ML20247A303

Regulatory and Technical Reports (Abstract Index Journal). Compilation for Second Quarter 1989,April-June

ML20247A303
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Issue date:	08/31/1989
From:	NRC OFFICE OF ADMINISTRATION (ADM)
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References
NUREG-0304, NUREG-0304-V14-N02, NUREG-304, NUREG-304-V14-N2, NUDOCS 8909120088
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NUREG-0304 Vol.14, No. 2 Regulatory ancL Technical Reports

/( Abstract Index Journall)

Compilation for Second Quarter 1989 April- June U.S. Nuclear Regulatory Commission OfTice of Administration jv# "'*%,

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3T Available from Superintendent of ' Documents U.S. Government Printing' Office .

Post Office Box 37082 Washington, D.C. 20013-7082 A year's subscription consists of 4 issues for .

this publication.

- Single copies of this publication are available from National Technical information Service, Springfield, VA'22161 1'

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,. s NUREG-0304- I Vol.14, No. 2 l i

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Regulatory and Technical Reports  !

(Abstract Index Journal) l Compilation for )

Second Quarter 1989 April- June Date Published: August 1989 Regulatory Publications Branch i Division of Freedo.n ofInformation and Publications Services Office of Administration U.S. Nuclear Regulatory Commission 1 Washington, DC 20555  !

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CONTENTS Preface. .. . .. .. . .. . . . .. . . . . . v index Tab Main Citations and Abstracts . . . . . . . . . . .. .. . . 1

• Staff Reports

• Conference Proceedings

• Contractor Reports

• International Agreement Reports Secondary Report Number index . . .. . . . . . .. . .. .. 2 Personal Author index . . . . ... .. . . .. .. . .3 Subject index . . . . . ...... ........... .. .. . . . . . .. .. ... .. . . . 4 NRC Originating Organization index (Staff Reports) . . . ... . . . .. .. 5 NRC Originating Organization Index (International Agreements) . . .. . . .6 NRC Contract Sponsor index (Contractor Reports) . .. .. .. . . . . . 7 Contractor index . . . . . . . . . . . . . . . . . . .. ... .. 8 International Organization index . .. . . . .. . . .. .. .. 9 Licensed Facility index . . ... . . . .. . . .10 iii

PREFACE This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the U.S. Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC's intention to publish this compilation quarterly and to cumulate it annually. Your comments will be ap-prcciated. Please send them to:

Division of Publications Services Policy and Publications Management Branch Publishing and Translat;ons Section Woodmont 537 U.S. Nuclear Regulatnry Commission Washington, D.C. 20555 The main citations and abstracts in this compilation are listed in NUREG numner order: NUREG-XXXX, NUREG/CP-XXXX, NUREG/CR-XXXX, and NUREG/lA-XXXX. These p.ocede the following indbxes:

Secondary Report Number index Personal Author index Subject Index NRC Originating Organization Index (Staff Reports)

NRC Originating Organization Index (International Agreements)

NRC Contract Sponsor index (Contractor Reports)

Contractor index International Organization Index Licensed Facility index A detailed explanation of the entries precedes cach index.

The bibliographic elements of the main citations are the following:

Staff Report NUREG-0808: MARK 11 CONTAINMENT PROGRAM EVALUATION AND ACCEPTANCE CRITERIA.

ANDERSON, C.J. Division of Safety Technology. August 1981. 90 pp. 8109140048 09570:200.

Where the entries are (1) report number, (2) report title, (3) report author, (4) organizational unit of author, (5) date report was published, (6) number of pages in the report, (7) the NRC Document Control System accession number, (B) the microfiche address (for internal NRC use).

Conference Report NUREG/CP-0017: EXECUT!'IE SEMINAR ON THE FUTURE ROLE OF RISK ASSESSMENT AND RELIABILITY ENGINEERING IN NUCLEAR REGULATION. JANERP, J.S. Argonne National Laboratory. May 1981.141 pp. 8105280299 ANL-81-3. 08632:070.

Where the entries are (1) report number, (2) report title, (3) report author, (4) organization that compiled the proceedings, (5) date report was published, (6) number of pages in the report, (7) the NRC Docu-ment Control System accesdon number, (8) the report number of the originating organization, IS) the microfiche address (for NRC intsmal use).

Contractor Report NUREG/CR-1556: STUDY OF ALT'cRNATE DECAY HEAT REMOVAL CONCEPTS FOR LIGHT WATER REACTORS-CURREhi SYSTEMS AND PROPOSED OPTIONS. BERRY, D.L.; BENNETT, P.R.

Sandia Laboratories. May 1981.100 pp. 8107010449. SAND 80-0929. 08912:242.

Where the entries are (1) report number, (2) report title. (3) report authors, (4) organizational unit of authors or publisher, (5) date report was published, (6) number of pages in the report. (7) the NRC Document Control System accession number, (8) the report number of the originating organization (if given), and (9) the microfiche address (for NRC internal use).

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. International Agreement Report I NUREG/lA-0001: ASSESSMENT OF TRAC-PD2 USING SUPER CANNON AND HDR EXPERIMENTAL DATA. NEUMANN, U. Kraftwerk Union. August 1986. 223 pp. 8608270424. 37659:138.

Where the entries are (1) report number, (2) report title, (3) report author, (4) organizational unit of author, l (5) date report was published, (6) number of pages in the report, (7) the NRC Document Control System ,

, accession number, (8) the report number of the originating organization (if given), and (9) the microfiche 1 I

! address (for NRC internal use).

The following abbreviations are used to identify the document status of a report:

ADD - addendum APP - appendix DRFT - draft ERR - errata N - number R - revision S - supplement V - volume Availability of NRC Publications Copies of NRC staff and contractor reports may be purchased either from the Government Printing Office (GPO) or from the National Technical Information Servico, Springfield, Virginia 22161. To purchase documents from the GPO, send a check or money order, payable to the Superintendent of Documents, to the following address:

Superintendent of Documents U.S. Govemment Printing Office Post Office Box 37082 Washington, DC 20013-7082 You may charge any purchase to your GPO Deposit Account, MasterCard charge card, or VISA charge card by calling the GPO on (202)275-2060 or (202)275-2171. Non-U.S. customers must make payment in advance either by International Postal Money Order, payable to the Superintendent of Documents, or by draft on a United States or Canadian bank, payable to the Superintendent of Documents.

NRC Report Codes The NUREG designation, NUREG-XXXX, indicates that the document is a formal NRC staff-generated report. Contractor-prepared formal NRC reports carry the report code NUREG/CR-XXXX. This type of identification replaces contractor established codes such as ORNL/NUREG/TM-XXX and TREE-NUREG-XXXX, as well as various other numbers that could not be correlated with NRC sponsorship of the work being reported.

In addition to the NUREG and NUREG/CR codes, NUREG/CP is used for NRC-sponsored conference proceedings and NUREG/lA is used for intemational agreement reports.

All these report codes are controlled and assigned by the staff of the Publishing and Translations Section of the NRC Division of Publications Services.

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Mdn Citati;ns cnd Abstrccts The report listings in this compilation are arranged by report number, where NUREG-XXXX is an NRC staff-originated report, NUREG/CP-XXXX is an NRC-sponsored conference report, NURE9/CR-XXXX is an NRC contractor-prepared report. and NUREG/lA-XXXX is an inter-national agreement report. The bibliographic information (see Preface for details) is followed by a brief abstract of this report.

NUREG-0020 V13 NO3: LICENSED OPERATIN3 REACTORS Section 208 of the Energy Reorgaruzation Act of 1974 identi-STATUS

SUMMARY

REPORT. Data As Of February fies an abnormal occurrence as an unscheduled incident or 28,1989.(Gray Book 1) SCHWARTZ,l. Division of Computer & event which the Nuclear Regulatory Commission determines to Telecommunications Services (Post 890205). March 1989. be significant from the standpoint of public heafth and safety 516pp. 8904240315. 49438:332. and requires a quarterly report of such events to be made to THE OPERATING UNITS STATUS REPORT - LICENSED Congress. This report covers the pened October 1 to December OPERATING REACTORS provides data on tne operation of nu- 31,1988. For this reporting penod, there were no abnormal oc-clear units as timely and accurately as possible. This informa- currences at nuclear power plants licensed to operate. There tion is collected by the Office of Information Resources Man- was one abnormal occurrence under other NRC-issued licenses agement from the Headquarters staff of NRC's Office of En- involving a medical therapy misadministration There were three forcement (OE), from NRC's Regional Offices, and from utihties. abnormal occurrences reported by Agreement States. The State The three sections of the report are: monthly highhghts and sta- of New York reported an event involving multiple medical ther-tistics for commercial operating units, and errata from previously apy misadministration. The State of Maryland reported two repc1od data; a compilation of detailed information on each events, both occurnng at the same hospital. One involved a unit, provided by NRC's Regional Offices, OE Headquarters and single medical therapy misadministration and the second in-tne utilities; and an appendix for miscellaneous information such volved multiple medical therapy misadministration. The roport as spent fuel storage capabikty, reactor-years of exponence and also contains information updating some previously reported ab-non-power reactors in the U. S. It is hoped the report is helpful normal occurrences.

swar ne of he U S en rgy tu tion sa ho NUREG-0304 V13 N04: REGULATORY AND TECHNICAL RE-PORTS (ABSTRACT INDEX JOURNAL). Annual Compilation NDREG-0020 V13 N04: LICENSED OPERATING REACTORS For 1988.

• Division of Freedom of Information & Pubhcations STATUS

SUMMARY

REPORT. Data As Of March 31.1989 (Gray Services (Post 890205). May 1989. 143pp. 8906120099.

Book I) SCHWARTZ,l. Division of Computer & Telecommunica- 50111.263.

tions Services (Post 890205). May 1989. 547pp. 8905220167. This journal includes all formal reports in the NUREG senes 49831:142. prepared by the NRC staff and contractors, proceedings of con.

See NUREG 0020,V13 NO3 abstract. ferences and workshops, as well as international agreement re-p rts. The entnes in this compilation are indexed for access by NUREG-0020 V13 N05: LICENSED OPERATING REACTORS title and abstract, secondary report number, personal author, STATUS

SUMMARY

REPORT. Data As Of April 30.1989.(Gray Book 1) LOVELACE.W.H. Division of Computer & Telecommune su@ct E oganizabon for sM and inwnahonal age cations Services (Post 890205). June 1989. 557pp. men s, contractor, inwnational oganeaton, and IcenW fach 8906260279. 50277.294. I See NUREG 0020,V13.NO3 abstract. NUREG-0386 005: UNITED STATES NUCLEAR REGULATORY b

NUREG-0040 V12 N04: LICENSEE CONTRACTOR AND DIGEST. Commission, Appeal Board And Licensing Board VENDOR INSPECTION STATUS REPORT, Quarterly Report, October December 1988.(White Book)

• Division of Re- Decisions. July 1972 - June 1988. Office of the Generu Coun-actor inspection & Safeguards (Post 870411) April 1989. 58pp. s st 86m1). April 1989. 845pp. 8905220199. 49823.142.

8905100254.49666:062. This fifth edition of the NRC Staff Practice and Procedure This penodical covers the results of inspections performed by gest contains a @est of a num d @nmssion, em the NRC's Vendor inspection Branch that have been distnbuted Safety and Licensing Appeal Board, and Atomic Safety and Le to the inspected organization dunng the penod from October censing Board decisions issued dunng the penod from July 1  ;

1988 through December 1988. 1972 to June 30,1988 interpreting the NRC's Rules of Practice in 10 CFR Part 2. This edition replaces in their entirety earher NUREG-0040 V13 N01: LICENSEE CONTRACTOR AND editions and supplements and includes appropnate changes re.

VENDOR INSPECTION STATUS REPORT. Quarterly flecting the amendments to the Rules of Practice effective Report, January-March 1989 (White Book)

• Division of Reactor through June 30,1988.

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' " ^P"' NUREG-0386 DOS R01: UNITED STATES NUCLEAR REGULA- l 9051 0182 497 29 This periodical covers the results of inspections performed by the NRC's Vendor inspection Branch that have been distabuted ommssion, Appeal Board And Licensing Board to the inspected organization ounng the penod from January Decisions July 1972 - September 1988.

• Office of the General .

1989 through March 1989. Counsel (Post 860701). April 1989. 54Bpp. 8905220191.

49826:292.

NUREG-0090 V11 N04: REPORT TO CONGRESS ON ABNOR. This Revision 1 of the fifth edition of the NRC Staff Practice MAL OCCURRENCES October-December 1988.

• Office for and Procedure Digest contains a digest of a number of Com-Analysis & Evaluation of Operational Data, Director. April 1989. mission, Atomic Safety cnd Licensing Appeal Board, and Atomic 33pp BP05220151 49830.142. Safety and Licensing Board decisions issued dunng the penod l

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2 Main Citabons and Abstracts from July 1,1972 through September 30,1988, interpreting the NUREG-0750 V29 N04: NUCLEAR REGULATORY COMMISSION NRC's Rules of Practice in 10 CFR Part 2. This Revision 1 re- ISSUANCES FOR APRIL 1989. Pages 345-393.

• Division of places, in part, earlier editions and supplements and includes Freedom of information & Publications Services (Post 890205).

appropnate changes reflecting the amendments to the Rules of June 1989. 55pp. 8907060098. 50356:195.

Practice effective through September 30,1988. See NUREG-0750,V29,N02 abstract.

NUREG-0420 S10: SAFETY EVALUATION REPORT RELATED NUREG-0797 S21: SAFETY EVALUATION REPORT RELATED TO THE OPERATION OF SHOREHAM NUCLEAR POWER TO THE OPERATION OF COMANCHE PEAK STEAM ELEC-STATION, UNIT 1. Docket No. 50-322. (Lrng Island Lighting TRIC STATION, UNITS 1 AND 2. Docket Nos. 50-445 And 50-Company)

• Division of Reactor Projects - 1/11 (Post 870411). 446.(Texas Utilit:es Generating Corp)

• Office of Nuclear Reac-April 1989. 72pp. 8905110311. 49724:092. tor Regulation, Director (Post 870411L April 1989. 223pp.

Supplement 10 to the Safety Evaluation Report on Long 8905110322. 49723:202.

Island Lighting Company's application for a license to operate Supplement 21 to the Safety Evaluation Report related to the the Shoreham Nuclear Power Station, Unit 1, located in Suffolk operation of the Comanche Peak Steam Electnc Station Units County, New York, has been prepared by the Office of Nuclear 1 and 2 (NUREG-0797), has been prepared by the Office of Nu-Reactor Regulation of the U.S. NucMr Regulatory Commission. clear Reactor Regulation of the U.S. Nuclear Regulatory Com-This supplement addresses several items that have been re- mission. The facility is located in Somervell County, Texas, ap-viewed by the staff since the previous supplement was issued proximately 40 miles southwest of Fort Worth, Texas. This sup-piement reports the status of certain issues that had not been NUREG-0540 V11 N01: TITLE LIST OF DOCUMENTS MADE resolved at the time of publication of the Safety Evaluation PUBLICLY AVAILABLE. January 1 31,1989.

• Division of Free-Report and Supplements 1, 2, 3, 4, 6, and 12 to that report.

dom of information & Publications Services (880515-890204). This supplement also lists the new issues that have been identi-March 1989. 409pp. 8904240309. 49440:280.

feed since Supplement 12 was issued and includes the evalua-This document is a monthly publication containing desenp- tions for hcensing items resolved in this intenm penod. Supple-tions of information received and generated by the U.S. Nuclear ment 5 has not been issued. Supplements 7 through 11 were Regulatory Commission (NRC). This information includes (1) limited to the staff evaluatson of allegations investigated by the docketed matenal associated with civilian nuclear power plants NRC Technical Review Team. Supplement 13 presented the and other uses of radioactive matenals, and (2) nondocketed staff's evaluation of the Comanche Peak Response Team matene! ceived and generated by NRC pertinent to its role as (CPRT) Program Plan, which was formulated by the applicant to a regulatory agency. The following indexes are included: Per- resolve vanous construction and design issues raised by sonal Author, Corporate Source, Report Number, and Cross sources external to the applicant. Supplements 14 througn 20 Reference to Principal Documents.

presented the staff's evaluation Of the applicant s Corrective NUREG 0540 V11 N02: TITLE LIST OF DOCUMENTS MADE Action Program and CPRT activities. Items identified in Supple-PUBLICLY AVAILARLE. February 1 28,1989.

• Division of Free- ments 7,8,9,10,11,13,14, and 15 through 20 are not includ-dom of Information & Publications i trvices (Post 890205). Apnl ed in this supplement, except to the extent that they affect the 1989,326pp. 8905110313. 49722:236. applicant's Final Safety Analysis Report.

See NUREG-0540,V11,N01 abstract' NUREG-0837 V08 N04: NRC TLD DIRECT RADIATION MONI.

NUREG-0940 V11 NO3: TITLE LIST OF DOCUMENTS MADE TORING NETWORK.Progr( as Report. October-December 1988.

PUBLICLY AVAILAELE. March 1-31,1989.

• Division of Free- STRUCKMEYER,R.; MCNAMARa N. Region 1, Ofc of the D# rec-dom of Information & Publications Services (Post 890205). May tor. April 1989. 322pp. 8905100289. 49661:122.

198p. 407pp. 8906050226. 50028:177. This report provides the status and results of the NRC Ther-l See NUREG-0540.V11,N01 abstract. moluminescent Dosimeter (TLD) Direct Radiation Monitonng

"*'*0 " P psents the radiation leds masud in N mnh l NUREG-0540 V11 N04: TITLE LIST OF DOCUMENTS MADE PUBLICLY AVAILABLE. Apnl 1-30,1989.

• Division of Freedom uh u eo18' of Information & Publications Services (Post 890205). June 1989. 400pp. 8907060242. 50374:066. NUREG-0896 SOB: SAFETY EVALUATION REPORT RELATED See NUREG 0540,V11,N01 abstract. TO THE OPERATION OF SEABROOK STATION, UNIT U e NUREG-0750 V28102: INDEXES TO NUCLEAR REGULATORY shird , Division t No. 50-443.(Pubhc Service of Reactor Projec's Company

.1/II (Post 870411) Of MayNew Hamp-COMMISSION ISSUANCES. July-December 1988.

• Division of 0#P 8906230155 50 5 148 Freedom of information & Publications Services (Post 890205). ple t Apnl 1989. 93pp. 8905220112. 49826'042. o eration of the Seabrook Station, Unit 1 addresses items relat-Digests and indexes for issuances of the Commission, the ing to the issuance of a 5% tow power license. The report re-Atomic Safety and Licensing Appeal Panel, the Atomic Safety Wes m me appl 6atior; filed by the Public Service Company of and Licensing Board Panel, the Administrative Law Judge, the New Hampshire for a license to operate the Seabrook Station, Directors Decisions, and the Denials of Petitions for Rutemak.

Unit i located in Rockingham County, New Hampshire.

ing are presented.

NUREG-0904 S01 V01: SUPPLEMENT TO THE FINAL ENVIRON-NUREG-0750 V29 N02: NUCLEAR REGULATORY COMMISS!ON MENTAL STATEMENT RELATED TO THE DECOMMISSION-ISSUANCES FOR FEBRUARY 1989 Pages89-209.

• Division FACILITY, WEST ING OF THE RARE EARTHS of Freedom of Information & Publications Services (Post CHICAGO.lLLINOIS. Volume 1: Main Text And Appendices A-G.

890205). April 1989.128pp. 8905220120. 49826:135.

Legal issuances of the Commission, the Atomic Safety and Li-Docket No. 40-2061.

• Division of Industnal & Medical Nuclear Safety (Post 870729) April 1989. 557pn. 8905100217. 83-495-censing Appeal Panel, the Atomic Safety and Licensing Board Panel the Administrative Law Judge, and NRC program offices O L.49 Supp m t to the Final Environmental Statement is issued by the U S. Nuclear Regulatory Commission in response NUREG-0750 V29 NO3: NUCLEAR REGULATORY COMMISSION to the Atomic Safety and Licensing Boaro's ruling that the staff (SSUANCES FOR MARCH 1989. Pages 211-343.

• Division of must supplement the Final Environmental Statement in order to Freedom of inforrrwt:on & Publications Services (Post 890205). evaluate the impact of permanent disposal of the Kerr-McGee May 1989 139pp. 8907060114 50356 253. Rare Earths Facility wastes located at West Chicago, Illinois.

See NUREG-0750,V29.N02 abstract. The statement considers the Kerr-McGee preferred plan and

M:in CitItians cnd Abstr: cts 3 vanous alternatives to the plar*. The action proposed by the however, we beheve it is useful to have a summary of each Commission is the renewal of the Kerr-McGee license to allow contractor's efforts for the year combined into one volume, disposal of wastes onsite and for possession of the wastes under license for an indeterminate time. The heense could be NUREG-0991 S07: SAFETY EVALUATION REPORT RElATED terminated at a later date if certain specified requirements were TO THE OPERATION OF LIMERICK GENERATING met. NUREG 0904 was published in draft for comment in June STATION, UNITS 1 AND 2. Docket Nos. 50-352 And 50-1D87. Comments have been received and are published with 353 (Philadelphia Electne Company)

• Division of Reactor their responses in this report Volume 1 contains the main text Nojects - 1/11 (Post 870411). April 1989. 8Bpp. 8905110317.

and Appendices A thru G. Volume 2 contains the comments re- 49724:150.

coived and their responses. In August 1983 the staff of the Nuclear Regulatory Commis-si n issued its Safety Evaluation Report (NUREG-0991) regard-NL* REG 0904 SDI V02: SUPPLEMENT TO THE FINAL ENVIRON- ing the appkcation of the Philadelphia Eiectnc Company (the le MENTAL STATEMENT RELATED TO THE DECOMMISSION- consee) f r licenses to operate the Limenck Generating Station, ING OF THE RARE EARTHS FACILITY, WEST n gomm and Nsmr ns an , a on 6 s CHICAGO,lLLINOIS Volume 2: Appendix H Docket No. 40-2061. Counties, Pennsylvania. Supplement 1 was issued in December

• Division of Industrial & Medical Nuclear Safety (Post B70729). 1983. Supplement 2 was issued in October 1984. Supplement 3 April 1989. 955pp. 8905100219. 83-495-01-ML. 49694199. was issued in October 1984. Supplement 4 was issued in May See NUREG-0904,S01,V01 abstract.

1985. Supplement 5 was issued in July 1985. Supplement 6 NUREG-0933 SO9: A PRIORITIZATION OF GENERIC SAFETY was issued in August 1985 and Supplement 7 issued in March 1989. This Supplement 7 addresses the major design differ-

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ISSUES EMRIT,R.; RIGGS.R4 MILSTEAD.W.; et al. Divrsion of Regulatory Applications (Post 870413). May 1989. 271pp. ences between Units 1 and 2, the resolution of all issues that 8906120105. 50113 006. remained open when the Unit 1109 power license was issued.

The report presents the pnonty rankings for generic safety the $;aff's assessment regarding the application by the licensee msues related to nuclear power plants. The purpos6 of these to operate Unit 2, and the issues that require resolution before rankings is to assist in the timely and efficient allocation of NRC issuance of an operating license for Unit 2 resources for the reso!ution of those safety issues that have a sigmficant potential for reducing nsk. The safety pncity rankings NUREG-0991 S08: SAFETY EVALUATION REPORT RELATED are HIGH, MEDIUM LOW, and DROP and have been assigned TO THE OPERATION OF LIMERICK GENERATING on the basis of nsk significance estimateis, the ratio of nsk to STATION, UNITS 1 AND 2. Docket Nos. 50-352 And 50-costs and other impacts estimated to result if resolutions of the 353(Philadelphia Electnc Company) ' Division of Reactor safety issues were implemented, and the consideration of un. Projects - Ull (Post 870411). June 1989. 76pp. 8907060264.

certainties and other quantitative or quahtative factors % the 50534 207.

extent pr ic%af, estimates are quantitative. In August 1983 the staff of the Nuclear Regulatory Commis-sion issued its Safety Evaluation Report (NUREG 0091) regard-NUREG-0936 V08 N01: NRC REGULATORY AGENDAOuarterly ing the application of the Philadelphia Electric Company (the li-Report. January-March 1989.

• Division of Freedom of informa- consee) for the licenses to operate the Limenck Generating tion & Publications Services (Post 890205). May 1989.123pp Station, Units 1 and 2, located on a site in Montgomery and 8905220131. 49830:010. Chester Counties, Pennsylvania Supplement 1 was issued in The NRC Regulatory Agenda is a compilation of all rules on December 1983. Supplement 2 was issued in October 1984.

which the NRC has proposed or is considenng action and e Supplement 3 was issued in October 1984 Supplement 4 was petitions for rulemaking which have been received by the Com- issued in May 1985. Supplement 5 was issued in July 1985.

rnission and are pending disposition by the Commission. The Supplement 6 was essued in August 1985 and Supplement 7 Regulatory Agenda is updated and issued each quarter. was issued in April 1989. Supplement 7 addresses the major NUREG 0940 V08 NO1: ENFORCEMENT ACTIONS SIGNIFICANT DOS'gn differences between Units 1 and 2. the resolution of all ACTIONS RESOLVED.Ouarterly Progress Report. January-March issues that remained operi when the Unit i full- power license 1989.

• Ofc of Enforcement (Post 870413). June 1989. 428pp. was issued, the staff's assessment regarding the application by 8906260379. 50283.329. the hcensee to operate Unit 2 and sssues that require resolution This compilation summanzes significant enforcerrnt actions before issuance of an operating heense for Unit 2. This Supple-that have been reselved dunng one quarterly penoo , January . ment 8 addresses further issues that require resolution pnor to March 1969) and includes copies of Ictters. Notces. and Orders issuance of an operating license.

sent by the Nuclear Regulatory Commission to heensees with respect to these et forcement actions. Also included are a NUREG 1125 V10: A COMPILATION OF REPORTS OF THE number of erdorcement actions that had been previously re.. ADIVSORY COMMITTEE ON REACTOR SAFEGUARDS.1988 solved but not pubhshed in tNs NUREG It is anticipated that Annual.

• ACRS - Advisory Committee on Reactor Safeguards.

the information in this pubhcation will be widely disseminated to Apnl 1989.159pp 8905110339. 49720 065.

managers and employees engaged in activities licensed by the This compilation contains 47 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 dunng ing future violations similar to those descnbod in this pubhca. calendar year 1988 lt also includes a report to the Congress on tion, the NRC Safety Research Program. All reports have been made avadable to the pubhc through the NRC Pubhc Document Room NUREG-0975 V07: COMP! ON OF CONTRACT RESEARCH and the U S. Library of Congress The reports are divided into FOR THE MATERIALS ENGINEERalG BRANCH. DIVISION OF two groups: Part 1. ACRS Reports on Project Reviews, and Part ENGINEERING. Annual Report For FY 1988.

• Division of Engi- 2: ACRS Reports on Genenc Subjects. Part 1 contains ACRS neenng (Post 870413). May 1989. 364pp. 8900020086. reports alphabet: red by project name and witnin protect name 49992.318. by chronological order. Part 2 categonzes the reports by the This report presents summanes of the research work per- most appropnate genenc subject area and within subject area forned dunng Fiscal Year 1988 by laboratones and organiza- by chronological order.

tions under contracts administered t'y the NRC's Matenals Engo noenng Branch. Oftace of Nuclear Regulatory Research Each NUREG-1145 V05: U S. NUCLEAR REGULATORY COMMISSION contractor has wntten a more complete and detailed anr;ual 1968 ANNUAL PEPORT.

• Office of Administration (Post report of its work which can be obtained by writing to NRC; 890205) June 1989 254pp. 8907050501. 50355:306 i - . _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _

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4 Main Cit;ti;ns e id Ab;tt2 cts This report covers the major activities, events, decisions, and NUREG-1275 V05: OPERATING EXPERIENCE FEEDBACK planning that took place dunng fiscal year 1988 within the U.S. REPORT - PROGRESS IN SCRAM REDUCTION. Commercial Nuclear Regulatory Commission (NRC) or involving the NRC. Power Reactors. BELL L.G.; O'REILLY,P.D. Division of Safety Programs (Post 870413). March 1989. 299pp. 8905100222.

NUREG-1174: EVALUATION OF SYSTEMS INTERACTIONS IN NUCLEAR POWER PLANTS. Technical Findings Related To

• Unresolved Safety issue A 17. THATCHER.D. Division of Safety Thi oport documents the results of a trends and patterns Issue Resolution (Post 880717). May 1989. 48pp. 8906120193^ analysis of unplanned reactor scrams at commercial U.S. nucle-ar power reactors from 1984- 87. Major objectives of this report This report presents a summary of the activities related to prepared by the Nuclear Regulatory Commission's (NRC's)

Unresolved Safety issue (USI) A-17. " Systems Interactions in Office for Analysis and Evaluation of Operational Data (AEOD)

Nuclear Power Plants," and also includes the NRC staff's con- are to (1) provide feedback of operational expenence regarding clusions based on those activities. The staff's technical findings reactor scram trends in support of the Commission's Strategic provide the framework for the final resolution of this unresolved Goals, (2) examine the causes of unplanned scrams, and (3) safety issue. The final resolubon will be published later as exam ne the relationship between the causes of unplanned NUREG 1229. scrams and industry initiatives undertaken to reduce the fre-quency of unplanned scrams, especially with a view to the po-NUREG-1232 VD3: SAFETY EVALUATION REPORT ON TEN- tential for future scram rate reduction.

NESSEE VALLEY AUTHORITY: BROWNS FERRY NUCLEAR PERFORMANCE PLAN. Browns Ferry Unit 2 Restart. NUREG-1312: SAFETY EVALUATION REPORT RELATED TO MORAN.D H. TVA Projects Division. April 1989. 86pp. THE RENEWAL OF THE FACILITY LICENSE FOR THE RE-8905100280. 49664:001. SEARCH REACTOR AT THE DOW CHEMICAL COMPANY.

• This safety evaluation report (SER) on the information submit _ Standardcation & Non-Power Reactor Project Directorate. April ted by the Tennessee Valley Authonty (TVA) :n its Nuclear Per- 1989. 79pp. 8905170118. 49763:047.

formance Plan, through Revision 2, for the Browns Ferry Nucle- This Safety Evaluation Report for the application filed by the er Power Plant and in supporting documents has been prepared Dow Chemical Company for renewal of Facility Operating Li.

by the U.S. Nuclear Regulatory Commission staff. The plan ad_ cense R-108 to continue to operate its research reactor at an dressed the plant. specific concerns requiring resolution before increased operating power level has been prepared by the startup of Unit 2. The staff wili anspect implementation of those Office of Nuclear Reactor Regulation of the U.S. Nuclear Regu-programs. Where systems are common to Units 1 and 2 or to latory Commission. The facility is located on the grounds of the Units 2 and 3, the staff safety evaluations of those systems are Michigan Division of the Dow Chemical Company in Midland, included herein. Future supplements to this SER will address Michigan. The staff concludes that the Dow Chemical Company open issues identifeed in Chapter 1. can continue to operate its reactor without endangenng the health and safety of the public.

NUREG-1251 V01: IMPLICATIONS OF THE ACCIDENT AT CHER.

NOBYL FOR SAFETY REGULATION OF COMMERCIAL NU- NUREG-1331: TECHNICAL SPECIFICATIONS FOR SEABROOK CLEAR POWER PLANTS IN THE UNITED STATES. Final STATION, UNIT 1. Appendix "A" To License No. NPF-Report. Main Report.

• NRC No Detailed Affikation Given. April 67. Docket No. 50-443.(Pubhc Service Company Of New Hamp-1989.106f r. 8905110300. 49727.025. shire)

• Division of Reactor Projects - t/11 (Post 870411). May This report was prepcred by the Nuclear Regulatory Commis. 1989. 417pp. 8906230135. 50238.298.

sian (NRC) staff to assess the implications of the accident at The Seabrook Station, Unit 1 Technical Specifications were the Chernobyl nuclear power plant as they relate to reactor prepared by the U.S. Nuclear Regulatory Commission to set safety regulation for commercial nuclear power plants in the forth the hmits, operating conditions, and other requirements ap-United States. The facts used in this assessment have been plicable to a nuclear reactor facihty as set forth in Section 50.36 d awn from the U.S. fact-finding report (NUREG-1250) and its of 10 CFR Part 50 for the protection of the health and safety of sources The report consists of two volumes: Volume 1 Main the pubhc.

Report and V'>lume 11, Appendix - Pubhc Comments and Their Disposition. NUREG-1341: REGULATORY ANALYSIS FOR THE RESOLU-TION OF GENERIC ISSUE 115. ENHANCEMENT OF THE RE-NUREG-1251 Vil: IMPLICATIONS OF THE ACCIDENT AT CHER- LIABILITY OF THE WESTINGHOUSE SOLID STATE PROTEC-NOBYL FOR SAFETY REGULATION OF COMMERCIAL NU. TION SYSTEM. BASDEKAS,0.L. Division of Safety issue Reso-CLEAR POWER PLANTS IN THE UNITED STATES Final lution (Post 880717). May 1989. 26pp. 8906230143. 50245:121.

