincludes all formal reports in the NUREG-series prepared by the NRC staff and contractors; proceedings of conferencas and workshops; as well as international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, intemational organtZetion, and licensed facility.

In Vol. 23, No.1, of NUREG-0304, the title was changed from " Regulatory and Technical Reports (Abstract Index Journal)."

12. KEY WORDSOESCRIPTORS itat made eparsam ret wamsiermeenchne An eceans me rspau 13 AvAuauTY shTEMENT compilation unlimited abstract indeX 14 SECURITYCLASSIFCATION abstract cine regns NRC publications unclassified NUREG-series publications (nim unclassified

15. NUMBER OF PAGES

16. PRICE NRC FORM 336 Q.es)

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• on recycled paper I,

Federal Recycling Program

z E 8 E Main Citations H E and Abstracts f y5 E g h f

p . b -

U Secondary Report 18 gg 8= y ir Numberindex gQ R s

@a Pensonal Authorindex I ,

5 EE 2

Subject index h'"g 5%;S50 8,

????za 5a saasAS. gE NRC Originating Organization 007$55 index (Staff Reports) dQ E 5E] Od M "' 85 E- EE NRC Originating Organization

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!i 52 NRC Contractor 5 "$ UE Sponsorindex y IE 3

ContractorIndex Intemational Oiganization index A "

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