Report. Appendix - Pubhc Comments And Their Disposition.

• Generic issue 115 addresses a concern related to the rehabil-NRC - No Detailed Affiliation Given. April 1989. 144pp. ity of the Westinghouse reactor protection system for piants 8905110273.49726:241. using the Westinghouse Sohd State Protec$on System (SSPS).

See NUREG-1251,V01 abstract. Several options for improving the reliability of the Westinghouse NUREG-1266 VD3: NRC SAFETY RESEARCH IN SUPPORT OF * "

REGULATION - 1988.

• Office of Nuclear Regulatory Research' Director (Post 860720). May 1989. 49pp. 8905260187- * * * ** " *

• costs and benefits associated with the vanous options for en-Ths rt, the fourth in a senes of annual reports, was pre- " "O "O pared in response to congressional inquines concerning how #

nuclear regulatory research is used. It summanzes the accom.

phshments of the Office of Nuclear Regulatory Research dunng NUREG-1342: A STATUS REPORT REGARDING INDUSTRY IM-1988. The goal of this office is to ensure that safety-related re- PLEMENTATION OF SAFETY PARAMETER DISPLAY SYS-search provides the technical bases for rulemaking and for re. TEMS. LAPINSKY,G.W.; ECKENRODE,R.J.; GOODMAN.P.C.; et late,d decisions in support of NRC heensing and inspection ac- al. Division of Licensee Performance & Ouakty Evaluation (Post tivities. This research is necessary to make certain that the reg- 870411). April 1989. 44pp. 8905100248. 49666197.

ulations that are imposed on hcensees provide an adequate This report provides a summary of the results of the U S. Nu-margin of safety so as to protect the health and safety of the clear Regulatory Commission staff's review of installed safety pubhc. This report desenber both the direct contnbutions to sci- parameter display systems (SPDS) at 57 nuclear units. The staff entific and technical knowieflo with regard to nuclear safety desenbes its rationale 87d practice for determining acceptabikty and their regulatory apphcations of some of the methods for satisfying the vanous requirements

l Miln Citations and Abstrtets 5 for SPDS as well as some methods that the staff has not ac- of this study did not indicate a safety concern relating to the cepted. The staff's discussion of identified strengths and weak- use of mismarked or counterfeit fasteners in the nuclear indus-nesses should aid licensees in solving some of the problems try, but 15ey did indicate a nonconformance rate of 8 to 12 per-they may be exponenc;ng with their SPDS. cent for fasteners. The NRC staff is considenng taking action to improve the effectiveness of receipt inspection and testing pro.

NUREG 1344: EROSf0N/ CORROSION-INDUCED PIPE WALL grams for all materials at nuclear power plants.

THINNING IN U.S. NUCLEAR POWER PLANTS. WU.P.C. Divi-

" " I 8 AP NUREG 1353: REGULATORY ANALYSIS FOR THE RESOLU-f989 8 p 890 300 49 5 - TION OF GENERIC ISSUE 82, "BEYOND DESIGN BASIS AC-Erosion / corrosion in single-phase piping systems was not CIDENTS IN SPENT FUEL POOLS." THROM.E.D. Division of clearly recognized as a potential safety issue before the pipe Safety issue Resolution (Post 880717). April 1989. 115pp.

rupture incident at the Surry Power Station in December 1986. 8906020075. 49994:034.

This incident reminded the nuclear industry and the regulators Genenc issue 82, "Beyond Design Basis Accidents in Spent that neither the U.S. Nuclear Regulatory Commission (NRC) nor Fuel Pools," addresses the concerns with the use of high densi-the American Society of Mechanical Engineers (ASME) Section ty storage racks for the storage of spent fuel, and is applicable XI Boiler and Pressure Vessel Code require utilities to mo itor to all Light Water Reactor spent fuel pouls. This report presents erosion / corrosion in the secondary systema of nuclear po ter the regulatory ana!ysts for Genene issue 82. It includes (1) a plants. This report provides a ,bnef review of the erosion /coi_." summary of the issue (2) a summary of the technical findings, ston phenomenon and its major occurrences in nuclear power (3) the proposed technical resolution, (4) alternative resolutions plants. In addition, efforts by the NRC, the industry, and the considered by the Nuclear Regulatory Commission, (5) an as-ASME Section XI Committee to address this issue are de- sessment of the benefits and cost of the attematives consid-senbed. Finally, results of the survey and plant audits conducted ered, (6) the decision rationale, and (7) the relationships be-by the NRC to assess the extent of erosion / corrosion-induced tween Generic issue 82 and other NRC programs and require-pipir,g degradation and the status of program implementation re- ments. Based on this evaluation, the NRC staff concludes that garding erosion / corrosion monitoring are discussed. This report no new regulatory requirements are warranted concerning the will support a staff recommendation for an additional regulatory use of high density storage racks.

requirement concerning erosion / corrosion monitonng NUREG-1348: REPORT ON THE VISIT OF U.S. NUCLEAR NUREG-1354: FITNESS FOR DUTY IN THE NUCLEAR POWER SAFETY DELEGATION TO THE SOVIET UNION, AUGUST 19- INDUSTRY: RESPONSES TO PUBLIC COMMENTS. BUSH.L.L.;

31,1988. SHEA.J.R. International Programs. March 1989. 7pp. GRIMES.B K. Division of Reactor inspection & Safeguards (Post 870411) May 1989. 265pp. 8906260271. 50279.131.

8904250162. 49532.133.

Du'nng August 1988 a U.S. delegatron of nuclear reactor The Nuclear Regulatory Commission published for public safety specialists, led by U.S. Nuclear Regulatory Commission comment a proposed rule conceming the fitness for duty of Chairman Lando W. Zech, Jr., visited the Soviet Union to initiate commercial nuclear power plant workers (53 FR 36795). The cooperative activities in civihan nuclear reacDr safety between proposed rule focused on methods for controlkng the use of the two countnes under their April 1988 Memorandum of Coop. substances that may affect the trustworthiness and perform-eration. Areas of future cooperation and a schedule of working ance of workers. It provides for chemical testing, behavioral ob-group meetings to explore these areas were defined in a proto- servation, employee awareness and education, and employee col signed dunng this visit. The delegation met with Soviet rep. assistance programs as means for assunng fitness for duty.

reson'atives in Moscow as the Joint Coordinatif :, Committee on This report summanzes the comments received on the pro-Civihan Nuclear Reactor Safety. Additionally, b me in Moscow, posed rule and provides the staff resolutions of the issues Chairman Zech held discussions with leaders and other senior raised by the comments.

officials of Soviet organizations with responsibility for nuciear power safety. Nuclear facilities were also visited, including the NUREG-1357: TECHNICAL SPECIFICATIONS FOR SHOREHAM NUCLEAR POWER STATION, UNfT 1, Docket No. 50-322.(Long Kurchatov Institute of Atomic Energy (Moscow), the Novovoron.

ezh Atomic Power Station, the Novovoronezh Training and Island Lighting Company)

• Division of Reactor Projects - l/l!

(Post 870411). April 1989. 494pp. 8905110307. 49721:076.

Commissioning Center, the Izhora Heavy Equipment Production The Shoreham. Unit 1 Technical Specifications were pro-Plant (Kolpino), the V. G. Khlopin Radium Institute (Gatchina),

pared by the U S. Nuclear Regulatory Commission lo set forth the Chernobyl Atomic Power Station, the All-Union Center for the limits, operating conditions, and other requirements applica-Radiation Medicine (Kiev). and the Rovno Atomic Power Sta. ble to a nuclear reactor facility as set forth in Section 50.36 of tion.

10 CFR Part 50 for the protection of the health and safety of NUREG-1349: COMPILATION OF FASTENER TESTING DATA the pubhc.

RECEIVED IN hESPONSE TO NRC COMPLIANCE BULLETIN 87-02. CWALINA G.C4 CONWAY,J T.; PARKER.L.B. Division of NUREG-1358: LESSONS LEARNED FROM THE SPECIAL IN-Reactor inspection & Safeguards (Post 870411). June 1980. SPECTION PROGRAM FOR EMERGENCY OPERATING 115pp. 890626036B IEB-87 002. 50280:076. PROCEDURES. Conducted March-October 1988. LAPINSKY,G.

On November 6,1987, the Nuclear Regulatory Commission Division of Licensee Performance & Quahty Evaluation (Post (NRC) issued Bulletin 87-02, " Fastener Testing to Determine 870411). April 1989. 30pp. 8905110267. 49726209.

Conformance With Applicable Matenal Specifications," to all The results of the team inspections conducted dunng 1988 holders of operating hcenses or construction permits for nuclear for the Nuclear Regulatory Commission (NRC) Emergency Op.

power reactors (hcensees). The bulletin was issued so that NRC erating Procedures (EOPs) Inspection Program are surnmarized staff could gather data to determine whether Counterfeit fasten- in this report. Inspection results are discussed in relation to past ers are a problem in the nuclear power industry. The bulletin re- staff guidance provided to the utihties for upgrading EOPs. In quested nuclear power plant owners to determine whethsir fas- this report the NRC informs the nuclear power industry of con-teners obtained from suppliers and/or manufacturers for use in cerns that were identified dunng the EOP team inspections and their facilities meet the mechanical and chemical Specifications restates the staff's previous guidance in a format that more stipulated in the procurement documents. The hcensees were clearly illustrates the consequences of programmatic weakness-requested to sample a minimum of 10 safety-related and 10 es. The information contained in this report is provided so that non- safety related fasteners (studs, bolts, and/or cap screws) hcensees may take advantage of the lessor.3 leamed from the and a sample of typical nuts that would be used with each fas- EOP inspection effort This report does not impose any new re-tener and to report the testing results to the NRC. The results quirements related to the upgrading of EOPs l

6 Main Citat.ons and Abstracts NUREG 1360: TECHNICAL SPECIFICATIONS FOR LIMERICK NUREG/CP-0098 V01: PROCEEDINGS OF THE 20TH DOE /NAC GENERATING STATION, UNIT 2. Docket No. 50-383.(Philadel- NUCLEAR AIR CLEANING CONFERENCE. Sections 1 - 5. Held phia Electnc Company)

• Division of Reactor Proj. cts - 1/11 in Boston, Massachusetts, August 22 25, 1988. FIRST.M.W.

(Post 870411). June 1989. 600pp. 8907100312. SC49) .089. Harvard School of Public Health, Boston, MA. May 1989.652pp.

The Limenck, Unit 2, Technical Specifications were prepared 8906230087. CONF-880822. 50241:086.

by the U S. Nuclear Regulatory Commission to set the limits. This document contains the papers and ttle associated dis-operating conditions, and other requirements applicable to a nu- cussions of the 20th DOE /NRC Nuclear Air Cleaning Confor-clear reactor facility as bet forth in Section 50.36 of 10 CFR ence. Major topics are (1) chemical processing systems, (2) re-Part 50 for the protection of the health and safety of the public- actor operations, (3) decommissioning and decontamination (e)

NUREG-1363 V01: ATOMIC SAFETY AND LICENSING BOARD particulate filter developments, including filter testing and filter PANEL ANNUAL REPORT FOR FISCAL YEAR 1988.

• Atomic response to physical stress, (5) adsorption and testing of acti-Safety and Latensing Board Panel. March 1989. 62pp. vated carbon and adsorber systems. (6) severe accident mitiga-8905120177.49735:220. tion, (7) radon, (8) tntium, (9) monitor ng and measurement sys-This is the fiscal year 1988 annual report of the Atomic Safety tems, (10) the development of standards and regulations, and and Licensing Board Panel in response to further reductions in (11) concerns with existing standards and regulations.

its authonzed staffing level and with an eye toward the pro-pcsed full text, electronic docket of the expected High-Level NUREG/CP-0098 V02: PROCEEDINGS OF THE 20TH DOE /NRC Waste Repository proceeding, the Panel stepped up efforts NUCLEAR AIR CLEANING CONFERENCE. Sessions 6 - 15. Held dunng FY 1988 to extend the sccpe, depth and availability of its in Boston, Massachusetts, August 22 25, 1988. FIRST,M.W.

Computer Assistance Project (CAP) through INOUIRE. IN_ Harvard Schoot of Public Health. Boston, MA May 1989.712pp.

QUIRE, and the Panefs ability to use the system to expeditious. 8906230091. CONF-880822. 50243:018.

ly manage and search the massive records that charactenze See NUREG/CP-0098,V01 abstract.

our most complex casek has generated great interest among legal practitioners and adjudicatory bodies throughout the NUREG/CP-0098 V03: PROCEEDINGS OF THE 20TH DOE /GC United States and Canada. NUCLEAR AIR CLEANING CONFERENCES Index To The 1st Through 20th AEC/ERDA/ DOE And DOE /NRC Nuclear Air NUREG/CP-0097 V01: PROCEEDINGS OF THE SIXTEENTH Cleaning Conferences. JENNINGS,S.D. Oak Ridge National WATER REACTOR SAFETY INFORMATION MEETING. Laboratory. May 1989. 445pp. 8906230081. CONF-880822.

WEISS.A.J. Brookhaven National Laboratory.

• Office of Nucle. 50240:001.

at Regulatory Research, Director (Post 860720). March 1989.

This document contains a cumulative index to the first Th s five vo u e epor ont ins 141 papers out of the 175 Cleaning Conferences and in'corporates corrections of errors that were presented at the Sixteenth Water Reactor Safety in-appeanng in prior intermediate indexes.

formation Meeting held at the National institute of Standards and Technology, Gaithersburg, Maryland, dunng the week of NUREG/CP-0100: PROCEEDINGS OF THE INTERNATIONAL October 2S27,1988. The papers are pnnted in the order of NUCLEAR POWER AGING SYMPOSIUM.

PLANT their presentahon in each session and describe progress and BERANEK,A.F. Office of Nuclear Regulatory Research, Director sesults of programs in nuclear safety research cc nducted in this (Post t>60720). March 1989. 396pp. 8905100270. 49662;144.

country and abroad. Foreign participation in the meeting includ.

ed twenty different papers presented by researchers from Ger. This report presents the proceedings of the Intemational Nu-many, Italy, Japan, Sweden, Switzerland, Tarwan and the United clear Power Plant Aging Symposium that was held at the Hyatt Kingdom. The %s of the papers and the names of the authors Regency Hotel in Bethesda, Maryland, on August 30 31 and ha b ed and may d er from those that appeared in Se tember 1,1988. The Symposium was presented in coopera-tion with the Amencan Nuclear Society, the Amencan Society of l Civil Engineers. the Amencan Society of Mechanical Engineers, 1

NUREG/CP-0097 V02: PROCEEDINGS OF THE SIXTEENTH and the institute of Electronics Engineers. There were approxi-WATER REACTOR SAFETY INFORMATION MEETING. matefy 550 participants from 16 countries at the Symposium.

WEISS A.J. Brookhaven National Laboratory.

• Office of Nucle-at Regulatory Research, Director (Post 860720). March 1989. NUREG/CP-0101: PROCEEDINGS OF THE WORKSHOP ON 398pp. 8904250107. 49460:233. ROLES FOR EXEMPTION FROM REGULATORY CONTROL.

• See NUREG/CP-0097,V01 abstract. Oak Ridge Associated Univs. April 1989. 312pp. 8905110326.

NUREG/CP-0097 V03: PROCEEDINGS OF THE SIXTEENTH This conference report documents the proceedings of an WATER REACTOR SAFETY INFORMATION MEETING '" " "*' * "

WEISS A.J. Brookhaven National Laboratory.

• Office of Nucle- 0*

or Regulatory Research, Director (Post 860720). March 1989 s urces and practices from regulatory control. The purpose of 562pp. 8904250110. 49455193. See NUREG/CP-0097,V01 ab the workshop was to provide national regulatory authorities an stract. opportunity to exchange information on their respective ap-proaches and practices involving exemptions and to enhance NUREG/CP-0097 V04: PROCEEDINGS OF THE SIXTEENTH international understanding and cooperation on the derivation WATER REACTOR SAFETY INFORMATION MEETING. and practical application of the undertying principles. In addition, WEISS,A.J. Brookhaven National Laboratory.

• Office of Nucle. Input from the workshop was intended to assist the NRC in the ar Regulatory Research, Director (Post 660720L March 1989. development of a policy statement on this issue. The workshop 610pp. 8904250118. 49458:237. See NUREG/CP-0097,V01 ab, was divided into five sessions. During the first four sessions, stract. papers were presented which defined the relative terms and concepts. outlined the national situations and approaches to the NUREG/CP-0097 V05: PROCEEDINGS OF THE SIXTEENTH establishment and development of exemption rules, identified WAT ER REACTOR SAFETY INFORMATION MEETING. and discussed the existing issues, and gave the status of the WEISS,A J Bros khaven National Laboratory.

• Office of Nucto- International guidelines on exemption rules. The fifth session ar Regulatory Rt Tearch. Director (Post 860720). March 1989. was devoted to summanzang the workshop and identifying the 576pp. 8905100262. 49668.229 areas consensus, the outstanding issues and the areas for See NUREG/CP-0097.V01 abstract future work.

Miln Citstlans cnd AbitrCCts 7 NUREG/CR 2000 V08 N2: LICENSEE EVENT REPORT (LER) NUREG/CR-3950 V05: FUEL PERFORMANCE ANNUAL COMPILATION For Month Of February 1989.

• Oak Ridge Na- REPORT FOR 1987. BAILEY,W.J. Battelle Memonal Institute, tional Laboratory. March 1989.166pp. 8904250168. ORNL/ Pacific Northwest Laboratory. WU.S. NRC - No Detailed Affili-NSIC 200. 49462:062. ation Given. March 1989. 152pp. 8904240303. PNL 5210.

This monthly report contains Licensee Event Report (LER) 49440:128.

operational information tnat was processed into the LER data This annual report, the tenth in a series, provides a brief de-file of the Nuclear Safety information Center (NSIC) during the scription of fuel performance dunng 1987 in commercial nuclear one month period identified on the cover of the document. The power plants. Brief summanes of fuel design changes, fuel sur- {

LERs, from which this information is derived, are submitted to veillance programs, fuel operating experience and trends, fuel the Nuclear Regulatory Commission (NRC) by nuclear power problems, high burnup fuel experience, and items of general sig-plant licensees in accordance with federal regulations. Proce, nific.ance are provided. References to additional, more detailed dures for LER reporting for revisions to those events occurnng information and related NRC evaluations are included.

pnor to 1984 are desenbed in NRC Regulatory Guide 1.16 and NUREG-1061, ' Instructions for Preparation of Data Entry NUREG/CR-3964 V01: TECHNIOUES FOR DETERMINING Sheets for Licensee Event Reports. For those events occumng PROBABILITIES OF EVENTS AND PROCESSES AFFECTING on and aftar January 1,1984. LER are being submitted in ac- THE PERFORMANCE OF GEOLOGIC REPOSITORIES. Literature Review. HUNTER R L. Sandia Na-cordance with the revised rule contained in Title 10 Part 50.73 tional Laboratories. MANN,C.J. filinois. Univ. of. Urbana, IL.

of the Code of Federal Regulations (10 CFR 50.73 - Licensee June 1989.186pp. 8907050519. SAND 86-0196. 50354:071.

Event Report System) which was published in the Federal Reg-ister (Vol. 48, No.144) on July 26,1983. NUREG-1022, Li- The U.S. Environmental Protection Agency (EPA) has set a probabilistic standard for the performance of geologic repositor-censee Event Report System - Desenption of Systems and ies for the disposal of radioactive waste. The EPA has not sug-Guidelines for Reporting, provides supporting guidance and in-gested ways to determine probabilities of events and processes formation on the revised LER rule. The LER summanes in this of interest in implementing such a standard, but Appendix B of report are uranged alphabetically by facility name and then the standard states that numencal ard analytical methods and chronologically by event date for each facility. Component' expert judgment are probably all acceptable. This report treats system, keyword, and compongnt vendor indexes follow the not only geologic events and processes like fault movement, summanes. Vendors are those sdentified by the utility when the but also events and processes that anse from the relationship LER form is initiated, the keywords for the component, system, between human actions and geology, like drilling for resources, and general keyword indexes are assigned by the computer and snme that anse from nongoologic processes that in turn using correlation tables from the Sequence Coding and Search affect a geologic process, like climatic change. It reviews the lit-System, erature in several fields to determine whether existing probabi-listic methods for predicting events and processes are adequate NUREG/CR-2000 V08 N3: LICENSEE EVENT REPORT (LER) f r implementation of the standard. Techniques exist for qualita-COMPILATION:For Month Of March 1989

• Oak Ridge Nation-tively estimating the potential for endowment of portions of al Laboratory. Apnl 1989.143pp. 8905110335. ORNL/NSIC- Earth's crust with mineral resources, but such techniques 200. 49720:224. cannot easily predict whether or not human intrusion will occur.

See NUREG/CR-2000,V08,N02 abstract.

The EPA standard offers explicit guidance for the treatment of uman intrusion, however. A complete method of climatic pre-NUREG/CR-2000 V08 N4: LICENSEE EVENT REPORT (LER) " " * "* " ** "

"O COMPILATION.For Month Of April 1989.

• Oak Ridge National such a combination had not been tested. Existing techniques to Laboratory. May 1989.189pp. 8906120097. ORNLINSIC-200.

support a probabilistic assessment of tectonic activity and seis-50*11:074.

mic hazard at a repository site should be combined with expert See NUREG/CR 2000,V08,N02 abstract-judgment in performance assessments. Depending on the re-gi nal setting, either analytic techniques or expert judgment NUREG/CR 2000 V08 N5: LICENSEE EVENT REPORT (LER) may be appropnate in assigning probabilities to volcanic activity.

COMPILATION.For Month Of May 1989.

• Oak Ridge National Laboratory. June 1989.139pp. 8907070115. ORNL/NSIC-200. NUREG/CR-4082 V07: DEGRADED PIPING PROGRAM - PHASE 50409:257. II. Seventh Program Report. October 1987 - January 1989.

See NUREG/CR-2000,V08,N02 abstract. WILKOWSKI,G.M.; GUERRIERI,D.; JONES D.; et al. Battelle Memonal Institute, Columbus Laboratories. March 1989.123pp.

, NUREG/CR-3469 V04: OCCUPATIONAL DOSE REDUCTION AT 8904250135. BMi 2120 49454:200.

I NUCLEAR POWER PLANTS: ANNOTATED BIBLIOGRAPHY Presented herein is the last progress report of the U S. Nucle-OF SELECTED READINGS IN RADIATION PROTECTION AND ar Regulatory Commission's Degraded Piping Program Phase ALARA. KHAN,T.A.: BAUM.J.W. Brookhaven National Laborato- Il This report gives details of the pipe fracture expenments con-ry. June 1989. 123pp. B906260416. BNL-NUREG-51708 ducted dunng the last year of the program. The program started 50283:053 in March 1984 and ended in January 1989. The intent of this This report is the fourth in the senes of bibliographies sup- program is to expenmentally validate and enhance available an-porting the efforts at the Brookhaven National Laboratory on afytical methods for evaluating the mechanical behavior of nu-dose reduction at nuclear power plants. Abstracts for this bibli- clear power plant piping containing circumferentially onented ography were selected from proceedings of technical meetings, defects. Sixty-one pipe expenments have been conducted.

journals, research reports and searches of the DOE's Energy These and approximately fifty additional pipe expenments from Data Base. The abstracts included in this report relate to oper- other programs have been analyzed The final report of this pro-ational health physics as well as other subjects which have a gram is being published concurrently as Volume 8. That report beanng on dose reduction at nuclear power plants, such as summann s the technical efforts dunng the course of this pro-stress corrosion cracking. plant chemistry, use of rot'otics and gram, discusses the significance of these results to LBB frac-remote devices. etc. Matenal on improved design, matenals Be- ture analyses and in-service flaw acceptance entena, and de-lection, planrung and other topics which are related to dose re- scribes future needs for piping integnty research. This report duction efforts are also included The report contains 327 ab- gives more details of pipe fracture expenments conducted stracts as well as subject and author indices. dunng the last year.

8 Main Citations and Abstracts The Heavy-Section Steel Technology (HSST) Program is an NUREG/CR-4082 V08: DEGRADED PIPING PROGRAM - PHASE ll. Summary Of Technical Results And Their Significance To engineering research activity conducted by the Oak Ridge Na-And in-Service Flaw Acceptance tional Laboratory for the Nuclear Regulatory Commission. The Leak-Before-Break Cntena, March 1904 - January 1989. WILKOWSKI,G.M.; Program compnses studies related to all areas of the technolo-AHMAD,J.; BARNES,C.R.; et al. Battelle Memonal Institute, Co- gy of materials fabricated into thick-section pnmary- coolant lumbus Laboratones. March 1989.129pp. 8904250193. BMI- containment systems of light-water cooled nuclear power reac-2120.49455:064, tors. The investigation focuses on the behavior and structural This document is the Fir'el Report of the U.S. NRC's Degrad- integrity of steel pressure vessels containing cracklike flaws.

ed Piping Program - Phase ll. The intent of this program is to Current work is organind into twelve tasks: (1) program man-expenmentally validate and enhance available analytical meth- agement, (2) fracture methodology and analysis, (3) matenal ods for evaluating the mechanical behavior of nuclear power characterization and properties, (4) special technical assistance, plant piping containing circumferentially onented defects. This (5) crack-arrest technology, (6) irradiation effects studies, (7) document describes the resutts of the approach taken by Bat- cladding evaluations, (8) intermediate vessel tests and anafysis, telle to provide state of-the-art analysis methods to predict the (9) thermal- shock technology, (10) pressurized thermal-shock behavior of degraded piping operating at LWR conditions. Sec- technology, (11) Pressure Vessel Research Users' Facihty, and tion 1 gives a s':mmary of the scope of the program. Section 2 (12) shipping-cask matenal evaluations.

of this report st.Timanzes the technical efforts dunng the course of this program, discusses the material charactenzation efforts, NUREG/CR-4409 V03: DATA BASE ON DOSE REDUCTION RE-and desenbes the full-scale pipe fracture expenments and frac- SEARCH PROJECTS FOR NUCLEAR POWER PLANTS.

ture mechanics analyses conducted. Section 3 discusses the KHAN.T.A.; BAUM.J.W. Brookhaven National Laboratory. May significance of results to LBB and in-service flaw acceptance 1989,172pp.8906260380. BNL-NUREG-51934. 50281:290.

cntena, and examines the potential impact of charactenzation This is the third volume in a 6,eries of reports that provide in-evaluations and unusual fracture modes observed in nuclear formation on dose-reduction research and health physics tech-piping materials on evaluation procedures. Section 4 summa' nology for nuclear power plants. The information is taken from a rizes imphcations of the program findings and indicates areas data base maintained by Brookhaven National Laboratory's for future study in the area of piping integnty research- ALARA Center for the Nuclear Regulatory Commission. This report presents information on 80 new projects, covenng a wide NUREG/CR-4214 Pil R1: HEALTH EFFECTS MODELS FOR NU- area of activities. Projects on steam generator degradation, de-CLEAR POWER PLANT ACCIDENT CONSEQUENCE contamination, robotics, improvement in reactor matenals, and ANALYSIS Low LET Radiation.Part it: Scientific Esses For inspection techniques, among others, are described in the re-Health Effects Liodeils. ABRAHAMSON.S.: BENDER.M.; search section. The section of hoalth physics technology in-BOOK,S.; et al. Saldia National Laboratories. May 1989.350pp. cludes some simple and very cost-effective projects to reduce 8907050509. SAND 85 7185. 50353.114. radiation exposures. Collective dose data from the United This report provides dose-response models intended to be States and other countries are also presented. In the conclu-used in estimating the radiological health effects of nuclear sion, we suggest that although new advanced reactor design power plant accidents. Modeis of early and continuing effects, technology will eventually reduce radiation exposu:es at nuclear cancers and thyroid nodules, and genetic effects are provided. power plants to levels below senous concern, in the intenm an l

Two parameter Weibull hazard functions are recommended for aggressive approach to dose reduce remains necessary.

estimating the nsks of early and continuing health effects. Three potentially lethal early effects-the hematopoietic, puimonary NUREG/CR-4550 V02: ANALYSIS OF CORE DAMAGE FRE-and gastrointestinal syndromes-are considered. In addition, OUENCY FROM INTERNAL EVENTS: EXPERT JUDGMENT models are provided for assessing the nsks of several non- ELICITATION.Part 1: Expert Panel Results. Part 2. Project Staff lethal early and continuing effects-- including prodromal vomit- Results. WHEELER,T.A.; HORA.S C.; CRAMOND,W.R.; et al.

ing and diarrhea, hypothyroidisin and radiation thyroidit2, skin Sandia National Laboratories. April 1989. 539pp. 8905170065.

burns, reproductive effects, and spontaneous abortions. Linear SAND 86-2084. 49764:050.

and linear quadratic models are recommended for estimating Quantitative modeling techniquu have limitations as to the cancer risks Parameters are given for analyzing the nsks of resolution of important issues in probabihstic nsk assessment seven types of cancer in adults--leukemia, bone, lung, breast, (PRA). Not all issues can be resolved via the existing set of gastrointestinal, thyroid and "other". The category, "other" can- methods such as fault trees, event trees, statistical analyses, cers, is intended to reflect the combined nsks of multiple mye. data collection, and computer romutation. Therefore, an expert loma, lymphoma, and cancers of the bladder, kidney, brain, judgment process was developed to address issues perceived ovary, uterus and cervix. Models of childhood cancers due to in as important to nsk in the NUREG-1150 analysis but which utero exposure are also provided. For most cancers, both inci. could not be resolved with existing techniques. This process dence and mortality are addressed The models of cancer nsk was apphed to several issues that could significant!y affect the i

are denved largely from information summanred in BEIR fit with internal event core damage frequencies of tne NUREG/CR-l some adystment to reflect more recent studies. The effect of 4550 PRAs performed on six hght water reactors. Detailed de-l the revised dosimetry in Hiroshima and Nagasaki has not been senptions of these issues and the results of the expert judgment l considered. Linear and linear quadratic models are also recom. elciata am reported here, as well as an explanation of the I mended for assessing genetic nsks. Five classes of genetic dts, methodology used and the procedure followed in performing the I ease-dominant, x-linked, aneuploidy, unbalanced translocations overall ehcitation task. The process is time-consuming and ex-and multifactonal diseases--are considered in addition, the pensive. However, the results are very useful, and represent an impact of radiation induced gr netic damage on the incidence of improvement over the draft NUREG-1150 anatysis in the areas peri-implantation embryo losses is discussed. The uncertainty in of expert selection, ohcitation training. issue selection and pres.

l modeling radiological health nsks is addressed by providing entation, ehestation of judgment and aggregation of results. The central, upper, and lower estimates of all model parameters. results are presented in two parts. Part 1 documents the expert l Data are provided which should enable analysts to consider the l panel excitations, where the most important issues were pre-timing and seventy of each type of heafth risk. sented to a panel of experts convened from throughout the nu-NUREG/CR-4219 V05 N2: HEAV%SECTION STEEL TECHNOL- clear power risk assessment community. Part 2 documents the OGY PROGRAM Semiannual Progress Report For April-Sep- process by which the NUREG/CR-4550 project star f performed tember 1988. CORWIN.W.R. Oak RUge National Laboratory. expert judgment on other important issues, using the project March 1989. 89pp. 8905100259. ORNL/TM-9593. 49661:033. staff as panel members.

Main Citations and Abstracts 9 NUREG/CR-4675: IN-PILE OBSERVATION OF FUEL AND CLAD other scenarios were considered perturbations of the base RELOCATION DURING LMFBR CORE-DISRUPTIVE ACCl- case, and a few were studied in terms of changes with respect DENTS. WRIGHT,S.A.; SCHUMACHER,G.; HENKEL.P.R. to initial conditions. The potential impact of these scenanos on Sandia National Laboratones. April 1989. 72pp. 8905170092. the long-term performance of the disposal system was ascer-SAND 86-1416. 49763:337. tained through comparison with the base-case scenano or the The changes in reactivity resulting from the initial fuel and undisturbed initial conditions.

clad motions that occur dunng an unprotected loss-of-flow (ULOF) accident in LMFBRs strongly influence the accident's NUREG/CR-4929: THE EFFECTS OF VARIABLE AMPLITUDE course. To study these accident induced phenomena, a senes LOADING ON A 533-B STEEL IN HIGH-TEMPERATURE AIR of in-pile expenments using small bundles of pins (the Sandia AND F:EACTOR WATER ENVIRONMENTS CULLEN,W.H. Ma-Transient Axial Relocation (9 TAR) expenments) are being per- tenals Engineering Associates, Inc. BROEK.D. Fracture 5earch, formed. In these expenmenth ULOF accident cond,tions are Inc. April 1989.106pp. 8904250160. MEA 2213. 49460:127.

simu!ated, and the accident-induced ~. sad motion and fuel dis- This report describes the efforts to develop an analybcal persal are recorded using high- Speed photography. The major model for the prediction of fatigue crack growth under service-parameters varied in the series c,re power level, type of fuel simulated loading typical of power reactor loadings. Expenmen-(fresh versus preirradiated), and the number of pins. The results tally, the program has involved development of a data base of of the first four experiments are presented here. The observa- constant amplitude crack growth rate data and a data base of hons rnade in these expenments show that early fuel disruption crack extension data for tests conducted with simple overloads caused by fission products occurs in ULOF accidents and is fol-and underloads. The final expenmental phase was to conduct a lowed almost immediately by both fuel sweepout and axial clad series of service sirrvilation tests using the spectrum proposed relocation.

by the International Cyclic Crack Growth Rate Group. In concert NUREG/CR-4721: THE USE OF FIBER OPTICS FOR REMOTE with this expenmental work, an analytical model was developed, TEMPERATURE MEASUREMENT IN FISSION PRODUCT RE- incorporating capabilities for modeling the load acceleration and LEASE TESTS. WEBSTER.C.S.; OSBORNE.M F. Oak Ridge retardation effects which were expenmentally observed. The de.

National Laboratory. Apnl 1989. 28pp. 8995110259. ORNL/TM- velopment stages of this model are desenbed. The results of 10366.49726.019. the application of this model to the service simulation tests are  ;

A system for remote temperature measurement in a highly erttemely encouraging. Suggestions to assist in the continued hostile environmer.t was developed. Fiber-optic cables were improvement and venfication of the model are presented.

used to conduct light signals from a high temperature induction furnace inside a hot cell to automatic two-color pyrometers NUREG/CR-4934: CLOSEOUT OF lE BULLETIN 83 06.Noncon-mounted outside the cell. This system was cahbrated with forming Matenals Supphed By Tube-Line Corporation Facihties manually operated, disappeanng filaent optical r7 meters At Long Island City, New York; Houston, Texas; And Carol ,

and high temperature thermocouple. This technique has pro- Stream, flhnois. DEAN.R.S.; FOLEY.W.J.; HENNICK A. PARAM. i vided rehable temperature data in several fission product re- ETER, Inc. May 1989.36pp.8906260390. PARAMETER IE169.

lease tests of highly irradiated reactor fuel at temperatures up 50282;102.

to 2425 degrees R Compared to the previously used tempera- Documentation is provided in this report for the closeout of IE ture measuremer method, this technique afforded the abikty to Bulletin 83-06 regarding nonconformities of certain materials obtain more data f om a smaller investment of assembly time which were obtained directly or indirectly from the Tube-Line and hot cell space, and it also increased safety through a re- Corporation (T-L) for use in safety related systems. Closeout is duction in radiation hazard to personnel and instrumentation.

based on the implementation and venfication of four (4) re-NUREG/CR-4759: DEMONSTRATION OF A PERFORMANCE quered actions by hcensees and holders of construction permits ASSESSMENT METHODOLOGY FOR HIGH-LEVEL RADIDAC. of nuclear power reactors and nuclear fuel facilities. From eval-TiVE WASTE DISPOSAL IN BASALT FORMATIONS. uation of responses and NRC/ Region inspection reports, it is BONANO,E.J.; DAVIS P.A.; SHIPERS,L.R.; et al. Sandia Nation- concluded that the concerns of the bulletin have been resolved.

al Laboratones. June 1989.183pp. 8907070066. SAND 86-2325. The bulletin is closed for all of the 120 power reactor facihties 50409:032. and for both of the two nuclear fuel facihtees to which it was This document describes a performance assessment method- issued for action. Background information is supplied in the in-ology developed by Sandia National Laboratones Albuquerque troduction and Appendix A.

for the U.S. Nuclear Regulatory Commission for a high-level ra-dioactive waste repository mined in deep t;asalt formations. This NUREG/CR-4961: A

SUMMARY

OF HYDROGEN-AIR DETONA-methodology is an extension of an earher one apphcable to TlON EXPERIMENTS. GUIRAO.C.M.; KNYSTAG AS.R.;

bedded salt. The differences between the two methodologies LEE J.H.; et al. McGill Univ., Montreal, Canada May 1989.

anse pnmarily in the modehng of ground-water flow and radionu. 86pp. 8907060051. SAND 87-7128. 50357.037.

Clide transport. Bedded salt was assumed to be a porous Dynamic detonation parameters are reviewed for hydrogen-medium, whereas basalt formations contain tractured zones. air-diluent detonations and deflagration to-detonation transitions Therefore, mathematical models and associated computer (DDT) These parameters include the characteristic chemical codes were developed to simulate the aforementioned phenom- length scale, such as the detonation cell width, associated with ena in fractured media. The use of the methodog,gy is demon- the three-dimensional cellular structure of detonation waves, strated at a hypothetical basalt site by analyzing seven scenar- crrtical transmission conditions of confined detonations into un-ios: (1) thermohydrological effects caused by heat released confined environments, entical initiation energy for unconfined from the repository, (2) mechanohydrological effects Caused by detonations, detonability hmits, and entical conditions for DDT.

an advancing and receding glacier. (3) normal ground-water The detonation cell width, which depends on hydrogen and dilu-flow, (4) pumping of ground water from a confined aquifer, (5) ent concentrations, pressure, and temperature is an important rerouting of river near the repository, (6) drilhng of a borehole parameter in the prediction of entical geometry-dependent con-through the repository, and (7) formation of a new fault inter. ditions for the transmission of confined detonations into uncon-secting the repository. The normal ground-water flow was con- fined environments and the entical energies for the direct initi-sidered the base-case scenario. This scenano was used to per- ation of unconfined detonations. Detonability hmits depend on form uncertainty and sensitivity analyses and to demonstrate both initial and boundary conditions and the hmit has been de-the existing capabihties for assessing compliance with the fined as the onset of single head spin. Four flame propagation ground-water travel time entenon in 10 CFR Part 60 and the regimes have been identified and the critenn't for DDT in a containment requirements in 40 CFR Part 191. Most of the smooth tube is discussed

10 M in Cit ti:ns and Abstr: Cts NUREG/CR-4994: CORECONCRETE INTERACTIONS USING NUREG/CR-5089: NUMERICAL MODELING OF GROUND-l MOLTEN STEEL WITH ZlRCONIUM ON A BASALTIC WATER FLOW SYSTEMS IN THE VICINITY OF THE REFER.

BASEMAT.THE SURC-4 EXPERIMENT. COPUS.E.R.; ENCE REPOSITORY LOCATION HANFORD, WASHINGTON.

BROCKMANN.J E.; et al. Sandia National Laboratories. DAVIS,P-; BEYELER,W.; LOGSDON,M.; et al. Sandia National BLOSE.R.E. Ktech Corp April 1989. 326pp. 8905220178. Laboratories. April 1989. 283pp. 8905100244. SAND 88-0141.

SAND 87-2008, 40830:176. 49666.234.

An experiment was performed in order to evaluate the addi- This report documents south central Washington State's tional effects of zirconium metal oxidation 01 core debns inter- Pasco Basin ground-water modeling studies conducted by actions using molten stainless steel as the core debns simulant. Sandia National Laboratones for the U S. Nuclear Regulatory The SURC-4 experiment eroded a total of 25 cm of basaltic Commission (NRC) This work was done to support the NRC's concrete dunng 62 minutes of sustained interaction. The melt- review of hydrogeologic studies under the Department of Ener-pool temperatures during the test ranged from 1500 degrees C gy's (DOE) Basalt Waste Isolation Project. The report provides before zirconium addition to 1650 degrees C dunng the zirconi- a brief overview of the geology, hydrology,- and hydrochemistry um- steel concrete phase of the test which tasted 42 minutes. of the Pasco Basin as a basis for the evaluation ot' previous Large increases in erosion rate, gas production, and aerosot re- conceptual and numerical ground-water flow models of the lease were also measured shortly after Zr metal was added to region. Numencal models were developed to test new concep-the melt. The data return from the test was outstanding and tual models of the site and to provide a means of1 evaluating the these results were subsequently used as input to an OECD Department of Energy's performance assessments and pro-code companson exercise. posed hydrologic testing Regional ground- water flow modeling of an area larger than the Pasco Basin revealed that current NUREG/CR-5081: TACTICAL EXERCISE PLANNING HAND- concepts on the existence and behavior of a hydrologic bamer BOOK. TELFAIR,W.D.; MOUL,D.A.; KLINGELHOEFER; et al. west of the proposed repository location are inconsistent with Battelle Memonal Institute, Columbus Laboratories. April 1989. available data. This modeling also demonstrated that the meas-143pp. 8905100261 BMI-2162. 49667:157. ured pattern of hydraulic heads cannot be produced with a This handbook provides guidance for the development, con" model that (1) has uniform layer properties over the entire duct, evaluation, and critique of secunty force tactical response domain; (2) has zones of large conductivity associated with anti-exercises at Category I fuel facilities licensed by the U.S. Nucle- clinal structures; or (3) includes recharge from the irriustrial dis-ar Regulatory Commission. Background information pertinent to posal ponds. Adequate representation of the measured hydrau-the development of the handbook and the intent of rulemaking lac heads was obtained with a model that contained regions of that revises 10 CFR Part 73 to require tactical response exer- larger hydraulic conductivity that corresponded to the presence cises is provided Step by-step instructions on exercise develop- of sedimentary interbeds. In addition, a detailed model of a ment, conduct, evaluation, and critique are furnished to assist region smaller than the Pasco Basin was constructed to provide licensees in meeting regulatory requirements Needs and re- the NRC staff with the ability to analyze proposed Department source requirements estimates are addressed in terms of per- of Energy hydrologic tests.

sonnel, staff-hours, equipment, weapons, and ammunition. Ap-pendices provide examples of all documents required to plan, NUREG/CR-5118: LEAK AND STRUCTURAL TEST OF PERSON-conduct, entique, and evaluate the exercises. NEL AIRLOCK FOR LWR CONTAINMENTS SUBJECTED TO PRESSURES AND TEMPERATURES BEYOND DESIGN*

NUREG/CR-5087: STEAM GENERATOR GROUP PROJECT.Tash LIMITS. JULIEN.J.T.; PETERS.S W. CBI Research Corp 7 Final Report Post-Service Baseline Eddy Current Examination. Sandia National Laboratories. May 1989. 600pp. 8907070120.

DOCTOR,P.G.; BIRKS,A.S.; FERRIS,R.H.; et al. Battelle Memo- SAND 88-7155. 50410:036.

nat institute, Pacific Northwest Laboratory. December 1988. As part of the U.S. Nuclear Regulatory Commission's 182pp. 8905110345, PNL 5940,49719:243. (USNRC) Containment Integnty Program, a leak rate test was The Steam Generator Group Project (SGGP) is using a re- performed on a full size personnel airlock for a nuclear contain-tired-from-service pressurized water reactor steam generator as mont building The airlock was subjected to conditions simulat.

a test bed to investigate the reliability of in-service nondestruc- ing severe accident conditions. Testing was performed by CBI tive (NDE) eddy current inspections. This information will pro- Research Corporation (CBIRC) under contract to Gandia Nation-vide the technical basis for recommended changes to the regu-al Laboratones (SNL) wtVch manages the Containment Integnty lations concerning in-service inspections of steam generator Program for the USNRC. The objective of the test was to char-tubes and tube plugging cntena. The estimates of inspection re- actenze the performance of airlock door seals when subjected liability are being made from NDE data collected dunng a series to conditions that simulate a severe accident condition. The of round robin inspections of a subset of tubes from the genera- gaskets tested had a cross-section known as a " double dog-tor. Segments of these tubes have been removed from the gen- ear" configuration and were made from EPDM E603. The seals erator and are being destructively analyzed to determine the were aged at an accelerated rate to simulate aging that might actual state of tube degradation To determine NDE reliability, a occur dunng 40 years of continuous service and a loss of cool-large number of service induced defects were needed in the set ant accident (LOCA) The data obtained from this test will be on tubes selected for the round robin inspections. Thus, two used by SNL as a benchmark for development of analytical complete baseline eddf current inspections were performed to methods. In addition to leak rate data, strain, temperature, dis-identify those tubes with a high probability of containing defects, placement and pressure data were measured and fecorded The results of the baseline inspections are desenbed in this from over 330 transducers. A total of nine tests were performed report. The baseline inspections were performed by field-experl- on the airlock. In the most ngorous of these tests, the airlock enced personnel using two different commercially available mul- inner door was subjected to pressures and temperatures of 300 titreguency eddy current systems. The analysis of the results psig (2.07 MPa) and 850 degrees F (454 degrees C).

showed larger than expected differences in the detection of suspected wall-loss defects (indications) and the subsequent NUREG/CR-5163: POWER BURST FACILITY (PBF) SEVERE estimates of the depth of the defects. One inspection reported FUEL DAMAGE TEST 1 -4 TEST RESULTS REPORT.

773 outer diameter (OD) indications and the o: hor 1041. The PETTI.D.A.; MARTINSON.Z.R.; HOBBINS.R.R.; et al. EG&G detection agreement between teams, based on the reporting of Idaho, Inc. (subs. of EG&G. Inc.). Apnl 1989. 1,071 pp.

the bame indication, was 84% and 61% for the inspections with 8906120132. EGG-2542. 50107:001.

the fewer and farger riumbers of indications, respectively. The An evaluation of the Severe Fuel Damage (SFD) Test 1-4 sees of the same indications ieported by diffeient teams were performed in the PBF at the INEL is presented. The objective of observed to be significantly d!fferent. the test was to Contnbute to the understanding of fuel and con-

Miln Cititisns cnd Ab;trccts 11 trol rod behavior, aerosol and hydrogen generation, and fission nuclear reactors. The U.S. Nuclear Regulatory Commission has product release and transport during a high- temperature, SFD made the development of mechanistic models for severe acci-tranaient. A test bundle, compnsed of 26 previously irradiated dent progression a major priority. The purpose of these models PWR-type fuel rods,2 fresh instrumented fuel rods, and 4 Ag- is to provide detailed, best estimate, coupled analyses of all the in-Cd control rods, was surrounded by an insulating shroud and major phenomena involved in the reacar vessel and coolant

} contained in a pressurized in-pile tube. The expenment consist- system in the course of the accident. To meet this objective, l ed of a 1.3-h transient at a coolant pressure of 6.95 MPa in the MELPROG computer code is being developed. This report which the inlet coolant flow was reduced to 0.6 g/s while fission describes the two-dimensional, Pres?unzed Water Reactor power was gradually increased until dryout, heatup, cladding (PWR) version of the MELPROG computer code MELPROG/

rupture, and oxidation occurred. With sustained fission power PWR-MODt. The purpose of MELPROG is to provide for an ac-and heat from oxidation, temperatures rose rapidly, resulting in cident sequence a desenption of (1) the state of the reactor zircaloy and control rod absorber alloy meiting, fuel liquefaction, core and surrounding in-vessel environment as a function of matenal relocation, and hydrogen, aerosol, and fission product time, (2) the disposition of core materials (in particular, tssion release. The transient was terminated over 2100 s by slowly re- productss contained within the reactor coolant system boundary ducing reactor power and cooling the damaged bundle with as a function of time, and (3) the state of the de%s that enters argon gas. A desenption and evaluation of major phenomena, the containment if the reactor vessel fails. IncLPROG can also based upon on-line instrumentation response, fission product be coupled to the TRAC-PF1 RCS thermal-hydraulics code to and arosol data analysis, fuel buncie PIE, and SCDAP/ provide an integrated analysis of the behavior of core, vessel, RELAPS computer code calculations, are presented- and reactor coolant systems during severe accidents. MEL-NUREG/CR 5172: TACTICAL 1 RAINING REFERENCE MANUAL. PROG treats core degradation and loss of geometry, debns for-TELFAIR W.D.; MOUL,D.A4 KLINGELHOEFER, et al. Battelle mation core melting, attack on supporting structures, slumping, Memonal Institute, Columbus Laboratones April 1989. 289pp, melt / water interactions and vessel failure. Emphasis is also 8905100257. BMI-2166. 49667:300. placed on the rates of hydrogen, steam and fission product for-This manual provides training information for U S. Nuclear mation, and transport to containment dunng the accident.

Regulatory Commission hcensees to assist in implementation of the lactical Response Team (TRT) training and exercise re- NUREG/CR-5208: WARM PRESTRESS quirements of the revised portions of 10 CFR Part 73, which re. MODELING:COMPAR! SON OF MODELS AND EXPERIMENTAL quires that hcensees possessing formula quantities of strategic RESULTS. STONESIFER,R.B.; RYBICKI,E.F,; MCCABE,0 E.

special nuclear matenal establish TRTs and conduct tactical re. Materials Engineenng Associates, Inc. Aprd 1989. 74pp.

sponse exercises to enhance the capabihties of security forces 8905100288. MEA-2305. 49666:120.

in protecting NRC licensed fuel facilities from potential adversar. The objectives of this study were to develop warm prestress les postulated in the design basis 1hreat. Step by step illustrated (WPS) data for which the enhanced toughness due to WPS instructional matenal is provided conceming both individual and could be separated from the statistical variability in K(Ic) of the team tactics and skills appropnate to meeting these require. virgin material and to evaluate several candidate WPS models.

ments. The manual consists of two parts. Part Onc addresses Two types of loading sequences were load- unload cool-fait adversary attributes and essential tactioni skills that each TRT (LUCF) and load-partial unload-cool-fail (LPUCF). The LUCF ex-member should master to assure persorial safety and effective periments showed 1.6 to 2.5 times K(ic) improvemen' over that response to adversary actions. Part Two discusses more ad- of the low temperature K(Ic) fracture toughness of virgin materi-vanced tactics, command, control, and orders. al. The LPUCF expenments showed about 3 times improvement l over low temperature K(ic). Mathematical WPS models of Chell, NUREG/CR 5187: PRA APPLICATIONS PROGRAM FOR IN- c mpact specimen stnp yield model of Newman and Mall and a SPECTION AT CALVERT CLIFFS UNIT 1 NUCLEAR POWER small scale yie!d entical stress model SSYCSM of Curry were PLANT. VO,T.V.; HARRIS.M S.; GORE B.F. Battelle Memonal used to predict experimental WPS results. The SSYCSM model institute, Pacific Northwest Laborato y. June 1989. 200pp 8907060247. PNL-6574. 50373:317, seemed t make the most sense on a physical basis and also The level one probabilistic risk assessment (PRA) for Calvert provide the most accurate predictions. These results suggest Cliffs Unit 1 (CC 1) has been analyzed to identify plant systems a e s ese senous mnshaMn h bs& We ant accident scenarios and in assessments applied to plant life and components important to minimizing pubhc nsk, as meas-ured by system contributions to plant coremelt frequency, and Mensbn cons &aWs.

to identify the pnmary failure modes of these components This information has been tabulated and correlated with inspection NUREG/CR-5216: POST IRRADIATION FRACTURE TOUGH-modules from the NRC Inspection and Enforcement Manual. NESS CHARACTER!ZATION OF FOUR LAB-MELT PLATES.

HISER,A.L. Matenals Engineenng Associates, Inc. April 1989.

The renrt presents a sdnes of tables, organized by system and 125pp. 8905170110. MEA-2311. 49763:126.

pnoritwd by nsk importance, which identify components associ-ated with 98% of the inspectable risk due to plant operation. Previous work indicated that the irradiation induced transition temperature elevation MT) evaluated from Charpy-V (C(v)) data The systems addressed, in descending order of nsk importance are: Reactor Protection, Auxiliary Feedwater, DC Power, AC at the 41 J (30 ft-Ib) level can give a nonconservative estimate Power, Power Conversion, High Pressure injection, Room Cool- of the T of the static fracture toughness (K(Jc)) curve at the 100 ing. Salt Water, Safety Re!ief Valvef,, and Chemical and Volume MPa/m (91 ksi/in.) level. This trend was most evident for base Control Systems. This ranking is based on the Fussel-Vesely metals (plate and forging). The present study looked at the measure of nsk importance, Le., the fraction of tt t total core effect of the chemical composition on the relationship between i melt frequency which involves failures of the system of interest. T trom C(v) and T from K(Jc). Four steel plates, having ditferent I contents of copper, nickel and phosphorus for different degrees  !

NUREG/CR-5193: MELPROG-PWR/ MOD 1: A TWO-DIMENSION- of radiation sensitivity, were used Static fracture toughness, AL, MECHANISTIC CODE FOR ANALYSIS OF REACTOR C(v) and tensile tests of the unerradiated and the irradiated con-CORE MELT PROGRESSION AND VESSEL ATTACK UNDER ditions were made. In addition, rapid load fracture toughness SEVERE ACCIDENT CONDITIONS, DOSANJH.S S. Sandia Na- and drop weight tests of the unirradiated condition were made. j tional Laboratones. May 1989. 39?pp. 8906120198. SAND 88- The results for the four plates indicate that the correspondence '

1824. 50110 042. between T from C(v) and T from K(Jc) is not affected signifi- I Since the Three Mile Island accident, increased emphasis has cantly by differences in copper, nickel and/or phosphorus con- ]

been placed on the analysis of severe reactor accidents be- tent. In each data set, the T from C(v) underestimates the T cause such accidents represent the dominant public nsk from from K(Jc) measured by CT tetts.

i I

12 Main Citations and Abstracts

} NUREG/CR-5216 R01: POST-IRRADIATION FRACTURE See NUREG/CR-5228,V01 abstract.

TOUGHNESS CHARACTERIZATION OF FOUR LAB-MELT PLATES. HISER A L Matenals Engineering Associates, Inc. NUREG/CR-5230: SHUTDOWN DECAY HEAT REMOVAL June 1989.121pp. 8907060254. MEA-2311. 50373:193. ANALYSIS: PLANT CASE STUDIES AND SPECIAL See NUREG/CR-5216 abstract. ISSUES. Summary Report. ERICSON,0.M.; CRAMOND,W.R.;

SANDERS,G.A.; et al. Sandia National Laboratories. April 1989.

NUREG/CR-5222: STATIC LOAD CYCLE TESTING OF A LOW- 570pp. 8905220180. SAND 88-2375. 49828:120.

ASPECT-RATIO SNINCH WALL TRG-TYPE STRUCTURE " Shutdown Decay Heat Removat Requirements" has been TRG-4-6 (1.0, 0.25). FARRAR,C R.; BENNETT,J.G.;

designated as Unresolved Safety issue (USI) A-45. The overall DUNWOODY,W E.; et al. Los Alamos National Laboratory. June 1989 140pp. 8907060059. LA 11422-MS. 50357:126. objectives of the USl A-45 program were to evaluate the safety Quasi-static load cycle testing of a 6-in. thick reinforced com adequacy of decay heat removal (DHR) systems in existing light crete shear wall structure is detailed in this report. The back- water reactor nuclear power plants and to assess the value and ground of this program and results that led to this senes of ex- impact (benefit cost) of alternative measures for improving the penments are reviewed. Geometry of the test structure, design overall reliability of the DHR function. To provide the technical parameters, prehminary modal testing and analysis to venty un- data required to meet these objectives, a program was devel-damaged dynamic properties. matenal property tests, instrumen- o ed that examined the state of DHR system rehabihty in a tation and results of this data reduction for stiffness, cracking sample of existing plants. This program identified potentsat vul-values, and energy losses are given. Results are compared with nerabilities and identified and established the feasibility of po-Other investigators' results, as well as with the Amencan Con- tent al measures to improve the rehability of the DHR function.

crete Institute 318-349 code predictions' A value/ impact (V/l) analysis of the more promising of such measures was conducted and documented. This report summa-NUREG/CR-5227 S01: FITNESS FOR DUTY IN THE NUCLEAR nzes those studies. In addition, because of the evolving nature POWER INDUSTRY:A REVIEW OF TECHNICAL ISSUES. of V/l analyses in support of regulation, a number of supporting MOORE.C.; BARNES,V.; HAUTH.J.; et al. Battelle Human Af- studies related to appropr: ate procedures and measures for the fairs Research Centers. May 1989.191pp. 6906260422. PNL- V/l analyses were also conducted. These studies are also sum-6652. 50280.191. marized herein. This report only summanzes findings of techni-This report presents information gathered and analyzed in cal studies performed by Sar'dra National Laboratones as part support of the U.S. Nuclear Regulatory Commission's (NRC's) of the program to resolve this issue. The reader is also referred efforts to develop a rule that will ensure that workers with unes- to a companion document, NUREG-1289, " Regulatory and corted access to protected areas of nuclear power plants are fit Backfit Analysis for the Resolution of Unresolved Safety issue for duty. This report supplements information previously pub- A-45 Shutdown Decay Heat Removal Requirements."

fished in NUREG/CR.5227, " Fitness for Duty in the Nuclear Power Industry: A Review of Technical issues" (Barnes et al., NUREG/CR-5235: THERMODYNAMICS OF TECHNETlUM RE-1988). The pnmary potential fitness-for duty concern addressed LATED TO NUCLEAR WASTE DISPOSAL. Solubilities of Tc(IV) in both of these reports is impairment caused by substance Oxides And The Electrode Potential Of The Tc(Vil)/Tc(IV)-Oxide abuse, although other fitness concerns are discussed. This Couple. MEYER,R E.; ARNOLD,W.D.; CASE,F.I.; et al. Oak report addresses issues pertaining to wosers' use and misuse Ridge National Laboratory. June 1989. 38pp. 8906260287.

of alcohol, presenption drugs, and over-the counter drugs as fit- ORNL-6503. 50280:036.

ness for duty concerns; rasponds to several questions raised by Solubilities of Tc(IV) oxides have been determined in a NRC Commissioners; discusses subversion of the chemical number of solutions in the pH range 1 to 10. Technetium oxide testing process and methods of preventing such subversion; was prepared either by precipitation upon punfied sand with a and examines concerns about the urinalysis cutoff levels used 30% excess of hydrazine or by electrodeposition. The concen-when testing for rnanjuana metabolites, arnphetamines, and trations of total technetium and Tc(IV) species in the solutions phencychdine (PCP). were penodically deternined by separating the OLized and re-NUREG/CR-5228 V01: TECHNIOUES FOR PREPARING FLOW- duced technetium species using a solvent extraction procedure CHART-FORMAT EMERGENCY OPERATING and counting the beta activity of the (99)Tc with a hquid scintil-PROCEDURES. Background (Sections 1.0-9 0). BARNES.V.E.; lation counter. In basic solutions, the concentrations M ,wv)

MOORE,C.J.; W!ERINGA D.R.; et al. Battelle Human Affairs Re- species in equilibrium with the oxide were in the range of 10(-8) search Centers. January 1989.19Bpp. 8905100281. PNL-6653. to 10(-9) mol/L and tended to increase slightly with pH. In acid 19694:001. solutions the concentrations were much higher and were con-This two volume report describes the actMties, findings, and sistent with hterature data or' the hydrolytic species of Tc(IV).

recommendations of a project entitled " Techniques for Present- These data can be used to estimate Tc(IV) solubihtbs for cases ing Flowchart Format Emergency Operating Procedures." The where solubility hm4s transport of technetium in reducing envi-project team surveyed the hterature pertaining to flowcharts, re- ronments of high-level waste repositones. Because there is viewed existing flowchart emergency operating procedures some disagreement among published values of E' for the (EOPs), interviewed consultants who produced flowcharts, and Tc(Vil)-Tc(IV) redox couple, a redetermination of the standard irderviewed reactor operator hcensing examiners about the use potential was completed. The value of E*was determined to be of flowcharts in nuclear power plants. Volume 1 of this report 0.74710.004V. Within the hmits of error, this agrees most close-discusses the use of flowchart-format EOPs in nuclear power ly w th the value E' = 0.741 d 0.004 V reported by Cartiedge and plants and presents issues to be addressed in the design and Smith (1955) implementation of flowchart EOPs. Volume 2 presents tech-niques for prepanng flowchart EOPs that were denved from the NUREG/CR-5237: USE OF LINEAR REDUCED-STIFFNESS ANA-information discussed in Volume 1 and from NUREG-0899 LYTICAL MODELS TO PREDICT SEISMIC RESPONSE OF

Guidehnes for the Preparation of Emergency Operating DAMAGED Proce.CONCRETE STRUCTURES. FARRAR C.R.;

dures (USNRC,1982)~ ALVORD.C.M. Los Alamos Nabonal Laboratory. May 1989.

51pp. 8906020095. LA-11444-MS. 49995:080.

NUREG/CR 5228 V02: TECHNIOUES FOR PREPARING FLOW- An extensive analysis of previously measured seismic re-CHART-FORMAT EMERGENCY OPERAT;NG sponse data trom tne Seismic Category l Structures program PROCEDURES User's Manual (Sections 10 0-17.0). was made to determine if reduced stiffness linear models can BARNES.V.E.; MOORE,C.J : WlERING A.D.R.; et al. Battelle be used to predict the response of damaged nuclear power Human Affairs Research Centers. January 1989 89pp. plant structures. Four structures ranging from one to three sto-89051002B2. PNL +653. 49670:141. nes were ana r y2ed for three different peak acceleration inputs.

Miln CitItions End Abstricts 13 All inputs were scaled versions of the 1940 El Centro earth. Reactor (PWR) are provided along with an example of contin-quake measured at the base of the test structures during gency plan changes necessary for implementation of this meth-shake-table testing. Comparisons between measured and ana- odology, a discussion of some contingency measures that can lytically predicted responses were made in terms of floor re- be used to kmit land vehicle access, and a bibhography.

sponse spectra. Stiffness in the analytical models was adjusted to obtain a match in frequency and damping was adjusted to NUREG/CR-5252: AEROSOL SAMPLING AND TRANSPORT EF-obtain a match in amplitude. Results showed that the reduced. FICIENCY CALCULATION (ASTEC) AND APPLICATION TO suffness knear models could accurately predict the response of SURTSEY/DCH AEROSOL SAMPLtNG SYSTEM Code Version the damaged structures and these results were consistent with 1.0: Code Desenption And User's Manual. YAMANO.N.:

the response observed during static cyche testing of similar BROCKMANN,J E. Sandia National Laboratories. YAMANO.N.

structrr Changes in damping with excitation levels are also Japan Atomic Energy Research Institute. May 1989. 160pp.

discusto. In addition to the analysis of the seismic response 8906260361, SAND 881447. 50282:141.

data, the stiffness of these structures was analyzed by a vanety This report desenbes the features and use of the Aerosol of methods currently used by industry and the stiffness values Sampling and Transport Efficiency Calculation (ASTEC) Code.

were compared with the values in the analytical mcdels that The ASTEC code has been developed to assess aerosol trans-best fit the measured response. por; efficiency source term expenments at Sandia National Lab-rato les. This code also has broad application for aerosol sam.

NUREG/CR-5238: DEVELOPMENT OF AN ENGINEERING DEFI-NITION OF THE EXTENT OF J SINGULARITY CONTROLLED "9 "" "# # " "" #""*'** ""

CRACK GROWTH. JOYCE J.A. U.S. Naval Academy, Annapolis, is u '

MD. HACKETT,E.M, David W. Taylor Naval Research & Devel-opment Center. May 1989. 41pp. 8907070099. 50409:214. NUREG/CR 5257: FURTHER NEOTECTONIC STUDIES OF An experimental definition is proposed for the extent of singu- EARTHOUAKE ZONES IN THE EASTERN UNITED STATES.

lanty controlled behavior in a J resistance fracture test. The sin- TALWANI,P.; COLOUHOUN D.J.; ACREE.S.D.; et al. South gularity zone is defined in terms of a constant ratio of plastic Carolina, Univ. of. Columbia, SC. June 1989. 112pp.

crack opening displacement and normalized crack extension. 8906260418. 50282:301.

Justification for this definition is given in terms of experimental Shallow stratigraphic investigations based on bonngs and rel-results on compact specimens of three steel alloys of varying stive travel time residuals of teleseismic events were used to in-matenal roughnesses and in terms of a simple analytical model. vestigate neotectonic activity and its relationship to seismicity in The expenmental limit can be evaluated from the data normally South Carolina. Data from 103 wells resulted in a structural con-obtained Qunng an unloading comphance single specimen J in- tour map of unconformity 8 in the Coastal Plain. Compansons of tegral resistance curve expenment. Generally the expenmental the structural cor. tours with magnetic and gravity maps and with singulanty limit extends the region of test validity well beyond epicenters in the Bowman and Charleston Summerville areas that which is presently allowed by the ASTM J-R test standard showed that the regional nonheast trend is interrupted by north-E1152. west trending features in the two seismic areas. The intersec-NUREG/CR-5244: EVALUATION OF NON-RADIOLOGICAL tion of the northwest and northeast trends appears to be relat-WATER CHEMISTRY AT POWER REACTORS. BANERJEE.S.; ed to the recent seismicity, and basement tectonic activity CASTROGIVANNI, CRUZ,C. Brookhaven National Laboratory. seems to have influenced the structure of the overlying sed!-

May 1989. 68pp. 8906120126. BNL-NUREG-52166. 50113:277. monts. Travel times from 180 teleseismic events were normal-The NRC's inspection program for the evaluation of non-radi- ired to a reference station and corrected for delays in the ological water chemistry practices at nuclear power plants in- Coastal Plain sediments. Analysis of the residuals shows a sys-cludes performance testing by licensees. Plant laboratones ana, tematic decrease in residuals with distance from the coast. Azi-lyze certified standards prepared by Brookhaven National Labo- muthal variations at individual stations can be correlated with ratory (BNL) during an on-site evaluation by an NRC inspector. basement lithology as indicated by gravity and magnetic data.

Additionally, coolant or other water samples are split for com- The postulated Ashley River fault coincides with a change in parative licensee /BNL analysis. This report summanzes and basement velocity structure. The travel time tesiduals, therefore, statistically evaluates bcensee performance data for 43 plants in confirm the presence of this subsurface fault.

Regions I-IV. The results are compared with those from an earli-er cycle in which only Region 1 participated. Substantial im-NUREG/CR-5261: SAFETY EVALUATION OF MHTGR LICENS-provement in Region l's performance was observed. Of the an- ING BASIS ACCIDENT SCENARIOS. KROEGER,P.G. Brookha-afytes considered, the greatest analytical uncertainty was con- ven National Laboratory. April 1989.100pp. 8905100215. BNL-si ly associated with chlonde, probably as a result of matnx NUREG-52174. 49664:082 The safety potential of the Modular High-Temperature Gas Reactor (MHTGR) was evaluated, based on the Preliminary NUREG/CR-5246: A METHODOLOGY TO ASSIST IN CONTIN- Safety Information Document (PSID), as submitted by the U.S.

GENCY PLANNING FOR PROTECTION OF NUCLEAR POWER Department of Energy to the U.S. Nuclear Regulatory Commis-l PLANTS AGAINST LAND VEHICLE BOMBS. JAMES,J.W.; sion. The relevant reactor safety codes were extended for this i GOLDMAN,L.A.; LOBNER,P.R.; et al. Science Applications purpose and app!;ed to this new reactor concept, searching pri-1 international Corp. (formerly Science Applications, Inc.) April marily for potential accident scenanos that might lead to fuel 1989, 86pp. 8905170104. SAIO 88/1885. 49763:251. failures due to excessive core temperatures anri/or to vessel This report provides a methodology which could be used by damage, due to excessive vessel temperatures. The design operators of licensed nuclear power reactors to address issues basis accident scenano leading to the highest vessel tempera-related to contingency planning for a land vehicle bomb, should tures is the depressunzed core heatup scenario without any such a threat anse. The methodology presented in this report forced cooling and with docay heat rejection to the passive Re-provides a structured framework for understanding factors to be actor Cavity Cooling System (RCCS) This scenario was evaluat-considered in contingency planning for a land vehicle bomb in- ed, including numerous parametne vanations of input param-cluding (1) system options available to maintain a safe condi- eters like matenal nroperties and decay heat. It was found that I i

tion, (2) associated components and equipment, (3) preferred significant safety margins exist, but that high confidence levels system options for estabbshing and maintaining a safe shut- in the core effective thermal conductivity, the reactor vessel and l i

dowri condition, and (4) contingency rneasures to preserve the RCCS thermal emissivities and the decay heat function are re-preferred system options. Example applications of the method- quiied to maintain this safety margin. Severe accident exten-ology for a Boiling Water Reactor (BWR) and Pressunzed Water sions of this depressunzed core heatup scenano included the 1 i

14 M in Cit:tions cnd Ab tr cts cases of complete RCCS failure, cases of massive air ingress, cy for DDT compared to similar tests without obstacles. Differ-core heatup without scram and cases of degraded RCCS per- ent obstacle configurations could have greater or lesser effects formance due to abs 9rbing gases in the reactor cavity. Except on flame acceleration and DDT. Large degrees of transverse for no-scram scenarios extending beyond 100 hr, the fuel never ventiri reduced the flame speeds, overpressure, and possibile-reached the limiting temperature of 1600 degrees C, below ty of ODT. For small degrees of transverse venting (13% top which measurable fuel failures are not expected. In some of the venting), the flame speeds and overpressure were higher than scenarios, excessive vessel and concrete temperatures could for no transverse venting with reactive mixtures (>18%H(2)), but lead to investment losses but are not expected to lead to any they were lower with leaner mixtures. The effect of the turbu-source term beyond that from the circulating inventory. Several lence generated by the flow out the vents on increasing flame future extensions of the current worir are suggested. speed can be larger than the effect of venting gas out of the NUREG/CR-5268: AGING STUDY OF BOILING WATER REAC- channel and hence reducing the overpressure. With no obsta-TOR RESIDUAL HEAT REMOVAL SYSTEM. LOFARO,R.; cles and 50% top venting, the flame speeds and overpressure SUBUDHI,M.; GUNTER,W.; et al. Brookhaven National Labora- were low, and there was no DDT. For all other cases. DDT was tory. June 1989. 210pp. 8907060073. BNL-NUREG 52177. observed above some threshold hydrogen concentration. DDT 50384:259. was obtained at 15% H(2) with obstacles and no transverse A study of the aging effects on Residual Heat Removat (RHR) venting.

systems in Boiling Water Reactors (BWRs) was performed as part of the Nuclear Plant Aging Research (NPAR) program. The NUREG/CR 5279: SULFATE-ATTACK RESISTANCE AND objectives of the NPAR program are to provide a technical GAMMA IRRADIATION RESISTANCE OF SOME PORTLAND CEMENT NSED MORTARS. SOO P.; MILIAN.L. Brookhaven basis for the identification and evaluation of degradation caused National Laboratory. March 1989. 54pp. 8904250171. BNL-by age in nuclear power plant applications. The information from NUREG 52179. 49462:020.

this and other NPAR studies will be used to assess the impact Sulfate. attack and gamma-irradiation tests were camed out of aging on plant safety and to develop effective mitigating ac-on three Portland cement mortars. For the sulfate attack work tions. The effects of aging in the RHR system were character-an accelerated test was used involving alternate Mmersion in ized using the Aging and Life Extension Assessment Program Na(2)SO(4) solution and oven drying of the samples. Attack was (ALEAP) Systems Level Plan developed by BNL. Failure data monitored through length-change rneasurements. Cement from vanous national data bases were reviewed and analyzed mortar containing silica fume gave unexpectedly poor resistance to identify predominant failure modes, causes and mechanisms to attack. Reasons for this behavior are unclear. Gamma irrad.a-Time-dependent failure frequencies for major components were tion was found to cause losses in compressive strength at low calculated to identify aging trends. Plant specific information doses in the 10(7) rad range. The irradiatica time is a major was also reviewed to supplement data base results. A computer factor in the strength-loss mechanism, whereas the dose rate is program (PRAAGE 1988) was developed and implemented to of secondsry importance for the testing conditions studied.

model a typical RHR design and perform time-dependent Prob-abilistic Risk Assessment (PRA) calculations. Time-dependent NUREG/CR-5281: VALUE/ IMPACT ANALYSES OF ACCIDENT failure probabilities were input to the PRAAGE program to PREVENTIVE AND MITIGATIVE OPTIONS FOR SPENT FUEL evaluate tne effocts of aging on component importance and POOLS. JO,J H.; ROSE,P.F.; UNWIN,S.D.; et at. Brookhaven system unavailabihty. National Laboratory. March 1989.109pp. 8904250173. BNL-NUREG/CR-5274: NUMERICAL SlMULATION OF NATURAL CIR- NUREG-52100. 49461:271.

CULATION PHENOMENA IN A PWR DURING TMLB' TRAN. A senes of value/ impact studies were performed for accident Sit'NTS PRIOR TO CORE DAMAGE. CHA,Y.S.; Preventive and mitigative options intended to reduce the risks DOMANUS,H.M.; LIU,K.V.; et al. Argonne National Laboratory, posed by the storage of spent fuel at nuclear power plants in May 1989. 291pp. 8906020099. ANL-88-47. 49994:149. spent fuel storage pools. Options studied included 'mited low-Multidimensional thermal-hydraulic simulation of natural circu- density reracking of spent fuel, installation of water sprays lation phenomena dunng a TMLB' transient pnor to core above the spent fuel pool, and the installation of redundant damage has been performed by using the COMMIX computer coohng and/or makeup systems. The results of these studies code. Both a three-loop and a four loop PWR plant are ana, indicated that the measures were in general not likely to be cost lyzed. Effects of vanous parameters on natural circulation are effective. The reason for this is due to both the low likelihood of investigated. The most important result is that natural circulation a spent fuel pool accident that could result in a significant radio-exists during a TMLB' transient for all the cases investigated so logical release and h;gh cost of proposed modifications. These far. insights are largely contingent upon compliance with guidelines developed for licensees to assure the safe handling of heavy NUREG/CR-5275: FLAME FACILITY.The Effect Of Obstacles And loads in the vicinity of spent fuel pools thus reducing the hkeli-Transverse Venting On Flame Acceleration And Transition To hood of the structural failure of the pool and rapid loss of water Detonation For Hydrogen Air Mixtures At Large Scale. inventory due to a cask drop event.

SHERMAN,M.P.; TIESZEN.S.R.; BENEDICK,W.B. Sandia Na-tional Laboratones. April 1989.161pp. 8905110262. SAND 85- NUREG/CR-5283: CLOSEOUT OF IE BULLETIN 79 03 LONGI-1264.49726:048. TUDINAL WELD DEFECTS IN ASME SA 312 TYPE 304 STAIN-This report describes research on flame acceleration and det- LESS STEEL PlPE SPOOLS MANUFACTURED BY YOUNGS-lagration-to- detonation transition (DDT) for hydrogen-air mix- TOWN WELDING AND ENGINEERING COMPANY.

tures camed out in the FLAME facihty, and describes its rel. FOLEY,W.J.; DEAN,R S.; HENNICK.A. PARAMETER, 'nc. April evance to nuclear reactor safety. Flame acceleration and DDT 1989.34pp.8905110308 PARAMETER IE174. 49724:065.

can generate high peak pressures that may cause failure of Documentation is provided in this report for the closecut of IE containment. FLAME is a large rectangular channel 30 5 m Bulletin 79 03, on the subject of fusion welded austenitic stain-long 2.44 m high, and 1.83 m wide. It is closed on the ignition less steel pipe (without filler metal) manufactured by the end and open on tt e far end. The three test vanables were hy- Youngstown Welding and Engineenng Company. Only pipe used so;Wn mole tract'.,n (12 30%). degree of transverse venting or planned for use in safety-related systems is considered. The (by moving steel 'op plates - 0%,13%, and 50%). and the ab- bulletin is closed out on the basis of definite en%na for all of sence or present a of certain obstacles in the channel (zero or the 121 facihties for which actions were required. This bulletin 33% blockage r,tio). The most important variable was the hy- was issued by the NRC on March 12,1979 to require certain drogen mole iaction. Tne presence of the obstacles tested actions by all holders of operating licenses and construction greatly increased the flame speeds, overpressure, and tencen- permits for power reactors. The NRC's concern was based on t _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

MIin Cit:ti:ns End Abstr; Cts 15 the discovenes of faulty longitudinal welds at Palo Verde and the 39 affected facilities. Background information is supphed in San Onofre. The investigations for Bulletin 79-03 led to the find- the Introduction and Appendix A of this report ing that volumetric examination of the fusion welds per the ASME Code requirements did not assure detection of centerline NUREG/CR-5319: RISK SENSITMTY TO HUMAN ERROR.

lack of penetration (CLP). Therefore, the problem of faulty SAMANTA.P.; WONG.S.; HABER.S.: et al. Brookhaven National welds applied to all manufacturers of SA- 312/A-312 Type 300 Laboratory.' April 1989. 190pp. 8905110321. BNL-NUREG-Series welded steel pipe. Bulletin 79-03A was issued on April 4, 52183.497?4:237.

1980 to supersede the required actions of Bulletin 79-03, and to A sensitiv:ty evaluation was conducted to assess the impact collect information on all of the subject pipe and fittings in of human errors on the internal event nsk parameters in the safety-related systems. Refer to NUREG/CR-5284 for the com- Ocones plant. The results provide the variation in the risk pa-panion closeout report on IE Bulletin 79-03A, " Longitudinal rameters, namely, core melt frequency and accident sequence Weld Defects in ASME SA-312 Type 304 Stainless Steel Pipe." frequencies due to chrnges in human error probabilities. Also Background information is provided in the introductiori arti Ap- provided are insignts denved from the results, which highlight pendix A of this report as well as NUREG/CR 5284. important areas for concentration of risk limitation efforts asso-ciated with human performance.

NUREG/CR-5284: CLOSEOUT OF IE BULLETIN 79-03A: LONGITUDINAL WELD DEFECTS IN ASME SA-312 TYPE NUREG/CR 5330: HIGH-TEMPERATURE CRACK-ARREST BE-304 STAINLESS STEEL PIPE. FOLEY,W.J.; DEAN R.S.; HAVIOR IN 152-MM THICK SEN WIDE PLATES OF HENNICK.A. PARAMETER, Inc. April 1989.25pp.8905110303. QUENCHED AND TEMPERED A 533 GRADE B CLASS 1 PARAMETER IE175. 49722:210- STEEL. NAUS.D.J.; KEENEY-WALKER; BASS,B.R.: et al. Oak Documentation is provided m this report for the closeout of IE Ridge National Laboratory. April 1989.155pp. 8905100275.

Bulletin 79-03A, on the subject of f aulty fusion welded austenitic ORNL/TM-11083. 49663:180.

stainless steel pipe (without filler metal) used or planned for use Two 152-mm-thick wide-plate crack-arrest tests (WP-1 Series) in safety-related systems. The investigation found that the bulle-are discussed in this report. Each test utilized a 1 x 1 x 0.15 m i tin has been closed administratively for all of the 121 facilities thick single edge notch specimen (a/w = 0.2), fabncated from for which responses were required. The bulletin asked hcensees A 533 grade B class 1 steel, that was subjected to a linear ther-for information only and did not include any requirement for cor- mal gradient along the plane of cr.1ck propagation. The tests rective action. It is concluded that the concems of the bulletin were conducted at the National Institute of Standards and have been resolved at all except four facilities (two locations), Technology and were designed to provide fracture toughness and a recommendation is given for followup. This bulletin was measurements at temperatures approaching or above the onset issued by the NRC on April 4,1980 as a followup to Bulletin 79- of the Charpy upper-shelf regime, in a nsing toughness region 03 (closecut report NUREG/CR-5283). The purpose of the fol- and with an increasing driving force. Results obtained from lowup bulletin was to obtain further information about the impact these tests have produced crack-arrest toughness values well of centerline lack of weld penetration (CLP) on the subject pipe- above the hmet recognized by the current ASME guidelines (220 The NRC's concern was based on the finding from responses MPa./mi with arrests occurring at 63 to 111 degrees C above and investigations for iniGal Bulletin 79 03 that the ASME Code the matenal RT(NDT) ( 23 degrees C). The fracture data sup-requirements for volumetnc examination of piping were insuffi- port (1) the use of fracture mechanics concepts to analyze cient for detection of CLP. The problem with SA 312/A312 cleavage run-arrest events, (2) the treatment of cleavage run-Type 300 Sones fusion welded matenal was found to apply to arrest and ductile fracture modes as separate events, and (3) all manufacturers, not just to the one mentioned in the initial the fact that cleavage arrest occurs above the ASME limit.

bulletin. )

NUREG/CR-5291: CLOSEOUT OF IE BULLETIN BO-09. HYDRA- NUREG/CR-5332:

SUMMARY

AND ANALYSIS OF PUBLIC COM-MOTOR ACTUATOR DEFICIENCIES. FOLEY W.J.; DEAN,R.S . MENTS ON NUREG-1317: REGULATORY OPTIONS FOR NU-HENNICK.A. PARAMETER, Inc. June 1989.24pp.8907050532' CLEAR PLANT LICENSE RENEWAL. Final Report. LIGON,D.M.;

PARAMETER IE182. 50355:279. SETH S.S. MITRE Corp. March 1989. 60pp. 8905100268. MTR-Bu e n 8 9 on he safety r a d ect of IfT enej n On Aug 29,1988, the U.S. Nuclear Regulatory Commis-trols (ITT-GC) Hydramotor actuators models AH-90 nd NH-90. sion (NRC) issued an Advance Notice of Proposed Hulemaking The problems reported about inadequate spnngs and faulty on nuclear plant flCense renewal and solicted public comments sszing could affect tha operation of safety- related equipment in- on NUREG-1317. " Regulatory Options for Nuclear Plant Li-stalled in nuclear power facilities. Closeout is based on the im- cense Renewal." NUREG 1317 presents a discussion of fifteen pigmentation and verification of actions required by this bulletin. topics involving technical, environmental, and procedural issues it is concluded that the concerns of the bulletin have been re. and poses a set of related questions. As part of its ongoing task solved. Evaluation of utility responses and NRC/ Region inspec- for the NRC. The MITRE Corporation has summarized and ana-tion reports indicates that the bulletin is closed for all of the 119 lyzed the public comments received. Fifty three wntten com-nuclear power reactor facilities in operation or under construc- ments were received. Of these, 83 percent were from nuclear tion. Background information is supplied in the introduction and industry representatives; the remaining comments represented Appendix A. Federal and State agencies, public interest groups, and a pn-vate citizen.

NUREG/CR 5293: CLOSEOUT OF IE BULLETIN 86-01. MINIMUM FLOW LOGIC PROBLEMS THAT COULD DISABLE RESIDUAL NUREG/CR-5336: SENSITIVITY OF THE STABILITY OF A HEAT REMOVAL PUMPS. FOLEY,W.J.; DEAN,R S.; WASTE EMPLACEMENT DRIFT TO VARIATION IN ASSUMED HENNICK.A. PARAMETER, Inc. March 1989. 20pp. ROCK JOINT PARAMETERS IN WELDED TUFF.

8905120173. PARAMETER IE184. 49735:284. CHRISTIANSON.M. Itasca Consulting Group, Inc. April 1989.

Documentation is provided in this report for the closecut of IE 217pp. 8905100242. 49665:129.

Bulletin 86-01 regarding minimum flow logic problems that could This report presents the results of a numerical analysis to de-disable residual heat removal (RHR) pumps in General Electnc termine the eflects of vanat:on of rock joint parameters on sta- I boiling water reactor facilities (GE/BWRs). Closcout is based on bihty of waste disposal rooms for vertrcal emplacements. Condi-the implementation and venfication of four required actions by tions and parameters used were taken from the Nevada Nucle-holders of operating licenses and construction permits of GE/ at Waste Storage investigation (NfJWSI) Project Site Character-BWR power reactors Evaluation of responses and NRC/ Region ization Plan Conceptual Design Report. Mechanical results are inspection reports indicates that the bulletin is closed for all of presented which illustrate the predacted distribution of stress, 1

____.._._______..____________________U

l 16 M In Cit ti:ns and Ab trccts ]

joint slip, and room deformations for times of initial excavation lights of steam generator research and unresolved safety ,

l and after 50 years heating. issues. The report concludes that cracking, both IGSCC on the j l tube outside diameter and PWSCC on the tube inside diameter, j NUREG/CR-5344: REPLACEMENT ENERGY COST ANALYSIS PACKAGE (RECAP): USER'S GUIDE. VANKUlKEN,J.C.; was the major cause of tube degradation dunng the 1987-1988 j DAUN,C.L.; JUSKO.M.J. Argonne National Laboratory. April period.

1989. 55pp. 8905100277. ANL/EES-TM-364. 49670:085. '

A microcomputer program called the Replacement Energy NUREG/CR-5350: MISSION SURVEY FOR THE PRESSURE 1 Cost Analysts Package (RECAP) has t,een developed to assist VESSEL RESEARCH USERS' FACILITY (PVRUF). {

the U.S. Nuclear Regulatory Commission (NRC) in determining PENNELL,W.E.; PUGH,C.E. Oak Ridge Natior,a! Laboratory.

the replacement energy costs associated with short-term shut. June 1989. 73pp. 8907060267, ORNL/TM 11133. 50373:015.

downs or deratings of one or more nuclear reactors. The calcu- Description is given of a mission survey conducted as an ex-lations are based on the seasonal, unit-specific cost estimates pioratory phase of the ORNL Pressure Vessel Research Users' for 1988- 1991 that were previously published in NRC Report Facility (PVRUF) PVRUF is a planned open access research fa-NUREG/CR-4012, Vol. 2 (1986), for all 117 U.S. reactors, with cility with a broad capability to perform R&D tasks necessary to updates that were made in July 1988. The program is menu- bring laboratory scale PWR pressure vessel technology ad-driven, allowing the user to define specific case studies in terms vances to a production status. The unique capability of PVRUF of such parameters as the units to be included, the length and to perform this function, for a wide range of emerging pressure timing of the shutdown or dorating periods, the unit capacity vetisel technology advances, derives from its use of a full scale factors, and the reference year for reporting cost results. In ad- production PWR reactor vessel as the facility test article. A full dition to simultaneous shutdown cases, more-complicated situa- scale prototype test article, while essential to the PVRUF mis-tions, such as overlapping shutdown periods or shutdowns that sion, introduces a particular need for rigor in the facility mission I occur in different years, can also be examined through the use definition, and in the associated selection of facility features and of a present-worth calculation option, systems. The scale of the test article dictates a matching scale NUREG/CR 5347: RECOMMENDATIONS FOR RESOLUTION OF in the facility features and systems. Each addition of a facility PUBLIC COMMENTS ON USI A-40, " SEISMIC DESIGN CRITE- hature or system can thus add a significant increment to the RIA." PHILIPPACOPOULO Brookhaven National Laboratory. facility mission and cost. The goal is to define the facility mis-June 1989. 153pp. 8906260411. BNL-NUREG-52191. sion as accurately as possible at this time and to reflect the 50283:176. dominant reactor pressure vessel R&D needs as defined by a in June 1988 the Nuclear Regulatory Commission (NRC) segment of the commercial nuclear power community. The fea- l issued for public comment the proposed Revision 2 of the tares and systems selected for inclusion in the facility conceptu-Standard Review Plan (SRP) Sections 2.5.2, 3.7.1, 3.7.2 and at design must be closely rnatched to the facility mission in 3.7.3. Comments were received from six organizations. Brook- order to achieve a cost-effective facility design.

haven National Laboratory (BNL) was requested by NRC to pro-vide expert consultation in the seismic and soil-structure interac- NUREG/CR-5351: MODELS FOR PULMONARY LETHALITY AND tion areas for the review and resolution of these comments. For MORBIDITY AFTER 1RRADIATION FROM INTERNAL AND EX.

this purpose, a panel of consultants was established to assist TERNAL SOURCES. SCOTT,B.R. Inhalation Toxicology Re-BNL with the review and evaluation of the public ccmments. search Institute. FILIPY,R.E. Battelle Memorial Institute, Pacific This review was camed out during the period of October 1988 Northwest Laboratory. HAHN F.F. Lovelace Biomed & Environ-through January 1989. Many of the suggestions given in the mental Research Institute. May 1989. 52pp. 8906020129. LMF-public comments were found to be significant and a number of modifications to appropriate SRP sections are recommended.

Other public comments were found to have no impact on the T eP rt Provides a hazard-function model for estimating the nsk of death from radiation pneumonitis and/or pulmonary proposed Revision 2 of the SRP. Major changes are recom-mended to the SRP sections dealing with (a) Power Spectral fibrosis following a light- water nuclear power plant accident. A Density (PSD) and ground motion requirements and (b) soil. simiiar model is also provided for estimating the prevalence of structure interaction requirements. This report contains specific respiratory functional morbidity among those that survive death recommendations to NRC for resolution of the public comments from acute effects. Hazard-function models for lethe.lity and for made on the proposed Revision 2 of the SRP, morbidity were constructed using the cumulative hazard estima-NUREG/CR-5349: STEAM GENERATOR OPERATING r H, w s aM to N M eshmaw R W@ h ma-EXPERIENCE, UPDATE tion R = 1 exp(-H). The estimator H can be calculated using FOR 1987-1988. FRANK,L.;

information provided in the report. The method of calculation STOKLEY.J. Science Applications international Corp. (formerly Science Applications, Inc.). June 1989.106pp. 8907060257. depends on the exposure scenario. In general, the total normal-SAIC 89/1113. 50373:005. ized dose X for lethality or for morbidity is calculated. For letha-This report summarizes operational events and degradation lity, X = 1 corresponds to a median lethal dose (LD(50)); for mechanisms affecting pressurized water reactor steam genera, morbidity, X = 1 corresponds to a median effective dose tor integrity, provides results of 1987 and 1988 steam generator (ED(50)). H is related to X by the equation H = In(2)X(V),

inspections, and tvghlights both prevalent problem areas and where V depends on the type of radiation (or radiations) in-improvements that have been made in nondestructive testing volved. Contnbutions to X can anse from each of two main methods, pf eventive measures, repair techniques, and replace. modes of exposure: (1) Onef exposure of lung, at a relatively ment procedures. It describes the equipment of the three major high dose rate, to mainly external gammas, followed by (2) suppliers and discusses recent examinations of 76 plants. Major chronic internal alpha, and/or beta, and/or gamma irradiation of areas of concern are the steam generator degradation mecha- the lung Equations are provided for calculating the contribu-nisms that affect tube integnty or cause tube leakage and tube tions to X from both modes of exposure. While uncertainty eval-failure. These include intergranular attack (IGA), intergranular uation is important for any risk assessment, an evaluation of the stress corrosion cracking (IGSCC), pnmary water stress corro- uncertainties related to predicting lethality and morbidity cases sien cracking (PWSCC), pitting, and vibrational wear and fa- after a nuclear accident is beyond the scope of this report.

tigue. Also discussed are plugging, sleeving. heat treatment. However, uncertainties are discussed in detail in a separate, peening. chemical cleaning, and steam generator replacements- follow-on report (NUREG/CR-4214) to be published in 1989.

the current status of regulatory instruments and inspection guidelines for ensuring the steam generator integrity, and high-

1 Miin Cit:tions atnd Abstr cts 17 NUREG/CR-$352: VAM2D . VARIABLY SATURATED ANALYSIS NUREG/CR-5356: IMPROVED MODEL FOR PREDICTING J-R MODEL IN TWO DIMENSIONS. Version 5 0 With Hysteresis CURVES FROM CHARPY DATA. Phase i Final Report.

And Chained Decay Transport Documentation And User's EASON E.D.; NELSON.E.E. Modeling & Computer Services.

Guide. HUYAKORN,P.S.; KOOL,J.B.; ROBERTSON J B. Hydro. April 1989. 48pp. 8905220162. MCS 890301. 49829:330.

Geologic, Inc. May 1989. 320pp. 8906120102. HGL/89-01. It is necessary to estimate J-R data for aging and residual life 50112:046.

studies, using data from surveillance capsute specimens that re-This report -documents a two-dimensional finale element flect the current state of the pressure vessel steel. An improved model. VAM2D, developed to simulate water flow and solute model is needed that will predict J-R data from Charpy data, transport in variably saturated porous media. Both flow and tensile properties, material composhion, temperature, and transport simulation can be handled concurrently or sequential- fluence. This report desenbes Phase I of a project to develop ly. The formulation of the governing equations and the numeri- such a model, using innovative pattern recognition and surface-cat orocedures used in the code are presented. The flow equa. fitting codes to identify the key parameters and optimal model-tion is approximated using the Galerkin finite element method. ing functions. In Phase 1, a readily-available sample of data on Nonlinear soil moisture characteristics are treated using Picard reactor pressure vessel and piping steels was collected and and Newton-Raphson sterations. Hysteresis effects and anisot- analyzed by the pattern recognition code. A preliminary model ropy in unsaturated hydraulic conductivity can be taken into ac- was fitted to the data, producing a more convenient model that count if needed. The contaminant transport simulation can ac. gives a better fit with fewer fatting constants, compared to La count for advection, hydrodynamic dispersion, linear equilibrium er models. The results are sufficiently encouraging to justify a sorption, and first-order degradation. Transport of a single com- Phase il project which would produce a calibrated, validated ponent or a mutti- component decay chain can be handled. The model for J-R data, with significantly better predictive capability transport equation is approximated using an upstream weighted and less data scatter than any model now available. The data residual method. Several test problems are presented to venty available for a Phase il effort are evaluated, and found to be the code and demonstrate its utility. These problems range from adequate for weld metal modeling A modest testing effort simple one dimensional to complex two dimensional and axb would make the database adequate for calibrating separate symmetric problems. This document has been produced as a weld and base metal models.

user's manual. It contains detailed imormation on the code structure along with instructions for input data preparation and NURE G!CR-5357: AN EXPLORATORY STUDY OF ELEMENT sample input and pnnted output for selected test problems. A'so INTERACTIONS AND COMPOSITION DEPENDENCIES IN RA-included are instructions for job set up and restarting proce. DIATION SENSITIVITY DEVELOPMENT. Final Report.

dures. HAWTHORNE J R. Materials Engineenng Associates, Inc. April 1989.178pp. 3905170054. MEA 2341. 49765:229.

NUREG/CR 5353: INHALED (147)PM AND/OR TOTAL-BODY This investigation employed laboratory melts of pressure GAMMA RADIATION EARLY MORTALITY AND MORBIDITY IN vessel steels (A 533-D or A 302-B base) to probe suspect inter-RATS. FILIPY,R E/, LAUHALA.K E.; MCGEE.D R.; et al. Battelle actions between copper impurities and manganese, molybde-Memorial institute, Pacific Northwest Laboratory. May 1989. num, chromium and nickol alloying as influencing elevated tem-202pp. 8906020107 PNL 6891. 49992116.

perature, radiation sensitivity development. Radiation sensitivity Rats were given doses c1 (60)Co gamma radiation and/or is judged on the basis of Charpy-V (C(v)) notch ductility and lung burdens of (147)Pm (in fused aluminosilicate particles) yield strength changes by 288 degrees C irradiation to-2.5 x within lethal ranges in an experiment to determine and compare 10(19) n/cm(2), E>1 MeV. The investigation also qualifies the in-morbidity and mortality responses for the radiation insults within fluence of phosphorus content on radiation resistance as a 1 year after exposure. Radiatioranduced morbidity was as- function of copper content and explores suspect contributions sessed by measunng char,ges in body weights, hematologic pa- of tin and arsenic. The findings demonstrate clearly that impor-rameters, and pulmonary-function parameters. Gamma radiation tant composition interactions exist in radiation sensitivity devel-caused transient morbidity, reflected by immedotely depressed opment. Observed radiation effects are compared to NRC Reg-blood cell levels and by reduced body weight gain in animals ulatory Guide 1.99, Revision 2 projections; cayses of maior out-that survived the acute gamma radiation syndrome. Inhaled pro- liers (unconservative projections) are discussed. The correla-methium caused a loss of body weight and diminished pulmo- tions of C(v) and tension test methods in weighing radiation nary function, but its only effect on blood cell levels was lym- sensitivity is assessed phocytopenia. Combined gamma irradiation and promethium lung burdens were synergistic, in that animals receiving both ra- NUREG/CR-5371: DEVELOPMENT AND USE OF RISKED-diation insults had higher morbidrty and mortality rates than BASED INSPECTION GUIDES. TAYLOR,J.H.; FRESCO,A.;

would be predicted based on the effect of either kind of radi- HIGGINS,J.: et al. Brookhaven National Laboratory, June 1989.

ation alone. Promethium lung burdens enhanced the effect of 88pp.8907100301. BNL-NUREG-52199. 50497;00' gamma radiation in rats within the first 30 days of exposure, and Risked-based system inspection guides, for nuclear power gamma radiation enhanced the later effect of promethium lung plants which have beun subjected to a probabilistic risk assess-l burdens. A model, be3ed on a statistical tool called the hazard ment (PRA), have been developed to provide guidance to NRC l

function, was applied to the data from rats exposed to either inspectors in priontizing their inspection activities. Systems are promethium aerosols or total-body gamma radiation and accu. pnontrzed, and then dominant component failure modes and rately predicted the LD(50/365) fung doses for rats exposed to human errors within those systems are identified for the above-comoined radiation insults stated purposes Examples of applications to specific types of NRC inspection activities are also presented Thus, the report NUREG/CR-5355: HTGR INGRESS ANALYSIS USING MINET provides guidance for both the development and use of nsk-VAN TUYLE,G.J.; YANG,J.W; KROEGER P.G.; et al. Brookha-based system inspection guides Work is proceeding to develop ven National Laboratory. Apnl 1989, 64pp. 8905100247. BNL-NUREG-52193. 49666:001.

a method methodology for nsk-based guidance for nuclear power plants not subject to a PRA.

Modeling of water / steam ingress into the primary (helium) cooling circuit of a High Temperature Gas Cooled Reactor NUREG/CR-5375: POST PENNSYLVANIAN REACTIVATION (HTGR) is described This modeling was implemented in the ALONG THE WASHITA VALLEY FAULT, SOUTHERN OKLAHO-MINET Code, wfuch is a program for analyzing transients in in. MA. VANARSDALE.R.; WARD.C.; COX.R. Arkansas. Univ. of.

incate fluid flow and heat transfer networks Results from the Fayetteville, AR. June 1989. 54pp. 8907060122. 50357:269 simulation of a water ingress event postulated for the Modular Surface exposures of faults of the Washita Valley fault (WVF)

HTGR are discussed. system in southern Oklahoma were studied to determine if there l

I l

l 18 Mdn Citati:n2 and Abstracts has been post- Pennsylvanian fault reactivation and to deter- calibration shifts and response time degradation, with the former mine If there has been any Ouaternary fault movement. This being the more pronounced problem. (3) The LER data base was undertaken through field mapping, by dating alluvium which contains 1,325 cases of reported problerr.s with pressure sens-overlies the faults, and by logging trenches excavated across ing systems over a nine year penod Potential age related cases the Washita Valley Fault. Investigations at several locations account for 38 percent of these problems. (4) Regulatory Guide along the fault zone revealed evidence of post-Pennsylvanian 1.118, IEEE Standard 338, and ISA Standard 67.06 can benefit displacement, and one site that showed offset as young post- from minor revisions to account for recent advances in perform-lower Cretaceous, but there is an absence of overlying strata ance testing technologies.

between those of Cretaceous age and Late Quaternary age.

Data obtained in this project indicated that (1) no surface rup- NUREG/CR-5389: ANALYSIS OF ALTERNATIVE WASTE ISOLA.

TION CONCEPTS. CHRISTIANSON.M.; BRADY,B. Itasca Con-ture has occurred along the southeaster portion of the WVF since the deposition of a Wisconsin age (18,000-20.000 yr. BP.)

sutting Group, Inc. June 1989.150pp. 8906260406. 50285 037.

terrace, (2) no fault movement has occurred along the WVF This report presents the results of numencal analysis which from Oil Creek to Wildhorse Creek within approximately the last compares the vertical and honzontal waste emplacement con-2 2,000 years, and (3) no fault movement has occurred along a cepts currently under considerattori for long-term nuclear waste storage. The two concepts are compared in terms of drift and N32 degrees W subsidiary fault en northem Murray County within the last 12,000 years. borehole stability and compliance with the suggested desigA cn-tena (U.S. DOE, CDSCP,1988). Thermal results are presented NUREG/CR-5379 V01: NUCLEAR PLANT SERVICE WATER which illustrate the thermomechanical response of the rock ad-SYSTEM AGING DEGRADATION ASSESSMENT. Phase 1. lacent to the emplacement dnfts and boreholes. Mechanical re-JARRELL.D.B.; JOHNSON.A.B; ZIMMERMAN,P.W.; et al. Bat- sults are presented which illustrate the stability of the emplace-telle Memonal institute, Pacific Northwest Laboratory. June ment rooms and boreholes as a result of in situ and thermally. j 1989. 92pp. 8907060067. PNL-6560. 50385101. induced stresses. Conclusions include the finding that the hon-Phase i of an aging assessment of nuclear power plant serv- zontal waste emplacement geometry does not meet the room ice water systems, was performed by the Pacific Northwest Lab- temperature design cntenon. It was also found that the dnft sup-oratory in support of the U.S. Nuclear Regulatory Commission portng honzontal emplacement is more sensitive to joint dis-Nuclear Plant Aging Research program. The service water placement than is the dnft employed for vertical emplacement system was selected for study because of its essential role in of waste packages.

the mitigation of and recovery from accident sconanos involving the potential for core melt. The objectives of the Service Water NUREG/CR-5391: FLOW OF GROUNDWATER AND TRANS-System (SWS) task are to identify and charactenze the principal PORT OF CONTAMINANTS THROUGH SATURATED FRAC-TURED GEOLOGIC MEDIA. STEELE.T.D.; KUNKEL.J.R.;

aging degradation mechanisms relevant to this system, t WAY,S C.; et al. in-Situ, Inc. June 1989. 400pp. 8907050526.

assess their impact on operational readiness, and to provide a methodology for the mitigation of aging on the service water p' ort documents results of several field investigations aspect of nuclear plant safety. The first two of these objectives are covered in this Phase i report. A review of available litera- dunng 1988 to charactenze the Roza Member basalt of the Wanapum Formation of the Cofumua River Group. A research ture and data base information indicated that motor operated valve torque switches (an electro mechanical device) were the wellfield was implemented and field tests conducted to catego-prime suspect in component service water system f ailures. More 800- W 1400 foot area six miles south of Cresten in Lincoln County, extensive and detailed data, however, obtained from cooperat-Washington. The relatively high-yielding Roza aquifers are sera-ing utility maintenance records and personnel accounts, contra-rated by claystone aquitards and interrupted by at least two dicted this conclusion indicating that organic accumulation and subsurface hydrologic structures. Continuous water level data corrosive attack of wetted component surfaces were, in fact' were used to assess hydraulic gradients; wellbore slug tests the pnmary degradation mechanisms.

and natural-gradient tracer tests enabled calculation of equiva-NUREG/CR 5383: EFFECT OF AGING ON RESPONSE TIME OF lent hydraulic apertures and effective porosities; information NUCLEAR PLANT PRESSURE SENSORS. HASHEMIAN,H.M.; from pumping tests permitted calculation of transmissivities and PETERSEN.K.M.; FAIN,R E.; et al. Analysis & Measurement storage coefficients; statistical analysis of fracture onentations Services Corp. June 1989.150pp. 8907070107. 50418:163. from drill cores provided data for incorporation into a discrete-Research was initiated for the effects of normal aging on per- fracture modet One conclusion of the testing is that structural formance of pressure transmitters in nuclear power plants. This and hydrologic complexities may not be apparent without a began with an expenmental assessment of the methods used dense monitonng-well network and several sterbtions of field for response time testing of transmitters, followed by aging tests tests. Wellfield expansion provided denser areal coverage for on representative transmitters. The project included a search of the 1988 tests. The report assimilates the project's findings for trie LER data base and a review of the Regulatory Guide 1.118 potential application to repository site charactenzation and per-and the related standards. The conclusions are (1) Five reason- formance prediction. Aquifer analyses in conjunction with model ably effective methodF are available for response time testing of studies identify techniques which will help to provide guidelines pressure transmitters, two of which provide on-line measure- for evaluating proposed sites for disposal of high-level nuclear ment capability. (2) The consequences of normal aging were waste in saturated fractured geologic media.

f S cendtry R::ptrt Numb 3r ind:x This index lists, in alphabetical order, the performing organization-issued report codes for the

NRC contractor and international agreement reports in this compilation. Each code is cross-

- referenced to the NUREG number for the report and to the 10-digit NRC Document Control System accession number.

SECONDARY RE00RT NUMBEfi REPORT NUMBER SECONDARY REPORT NUMBER REPORT NUMBER 83 495-01 ML NUREG 0904 S01 V01 ME A-2311 NUREG/CR-5216 RO1 83-495-01-ML ' NUREG 0904 S01 V02 MEA-2341 NUREG/CR-5357

' ANL-88-47 NUREG/CR 5274 MTR-89W00031 NUREG/CR 5332 ANL/EES-TM 364 NUREG/CR 5344 ORNL-6503 NUREG/CR-5235 BHARC700/88/017 NUREG/CR-5228 V01 ORNL/NSIC-200 NUREG/CR-2000 V08 N2 BHARC700/b8/017 NUREG/CR-52?8 V02 ORNL/NStC-200 NUREG/CR 2000 V08 N3 BHARC700/88/018 NUREG/CR-5227 S01 ORNL/NSIC 200 NUREG/CR 2000 V08 N4 BMI2120 NUREG/CR-4082 V07 ORNL/NSIC-200 NUREG/CR-2000 V08 N5 BMb2120 BMi-2162 NUREG/CR-4082 V08 NUREG/CR 5081 j$ [U /

^

ORNL/TM-11133 NUREG/CR-5350 BML2166 NUREG/CR-5172 ORNL/TM-9593 ~ NUREG/CR-4219 V05 N2 BNL-NUREG 51708 NUREG/CR 3469 V04 PARAMETER IE169 NUREG/CR-4934 BNL-NUREG 51934 NUREG/CR-4409 V03 PARAMETER lE174 NUREG/CR-5283 BNL NUREG-52166 NUREG/CR-5244 PARAMETER IE175 NUREG/CR-5284 BNL NUREG 52174 NUREG/CR-5261 PARAMETERIE182 NUREG/CR 5291 )

BNL-NUREG 52177 NUREG/CR-5268 PAR AMETER IE184 NUREG/CR 5293 BNL-NUREG 52179 NUREG/CR-5279 PNL 5210 NUREG/CR 3950 V05 BNL NUREG 52100 NUREG/CR-5281 PNL-5940 NUREG/CR-5087 BNL-NUREG-52183 NUREG/CR-5319 PNL-6560 NUREG/CR-5379 V01 '

. BNL NUREG-52191 NUREG/CR-5347 PNL $574 NUREG/CR-5187 BNL NUREG 52193 NUREG/CR-5355 PNL-6652 NUREG/CR-5227 S01 BNL NUREG-52199 NUREG/CR-5?71 PNL-6653 NUREG/CR-5228 V01 )

CONF 880822 NUREG/CP-0098 V03 PNL 6653 NUREG/CR-5228 V02 CONF 880822 NUREG/CD 0033 V01 PNL 6891 NUREG/CR-5353 CONF.880822 NUREG/CP-0098 v02 SAIC 88/1885 NUREG/CR 5246 EGG 2542 NUREG/CR-5163 HGL/89 01 NUREG/CR-5352 N 85 SAND 85-7185 NUREG/CR 4214 Pit R1 IEB 79-03 NUREG/CR 5283 SAND 86 0196 NUREG/CR 3964 V01 IEB 79-03A NUREG/CR-5284 SANDB61416 NUREG/CR-4675 IEB-86 001 NUREG/CR-5293 SAND 66-2004 NUREG/CR-4550 V02

. IEB-87 002 NUREG-1349 SAND 86-2325 NUREG/CR-4759 LA 11422-M3 NUREG/CR-5222 SAND 87-2000 NUREG/CR 4994 LA 11444 MS NUREG/CR-5237 SAND 87 7128 NUREG/CR 4961 LMF-122 NUREG/CR-5351 SAND 88 0141 NUREG/GR-5089

- MCS 890301 NUREG/CR 5356 SAND 88-1447 NUREG/CR-5252 MEA-2213 NUREG/CR 4929 SAND 881824 NUREG/CR-5193 MEA-2305 NUREG/CR-5208 SAND 88-2375 NUREG/CR-5230 MEA 2311 NUREG/CR-5216 SAND 88-7155 NUREG/CR 5118 19 l

t

Parcenal Authcr Ind3x This index lists the personal authors of NRC staff, contractor, and international agreement reports in alphabetical order. Each name is followed by the NUREG number and the title of the report (s) prepared by the author. If further information is needed, refer to the main cita-tion by the NUREG number.

ABRAHAMSON,S.

BASS.B.R.

NUREG/CH-4214 Pil R1: HEALTH EFFECTS MODELS FOR NUCLEAR NUREG/CR-5330, HIGH-TEMPERATURE CRACK ARREST BEHAVIOR POWER PLANT ACCIDENT CONSEQUENCE ANALYSIS Low LET IN 152-MM-THICK SEN WIDE PLATES OF OUENCHED AND TEM-Pediation.Part 11: Scientific Bases For Health Effects Models. PERED A 533 GRADE B CLASS 1 STEEL.

ACREE S.D. BAUM,J.W.

NUREG/CR 5257. FURTHER NEOTECTONIC STUDIES OF EARTH-QUAKE ZONES IN THE E ASTERN UNITED STATES. NUREG/CR-3469 V04. OCCUPATIONAL DOSE REDUCTION AT NU-CLEAR POWER PLANTS ANNOTATED BIBLIOGRAPHY OF SELECT-AHMAD,J. ED READINGS IN RADIATION PROTECTION AND ALARA NUREG/CR-4082 V08- CEGRADED PIPING PROGRAM PHASE NUREG/CR 4409 V03: DATA BASE ON DOSE REDUCTION RE.

II Summary Of Technical Results And Their Significance To Leak- SEARCH PROJECTS FOR NUCLEAR POWER PLANTS.

Before Break And in-Service Flaw Acceptance Cntena. March 1984 - gg

"""7 NUREG-1275 V05: OPERATING EXPERIENC.E FEEDDACK REPORT -

ALLISON.C.M. PROGRESS IN SCRAM REDUCTION Commercial Power Reactors NUREG/CR 5163 POWER BURST FACILITY (PBF) SEVERE FUEL DAMAGE TEST 1-4 TEST RESULTS REPORT. BENDER M.

NUREG/CR-4214 Pil R1. HEALTH EFFECTS MODELS FOR NUCLEAR .

ALVORD.C.M.

POWER PLANT ACCIDENT CONSEQUENCE ANALYSIS Low LET NUREG/CR 5237: USE OF LINEAR REDUCED-STIFFNESS ANALYTI- Radiation Part il Scientific Bases For Health Effects Models.

CAL MODELS TO PREDICT SEISMIC RESPONSE OF DAMAGED CONCRETE STRUCTURES. BENEDICK.W B-ARNOLD,W.D- NUREG/CR-5275- FLAME FACILITY.The Effect Of Obstacles And Trans-verse Venting On Flame Acceleration And Transition To Detonation For NUREG/CR 5235; THERMODYNAMICS OF TECHNETIUM RELATED HydrogervAir fAxtures At Large Scale TO NUCLEAR WASTE DISPOSALSolubilities of Tc(IV) Oxides And The Electrode Potential Of The Tc(Vil)/Tc(IV) Oxide Couple. BENNETT J.G.

NUREG/CR-5222. ST ATIC LOAD CYCLE TESTING OF A LOW-ASPECT-NUREG FI 5355- HTGR INGRESS ANALYSIS USING MINET. O SMNCH N NM SNM BM6 O A 0 m B AILEY,W.J. BERANEK A.F.

NUREG/CR-3950 VOS FUEL PERFORMANCE ANNUAL REPORT FOR NUREG/CP 0100. PROCEEDINGS OF THE INTERNATIONAL NUCLEAR 1987. POWER PLANT AGING SYMPOSIUM.

BAKER,K. BEYELER,W.

NUREG/CR-5227 S01: FITNESS FOR DUTY IN THE NUCLEAR POWER NUREG/CR-5089: NUMERICAL MODEUNG OF GROUND-WATER INDUSTRY.A REVIEW OF lECHNICAL ISSUES. FLOW SYSTEMS IN THE VICINITY OF THE REFERENCE REPOSt.

TORY LOCATION.HANFORD. WASHINGTON BAKER,W.E.

NUREGICR 5222: ST ATIC LOAD CYCLE TESTING OF A LOW-ASPECT. BEYELER.W.E.

RATIO SIX INCH WALL TRG. TYPE STRUCTURE TRG 4-6 (10,0 25). NUREG/CR-4759- DEMONSTRATION OF A PERFORMANCE ASSESS.

MENT METHODOLOGY FOR HIGH-LEVEL RADIOACTIVE WASTE NUREG/CR 5244: EVALUATION OF NON-RADIOLOGICAL WATER CHEMISTRY AT POWEH REACTORS. BIRKS,A.S.

BARNES,C.R NUREG/CR-5087: STEAM GENERATOR GROUP PROJECT Task 7 NUREG/CR-4082 V08, DEGRADED PIPING PROGRAM PHASE nel Repad Nshim Dasdine W Mont banunahon.

ll Summary Of Technical Results And Their Significance To leak- BLOSE.R.E.

Before Ureak And in-Service Flaw Acceptance Cntena. March 1984 -

January 1989 NUREG/CR-4994 CORE CONCRETE INTERACTIONS USING MOLTEN STEEL WITH ZlRCONIUM ON A BASALTIC BASEMAT:THE SURC 4 BARNES.V. EXPERIMENT.

NUREG/CR-5227 S01- FITNESS FOR DUTY IN THE NUCLEAR POWER INDUSTRY.A REVIEW OF TECHNICAL ISSUES. BOL NU E /CR-5330. HIGH-TEMPERATURE CRACK-ARREST BEHAVIOR BARNES,V.E. IN 152-MM-THICK SEN WIDE PLATES OF OUENCHED AND TEM-NUREG/CR 522B VD1- TECHNIOUES FOR PREPARING FLOWCHART- PERED A 533 GRADE B CLASS 1 STEEL.

FORMAT EMERGENCY OPERATING PROCEDURES Background (Sections 10-9 0) BONANO,E.J.

NUREG/CR-5228 V02. TECHNIOUES FOR PREPARING FLOWCHART- NUREG/CR-4759. DEMONSTRATION OF A PERFORMANCE ASSESS-FORMAT EMERGENCY OPERATING PROCEDURES User's Manual MENT METHODOLOGY FOR HIGH LEVEL RADIOACTIVE WASTE (Sections 100-17.0). DISPOSAL IN BASALT FORMATIONS BASDEKAS.D.L BOOK.S.

NUREG-1341. REGULATORY ANALYSIS FOR THE RESOLUTION OF NUREG/CR-4214 Pil R1 HEALTH EFFECTS MODELS FOR NUCLEAR GENEMIC ISSUE 115, ENHANCEMENT OF THE RELIABILITY OF THE POWER PLANT ACCIDENT CONSEQUENCE ANALY$lS Low LET WESTINGHOUSE SOLID ST ATE PROTECTION SYSTEM. Radiation Part II. Scientific Bases For Healih Effects Models 21

l I 22 Person:1 Author Index l-BRADY,B- COLEMAN,N.

NUREG/CR-53B9: ANALY$1S OF ALTERNATIVE WASTE ISOLATION NUREG/CR-5089. NUMERICAL MODELING OF GROUND-WATER CONCEPTS. FLOW SYSTEMS IN THE VICINITY OF THE REFERENCE REPOSI-TORY LOCATION,HANFORD. WASHINGTON.

NUREG/CFb5089: NUMERICAL MODELING OF GROUND-WATER COLQUHOUN,0.J.

FLOW SYSTEMS IN THE VICINITY OF THE REFERENCE REPOSk NUREG/CR-5257. FURTHER NEOTECTONIC STUDIES OF EARTH-TORY LOCATION.HANFORD. WASHINGTON. QUAKE ZONES IN THE EASTERN UNITED STATES.

BRINSTER.K.F. CONWAY,J.T.

NUREG/CR4759: DEMONSTRATION OF A PERFORMANCE ASSESS. NUREG-1349: COMPILATION OF FASTENER TESTING DATA RE-MENT METHODOLOGY FOR HIGH LEVEL RADIOACTIVE WASTE CElVED IN RESPONSE TO NRC COMPLIANCE BULLETIN 87 02.

DISPOSAL IN BASALT FORMATIONS.

BROCKMANN,J.E. NUREG/CR-4994: CORE CONCRETE INTERACTIONS USING MOLTEN NUREG/CR-4994: CORE-CONCRETE INTERACTIONS USING MOLTEN STEEL WITH ZlRCONIUM ON A BASALTIC BASEMRTHE SURC-4 STEEL WITH ZlRCONIUM ON A BASALTIC BASEMAT;THE SURC-4 EXPERIMENT.

EXPERIMENT.

CORREIA,R.P.

NUREG/CR-5252: AEROSOL SAMPLING AND TRANSPORT EFFICIEN.

CY CALCULATION (ASTEC) AND APPLICATION TO SURTSEY/DCH NUREG-1342: A STATUS REPORT REGARDING INDUSTRY IMPLE-AEROSOL SAMPLING SYSTEM Code Version 1.0: Code Descnption MENTATION OF SAFETY PARAMETER DISPLAY SYSTEMS.

And User's Manual.

CORWIN,W.R.

BROEK,D. NUREG/CR-4219 VOS N2: HEAVY-SECTION STEEL TECHNOLOGY NUREG/CR4929. THE EFFECTS OF VARIABLE AMPLITUDE LOADING PROGRAM. Semiannual Progress Report For April-September 1988.

ON A 533-D STEEL IN HlCH-TEMPERATURE AIR AND REACTOR COX'R WATER ENVIRONMEN TS.

NUREG/CR 5375: POST PENNSYLVANIAN REACTIVATION ALONG CnUST,F. THE WASHITA VALLEY FAULT. SOUTHERN OKLAHOMA.

NUREG/CR-4082 V08. DEGRADED PIP:NG PROGRAM - PHASE CRAMOND,W.R.

IISummary Of Technical Results. And Their Sigruficance To Leak' NUREG/CR4550 V02: ANALYSIS OF CORE DAMAGE FREQUENCY Before-Break And in-Service Flaw Acceptance Cntena. March 1984 '

FROM INTERNAL EVENTS: EXPERT JUDGMENT ELICITATION Part January 1989. 1: Expert Panet Results. Part 2' Project Staff Results.

NUREG/CR-5230. SHUTDOWN DECAY HEAT REMOVAL EUNCHER C NUREG/Chl-4214 Pil R1: HEALTH EFFECTS MODELS FOR NUCLEAR POWER PLANT ACCIDENT CONSEQUENCE ANALYSIS. Low LET P#

Radiation.Part 11: ScMtific Bases For Health Effects Models- CROUCH D.

DUSCHBOM,R.L NUREG/CR 5319. RISK SENSITIVITY TO HUMAN ERROR.

NUREG/CR-5353: INHALED (147)PM AND/OR TOTAL BODY GAMMA CRUZ,C.

RADIATION.EARLY MORTALITY AND MORBIDITY IN RATS. NUREG/CR-5244: EVALUATION OF NON. RADIOLOGICAL WATER CUSH,LL NUREG-1354: FITNESS FOR DUTY IN THE NUCLEAR POWER CULLEN.W.H.

INDUSTRY. RESPONSES TO PUBLIC COMMENTS. NUREG/CR-4929: THE EFFECTS OF VARIABLE AMPLITUDE LOADING ON A 533-B STEEL IN HIGH. TEMPERATURE AIR AND REACTOR NUREG'/C'R 5353: INHALED (147)PM AND/OR TOTAL-BODY GAMMA RADIATION EARLY MORTALITY AND MORBIDITY IN FIATS. CWALINA,G.C.

NUREG-1349: COMPILATION OF FASTENER TESTING DATA RE-CARLSON,E.R.

CEIVED IN RESPONSE TO NRC COMPLIANCE BULLETIN 87 02.

NUREG/CR-5163. POWER BURST FACILITY (PBF) SEVERE FUEL DAMAGE TEST 14 TEST RESULTS REPORT. DAUN,C.L NUREG/CR 5344; REPLACEMENT ENERGY COST ANALYSTS PACK-CASE,F.L AGE (RECAP)' USER'S GUIDE.

NUREGICR 5235' THERMODYNAMICS OF TECHNETIUM RELATED TO NUCLEAR WASTE DISPOSALSolubHities of Tc(IV) Oxides And DAVIS.P.

The Electrode Potential Of The Tc(Vil)/Tc(IV) Oxide Couple. NUREG/CR-5089- NUMERICAL MODELING OF GROUND-WATER FLOW SYSTEMS IN THE VICINITY OF THE REFERENCE REPOSI-CASTROGIVANNI TORY LOCATION.HANFORD, WASHINGTON.

NUREG/CR-5244 EVALUATION OF NON-RADIOLOGICAL WATEFI CHEMISTRY AT POWER REACTORS. DAVIS.P.A.

NUREG/CR-4759. DEMONSTRATION OF A PERFORMANCE ASSESS-CHA,Y.S. MENT METHODOLOGY FOR HIGH-LEVEL RADIOACTIVE WASTE NUREG/CR-5274. NUMERICAL SIMULATION OF NATURAL CIRCULA. DISPOSAL IN BAS ALT FORMATIONS.

TION PHENOMENA IN A PWR DURING TMLB' TRANSIENTS PRIOR TO CORE DAMAGE. DE AN,R.S.

NUREG/CR 4934: CLOSEOUT OF IE BULLETIN 83-06 Nonconforming CHENG,T.C. Matenals Supplied By Tutie-Line Corporation Facilities At Long Island NUREG/CR-5163. POWER BURST FACILITY (PBF) SEVERE FUEL City. New York; Houston, Texas: And Carot Stream. lllinois.

DAMAGE TEST 1-4 TEST RESULTS REPORT. NU9EG/CR 5283. CLOSEOUT OF IE BULLETIN 79-0310NGITUDINAL WELD DEFECTS IN ASME SA-312 TYPE 304 STAINLESS STEEL CHRISTENSEN,J. PIPE SPOOLS MANUFACTURED BY YOUNGSTOWN WELDING AND NUREG/CR-5227 S01: FITNESS FOR DUTY IN THE NUCLEAR POWER ENGINEERING COMPANY.

INDUSTRY.A REVIEW OF TECHNICAL ISSUES NUREG/CR-52B4 CLOSEOUT OF IE BULLETIN 79-03A: LONGITUDINAL WELD DEFECTS IN ASME SA-312 TYPE 304 STAINLESS STEEL CHRISTIANSON.M- PIPE.

NUREGICR 5336 SENSITIVITY OF THE STABILITY OF A WASTE EM- NUREG/CR-5291: CLOSEOUT OF IE BULLETIN 80 09 HYDRAMOTOR PLACEMENT DRIFT TO VARIATION IN ASSUMED ROCK JOINT PA- ACTUATOR DEFICIENCIES.

RAMETERS IN WELDED TUFF. NUREG/CR-5293: CLOSEOUT OF IE BULLETIN 86-01 MINIMUM FLOW NUREG/CR-5389 ANALYSIS OF ALTERNATIVE WASTE ISOLATION LOGIC PROBLEMS THAT COULD DISABLE RESIDUAL HEAT RE.

CONCEPTS. MOVAL PUMPS.

l l

P:r0:n I Auth:r ind;x 23 DECKER,J.R. FIRST,M W.

NUREG/CR4353 INHALED 4147)PM AND/OR TOTAL BODY GAMMA NUREG/CP-0098 V01: PROCEEDINGS OF THE 20TH DOE /NRC NU-RADIATION.EARLY MORTALITY AND MORBIDfTY IN RATS. CLEAR AIR CLEANING CONFERENCE. Sections 1 5. Held in Boston, Massachusetts, August 22-25,1988.

DENNISTON.C.

NUREG/CP-0098 V02: PROCEEDINGS OF THE 20TH DOE /NRC NU.

NUREG/CR-4214 Pil R1: HEALTH EFFECTS MODELS FOR NUCLEAR CLEAR AIR CLEANING CONFERENCE. Sessions 6 15. Held in POWER PLANT 4.;CIDENT CONSEQUENCE ANALYSIS. Low LET Boston, Massachusetts, August 22-25,1988.

Radiation Part it: Scientit:c Bases For Health Effects Models.

F OLE Y,W.J.

DEMTA NUREG/CR 4934. CLOSEOUT OF IE BULLETIN 83-06. Nonconforming NUREG/CR 5330 HIGH-TEMPERATURE CRACK. ARREST BEHAVIOR Materats Suppled By Tut +Line Corporation Facdites At Long Island IN 152 MM THICK SEN WIDE PLATES OF OUENCHED AND TEM- City, New York; Houston. Texas: And Carol Stream. Illinois.

PERED A $33 GRADE B CLASS 1 STEEL-NUREG/CR42R3: CLOSEOUT OF IE BULLETIN 79-03 LONGITUDINAL DOCTOR'P.G WELD DEFECTS IN ASME SA-312 TYPE 304 STAINLESS STEEL NUREG/CR 5087. STEAM GENERATOR GROUP PROJECT. Task 7 y f[g py Final Report Post-Serwce Basehne Eddy Current Examination-NUREG/CR 5284: CLOSEOU'T OF IE BULLETIN r9-03A: LONGITUDINAL DOMANUS.H.M. WELD DEFECTS IN ASME SA-312 TYPE 304 STAINLESS STEEL T N PH AN P RDR T B TR NT PR NU G/CR 2 : OS UT OF IE BULLETIN 80-09 HYORAMOTOR NUREG/CR4293. CLOSEOUT OF IE BULLETIN 86-01. MINIMUM FLOW DOSANJH,$.S, LOGIC PROBLEMS THAT COULD DISABLE RESIDUAL HEAT RE-NUREG/CR 5193: MELPROG.PWR/ MOD 1: A TWO-DIMENSIONAL, MOVAL PUMPS.

MECHANISTIC CODE FOR ANALYSIS OF REACTOR CORE MELT PR ON AND VESSEL ATTACK UNDER SEVERE ACCIDENT

~

NURE /CR4349 STEAM GENERATOR OPERATING EXPERIENCE. UPDATE FOR 1987-1988.

DUNWOODY,W.E.

NUREG/CR4222 STATIC LOAD CYCLE TESTING OF A LOW ASPECT- FRESCOA RATIO Six-INCH WALL TRG TYPE STRUCTURE TRG-4-6 (1.0,0.25) NUREG/CR 5371: DEVELOPMENT AND USE OF RISKED-BASED IN-SPECTION GUIDES EASON.E.D.

NUREG/CR4358: IMPROVED MODEL FOR PREDICTING J-R CURVES FULLWOOD,R.

FROM CHARPY DATA. Phase 1 Final Report NUREG/CR 5268 AGING STUDY OF BOILING WATER REACTOR RE-SIDUAL HEAT REMOVAL SYSTEM.

ECKENRODE,R.J.

NUREG-1342: A STATUS REPORT REGARDING !NDUSTRY IMPLE. GHADIAll,N.

MENTATION OF SAFETY PARAMETER DISPLAY SYSTEMS. NUREG/CR 4082 V08 DEGRADED PIPING PROGRAM PHASE 11 Summary Of Technical Resuits And Their Significance To Leak-EMRIT R. Before-Break And in Service Flaw Acceptance Cnteria March 1984 -

NUREG 0933 SO9: A PRIORITIZATION OF GENERIC SAFETY ISSUES. January 1989, ERICBON.D.M. GILBERT,E.

NUREG/CR 5230. SHUTDOWN DECAY HEAT REfviOVAL NUREG/CR-4214 Pil R1: HEALTH EFFECTS MODELS FOR NUCLEAR ANALYSIS. PLANT CASE STUDIES AND SPECIAL ISSUES Summary Report, POWER PLANT ACCIDENT CONSEQUENCE ANALYSIS Low LET Radiation.Part II: Scientific Bases For Heatlh Effects Models FAIN R.E.

GINGRICH J.J.

NUREG/CR 5383. EFFECT OF AGING ON RESPONSE TIME OF NU- NUREG/CR 5383. EFFECT OF AGING ON RESPONSE TIME OF NU-CLEAR PLANT PRESSURE SENSORS-CLEAR PLANT PRESSURE SENSORS.

FARRAR.C.R.

GOLDMAN,LA.

NUREG/CR 5222: STATIC LOAD CYCLE TESTING OF A LOW. ASPECT.

NUREG/CR 5246: A METHODOLOGY TO AS$1ST IN CONTINGENCY RATIO Six-INCH WALL TRG-TYPE STRUCTURE TAG 4 6 (1.0. 0.25).

NUREG/CR-5237: USE OF LINEAR REDUCED-STIFFNESS ANALYTI- PLANNING FOR PROTECTION OF NUCLEAR POWER PLANTS AGAINST LAND VEHICLE BOMBS' CAL MODELS TO PREDICT SElSMIC RESPONSE OF DAMAGED CONCRETE STRUCTURES.

GOME2AD.

FAWCETT-LONG,J. NUREG/CR 4994. CORE CONCRETE INTERACTIONS USING MOLTEN NUREG/CR4227 S01: FITNESS FOR DUTY IN THE NUCLE AR POWER STEEL WITH ZlRCONIUM ON A BASALTIC BASEMAT:THE SURC-4 INDUSTRY.A REVIEW OF TECHNICAL ISSUES. EXPERIMENT.

FERRIS,R.H. GOODMAN,P.C.

NUREG/CR 5087: STEAM GENERATOR GROUP PROJECT. Task 7 NUREG 1342. A STATUS REPORT REGARDING INDUSTRY IMPLE-Final Report Post Serwce Baschne Eddy Current Exarnination. MEN 1 ATION OF SAFETY PARAMETER DISPLAY SYSTEMS FIEi.DS.R.J. GORE.B.F.

NUREG/CR4330: HIGH-TEMPERATURE CRACK ARREST BEHAVIOq NUREG/CR 5187: PRA APPLICATIONS PROGRAM FOR INSPECTION IN 152-MM-THICK SEN WIDE PLATES OF OUENCHED AND TEM. AT CALVERT CLIFFS UN!T 1 NUCLEAR POWER PLANT.

PERED A 533 GRADE B CLASS 1 STEEL GORE M.L.

FILIPY,R.E. NUREG/CR 5379 V01: NUCLEAR PLANT SERVICE WATER SYSTEM NUREG/CR-5351: MODELS FOR PULMONARY LETHALITY AND MOR-AGING DEGRADATION ASSESSMENT. Phase 1.

BIDITY AFTER 1RRADIATION FROM INTERNAL AND EXTERNAL SOURCES. GRIMES.B.K.

NUREG/CR4353: INHALED (147)PM AND/OR TOTAL-BODY GAMMA NUREG-1354 FITNESS FOR DUTY IN THE NUCLEAR POWER RADIATION EARLY MORTALITY AND MORBIDITY IN RATS INDUSTRY: RESPONSES TO PUBLIC COMMENTS.

FINN.S.P. GRUEL,R.L NUREG/CR 5246. A METHODOLOGY TO ASSIST IN CONTINGENCY NUREG/CR 5228 V01: TECHNIQUES FOR PREPARING FLOWCHART-PLANNING FOR PROTECTION OF NUCLEAR POWER PLANTS FORMAT EMERGENCY OPERATING PROCEDURES Background AGAINST LAND VEHICLE BOMBS. (Sections 1.0-0 0)

l L

Tef Persovial/ Author irulex:

l3 . NUREG/CR-5228 V02: TECHNIQUES FOR PREPARING FLOWCHART- NUREG/CR 5291: CLOSEOUT OF IE BULLETIN BD-09:HYDRAMOTOR FORMAT EMERGENCY OPERATWG PROCEDURES. User's Manual ACTUATOR DEFICIENCIES.

(k clons10.0-17.0). . NUREG/CR 5293: CLOSEOUT OF IE BULLETIN 06 01: MINIMUM FLOW LOGIC PROBLEMS THAT COULD DISABLE RESIDUAL HEAT RE-GUERRIERLD. uoyAtpuups, NUREG/CH 4062 V07: DEGRADED PIPING PROGRAM - PHASE il Seventh Program Report October 1987. January 1989. HERTZBERG,V. '

NUREG/CR 4082 Voe: DEGRADED PIPING PROGRAM . PHASE NUREG/CR4214 Pil R1: HEALTH EFFECTS MODELS FOR NUCLEAR 11 Summary Of Technical Results And Their Segnifcance To Leak- POWER PLANT ACCIDENT CONSEQUENCE ANALYSIS. Low LET Before-Break And tr> Service Flaw Acceptarco Critena. March 1984 i Radiation.Part it:Scente Bases For Health Effects Models.

Ja cuary 1989.

HIGGINSA l.- AO.CR. NUREG/CR-5319: RISK SENSITIVITY TO HUMAN ERROR.

NUREG/CR4961: A

SUMMARY

OF HYDROGEN-AIR DETONATION EX- NUREG/CR-5371: DEVELOPMENT AND USE OF RISKED. BASED IN-PERIMENTS. SPECTION GUIDES.

CUNTER,W.

SDULH REM VAL Y TE UREG CR 5216. POST-IRRADIATION FRACTURE TOUGHNESS CHARACTER 12ATION OF FOUR LAB-MELT PLATES.

HABER.S. .

NUREG/CR 5216 RO1: POST IRRADIATION FRACTURE TOUGHNESS NUREG/CR-5319 RISK SENSITIVITY TO HUMAN ERROR. CHARACTERl2ATION OF FOUR LAB-MELT PLATES.

HACKETT.E.M. HOBBINS,R.R.

NUREG/CFv5238: DEVELOPMENT OF AN ENGINEERING DEFINITION NUREG/CR-5163: POWER BURST FACILITY (PBF) SEVERE FUEL OF THE EXTENT OF J SINGULARITY CONTROLLED CRACK DAMAGE TEST 14 TEST RESULTS REPORT.

GROWTH.

HORA,$.C. -

HAGRMAN,D.L NUREG/CR4550 V02: ANALYSIS OF CORE DAMAGE FREQUENCY NUREG/CR-5163: POWER BURST FACILITY (PDF) SEVERE FUEL FROM INTERNAL EVENTS: EXPERT JUDGMENT ELICITATIONPart DAMAGE TEST 14 TEST RESULTS REPORT. 1: Expert Pane: Results. Part 2: Project Staff Results.

HAHN,F. HUNTER.RJL.

NUREG/CR4214 Pil R1: HEALTH EFFECTS MODELS FOR NUCLEAR NUREG/CR-3964 VD1: TECHNIQUES FOR DETERMINING PROBABIL.

POWER PLANT ACCIDENT CONSEQUENCE ANALYSIS. Low LET ITIES OF EVENTS AND PROCESSES AFFECTING THE PERFORM-Radiaten.Part IL Scientifs Bases for Health Effects Modeis- ANCE OF GEOLOGIC REPOSITORIES. Literature Review.

HAHN,F.F.

HUYAKORN.P.S

! NUREG/CR-5351: MODELS FOR PULMONARY LETHALITY AND MOR- NUREG/CR-5352: VAM2D - VARIABLY SATURATED ANALYSIS BIDITY AFTER 1RRADIATION FROM INTERNAL AND EXTERNAL MODEL IN TWO DIMENSIONS. Version 50 With Hysteresis And SOURCES. Chained Decay Transport Documentaten And User's Guide.

HARRIS M.S.

NUREG/CR.5107 M A APPLICATIONS PROGRAM FOR INSPECTION ISAKSONAS.

AT CALVERT CLIFFS UNIT 1 NUCLEAR POWER PLANT, NUREG/CR4228 VO1: TECHNIQUES FOR PREPARING FLOWCHART..

FORMAT EMERGENCY OPERATING PROCEDURES Background HARTWELL.J.K. (Sections 1.0-9.0L NUREG/CR-5163: POWER BURST FACILITY (PBF) SEVERE FUEL NUREGICR4228 V02: TECHNIQUES FOR PREPARING FLOWCHART-DAMAGE TEST 14 TEST RESULTS REPORT. FORMAT EMERGENCY OPERATING PROCEDURESUser's Manual (Sections 10.0 17.0).

NUREG/CR-5087. STEAM GENERATOR GROUP PROJECT. Task 7 JAMES.J.W.

Fmat Report Post Sennce esseline Eddy Current Exammaten. NUREG/CR4246; A METHODOLOGY TO ASSIST IN CONTINGENCY PLANNING FOR PROTECTION OF NUCLEAR POWER PLANTS NURE C 5 83: EFFECT OF AGING ON RESPONSE TIME OF NU.

CLEAR PLANT PRESSURE SENSORS. JARRELL.D.B.

HATCH,S.W NUREG/CR 5379 V01: NUCLEAR PLANT SERVICE WATER SYSTEM AGING DEGRADATION ASSESSMENT. Phase L' .

NUREG/CR 5230: SHUTDOWN DECAY HEAT REMOVAL ANALYSIS PLANT CASE STUDIES AND GPECIAL ISSUES. Summary JENNINGS.S.D.

Report NUREG/CP40098 V03: PROCEEDINGS OF THE 20TH DOE /NRC NU-HAUTH.J CLEAR AIR CLEANING CONFERENCE.An Index To The 1st ThrouDb 20th AEC/ERDA/ DOE And DOE /NRC Nuclear Air Cleanmg Confer-NUREG/CR.5227 501: FITNESS FOR DUTY IN THE NUCLEAR POWER INDUSTRY;A REVIEW OF TECHNICAL ISSUES. ences.

HAWTHORNEAR. JO J.H.

NUREG/CR 5357 AN EXPLORATORY STUDY OF ELEMENT INTERAC. NUREG/CR4281: VALUEllMPACT ANALYSES OF ACCIDEfC PRE-TlONS AND COMPOSITION DEPENDENCIES IN RADIATION SENSI. VENTIVE AND MITIGATIVE OPTIONS FOR SPENT FUEL POOLS.

TiVITY DEVELOPMENT. Final Report.

HENKEL,P.R. NUREG/CR4379 V01: NUCLEAR PLANT SERVICE WATER SYSTEM NUREG/CR 4175: IN-PILE OBSERVATION OF FUEL AND CLAD RELO. AGING DEGRADATION ASSESSMENT. Phase 1.

CATION CUillNG LMFBR CORE-DISRUPTIVE ACCIDENTS HENNICK,A. NUREG/CR-4082 V07; DEGRADED PIPtNG PROGRAM - PHASE NUREG/CRo r.34. CLOSEOUT OF IE BULLETIN 83-06.Nonconformmg 11 Seventh Program Report. October 1987 - January 1989.

. Matenals Suppled By Tube-Lme Corporaton fac61 sties At Long Island NUREG/CR 40B2 V0B: DEGRADED PIPING PROGRAM - PHASE

11. Summary Of Technical Results And Their Significance To Leak.

Citv. New York; Houston. Texas: And Carol Stream lilmois NUREG/CR 5283. CLOSEOUT OF IE BULLETIN 79 03. LONGITUDINAL Belore. Break And tr>Servce Flaw Acceptance Critena, March 1984 -

WELD DEFFCTS IN ASME SA.312 TYPE 304 STAINLESS STEEL January 1989 PIPE SPOOLS MANUFACTURED BY YOUNGSTOWN WELDING AND ENGINEERING COMDANY. JOYCE.J.A.

. NUREG/CR.5284 CLOSEOUT OF IE BULLETIN 79-03A: LONGITUDINAL NUREG/CR 5238: DEVELOPMENT OF AN ENGINEERING DEFINITION WELD DEFECTS IN ASME SA-312 TYPE 304 STAINLESS STEEL OF THE EXTENT OF J SINGULARITY CONTROLLED CRACK PIPE. GROWTH.

P;rsonal Author index 25 JULIEN.J.T. LAPINSKY,G.

NUREG/CR4118: LEAK AND STRUCTURAL TEST OF PERSONNEL NUREG 1358 LESSONS LEARNED FROM THE SPECIAL INSPECTION AIRLOCK FOR LWR CONTAINMENTS SUBJECTED TO PRESSURES PROGRAM FOR EMERGENCY OPERATING AND TEMPERATURE S BEYOND DESIGN LIMITS. PROCEDURES Conducted March Octotier 1988 JURYEVICH.K.M. LAPINSKY,G W.

NUREG/CR 5172: TACTICAL TRAINING REFERENCE MANUAL NUREG-1342. A STATUS REPORT REGARDING INDUSTRY IMPLE-MENTATION OF SAFETY F ARAMETER D SPLAY SYSTEMS.

NUREG/CR 5344. REPLACEMENT ENERGY COST ANALYSIS PACK. LAUHALA.K.E.

AGE (FIECAP) USER'S GUIDE. NUREG/CR4353 INHALED (147)PM AND/OR TOTAL-BODY GAMMA RADIATION EARLY MORTALITY AND MORBIDITY IN RATS.

NUREG/CR4330: HIGH-TEMPERATURE CRACK ARREST BEHAVIOR LE E.J.H.

IN 152-MM. THICK SEN WIDE PLATES OF OVENCHED AND TEM. NUREG/CR 4961: A

SUMMARY

OF HYDROGEN AIR DETONATION Ex-PERED A 533 GRADE B CLASS 1 STEEL PE RIMENTS.

KHAN.T.A. LEONARD W.R.

NUREG/CR-3469 VD4. OCCUPATIONAL DOSE REDUCTION AT NO. NUREG/CR4081: TACTICAL EXERCISE PLANNING HANDBOOK.

CLEAR POWER PLANTS. ANNOTATED BIBLIOGRAPHY OF SELECT, NUREG/CR 5172. TACTICAL TRAINING REFERENCE MANUAL ED FIEADINGS IN RADIATION PROTECTION AND ALARA NUREG/CR 4409 V03 DATA BASE ON DOSE REDUCTION FIE, UGON,D.M.

SEARCH PROJECTS FOR NUCLEAR POWER PLANTS. NUREG/CR4332:

SUMMARY

AND ANALYSIS OF PUBLIC COMMENTS ON NUREG-1317. FIEGULATORY OPTIONS FOR NUCLEAR PLANT KLINGELHOEFER LICENSE RENEWAL.Fmal Report.

NUREG/CR 5081: TACTICAL EXERCISE PLANNING HANDDOOK, NUREG/CR-5172: T ACTICAL TRAINING REFERENCE MANUAL UU K V*

NUREG/CR 5274: NUMERICAL SIMULATION OF NATURAL CIRCULA-KNYST AUT AS,R. TION FHENOMENA IN A PWR DURING TMLB' TRANSIENTS PRIOR NUREG/CR-4961; A

SUMMARY

OF HYDROGLN-AIR DETONATION Ex. TO CORE DAMAGE, LOBNER,P.R.

KOCH.T.H. NUREG/CR4246 A METHODOLOGY TO AS$1ST IN CONTINGENCY NUREG/CR-5246 A METHODOLOGY TO ASSIST IN CONTINGENCY PLANNING FOR PROTECTION OF NUCLEAR POWER PLANTS PLANNING FOR PROTECTION OF NUCLEAR POWER PLANTS AGAINST LAND VEHICLE BOMBS.

AGAINST LAND VEHICLE BOMBS.

KOENIG,R.A. NUREG/CR 5268. AGING STUDY OF DOILING WATER REACTOR RE-NUREG/CH-5391: FLOW OF GROUNDWATER AND TRANSPORT OF SIDUAL HEAT REMOVAL SYSTEM.

CONTAMINANTS THROUGH SATURATED FRACTURED GEOLOGIC MEDIA. LOGSDON M.

NUREG/CR-50B9 NUMERICAL MODELING OF GROUND-WATER KONO.B.K. FLOW SYSTEMS IN THE VICINITY OF THE REFERENCE REPOSI-NUREG/CR4228 Vot: TECHNIOUES FOR PREPARING FLOWCHART. TORY LOCATION.HANFORD. WASHINGTON.

f ORMAT EMERGENCY OPERATING PROCEDURES Background LONG.S.M.

N RE R5 8 2. TECHNIQUES FOR PREPARING FLOWCHART. NUREG/CR4371: DEVELOPMENT AND USE OF RISKED' BASED IN-FORMAT EMERGENCY OPERATING PROCEDURES User's Manual SPECTION GUIDES (Sections 10()17 0). LOVELACE,W.H.

B NUREG-0020 V13 N05: LICENSED OPERATIN3 REACTORS STATUS KOOL.J'G/CR4382.

NURE VAM2D VARIABLY SATURATED ANALYSIS sta As O W 3W % h 4 MODEL IN TWO DIMENSIONS *, ersion 5.0 With Hysteresis And LOW S.R.

Chained Decay Transport Documentation And Uber's Guede NUREG/CR 533D: HIGH TEMPERATURE CRACK ARREST BEHAVIOR KRAMER,G IN 152-MM-T*llCK SEN WIDE PLATES OF OUENCHED AND TEM-NUREG/CR-4082 V07: DEGRADED PIPING PROGRAM - PHASE D A 533 NE B MS t mR 11 Seventh Program Report October 1987 - January 1989 LUCERO.D.A.

NUREG/CR-4DB2 V0B DEGRADED PIPING PROGRAM - PHASE NUREG/CR 4994 CORE CONCRETE INTERACTIONS USING MOLTEN llSummary Of Technical Results And Their Significance To Leal Before-Dreak And in Service Flaw Acceptance Cntena, March 1964 ' STEEL WITH ZlRCONtVM ON A BASALTIC SASEMAT THE SURC 4 January 1989. EXPERIMENT.

LUCKAS,W.

KROEGER.P.G.

NUREG/CR 5319 RISK SENSITIV!TY TO HUMAN ERROR NURE G/CR.5261: SAFETY EVALUATION OF MHTGR LICENSING BASIS ACCIDENT SCENARIO 3 MALLEN,A.N.

NURE G/CR4355: HTGR INGRESS ANALYS!S USING MINET NUREG/CR 5355: HTGR INGRESS ANALYSIS USING MINET.

KUFFEL,E.G.

M ANN.C.J.

NUREG/CR.5353. INHALED (147)PM AND/OR TOTAL BODY GAMMA NUREG/CR-3964 VD1: TECHNIQUES FOR DETERMINING PROBABIL-RADlATION EARLY MORTALITY AND MORBIDITY IN RATS ITIES OF EVENTS AND PROCESSES AFFECTING THE PERFORM-KUNKEL.J.R. ANCE OF GEOLOGIC REPOS: TORIES Literature Review.

NUREG/CR 5391: FLOW OF GROUNDWATER AND TRANSPORT OF MARSCHALL.C.W.

CONTAMINANTS THROUGH SATURATED FRACTURED GEOLOGIC NUREG/CR 4082 V07: DEGRADED PIPING PROGRAM - PHASE MEDIA. Il Seventt Program Report October 19E7 January 1989 NUREG 'CR-4DB2 V0B DEGRADED PIPING PROGRAM PHASE LANDOW.M. li Summary Of Technical Results And Then S'Onif8cance 10 Leak-NUREG/CR-4082 VD7. DEGRADED PIPING PROGRAM PHASE Before-Break And in-Service Flaw Acceptance Cntena. March 1984 -

11 Seventh Program Report October 1967 - January 1989 January 1969 NURE G/CR-4002 Vue DEGRADED PIPING PROGRAM PHASE ilSummary Of Techmcel Results And Traw Sqn$cance To Leak. MARTINSON,Z.R.

Before Break And in.Servece Flaw Acceptance Cntena, March 1984 - NUREG/CR4163. POWER BURST FACILITY (PBF) SEVERE FUEL January 1909 DAMAGE TEST 1-4 TEST RESULTS REPORT i

26 Person:1 Author index MAKON,H, OSBORNE.M.F.

NUREG/CR.42t4 Pil R1: HEALTH EFFECTS MODELS FO3 NUCLEAR NUREG/CR-4721: THE USE OF FIBER OPTICS FOR REMOTE TEM-POWER PLANT ACCIDENT CONSEQUENCE ANALYSIS Low LET PERATURE MEASUREMENT IN FISSION PRODUCT RELEASE Radiation.Part il Scentihc Bases For Health Effects Models TESTS.

MCCABE,0.E. PAPASPYROPOULOS NUREG/CR4208. WARM PRESTRESS MODELING: COMPARISON OF NUREG/CR.4082 V0B- DEGRADED PIPING PROGRAM - PHASE MODELS AND EXPERIMENTAL RE SULTS It Summary Of Techncal Resutts And Their Sigmficance To Leak.

Before.Bieak And IrvSemce Flaw Acceptance Cntena. March 1964 -

MCGEE.D.R. January 1989 NUREG/CR 5353 INHALED (147)PM AND/OR TOTAL-BODY GAMMA RADIATION EARLY MORTAllTY AND MORBIDITY IN RATS. P ARK.J.F.

NUREG/CR4353. INHALED (147)PM AND/06 ?OTAL DODY GAMMA MCNAMARA.N- RADIATION EARLY MORTALITY AND MORBID <1Y IN RATS.

l s NUREG.0837 V06 N04. NRC TLD DIRECT RADIATION MONITORING l NETWORK. Progress Report October.Ducember 19B8, PARKER.L.B.

NUREG-1349 COMPILATION OF FASTENER TESTING DATA RE-MEYER.RL CEIVED IN RESPONSE TO NRC COMPUANCE BULLETIN 87 02.

NUREG/CR4235: THERMODYt4AMICS OF TECHNETIUM RELATED 9

TO NUCLEAR WASTE DISPOSAL $olubihties of TC(IV) Oxides And PASUPATHl.V.

The Electrode Potental Of The Tc(vil)/Tc(IVFOrsde Couple. NUREG/CR-4082 V0B- DEGRADED PIPING PROGRAM PHASE le Summary Of Techercal Results And Their Signifmance To Leak-MILIAN.L g piore. Break And in-Servce Flaw Acceptance Cntena. March 1984 -

NUREG/CR 5279 SULFATE-ATTACK RESIST ANCE AND GAMMA lR. J anuary 1989.

HADIATION RESGTANCE OF SOME PORTLAND CEMENT BASED MORTARS. PE NNELL,W.E.

NUREG/CR4350: MISSION SURVEY FOR THE PRESSURE VESSEL MILSTEAD.W. FIESEARCH USERS' F ACILITY (PVRUF).

NUREG.0933 $09 A PRIORITIZATION OF GENERIC SAFETY ISSUES.

PERKINS.K.R.

MOORE,C. NURLG/CR-5261: VALUE/ IMPACT ANALYSES OF ACCIDENT PRE-NUREG/CR-5227 SDI: FITNESS FOR DUTY IN THE NUCLEAR POWER VENTIVE AND MITIGATIVE OPTIONS FOR SPENT FUEL POOLS.

INDUSTRY.A REVIEW OF TECHNICAL ISSUES.

PETERS.S.W.

MOORE C.J. NUREG/CR-5118 LEAK AND STRUCTURAL TEST OF PERSONNEL NUREG/CR 5228 VOI. TECHNIQUES FOR PREPARING FLOWCHART- AIRLOCK FOR LWR CONTAINMENTS SUBJECTED TO PRESSURES FORMAT EMERGENCY OPERATING PROCEDURES Dackground AND TEMPERATURES BEYOND DESIGN LIMITS (Sections 10-9 0)

NUREG/CR-5228 V02. TECHNIQUES FOR PREPARING FLOWCHART- PETERSEN.K.M.

FORMAT EMERGENCY OPERATING PROCEDURES Usert Manual NUREGrCR-53B3: EFFECT OF AGING ON RE SPONSE TIME OF NU-(Sections 10,0-17.0). CLEAR PLANT PRESSURE SENSORS MORAN,D.H. PETTI.D.A.

NUREG-1232 V03: SAFETY EVALUATION REPORT ON TENNESSEE NUREG/CR-5163. POWER BURST F ACILITY (PBF) SEVERE FUEL VALLEY AUTHORITY: BROWNS FERRY NUCLEAR PERFORMANCE DAMAGE TEST 14 TEST RESULTS REPORT.

PLAN Browns Ferry Unit 2 Restart.

PHILIPPACOPOULO M OUL.D. A. NUREG/CR4347: RECOMMENDATIONS FOR RE SOLUTION OF NUREG/CR4001. TACTICAL E XERCISE PLANNING HANDBOOK. PUBLIC COMMENTS ON USl A 40 " SEISMIC DESIGN CRITERLA."

NUREG/CR4172, TACT (CAL TRAINING REFERENCE MANUAL PITTMAN.J.

MUTHANNAA NUREG 0933 SDD. A PRIORIT12ATION OF GENERIC SAFETY ISSUES.

NUREG/CR428.7: FURTHER NEOTECTONIC STUDIES OF EARTH-OUAKE 20NLS IN THE EASTERN UNITED STATES PUGH,CL NUREG/CR-5350* MISSION SURVEY FOR THE PRESSURE VESSEL NAUS.DJ. RESEARCH USERS' F ACILITY (PVRUF).

NUREG/CR4330: HIGH-TEMPERATURE CRACK. ARREST BEHAVIOR IN 152.MM THICK SEN WIDE PLATES OF OVENCHED AND TEM. RAGAN,HA PERED A $33 GRADE B CLASS 1 STEEL NUREG/CR4353' INHALED (147)PM AND/OR TOTAL BODY GAMMA RADIATION EARLY MORTALITY AND MORBIDITY IN RATS NUREG/CR 5356: IMPROVED MODEL FLW. DREDIC11NG J-R CURVES RIGGS.R.

FROM CHARPY DATA Phase i Final Report NUREG-0933 $09 A PRIORITIZATION OF GENERIC SAFETY ISSUES.

O'KELLEY,G.D. ROBERTSON,J.B.

NUREG/CR4235. THERMODYNAMICS OF TECHNETIUM FtELATED NUREG/CR4352: VAM2D - VARIABLY SATURATED ANALYSIS TO NUCLEAR WASTE DISPOSAL Solubthties of TC(IV) Oxides And MODEL IN TWO DIMENSIONS. Version 50 With Hysteresis And The Eiuctrode Potent al Of The Tc(Vil)/TctfVFOxide Coucle. Chamed Decay Traiispart Documentation And User's Guide.

O'REILL Y,P.D. ROSE.P.F.

NUREG 1275 VD5 OPERATING EXPERIENCE FEEDBACK REPORT . NUREG/CR 52B1: VALUE/ IMPACT ANALYSES OF ACCIDENT PRE-PROGRESS IN SCRAM REDUCTION Commercial Power Reactors. VENTIVE AND MITIGATIVE OPTIONS FOR SPENT FUEL POOLS.

OLSON J- ROSENFELD M.

NUREG/CR 5227 S01: F;TNESS FOR DUTY IN THE NUCLE AR POWER NUREG/CR 4082 V07: DEGRADED PIPING PROGRAM - PHASE fNDUSTRY.A REvaEW OF TECHNICAL iSSJES. II. Seventh Program Report. October 1987 - January 1989.

NUREG/CR-4062 V0B: DEGRADED PIPING PROGRAM - PHASE OLSON,R. IISummary Of Technical Results And TMn Sigmfcance To Leak-NUREG/CR 4082 V07; DEGRADED PIPING PROGRAM PHASE Before. Break And IrvServce Flaw Acceptance Critena Murch 1984 -

11 Seventh Program Report Oatober 1987 January 1989 January 1989. i l NURE G/CR.40B2 V0B. DEGRADED PIP:NG PROGRAM - PHASE  !

l II Summary Of Ternmtal Resutts And Theu SiDnifcance To Leak. ROWLEY,M. '

l Before.Brunk And in.Gervce Flaw Acceptance Critona. March 1984 - NUREG/CR 5227 S01 FITNESS FOR DUTY IN THE NUCLE AR POWER l January 1989 INDUSTRY.A REVIEW OF TECHNICAL ISSUES l

l

Personal Author inder 27 RVBBCKl.E F. SHERMAN,M.P.

NUREG/CR-5208: WARM PRESTRESS MODELING: COMPARISON OF NUREG/CR-5275: FLAME FACILITY.The Ettect Of Obstacies And Trans-MODELS AND EXPERIMENTAL RESULTS. verse Venting On Flame Acceleration And Transition To Detonation For Hydrogen-Air Mixtures At Large Scale.

NUREG/CR-5281: VALUE/lMPACT ANALYSES OF ACCIDENT PRE- SHIER,W.

VENTIVE AND MITIGATIVE OPTIONS FOR SPENT FUEL POOLS. NUREG/CR 5268. AGING STUDY OF dOfLING WATER REACTOR RE-S! DUAL HEAT REMOVAL SYSTEM.

g p, NUREG/CR.5319 RISK SENSITIVITY TO HUMAN ERROR. SHIPERS,L.R.

NUREG/CR4759: DEMONSTRATION OF A PERFORMANCE ASSESS-NUREG/C 5230- SHUTDOWN DECAY HEAT REMOVAL NB T O AT S ANALYSIS. PLAN 1 CASE STUDIES AND SPECIAL ISSUES. Summary Report. goo,p, NUREG/CR-5279: SULFATE-ATTACK RESISTANCE AN". GAMMA-lR.

SCHMITT.R.C ^ ' ^ " ^" ^"

NUREG/CR$ 5274: NUMERICAL SIMULATION OF NATURAL CIRCULA- MORTA S' TION PHENOMENA IN A PWR DURING TMLB' TRANSIENTS PRIOR '

TO CORE DAMAGE. SPANNER,G.E.

NUREG/CR5087: STEAM GENERATOR GROUP PROJECT. Task 7 SCHULL.W Final Report. Post-Servce Basehne Eddy Current Examination.

NUMEG/CR-4214 Pil R1: HEALTH EFFECTS MODELS Fort NUCLEAR POWER PLANT ACCIDENT CONSEQUENCE AN#. LYSIS. Low LET STEELE,T.D.

Radiatsor;.Part 11 Saentific Bases Far Health Effects Models.

NUREG/CR-5301: FLOW OF GROUNDWATER AND TRANSPORT OF SCHUMACHER,G. CONTAM!NANTS THROUGH SATURATED FRACTURED GEOLOGIC NUREG/CR 4575; lN-PILE OBSERVATION OF FUEL AND CLAD RELO- * ^^

CATION DURING LMFBR CORE DlSRUFTIVE ACCIDENTS ~ STOKLEY,J.

SCHWARTZ,l. NUREG/CR 5349. STEAM GENERATOR OPERATING EXPERIENCE, UPDATE FOR 1987-1988.

NUREG-0020 V13 NO3: LICENSED OPERATING REACTORS STATUS

SUMMARY

REPORT. Data As Of February 28,1989 (Gray Book 1)

STONESIFER*R.B*

NUREG-0020 V13 N04: LICENSED OPERATING REACTORS STATUS I NUREG/CR-5208: WARM PRESTRESS MODELING: COMPARISON OF

SUMMARY

REH')RT. Data As Of March 31,1989.(Gray Book 1)

MODELS AND EXPERIMENTAL RESULTS.

SCOTT,B.

STRUCKMEYER,R.

NUREG/CR-4214 Pil R1: HEALTH EFFECTS MODELS FOR NUCLFAR POWER PLANT ACCIDENT CONSEQUENCE ANALYS:S. Low LET NUREG-0837 V0B N04: NRC TLD DIRECT RADIATION MONITORING Radiation.Part II: Scientific Bases For Health Effects Models. NETWORK. Progress Report. October December 1988.

SCO ff,B.R. SUBUDHI,b.

NUREG/CR-5351: MODELS FOR PULMONARY LETHALITY AND MOR. NUREG/CR-5268- AGING STUDY OF BOILING WATER REACTOR RE-BIDITY AFTER IRRADIATION FROM INTERNAL AND EXTERNAL SIDUAL HEAT REMOVAL SYSTEM.

SOURCES.

TALWANI,P.

NUREG/CR-5353: INHALED (147)PM AND/OR TOTAL BODY GAMMA NUREG/CR 5257: FURTHER NEOTE'; TONIC STUDidS OF EARTH.

RADIATION.EARLY MORTALITY AND MORDIDITY IN RATS.

QUAKE ZONES !N THE EASTERN UNITED STATES.

SCOTT P.

NUREG/CR-4082 V07: DEGRADED PIPING PROGRAM - PHASE TAYLOR.J.H.

11 Seventh Program Report October 1987 - January 1989. NUREG/CR-5268 AGING STUDY OF BOILING WATER REACTOR RE-NUREG/CR-4082 V08: DEGRADED PIPING PROGRAM - PHASE SIDUAL HEAT REMOVAL SYSTEM.

fl.Sumrnary Of Technical Results And Their Significance To Leak. NUREG/CR-5371: DEVEL OPMENT AND USE OF RISKED-BASED IN.

Before-Break And in-Servce Flaw Acceptance Cntena, March 1984 , SPECTION GUIDES.

TELFAIR,W.D.

SEIFKEN,LJ. NUREG/CR-5081: TACTICAL EXERCISE PLANNING HANDBOOK.

NUREG/CR-5163: POWER BURST FACILITY (PBF) SEVERE FUEL NUREG/CR-5172: TACTICAL TRAINING REFERENCE MANUAL DAMAGE TEST 1-4 TEST RESULTS REPORT.

SETH,S.S. NUREG-1174: EVAlbATION OF SYSTEMS INTERACTIONS IN NUCLE.

NUREG/CR-5332.

SUMMARY

AND ANALYSIS OF PUBLIC COMMENTS AR POWER PLANTS. Technical Findings Related To Unresolved ON NUREG 1317: REGULATORY OPTIONS FOR NUCLEAR PLANT Safety lasue A-17.

LICENSE RENEWAL.F nal Report.

SHA,W.T. NUREG/CR-4214 Pil R1: HEALTH EFFECTS MODELS FOR NUCLEAR NUREG/CR-5274: NUMERICAL SIMULATION OF NATURAL CIRCULA. PC WER PLANT ACCIDENT CONSEQUENCE ANALYSIS. Low LET TION PHENOMENA IN A PWR DURING TMLB' TRANSIENTS PRIOR Radietton.Part 11: Scientific Bases For Health Effects Models.

TO CORE DAMAGE.

SHAH,V.L NUREG-1353 REGULATORY ANALYSIS FOR THE RESOLUTION OF NUREG/CR 5274 NUMERI' AL SIMULATION OF NATURAL CIRCULA- GENERIC ISSUE 82, "BEYOND DESIGN BASIS ACCIDENTS IN TION PHENOMENA IN A ;WR DURING TMLB' TRANSIENTS "910R SPENT FUEL POOLS." .

TO CORE DAMAGE.

TIESZEN,V.

SHEA J.R. NUREG/CR 5275: FLAME FACILITY.The Effect Of Obstacles And Trans-NUREW1348. REPORT ON THE VISIT OF U.S. NUCLEAR SAFETY verse Vent:ng On Flame Acceleration And Transition To Detonation For DELEGATION TO THE SOVIET UNION, AUGUST 19-31, 1988. Hydrogen Air Mixtures At Large Scale.

SHEPHERD,E.R. TILTON,L.M.

NUREG/CR 4759 DEMONSTRATION OF A PERFORMANCE ASSESS- NUREG/CR 4759 DEMONSTRATION OF A PERFORMANCE ASSESS-MENT METHODOLOGY FOR HtGH-LEVEL RADIOACTlW WASTE MENT METHODOLOGY FOR HIGH4EVEL RADIOACTIVE WASTE DISPOSAL IN BASALT FORMATIONS. DISPOSAL IN BASALT FORMATIONS.

28 Personal Author index TINGLE.A.G. WEISS.A.J.

NUREG/CR4281: VALUE/ IMPACT ANALYSES OF ACCIDENT PRE- NUREG/CP-0097 V0t PROCEEDINGS OF THE SIXTEENTH WATER VENTIVE AND MlllGATIVE OPTIONS FOR SPENT FUEL POOLS. REACTOR SArETY INFORMATION MEETING TOOUAMJ. NUREG/CP-0097 V02: PROCEEDINGS OF THE SIXTEENTH WATER REACTOR SAFETY INFORMATION MEETING.

NUREG/CR4227 SQL FITNESS FOR DUTY IN THE NUCLEAR POWER NUREG/CP-0097 V03: PROCEEDINGS OF THE SIXTEENTH WATER INDUSTRY.A REVIEW OF TECHNICAL ISSUES-RE ACTOR SAFETY INFORMATION MEETING.

UNWIN,5.D NUREG/CP-0007 V04- PROCEEDINGS OF THE SIXTEENTH WATER NUREG/bR-4550 V02: ANALYSIS OF CORE DAW, AGE FREOUENCY NUREG/ P 7 V05 PR CEE NG O T E SIXTEENTH WATER FROM INTERNAL EVENTS EXPERT JUDGMENT ELICITATION Part O Expert Panel Results. Part 2- Protect Staff Resutts. REACTOR SAFETY INFORMATION MEETING.

NUREG/CR42Bt VALUE/ IMPACT ANALYSES OF ACCIDENT PRE' WHEELER,T.A VENTIVE AND MITIGATIVE OPTIONS FOR SPENT FUEL POOLS-NUREG/CRd550 V02: ANALYSIS OF CORE DAMAGE FREQUENCY UPDE GRAFF,C.D. FROM INTERNAL EVENTS EXPERT JUDGMENT ELICITATION Part NUREG/CR #759: DEMONSTRATION OF A PERFORMANCE ASSESS. t Expert Panel Results. Part 2. Project Statt Resu!!s.

MENT METHODOLOGY FOR HIGH-LEVEL RADICf,CTIVE WASTE DISPOSAL IN BASALT FORMATIONS. #

NU EG R4227 S0t FITNESS FOR DUTY fN THE NUCLEAR POvi CR USUER.J. INDUSTRY.A REVIEW OF TECHNICAL ISSUES.

NUREG/CR-5370 DEVELOPMENT AND USE OF RISKED-BASED IN.

SPECTION GUIDES. WiERINGA.D.R.

NUREG/CR4228 Vot TECHNIOUES FOR PREPARING FLOWCHART-VAN TUYLE.G.J. FORMAT EMERGENCY OPERATING PROCEDURES. Background NUF/3/CR 5355. HTGR INGRESS ANALYSIS USING MINET. (Sechons 1.0-9 0).

VANARSDALE.R. NUREG/CR4228 V02: TECHNIOUES FOR PREPARINC FLOWCHART-FORMAT EMERGENCY OPERATING PROrEDURES User's Manual NUREG/CR4375 POST PENNSYLVANIAN REACTIVATION ALONG (Sections 10.0-17.0)

THE WASHITA VALLEY FAULT. SOUTHERN OKLAHOMA.

WILKOWSKl,G.M.

~

N E CR 5344. REPLACEMENT ENERGY COST ANALYSIS PACK" I th P o em R Oc be 1987 - January 99.

AGE (RECAP): USER'S GUIDE.

NUREG/CR-400.J V08. DEGRADED PIPING PROGRAM PHASE VEATCH,J.D. RSummay Of Technical Results And Their Significance To Leak-k* NUREG/CR-5246 A METHODOLOGY TO ASSIST IN CONTINGENCY Before-Break And in.Servce Flaw Acceptance Cntena. March 1984 -

January 1989.

PLANNING FOR PROTECTION OF NUCLEAR POWER PLANTS AGAINST LAND VEHICLE BOMBS. WILSON,R.

VIETH.P. NUREG/CR 5227 S01 FITNESS FOR DUTY IN THE NUCLEAR POWER NUREG/CR-4082 V07. DEGRADED PIPING PROGRAM PHASE INDUSTRY A REVIEW OF TECHNICAL ISSUES.

II. Seventh Pr NUREG/CR-40hram Report V08 October 1987 DEGRADED PIPING- January PR7 GRAM1989 PHASE W

11 Summary Of Techncal Results And Their Sigmfcance To Leak- /CR.5319. RISK SENSITIVITY TO HUMAN ERROR-Before-Break And in-Serv 6ca Flaw Acceptance Cntena, March 1984 -

anuay % BE WRIGHT,S.A.

NUREG/CR-4675: IN-PILE OBSERVATION OF FUEL AND CLAD RELO-VINJAMURI.K. CATION DURING LMFBR CORE DISRUPTIVE ACCIDENTS NUREG/CR 5163: POWER BURST F ACILITY (PBF) SEVERE FUEL DAMAGE TEST 1-4 TEST RESULTS REPORT.

NUREG-1344. EROSION /CORF 3SION-INDUCED PIPE WALL THIN.

VO T.V. NING !N U.S. NUCLEAR POW ER PLANTS.

NUREG/CR-5197: PRA APPLICATIONS PROGRAM FOR INSPECTION AT CALVERT CLIFFS UNIT 1 NUCLEAR POWER PLANT WU NU EG/CR-3950 V05. FUEL l'ERFORMANCE ANNUAL REPORT FOR WAHI,K.K. t987.

NUREG/CR 4759. DEMONSTRATION OF A PERFORMANCE ASSESS-MENT METHODOLOGY FOR HIGH-LEVEL RADIOACTIVE WASTE YAMANO.N.

DISPOSAL IN BASALT FORMATIONS NUREG/CR-5252- ATROSOL SAMPLING AND TRANSPORT EFFICIEN-CY CALCULATION (ASTEC) AND APPLICATION TO SURTSEY/DCH WARD.C. AEROSOL SAMPLING SYSTEM Code Version 1.0: Code Desenption NUREG/CR-5375: POST-PENNSYLVANIAN REACTIVATION ALONG And User's Manual.

THE WASHITA VALLEY FAULT. SOUTHERN OKLAHOMA.

Y ANG.J.W.

W A Y,$.C.

NUREG/CR4355. HTGR INGRESS ANALYSIS USING MINET.

NUREG/CR 539t FLOW OF GROUNDWATER AND TRANSPORT OF CONTAMINANTS THROUGH SATURATED FRACTURED GEOLOGIC YANfv,S.S.

MEDIA. NUREG/CR 5353: INHALED (147)PM AND/OR TOTAL-BODY GAMMA WEBSTER,C.S. RADIATION.EARLY MORTALITY AND MORBIDITY IN RATS NUREG/CR-472t THE USE OF FIBER OPTICS FOR REMOTE TEM- ZlMMERMAN,P.W.

PERATURE MEASUREMENT IN FISSION PRODUCT RELEASE NUREG/CR-T.379 V00 NUCLEAR PLANT SERVICE WATER SYSTEM TESTS. AGING DEGRADATION ASSESSMENT. Phase i l 1

Subj:ct Ind x This index was developed frorn 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.

A 533 B Steel Basalt Waste Isolation Project NUREG/CR 4929 THE EFFECTS OF VARIABLE AMPLITUDE LOADING NUREG/CR-5089. NUMERICAL MODELING OF GROUND WATER ON A 533-B STEEL IN HIGH-TEMPERATURE AIR AND REACTOR FLOW SYSTEMS IN THE VICINITY OF THE REFERENCE REPOSI-WATER ENVIRONMENTS. TORY LOCATION.HANFORD. WASHINGTON.

ACRS Reports Basattic Basemat NUREG-1125 V10- A COMPILATION OF REPORTS OF THE ADIVSORY NUREG/CR-4994. CORE-CONCRETE INTERACTIONS USING MOLTEN COMMITTEE ON REACTOR SAFEGUARDS.1988 Annual STEEL WITH ZlRCONIUM ON A BASALTIC BASEMA1.THE SURC 4 ALARA EXPERIMENT.

I NUREG/CR 34R9 V04 OCCUPAT!ONAL DOSE REDUCTION AT NU.

Below Regula% Concern CLEAR POWER PLANTS. ANNOTATED BIBLIOGRAPHY OF SELECT-ED READINGS IN RADIATION PROTECTION AND ALARA NUREG/CP-0101. PROCEEDINGS OF THE WORKSHOP ON RULES NUREG/CR-4409 V01 DATA BASE ON DOSE REDUCTION RE. FOR EXEMPTION FROM REGULATORY CONTROL SEARCH PROJECTS FOR NUCLEAR POWER PLANTS.

swim. w wrw.ww ASTEC Code NUREG/CR-5268. AGING STUDY OF BOILING WATER REACTOR RE, NUREG/CR 5252 AEROSOL SAMPUNG AND TRANSPORT EFFICIEN- SIDUAL HEAT REMOVAL SYSTEM.

CY CALCULATION (ASTEC) AND APPLICATION TO SURTSEY/DCH AEROSOL SAMPi. G SYSTEM Code Version 1.0. Code Desenption Bulletin 83 06 1 And User's Manusf. NUREG/CR-4934: CLOSEOUT OF IE BULLETIN B3-06 Nonconforming Matenals Supplied By Tube-Line Corporation Facilities At Long Island NU G- 90 11 N04: REPORT TO CONGRESS ON ABNORMAL OCCURRENCES. October December 1988. Bullet 6n 87 02 Abstract NUREG 1349. COMPILATION OF FASTENER TESTING DATA RE-NUREG-0304 V13 N04: REGULATORY AND TECHNICAL REPORTS CEIVED IN RESPONSE TO NRC COMPLIANCE BULLETIN 87-02.

(ABSTRACT INDEX JOURNAL) Annual Compilation For 1988' CMW Accident NUREG/CR-5244. EVALUATION OF NON-RADIOLOGICAL WATER NUREG/CR-4214 Pil R1: HEALTH EFFECTS MODELS FOR NUCLEAR CHEMISTRY AT POWER REACTORS.

POWER PLANT ACCIDENT CONSEQUENCE ANALYSIS. Low LET Radiation.Part II. Scientific Bases For Health Effects Models, Chernobyl Accident NUREG-1251 VOI- IMPLICATIONS OF THE ACCIDENT AT CHERNOBYL Aerosol Sampling FOR SAFETY REGULATION OF COMMERCIAL NUCLEAR POWER NUREG/CR-5252: AEROSOL SAMPLING AND TRANSPORT ETFICIEN- PLANTS IN THE UNITED ST ATES. Final Report Main Report.

CY CALCULATION (ASTEC) AND APPLICATION TO SURTSEY/DCH NUREG-1251 Vit. IMPLICATIONS OF THE ACCIDENT AT CHERNOBYL AEROSOL SAMPLING SYSTEM Code Version 1.0 Code Desenption FOR SAFETY REGULATION OF COMMERCIAL NUCLEAH POWER And User's Manual- PLANTS IN THE UNITED STATES Final Report Appendix . Public m nts And Their Disposition.

Aging NUREG/CR 5268: AGING STUDY OF BOILING WATER REACTOR RE- Chloride SIDUAL HEAT REMOVAL SYSTEM- NUREG/CR-5244. EVALUATION OF NON RADIOLOGICAL WATER Aging Degradation CHEMISTRY AT POWER REACTORS.

NUREG/CR-5379 V01: NUCLEAR PLANT SERVICE WATER SYSTEM AGING DEGRADATION ASSESSMENT. Phase *. Class 1 Steel NUREG/CR-5383- EFF ECT OF AGING ON RESPONSE TIME OF NU- NUREG/CR-5330 HIGH-TEMPERATURE CRACK ARREST BEHAVIOR CLEAR PLANT PRESSURE SENSORS IN 152-MM-THICK SEN WIDE PLATES OF OUENCHED AND TEM-PERED A 533 GRADE B CLASS 1 STEEL Annual Report NUREG 1145 VOS: U S. NUCLEAR REGULATORY COMMrSSION 1988 Closeout ANNUAL REPORT. NUREG/CR-4934 CLOSEOUT OF IE BULLETIN 83 06. Nonconforming NUREG 1363 V01 ATOMIC SAFETY AND LICENSING BOARD PANEL Matenals Supplied By Tube-Line Corporation Facihties At Long Island ANNUAL REPORT FOR FISCAL YEAR 1988- City. New York; Houston. Texas. And Carol Stream, Illinois.  :

NUREG/CR-5283. CLOSEOUT OF IE BULLETIN 79 03: LONGITUDINAL EG 13 3 VD1 AT S

^

ND LICENSING BOARD PANE'L ANNUAL REPORT FOR FISCAL YEAR 1988.

ENGINEERING COMPANY.

DWR NUREG/CR-5284. CLOSEOUT OF IE BULLETIN 79-03A: LONGITUDINAL NUREG/CR 5268. AGING STUDY OF BOILING WnTER REACTOR RE. WELO DEFECTS IN ASME SA-312 TYPE 304 ST AINLESS RTEEL l SIDUAL HEAT REMOVAL SYSTEM. PIPE  !

NUREG/CR 529t. CLOSEOUT OF IE BULLETIN 80-09 HYDRAMOTOR l Basalt Format 60n ACTUATOR DEFICIENCIES.

NUREG/CR 4759 DEMONSTRATION OF A PERFORMANCE ASSESS- NUREG!CR-5293 CLOSEOUT OF IE BULLETIN 86-01 MINIMUM FLOW MENT METHODOLOGY FOR HIGH-LEVEL RADIOACTIVE WASTE LOGIC PROBLEMS THAT COULD D: SABLE RESIDUAL HEAT RE-DISPOSAL IN BASALT FORMATIONS MOVAL PUMPS.

29

30 Subject Index Concrete NUREG/CP-0097 V03: PROCEEDINGS OF THE SIXTEENTH WATER NUREG/CR-5237: USE OF LINEAR REDUCED STIFFNESS ANALYTI- REACTOR SAFETY INFORMATION MEETING CAL MODELS TO PREDICT SElSMIC RESPONSE F DAMAGED NUREG/CP-0097 V04: PROCEEDINGS OF THE SIXTEENTH WATER CONCRETE STRUCTURES REACTOR SAFETY INFORMATION MEETING.

NUREG/CP-0097 V05: PROCEEDINGS OF THE SIXTEENTH WATER Concrete Structure REACTOR SAFETY INFORMATION MEETING NUREGICR-5222 STATIC LOAD CYCLE TESTING OF A LOW ASPECT- NUREG/CP 0098 V01: PROCEEDINGS OF THE 20TH DOE /NRC NU-RATIO SIX INCH WALL TRG-TYPE STRUCTURE TAG 4 6 (1.0, DR5). CLEAR AIR CLEANING CONFERENCE. Sections 1 5 Held in Boston, Massachusetts, August 22-25.1988.

Containment NUREG/CPJ)D98 V02 PROCEEDINGS OF 'HE 20TH DOE /NRC NU-NUREG 1251 V01- IMPLICATIONS OF THE ACCIDENT AT CHERNOBYL CLEAR AIR Cl EANING CONFERENCE. Sessions 6 - 15. Held in FOR SAFETY REGULATION OF COMMERCIAL NUCLEAR POWER Boston Massachusetts August 22 25,1988.

PLANTS IN THE UNITED STATES Final Report.Mam Report NUREG 1251 Vil: IMPLICATIONS OF THE ACCIDENT Al CHERNOBYL Decontamination FOR SArETY REGULATION OF COMMERCIAL NUCLEAR POWER NUREG/CP-0097 V01: PROCEEDINGS OF THE SIXTEENTH WATER PLANTS IN THE UNfTED STATES. Fir rm Report. Appendix - Put4: Com- REACTOR SAFETY INFORMATION MEETING.

ments And Ttwm Disposition. NUREG/CP-0097 V02: PROCEEDINGS OF THE SIXTEENTH WATER NUREG/CR-4994: CORE CONCRETE INTERACTIONS USING MOLTEN REACTOR SAFETY INFORMATION MEETING.

STEEL WITH ZlRCONIUM ON A BASALTIC BASEMAT THF SURC-4 NUREG/CP-0097 V03: PROCEEDINGS OF THE SIXTEENTH WATER EXPERIMENT. REACTOR SAFETY INFORMATION MEETING.

NUREG/CP-0097 V04: PROCrIEDINGS OF THE SIXTEENTH WATER Contingency Plannin9 REACTOR SAFETY INFORMATION MEETING.

NUREG/CR-5246: A METHODOLOGY TO ASSIST IN CONTINGENCY NUREG/CP 0097 V05: PROCEEDINGS OF THE SIXTEENTH WATER PLANNING FOR PROTECTION OF piCLEAR POWER PLANTS REACTOR SAFETY INFORMATION MEETING.

AGAINST LAND VEHICLE BOMBS. NUREG/CP-0098 V01: PROCEEDINGS OF THE 20TH DOE /NRC NU-CLEAR AIR CLEANING CONFERENCE. Sections 1 5 Held in Boston, Contract Research Massachusetts, August 22-25.1988.

NUREG-0975 V07: COMPILATION OF CONTRACT RESEARCH FOR NUREG/CP 0098 V02: PROCEEDINGS OF THE 20TH DOE /NRC NU-THE MATERIALS ENGINEERING BRANCH. DIVISION OF CLEAR AIR CLEANING CONFERENCE. Sessions 6 - 15. Held in ENGINEERING Annual Report For FY 1988. Boston, Massachusetts, August 22-25,1988.

Control Room NUREG-1342: A STATUS REPORT REGARDING INDUSTRY IMPLE- N REG /C -4 2 V07: DEGRADED PIPING PROGRAM PHASE fAENTATION OF SAFETY PARAMETER DISPLAY SYSTEMS II. Seventh Program Report. October 1987 January 1989.

Core Damage NUREf'/CR-4082 V08: DEGRADED PIPING PROGRAM PHASE dummary Of Techmcal Results And Their Significance To leak-NUREG/CR-4550 V02: ANALYSIS OF CORE DAMAGE FREQUENCY Before-Break And in-Service Flaw Acceptance Critena. March 1984 -

FROM INTERNAL EVENTS: EXPERT JUDGMENT ELICITATION.Part 1- Expert Panel Results Part 2: Project Staff Results. January 1989.

NUREG/CR-5274: NUMERICAL SlMULATION OF NATURAL CIRCULA-N EN M IN A PWR DURING TMLB' TRANSIENTS PRIOR N REG  : GLLATORY ANALYSIS FOR THE RESOLUTION OF GENERIC ISSUE 82, "BEYOND DESIGN BASIS ACCIDCNTS IN Core Melt SPENT FUEL POOLS."

NUREG/CR-5187: PRA APPLICATIONS Ph0 GRAM FOR INSPECTION NUREG/CR-5261 SAFETY EVALUATION OF MHTGR LICENSING AT CALVERT CLIFFS UNIT 1 NUCLEAR POWER PLANT. BASIS ACCIDENT SCENARIOS.

NUREG/CR-5319: RISK SENSITIVITY TO HUMAN ERROR.

Rem Corrosion NUREG/CA-3469 V04: OCCUPATIONAL DOSE REDUCTION AT NU-NUREG/CR 5244. EVALUATION Oc NON-RADIOLOGICAL WATER CLEAR POWER PLANTS: ANNOTATED BIBLIOGRAPHY OF SELECT.

CHEMISTRY AT POWER REACTORS. ED READINGS IN RADIATION PROTECTION AND ALARA.

NUREG/CR-4409 V03: DATA BASE ON DOSE REDUCTION RE-Crack Growth SEARCH PROJECTS FOR NUCLEAR POWER PLANTS.

NUREG/CR-5238. DEVELOPMENT OF AN ENGINEERING DEFINITION OF THE EXTENT OF J SINGULARITY CONTROLLED CRACK Drug Abuse GROWTH NUREG-1354: FITNESS FOR DUTY IN THE NUCLEAR POWER INDUSTRY: RESPONSES TO PUBUC COMMENTS.

CrocbArrest Toughness NUREG/CR 5330- HIGH TEMPERATURE CRACK-ARREST BEHAVIOR Drug Testing lN 152-MM. THICK SEN WIDE PLATES OF OUENCHED AND TEM- NUREG/CR 5227 S01: FITNESS FOR DUTY IN THE NUCLEAR POWER PERED A 533 GRADE B CLASS 1 STEEL INDUSTRY A REVIEW OF TECHN:CALISSUES.

Decay Earthquake NUREG/CR-5352. VAM2D . VARIABLY SATURATED ANALYS$ NUREG/CR 5257 FURTHER NEOTECTONIC STUDIES OF EARTH-MODEL IN TWO DIMENSIONS. Version 5.0 With Hysteresis And OUAKE ZONES IN THE EASTERN UNITED STATES.

Chained Decay Tiensport Documentation And User's Guido Eddy Current Decoy Heat Removal NUREG/CR-5087: STEAM GENERATOR GROUP PROJECT. Task 7 NUREG/CR-5230: SHUTDOWN DECAY HEAT REMOVAL Final Report Post-Sernce Baseline Eddy Cumint Examination ANALYSIS. PLANT CASE STUDIES AND SPECIAL ISSUES. Summary Report. Element interaction NUREG/CR-5357: AN EXPLORATORY STUDY OF ELEMENT INTERAC-Decommissioning TIONS AND COMPOSITION DEPENDENCIES IN RADIATION SENSI-NUREG 0904 S01 V01: SUPPLEMENT TO THE rlNAL ENVIRONMEN- TiVITY DEVELOPMENT. Final Report.

TAL STATEMENT RELATED TO THE DECOMMISSIONING OF THE RARE EARTHS FACILITY. WEST CHICAGF. '.LINOIS volume 1: Main Emergency Operating Procedure Text And Appendices A-G Docket No 40-206t NUREG-1358: LESSONS LEARNED FROM THE SPECLAL INSPECTION NUREG-0904 S01 V02: SUPPLEMENT TO THE FINAL ENVIRONMEN- PROGRAM FOR EMERGENCY OPERATING TAL STATEMENT RELATED TO THE DECOMMISSIONING OF THE PROCEDURES Conducted March October 1988.

RARE EARTHS FACILITY. WEST CHICAGO.lLLINOISVolume 2: Ap- NUREG/CR-5228 V01: TECHNIQUES FOR PREPARING FLOWCHART.

pondm H Docket No. a0-2061 FORMAT EMERGENCY OPERATING PROCEDURES. Background NUREG/CP-0097 VD1: PROCEEDINGS OF THE SIXTEENTH WATER (Sections 1.0 9 0).

RE ACYOR SAF ETY INFORMATION MEETING NUREG/CR-5228 V02: TECHNIOUES FOR PREPARING FLOWCHART.

NUREG/CP-0097 V02: PROCEEDINGS OF THE SIXTEENTH WATER FORMAT EMERGENCY OPERATING PROCEDURES. User's Manual REACTOR SAFETY INFORMATION MEETING. (Sections 10017.0).

1

SubjIct index 31 Emergency Planrang NUREG/CR-5356: IMPROVED MODEL FOR PREDICTING J-R CURVES NUREG-1251 V0t: IMPUTATIONS OF THE ACCIDENT AT CHERNOBYL FROM CHARPY DATA. Phase i Final Report.

FOR SAFETY REGULATION OF COMMERCIAL NUCLEAR POWER PLANTS IN THE UNITED STATES Final Report.Mam Report Fractured Rock

. NUREG-1251 Vit IMPLICATIONS OF THE ACCIDEN1 AT CHERNOBYL NUREG/CR-5391: FLOW OF GROUNDWATER AND TRANSPORT OF FOR SAFETY REGULATION OF COMMERCIAL NUCLEAR POWER CONTAMINANTS THROUGH SATURATED FRACTURED GEOLOGIC PLANTS IN THE UNITED STATES. Final Report. Appends - Public Com- MEDIA.

ments And Their Disposition.

Fuel Damage Enforcement Action NUREG/CR-5163. POWER BURST FACILITY (PBF) SEVERE FUEL NUREG 0940 V08 N01: ENFORCEMEN1 ACTIONS.SIGNIFICANT AC- DAMAGE TEST 14 TEST RESULTS REPORT.

TIONS RESOLVED Quarterly Progress Report. January-March 1989.

Fuel Description NUREG/CR46751N-PILE OBSERVATION OF FUEL AND CLAD RELO-U G 34 EROSION / CORROSION 4NDUCED PIPE WALL THIN. CATION DURING LMFBR CORE-DISRUPTIVE ACCIDENTS.

NING IN U.S. NUCLEAR POWER PLANTS.

Exercise Planning Handbook Fuel Performance NUREG/CR-5081: TACTICAL EXERCISE PLANNING HANDBOOK, NUREG/CR-3950 V05: FUEL PERFORMANCE ANNUAL REPORT FOR 1987.

FLAME Facility NUREG/CR 5275: FLAME FACluTY.The Effect Of Otsiacles And Trans- Gamma irradiation verse Venting On Flame Acceleration And Transthon To Detonation For NUREGICR-5279: SULFATE ATTACK RES: STANCE AND GAMMA-IR.

Hydrogen-Air Mnctures At Large Scale. RADIATION RESISTANCE OF SOME PORTLAND CEMENT BASED MORTARS.

Fastener NUREG-1349. COMPILATION OF FASTENEH TES11NG DATA RE- Generic tasue 082 CEIVED IN RESPONSE TO NRC COMPLIANCE BULLETIN 87-02. NUREG 1353: REGULATORY ANALYSIS FOR THE RESOLUTION OF GENERIC ISSUE 82, "BEYOND DESIGN BASIS ACCIDENTS IN Fatique Crack SPENT FUEL POOLS."

NUREG/CR-4929 THE EFFECTS OF VARIABLE AMPLITUDE LOADING ON A 533 8 STEEL IN HIGH-TEMPERATURE AIR AND REACTOR Generic lasue 116 WATER ENVIRONMENTS NUAEG 1341: REGULATORY ANALYSIS FOR THE RESOLUTION OF Fiber Optic GENERIC ISSUE 115. ENHANCEMENT OF THE RELIABlWTY OF THE NUREG/CR-4721: THE USE OF FIBER OPTICS FOR REMOTE TEM- WESTINGHOUSE SOLID STATE PROTECTION SYSTEM.

PERATURE MEASUREMENT IN FISSION PRODUCT RELEASE Generic Safety issue TESTS.

NUREG 0933 SO9 A PRIORITIZATION OF GENERIC SAFETY ISSUES-F6nal Environmental Statement NUREG-0904 S01 V01: SUPPLEMENT TO THE FINAL ENVIRONMEN- Gener6c Safety issue 82 TAL STATEMENT RELATED TO THE DECOMMISSIONING OF THE NUREG/CR-5281: VALUE/ IMPACT ANALYSES OF ACCIDENT PRE RARE EARTHS FACILITY, WEST CHICAGO,tLUNOIS. Volume 1: Main VENTIVE AND MITIGATIVE OPTIONS FOR SPENT FUEL POOLS.

Text And Appendices A G. Docket No. 40-2061.

NUREG-0904 S01 V02: SUPPLEMENT TO THE FINAL ENVIRONMEN- Geolog e Media TAL STATEMENT RELATED TO THE DECOMMISSIONING OF THE NUT %/CP-5391: FLOW OF GROUNDWATER AND TRANSPORT OF RARE EARTHS FACILITY, WEST CHICAGO.lLLINOISVolume 2: Ap- CC,NTAMINANTS THROUGH SATURATED FRACTURED GEOLOGIC pendix H. Docket No.40 2061. MEDIA.

F6ssion Gegm ReposHory HUREG/CR4721: THE USE OF FIBER OPTICS FOR REMOTE TEM- NUREG/CR-3964 V01: TECHNIOUES FOR DETERMINING PROBABIL-P ATURE MEASUREMENT IN FISSION PRODUCT RELEASE ITIES OF EVENTS AND PROCESSES AFFECTING THE PERFORM-

~

ANCE OF GEOLOGIC REPOSITORIES. Literature Review.

F;.tness For Duty Geological Dspesaf NUREG 1354: FITNESS FOR DUTY IN THE NUCLEAR POWER NUREG/CR4336: SENSITIVITY OF THE STABILfTY OF A WASTE EM-INDUSTRY RESPONSES TO PUBLIC COMMENTS.

NUREG/CH-5227 S01: FITNESS FOR DUTY IN THE NUCLEAR POWER PLACEMENT DRIFT TO VARIATION IN ASSUMED ROCK JOINT PA-INDUSTRY.A REVIEW OF TECHNICAL ISSUES. RAMETERS IN WELDED TUcF.

Flame Acceleration Groundwater NUREG/CR-5275: FLAME FACluTY.The Effect Of Obstacles And Trans- NUREG/CR-5089. NUMERICAL MODELING OF GROUND-WATER verse Venting On Flame Acceleration And Transition To Detonation For FLOW SYSTEMS IN THE VICINITY OF THE REFERENCE REPOSI.

Hydrogen-Air Mixtures At Large Scale- TORY LOCATION,HANFORD. WASHINGTON.

NUREG/CR-539t: FLOW OF GROUNDWATER AND TRANSPORT OF F'seture Mechanics CONTAMINANTS THROUGH SATURATED FRACTURED GEOLOGIC NUREGICR 4082 V07: DEGRADED PIPING PROGRAM - PHASE ugpig, 11 Seventh Program Report October 1987 January 1989.

NURE G/CR-4082 V0B: DEGRADED PIPING PROGRAM PHASE Health Effect lisummary Of Technical Results And Their Significance To Leak. NUREG/CR-4214 Pil R1: HEALTH EFFECTS MODELS FOR NUCLEAR Before-Break And in-Service Flaw Acceptance Cnter:a, March 1984 - POWER PLANT ACCIDENT CONSEQUENCE ANALYSIS. Low LET Radiation.Part 11: Scientific Bases For Health Effects Models.

N /C 42 9 VOS N2. HEAVY SECTION STEEL TECHNOLOGY PROGRAM Semlannual Pr ess Report For April-September 1968 Health Physic NUREG/CR-3469 V04 OCCUPATIONAL DOSE REDUCTION AT NU.

RES AR L ER AC Li ( VRU ~ CLEAR POWER PLANTS: ANNOTATED BIBLIOGRAPHY OF SELECT-Fradure Toughness ED READINGS IN RADIATION PROTECTION AND ALARA.

NUREG/CR 5216. POST IRRADIATION FRACTURE TOUGHNESS Heavy-Section Steel Technology Program CHARACTERIZATION OF FOUR LAB-MELT PLATES NUREG/CR 5216 RO1: POST-IRRADIATION FRACTURE TOUGHNESS NUREG/CR4219 VOS N2: HE AVY SECTION STEEL TECHNOLOGY PROGRAM Semiannual Progress Report For Apni-September 19B8.

CHARACTER 12ATION OF FOUR LAB MELT PLATES NUREG/CR 523B DEVELOPMENT OF AN ENGINEERING DEFINITION OF THE EXTENT OF J SINGULARITY CONTROLLED CRACK High Temperature Gas Cooled Reactor CROWTH NUAFWrAMW HTGR INGRESS ANALYS!S USING MINET.

1 J

I

32 SubsetInd3x High-Level Radioactive Waste Disposal NUREG/CR-5216 Rot: POST IRRADIATION FRACTURE TOUGHNESS NUREG/CR 4759. DEMONSTRATION OF A PERFORMANCE ASSESS. CHARACTER!ZATION OF FOUR LAB. MELT PLATES.

MENT METHODOLOGY FOR H GH LEVEL RADIOACTIVE WASTE UlSPOSAL IN BASALT FORMATIONS. J-R Curve NUREG/CR 5356: IMPROVED MODEL FOR PREDICTING J-R CURVES Human Error FROM CHARPY DATA. Phase i Final Report.

NUREG/CR-5319. RISK SENSITIVITY TO HUMAN ERROR.

LER Hydramotor Actuator NUREG/CR-2000 V08 N2: LICENSEE EVENT REPORT (LER)

NUREG/CR-5291: CLOSEOUT OF IE BULLETIN 80-09 HYDRAMOTOR COMPILATION For Month Of February 1989.

ACTUATOR DEFICIENCIES NUREG/CR-2000 V08 N 3. LICENSEE EVENT REPORT (LER)

COMPILATION For Month Of March 1989 Hydrogen Air Combustion MIREG/CR 2000 V08 N4. LICENSEE EVENT REPORT (LER)

NUREG/CR 5275. FLAME FACILITY.The Effect Of Obstacles And Trans- 00MP!LATION For Month Of April 1989 verse Venting On Hame Acceleration And Transition To Detonation For NUREG/CR-2000 V08 N5. LICENSEE EVENT REPORT (LER)

Hydrogen-Air Mmtures At Large Scale. COMPILATION For Month Of May 1989.

Hydrogen-Air Detonat6on LOCA NUREG/CR 4961: A

SUMMARY

OF HYDROGEN AIR DETONATION EX- NUREG/CR-5208: WARM PRESTRESS MODELING' COMPARISON OF PERIMENTS. MODELS AND EXPERIMENTAL FIESULTS.

Hydrogeology LWR NUREG/CR-5089: NUMERICAL MODELING OF GROUND-WATER NUREG/CR-5163 POWER BURST FACILITY (PBF) SEVERE FUEL FLOW SYSTEMS IN THE VICINITY OF THE REFEnENCE REPOSl* DAMAGE TEST 1-4 TEST RESULTS REPORT.

TORY LOCATION.HANFORD, WASHINGTON NUREG/CR 5330: HIGH-TEMPERATURE CRACK-ARREST BEHAVIOR IN 152 MM-THICK SFN WIDE PLATES OF OUENCHED AND TEM-PERED A 533 GRADE B CLASS 1 STEEL NU E / 5283: CLNOUT OF IE BULLETIN 79-0310NGITUDINAL WELD DEFECTS IN ASME SA 312 TYPE 304 STAINLESS STEEL Leak Rate PIPE SPOOLS MANUFACTURED BY YOUNGSTOWN WELDING AND NUREG/CR-5118. LEAK AND STRUCTURAL TEST OF PERSONNEL ENGINEERING COMPANY. AIRLOCK FOR LWR CONTAINMENTS SUBJECTED TO PRESSURES tE Bulletin 79 03A NUREG/CR 5284. CLOSEOUT OF IE BULLETIN 79 03A10NGITUDINAL Leak Before-Break WELD DEFECTS IN ASME SA 312 TYPE 304 STAINLESS STEEL NUREG/CR-4082 V07. DEGRAGEv PIPING PROGRAM . PHASE PIPE, 11 Seventh Program Report October 1987 January 1989 NUREG/CR-4082 V08. DEGPADED PlPING PROGRAM PHASE IE Bulletin 80-09 11 Summary Of Technical Results And Their Significance To Leak-NUREG/CR-5291: CLOSEOUT OF IE BULLETIN 80-09.HYORAMOTOR Before Break And !n-Service Flaw Accep ance Cntena, March 1984 -

ACTUATOR DEFICIENCIES.

January 1989.

IE Bulletin 86-01 Legal issuances i

l NUREG/CR-5293: CLOSEOUT OF IE BULLETIN 86-01. MINIMUM FLOW i LOGIC PROBLEMS THAT COULD DISABLE RESIDUAL HEAT RE. NUREG-0750 V28102: INDEXES TO NUCLEAR REGULATORY COM-l MISSION ISSUANCES. July-December 1988.

' MOVAL PULtPS' NUREG-0750 V29 NO2: NUCLEAR REGULATORY COMMISSION IS-inden SUANCES FOR FEBRUARY 1989 Pages89-209.

NUREG-0304 V13 N04. REGULATORY AND TECHNICAL REPORTS NUREG 0750 V29 NO3: NUCLEAR REGULATORY COMMIS$10N IS-(ABSTRACT INDEX JOURNAL). Annual Compilation For 1988. 8 R M RCH 19 P ge NUR 0 2g inhaled Promethium SUANCES FOR APRIL 1989 Pages 345-393.

NUREG/CR-5353: INHALED (147)PM AND/OR TOTAL-BODY GAMMA RADIATION EARLY MORTALITY AND MORBIDITY IN RATS.

Uc " '8" '

NA /CR 332

SUMMARY

AND ANALYSIS OF PUBLIC COMMENTS Inspection ON NUREG 1317: REGULATORY OPTIONS FOR NUCLEAR PLANT NUREG-0040 V13 N01: LICENSEE CONTRACTOR AND VENDOR IN. LICENSE RENEWAL. Final Report SPECTION STATUS REPORT. Ouarterly Report. January-March License Renewal I 1989 (White Book)

NUREG/CR.5187: PRA APPLICATIONS PROGRAM M9 INSPECTION NUREG/CR-5332:

SUMMARY

AND ANALYSIS OF PUBLIC COMMENTS AT CALVERT CLIFFS UNIT 1 NUCLEAR POWER PL,1 ON NUREG 1317: REGULATORY OPTIONS FOR NUCLEAR PLANT LICENSE RENEWAL. Final Repoit inspection Guide NUREGICR 5371: DEVELOPMENT AND USE OF R!SKED-BASED IN- Licensed Operating Reactors SPECTION GUIDES. NU9EG-0020 V13 NO3: LICENSED OPERATING RE ACTORS STATUS

SUMMARY

REPORT. Data As Of February 28,1989 (Gray Book 1)

Inspection Program NUREG-0020 V13 N04 LICENSED OPERATING REACTORS STATUS ,

NUREG/CR 5244. EVALUATION OF NON-RADIOLOGICAL WATER

SUMMARY

REPORT. Data As Of March 31.1989 (Gray Book 1) I CHEMISTRY AT POWER REACTORS. NUREG-0020 V13 Nos. LICENSED OPERATING REACTORS STATUS

SUMMARY

REPORT. Data As Of April 30,1989.(Gray Book 1) inspection Report NUREG 1358: LESSONS LEARNED FROM THE SPECIAL INSPECTION Ucensee Event Report PROGRAM FOR EMERGENCY OPERATING NUREG/CR-2000 V08 N2: LICENSEE EVENT REPORT (LER) i PROCEDURES Conducted March-October 1968. COMPILATION For Month Of February 1989

! NUREG/CR-2000 V08 N3: LICENSEE EVENT REPORT (LER) l- Intergranular Stress Corrosion Cracking COMPILATION For Month Of March 1989 NUREG/CR 5349. STEAM GENERATOR OPERATING NUREG/CR-2000 V06 N4. LICENSEE EVENT REPORT (LER)

EXPERIENCE. UPDATE FOR 1987 1988 COMPILATION For Month Of Apnl 1989 NUREG/CR 2000 V0B N5: LICENFEE EVENT REPORT (LER)

Irradiation COMPILATION For Month Of May 1989.

NUREG/CR-5351: MODELS FOR PULMONARY LETHALITY AND MOR-BIDITY AFTER 1RRADIATION FROM INTERNAL AND EXTERNAL Ught Water Reactor SOURCES NUREG/CL5163. POWER BURST FACILITY (PBF) SEVERE FUEL DAMAGE TEST 14 TEST RESULTS REPORT.

Irradiation Embrittlement NUREG/CR-5330. HIGH-TEMPERATURE CRACK ARREST BEHAVIOR NUREG/CR-5216. POST IRRADIATION FRACTURE TOUGHNESS IN 152-MM THICK SEN WIDE PLATES OF QUENCHED AND TEM-CHARACTERIZATION OF FOUR LAB MELT PLATES PERED A 533 GRADE B CLASS 1 STEEL

l Sub);ct Ind;x 33 Loss Of Flow Acc6 dent NUREG/CR 5275: FLAME F ACILITY The Ettect Of Obstacles And Trans.

NUREG/CR 4675: IN PILE OBSERVATION Or FUEL AND CLAD RELO- verse ver' ting On Flame Acceleration And Transition To Detonsuon For CATION DURING LMFBR CORE-DISRUPT!VE ACCIDENTS. Hydrogen-Air Mixtures At Large Scale.

Low Level waste Disposal Nuclear Waste NUREG/CR-5352. VAM2D . VARIABLY SATURATED ANALYSIS NUREG/CR-5336: SENSITIVITY OF THE STABILfTY OF A WASTE EM-MODEL IN TWO DIMENSIONS. Version 5.0 With Hysteresis And PLACEMENT DRIFT TO VARIATION IN ASSUMED ROCK JOINT PA.

Channed Decay Transport Documentation And User's Guide. RAMETERS IN WELDED TUFF, MELPROG NUREG/CR-5389 ANALYSIS OF ALTERNATIVE WASTE ISOLATION NUREG/CR 5193. MELPROG PWR/ MOD 1: A TWO-DIMENSIONAL. CONCEPTS.

MECHANISTIC CODE FOR ANALYSIS OF REACTOR CORE MELT Nuclear Wast. Disposal PROGRES$10N AND VESSEL ATTACK UNDER SEVERE ACCIDENT CONDITIONS.

NUREG/CR-5235: THERMODYNAMICS OF TECHNETIUM RELATED TO NUCLEAR WASTE DISPOSAL Solubilities of Tc(IV) Omdes And MHTGR The Electrode Potentini Of The To(Vil)/Tc(IV) Oxide Couple.

NUREG/CR-5261: SAFETY EVALUATION OF MHTGR LICENSING BASIS ACCIDENT SCENARtOS. Operating Experience j NUREG-1275 V05 OPERATING EXPERIENCE FEEDBACK REPORT -

MINET Ccde PROGRESS IN SCRAM REDUCTION Commercial Power Reactors.

NUREG/CR-5355 HTGR INGRESS ANALYSIS USING MINET. NUREG/CR-5349: STEAM GENERATOR OPERATING Melt Progression EXPERIENCE. UPDATE FOR 1987 1988.

NUREG/CFI-5103. MELPROG-PWR/ MOD 1: A TWO-DIMENSIONAL.

PRA MECHANISTIC CODE FOR ANALYSIS OF REACTOR CORE MELT PROGRESSION AND VESSEL ATTACK UNDER SEVERE ACCIDENT NUREG/CR-4550 V02: ANALYSIS OF CORE DAMAGE FREOUENCY CONDITIONS. FROM INTERNAL EVLNTS: EXPERT JUDGMENT ELICITATION Part ,

1: Expert Panel Results. Part 2: Protect Staff Resofts. {

Metal Oxidation NUREG/CR-5tB7: PRA APPLICATIONS PROGRAM FOR INSPECTION j NUREG/CR-4931 CORE CONCRETE INTERACTIONS USING MOLTEN AT CALVERT CLIFFS UNIT 1 NUCLEAR POWER PLANT.

STEEL WITH ZlRCONIUM ON A BASALTIC BASEMAT;THE SURC-4 NUREG/CR 5371: DEVELOPMENT AND USE OF RISKED-BASED IN-EXPERIMENT. SPECTION GUIDES.

Modular High-Temperature Gas Reactor PWR NURE G/CR-526t; SAFETY EVALUATION OF MHTGR LICENSING NUREG/CR-5274 NUMERICAL SIMULATION OF NATURAL CIRCULA-BASIS ACCIDENT SCENARIOS TION PHENOMENA IN A PWR DURING TMLB' TRANSIENTS PRIOR Molten Steel TO CORE DAMAGE.

NUREG/CR-4994. CORE-CONCRETE INTERACTIONS USING MOLTEN STEEL WITH ZlRCONIUM ON A BASALTIC BASEMAT.THE SURC.4 Paleoseismic EXPERIMENT. NUREG/CR-5375: POST PENNSYLVANIAN REACTIVATION ALONG THE WASHITA VALLEY FAULT. SOUTHERN OKLAHOMA.

Morbidity NUREG/CR 5351. MODELS FOR PULMONARY LETHALITY AND MOR- Performance Plan BIDfTY AFTER IRRADIATION FROM INTERNAL AND EXTERNAL NUREG-1232 V03 SAFETY EVALUATION REPORT ON TENNESSEE SOURCES. VALLEY AUTHORITY: BROWNS FERRY NUCLEAR PERFORMANCE PLAN Drowns Ferry Unit 2 Restart.

MortaMy NUREG/CR 5353: INHALED (147)PM AND/OR TOTAL-BODY GAMMA Personnel Airlock RADIATION EARLY MORTALITY ANO MORBIDITY IN RATS' NUREG/CR-5118. LEAK AND STRUCTURAL TEST OF PERSONNEL NDg AIRLOCK FOR LWR CONTAINMENTS SUBJECTED TO PRESSURES NUREG/CR4360: MISSION SURVEY FOR THE PRESSURE VESSEL AND TEMPERATURES BEYOND DESIGN LIMITS.

RESEARCH USERS' FACILITY (PVRUF) p Neotectonic NUREG 0936 V08 N01: NRC REGULATORY AGENDA.Ouarterly i NUREG/CR 5257. FURT'IER NEOTECTONIC STUDIES OF EARTH- Report. January March 1989. I OUAKE ZONES IN THE EASTERN UNITED ST ATES. j Pipe Wall Thinning Nondestructive Eddy NUREG 1344. EROSION / CORROSION-INDUCED PIPE WALL THIN-NUREG/CR 5087: STEAM GENERATOR GROUP PROJECT. Task 7 NING IN U S NUCLEAR POWER PLANTS Final Report Post. Service Baseline Eddy Cunent Examination.

Piping Nondestructive Examination NUREG 1344. EROSION / CORROSION INDUCED PlPE W All THIN. NUREG-0975 V07: COMPILATION OF CONTRACT RESEARCH FOR THE MATERIALS ENGINEERING BRANCH DIVISION OF NING IN U.S. NUCLEAR POWER PLANTS.

ENGINEERING. Annual Report For F Y 1988.

Nuclear Air Cleaning NUREG/CP 0098 V01: PROCEEDINGS OF THE 20TH DOE /NRC NU- Plant Aging CLEAR AIR CLEANING CONFERENCE Sections 1 - 5 Held in Boston. NUREG/CP-0100 PROCEEDINGS OF THE INTERNATIONAL NUCLEAR Massachusetts. August 22 25.1988- POWER PLANT AGING SYMPOSIUM NURLG/CP-0008 VOL PROCEEDINGS OF THE 20TH DOE /NRC NU-CLEAR AIR CLE.NING CONFERENCE Sessions 6 15 Held in Portland Cement Boston, Massachusetts. Aucast 22-25.1988 NUREG/CR-5279 SULF ATE ATTACK RESISTANCE AND GAMMA IR-NUREG/CP 0098 V03 PROCEEDINGS OF THE 20TH DOE /NRC NU- PADIATION RESIST ANCE OF SOME PORTLAND CEMENT BASED CLEAR AIR CLEANING CONFERENCE.An index To The 1st Through MORTARS ~

20th AEC/ERDA/ DOE And DOE /NRC Nuclear Au Cleaning Confer.

ences Practice And Procedure Digest NUREG-0386 DOS UNITED STATES NUCLEAR REGULATORY COM-Nuclear Reactor PRACTICE AND PROCEDURE MISSION STAFF NUREG/CR 5357 AN EXPLORATORY STUDY OF ELEMENT INTERAC.

DIGEST Commission. Appeal Board And Licensing Board Decisions. July TIONS AND COMPOSITION DEPENDENCIES IN RADIATION SENSI.

TlVITY DEVELOPMENT Janal Report 2 J ne 9 0 R01. UN!TED STATES NUCLEAR REGULATORY Nuclear Reactor Safety COMMlSSION STAFF . DRACTICE AND PROCEDURE NUREG-1348 REPORT ON THE VISIT OF U.S NUCLE AR SAFETY DIGEST Comnvssion, Appeal Board And Licensing Board Decisions July DELEGATION TO THE SOVIET UNION. AUGUST 19-31,1968 1972 - September 19BB j

i

l l

34 Subject ind;x l Pressure Radiological Protection NUREG/CR-5118: LEAK AND STHUCTURAL TEST OF PERSONNEL NUREG/CP-0101: PROCEEDINGS OF THE WORKSHOP ON RULES AIRLOCK FOR LWR CONTAINMENTS SUBJECTED TO PRESSURES FOR EXEMPTION FROM REGULATORY CONTROL, AND TEMPERATURES BEYOND DESIGN LIMITS.

Reactivation Pressure Sensor NUREG/CR-5375: POST-PENNSYLVANIAN REACTIVATION ALONG NUREG/CR-5383' EFFECT OF AGING ON RESPONSE TIME OF NU. THE WASHITA VALLEY FAULT, SOUTHERN OKLAHOMA.

CLEAR PLANT PRESSURE SENSORS p p Pressure Vessel NUREG 1341: REGULATORY ANALYSIS FOR THE REPOLUTION OF NUREG 0975 V07: COMPILATION OF CONTRACT RESEARCH FOR GENERIC ISSUE 115. ENHANCEMENT OF THE RELIABILITY OF THE THE MATERIALS ENGINEERING BRANCH. DIVISION OF WESTINGHOUSE SOLID STATE PROTECTION SYSTEM.

ENGINEERING. Annual Report For FY 1988 NUREG/CR 4219 V05 N2: HEAVY-SECTION STEEL TECHNOLOGY Reactor Safety PROGRAM. Semiannual Progress Report For Apni September 1988. NUREG/CP 0097 V0t PROCEEDINGS OF THE SIXTEENTH WATER NUREG/CR-4929 THE EFFECTS OF VMllABLE AMPLITUDE LOADING REACTOR SAFETY INFORMAT!ON MEETING.

ON A 533-B STEEL IN HIGH-TEMPERATURE AIR AND REACTOR NUREG/CP 0097 V02: PROCEEDINGS OF THE SIXTEENTH WATER WATER ENVIRONMENTS REACTOR SAFETY INFORMATION MEETING.

NUREG/CR-5216. POST IRRADIATION FRACTURE TOUGHNESS NUREG/CP-0037 V03: PROCEEDINGS OF THE SIXTEENTH WATER CHARACTERIZATION OF FOUR LAB-MELT PLATES REACTOR SAFETY INFORMATION MEETING.

NUREG/CR-5218 ROI: POST-IRRADIATION FRACTURE TOUGHNESS NUREG/CP-0097 V04' PROCEEDINGS OF THE SIXTEENTH WATER CHARACTERIZATION OF FOUR LAB-MELT PLATES REACTOR SAFETY INFORMATION MEET'NG.

NUREG/CP-0097 V05. PROCEEDINGS OF THE SIXTEENTH WATER NUREG/CR-5330. HIGH-TEMPERATURE CRACK-ARREST BEHAVIOR IN 152 MM-THICK SEN WIDE PLATES OF QUENCHED AND TEM- NURE /CR 46 N LE OBSE T Of FUEL AND CLAD RELO-RESEARC S FAC Li P UF PERIMENTS NUREG/CR-5356: IMPROVED MODEL FOR PREDICTING J.R CURVES FROM CHARPY DATA. Phase i Final Report. Reactor Shutdown NUREG/CR-5357: AN EXPLORATORY STUDY OF ELEMENT INTERAC. NUREG/CR-5344: REPLACEMENT ENERGY COST ANALYSIS PACK-TiONS AND COMPOSITION DEPENDENCIES IN RADIATION SENSI-AGE (RECAP). USER'S GUIDE.

TIVITY DEVELOPMENT.F:nal Report.

Regulation UR G/CR 5 74 U ERICAL SIMULATION OF NATURAL CIRCULA- T - 988' TION PHENOMENA IN A PWR DURING TMLB' TRANSIENTS PRIOR TO CORE DAMAGE. Regulatory Agenda NUREU-0936 V08 Not NRC REGULATORY AGENDA.Ouarterly Probabilistic Risk Assessment Report. January-March 1989.

NUREG/CR-4550 V02: ANALYSIS OF CORE DAMAGE FREOUENCY FROM INTERNAL EVENTS: EXPERT JUDGMENT ELICITATION Part Regulatory And Technical Report 1 Expert Panet Results. Part 2: Project Staff Results NUREG 0304 V13 N04. REGULATORY AND TECHNICAL REPORTS NUREG/CR-5230: SHUTDOWN DECAY HEAT REMOVAL (ABSTRACT INDEX JOURNAL). Annual Compilaten For 1988.

ANALYSIS PLANT CASE STUDIES AND SPECIAL ISSUES Summary Report. Replacement Energy Cost NUREG/CR-537t DEVELOPMENT AND USE OF RISKED-BASED IN- NUREG/CR-5344 REPLACEMENT ENERGY COST ANALYSIS PACK-SPECTION GUTES. AGE (RECAP)' USER'S GUIDE.

Pulmonary Lethality Heracking NUREG/CR-535t MODELS FOR PULMONARY LETHALITY AND MOR. NUREG/CR-5281. VALUE/ IMPACT ANALYSES OF ACCIDENT PRE-BiDITY AFTER 1RRADIATION FROM INTERNAL AND EXTERNAL VENTIVE AND MITIGATIVE OPTIONS FOR SPENT FUEL POOLS.

SOURCES.

Residual H.st Removal Quatw.sary Fault NUREG/CR-5268: AGING STUDY OF BOILING WATER REACTOR RE-NUREG/CR-5375: POST PENNSYLVANIAN REACTIVATION ALONG SIDUAL HEAT REMOVAL SYSTEM.

THE WASHITA VALLEY FAULT. SOUTHERN OKLAHOMA. NUREG/CR 5293: CLOSEOUT OF IE BULLETIN 86 OLMINIMUM FLOW LOGIC PROBLEMS THAT COULD DISABLE RESIDUAL HEAT RE-Radsat6on MOVAL PUMPS.

NUPEG/CR 4214 Pfl R1: HEALTH EFFECTS MODELS FOR NUCLEAR POWER PLANT ACCIDENT CONSEQUENCE ANALYSIS. Low LET Response T6me Radiation.Part II: Scientific Bases For Health Effects Models NUREG/CR-5383. EFFECT OF AGING ON RESPONSE TIME OF NU-NUREG/CR 5353. INHALED (147)PM AND/OR TOTAL-BODY GAMMA CLEAR PLANT PRESSURE SENSORS.

RADIATION EARLY MORTALITY AND MORBIDITY IN RATS.

Rules Of Practice Radiatlon Embrittlement NUREG-0386 DOS: UNITED STATES NUCLEAR REGULATORY COM.

NUREG/CR-5357 AN EXPLORATORY STUDY OF ELEMENT INTERAC. MISSION STAFF PRACTICE AND PROCEDURE TIONS AND COMPOSITION DEPENDENCIES IN RADIATION SENSI. DIGEST. Commission. Appeal Board And Leensing Board Decisions. July TIVITY DEVELOPMENT. Final Report 1972 - June 1988.

NUREG 0386 D05 RO1: UNITED STATES NUCLEAR REGULATORY Radiation Protection COMMISSION STAFF PRACTICE AND PROCEDURE NUREG/CR-3469 V04. OCCUPATIONAL DOSE REDUCTION AT NU- DIGEST. Commission, Appeal Board And L. censing Board Decisions July CLEAR POWER PLANTS ANNOTATED BIBLIOGRAPHY OF SELECT- 1972 September 1968.

ED READINGS IN RADIATION PROTECTION AND ALARA.

NUREG/CR-4409 V03 DATA BASE ON DOSE REDUCTION RE- Safe Shutdown SEARCH PROJECTS FOR NUCLEAR POWER PLANTS. NUREG/CA-5246 A METHODOLOGY TO ASS!ST IN CONTINGENCY PLANNING FOR PROTECTION OF NUCLEAR POWER PLANTS Radiation Source AGAINST LAND VEHICLE BOMBS.

NUREG/CP 0101: PROCEEDINGS OF THE WORKSHOP ON RULES FOR EXEMPTION FROM REGULATORY CONTROL. Safety Evaluation Report NUREG 0420 S10 SAFETY EVALUATION REPORT RELATED TO THE Radioactive Waste OPERATION OF SHOREHAM NUCLEAR POWER STATION UNIT NUREG/CR-3964 V00 TECHNIQUES FOR DETERMINING PROBABIL- 1. Docket No 50-322 (Long Island Lighting Company)

' TIES OF EVENTS AND PROCESSES AFFECTING THE PERFORM. NUREG 0797 S20 SAFETY EVALUATION REPOF" RELATED TO THE ANCE OF GEOLOGIC REPOSITOR:ES '_iterature Review OPERATION OF COMANCHE PEAK 'EAM ELECTRIC

_ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ ._ ._ m

Subjzct Ind3x 35 STATION. UNITS 1 AND 2 Docket Nos. 50-445 And 50-446.(Texas Utili. Solid State Protection System ties Generstmp Corp) . NUREG 1341: REGULATORY ANALYSIS F 7 THE RESOLUTION OF NUREG-0896 SJB: SAFETY EVALUATON REPORT RELATED TO THE GENERIC ISSUE 115. ENHANCEMENT OF HE RELIABILITY OF THE CPERATION OF SEABROOK STATION. UNIT 1. Docket No. 50- WESTINGHOUSE SOLID STATE PROTECTION SYSTEM. j d43 (Pubhc Service Company Of New Ilampshire) i NUREG 0991 S07: SAFETY EVALUATION REPORT RELATED TO THE Special Nuclear Material OPERATION OF LIMERICK GENERATING STATION. UNITS 1 AND NUREG/CR 5172: TACTICAL TRAINING REFERENCE MANUAL.

2 Docket Nos. 50-352 And 50-353.(Philadelphia Electnc Company)

NUREG-0W1508. SAFETY EVALUATION REPORT RELATED TO THE Spent Fuel Pool OPERATION OF LIMERICK GENERATING STATION. UNITS 1 AND NUREG 1353 REGULATORY ANALYSIS FOR THE RESOLUTION OF 2 Docket Nos. 50-352 And 50-353 (Philadelphia Electnc Company) GENERIC ISSUE 82. "BEYOND DESIGN BASIS ACCIDENTS IN NUREG-1232 V03: SAFETY EVALUATON REPORT ON TENNESSEE SPENT FUEL POOLS "

VALLEY AUTHORITY: BROWNS FERRY NUCLEAR PERFORMANCE NUREG/CR 5281: VALUE/ IMPACT ANALYSES OF ACCIDENT PRE-PLAN Browns Ferry Unit 2 Restart. VENTIVE AND MITIGATIVE OPTIONS FOR SPENT FUEL POOLS.

NUREG 1312. SAFETY EVALUATION FIEPORT RELATED TO THE RE-NEWAL OF THE FACILITY LICENSE FOR THE RESEARCH REAC- Stainless Steel Pipe TOR AT THE DOW CHEMICAL COMPANY- NUREG/CR-5283 CLOSEOUT OF IE BULLETIN 79-03: LONGITUDINAL WELD DEFECTS IN ASME SA 312 TYPE 304 STAINLESS STEEL UE 1342 A T TU R PORT REGARDING INDUSTRY IMPLE- INE G CO PA Y MENTATION OF SAFETY PARAMETER DISPLAY SYSTEMS.

NUREG/CR-5284. CLOSEOUT OF IE BULLETIN 79 03A. LONGITUDINAL Safety Research WELD DEFECTS W ASME SA-312 TYPE 304 STAINLESS STEEL NUREG 1266 V03 NRC WETY RESEARCH IN SUPPORT OF REGU- PIPE.

LA N - 1 BBL Static Load Cycle Scram Reduction NUREG/CR-5222; STATIC LOAD CYCLE TESTING OF A LOW ASPECT-NUREG 1275 V05: OPERATING EXPERIENCE FEEDBACK REPORT . RATIO SIX-INCH WALL TRG-TYPE STRUCTURE TRG 4-6 (1.0. 0.25).

PROGRESS IN SCRAM REDUCTON Commercial Power Reactors.

g Security System NUREG/CR-5087. STEAM GENERATOR GROUP PROJECT. Task 7 NUREG/CR-5081: TACTICAL EXERCISE PLANNING HANDBOOK. Final Report. Post-Service Baseline Eddy Current Examination.

NUREG/CR 5172. TACTICAL TRAINING REFERENCE MANUAL. NUREG/CR-5349. STEAM GENERATOR OPERATING EXPERIENCE. UPDATE FOR 1987 1988.

Seismic Design NUREG/CR-5347: RECOMMENDATIONS FOR RESOLUTION OF Steam ingress PUBLIC COMMENTS ON USI A 40, " SEISMIC DESIGN CRITERIA? NUREG/CR-5355: HTGR INGRESS ANALYSIS USING MINET.

Seismic Hazard Substance Abuse NUREG/CR-3964 VD1: TECHNIOUES FOR DETERMINING PROBABIL* NUREG/CR-5227 S01: FITNESS FOR DUTY IN THE NUCLEAR POWER ITIES OF EVENTS AND PROCESSES AFF7 TING THE PERFORM- INDUSTRY.A REVIEW OF TECHNICAL ISSUES.

ANCE OF GEOLOGIC REPOSITORIES.Uterature Review.

Sulfate Attack Seismic Response NUREG/CR-5279: SULFATE-ATTACK RESISTANCE AND GAMMA-lR.

NUREG/CR-5237: USE OF LINEAR REDUCED' STIFFNESS ANALYTI- RADIATION RESISTANCE OF SOME PORTLAND CEMENT BASED CAL MODELS TO PREDICT SEISMIC RESPONSE OF DAMAGED MORTARS CONCRETE STRUCTURES.

Systems interacWn Seismicity

^

NUREG/CR-5257: FURTHER NEOTECTONIC STUDIES OF EARTH- AR POWER PLANTS. Technical Findings Related To Unresolved OUAKE ZONES IN THE EASTERN UNITED STATES.

Safety issue A-17.

Service Water System NUREG/CR-5379 VOI: NUCLEAR PLANT SERVICE WATER SYSTEM M

AGING DEGRADATON # SSESSMENT. Phase 1. NUREG 0B37 V08 N04: NRC TLD DIRECT RADIATION MONITORING NETWORK. Progress Report October December 1988.

Severe Accident NUREG 1251 V01: IMPLICATIONS OF THE ACCIDENT AT CHERNOBYL MLB FOR SAFETY REGULATION OF COMMERCIAL NUCLEAR POWER NUREG/CR-5274: NUMERICAL SIMULATION OF NATURAL CIRCULA-FLANTS IN THE UNITED STATES.F nal Report Main Report TION PHENOMENA IN A PWR DURING TMLB' TRANSIENTS PRIOR NUREG-1251 Vit IMPLICATIONS OF THE ACCIDENT AT CHERNOBYL TO CORE DAMAGE.

FOR SAFETY REGULATION OF COMMERCIAL NUCLEAR POWER PLANTS IN THE UNITED STATES. Final Report. Appendix Pubhc Com- Tactical Training ments And Their Disposition. NUREG/CR-5172: TACTICAL TRAINING REFERENCE MANUAL NUREGiCP 0098 V01: PROCEEDINGS OF THE 20TH DOE /NRC NU-CLEAR AIR CLEANING CONFERENCE. Sections 1 - 5. Held in Boston.

Technetium Massachusetts. August 22-25.1988 NUREG/CR 5235: THERMODYNAMICS OF TECHNETIUM RELATED NUREG/CP-0098 V02: PROCEEDINGS OF THE 20TH DOE /NRC NU. TO NUCLEAR WASTE DISPOSAL.Solubihties of Tc(IV) Oxides And CLEAR AIR CLEANING CONFERENCE Sessions 6 15 Held in The Electrode Potential Of The Tc(Vil)/Tc(IVFOxide Couple Boston. Massachusetts. August 22 25,1988.

Technical Specification NUREG/CR-5163: POWER BURST FACILITY (PBF) SEVERE FUEL DAMAGE TEST 1-4 TEST RESULTS REPORT. NUREG 1331: TECHNICAL SPECIFICATIONS FOR SEABROOK STA-NUREG/CR-5193: MELPROG-PWR/ MOD 1: A TWO-DIMENSIONAL. TION. UNIT 1. Appendix A" To License No. NPF-67. Docket No. 50-MECHANISTIC CODE FOR ANALYSIS OF REACTOR CORE MELT 443fPubhc Sorwce Company Of New Hampshire)

PROGRESSON AND VESSEL ATTACK UNDER SEVERE ACCIDENT NUREG-1357 TECHNICAL SPECIFICATIONS FOR SHOREHAM NU-CONDITIONS. CLEAR POWER STATION. UNIT 1. Docket No. 50-322(Long Island l Lighting Company) {

Shear Wall NUREG-1360 TECHNICAL SPECIFICATIONS FOR LIMERICK GENER.

NUREG/CR 5222. STATIC LOAD CYCLE TESTING OF A LOW-ASPECT- ATING STATION. UNIT 2 Docket No 50-383 (Philadelphia Electnc  !

RATIO SIX-INCH WALL TAG-TYPE STRUCTURE TRG-4-6 (1.0. 0.25) Company)

Site Characterization Tectonic Activity NUREG/CR 5391: FLOW OF GROUNDWATER AND TRANSPURT OF NUREG/CR-3964 V01: TECHNIOUES FOR DETERMINING PROBABIL-CONTAMINANTS THROUGH SATURATED FRACTURED GEOLOGIC ITIES OF EVENTS AND PROCESSES AFFECTING THE PERFORM-MEDIA. ANCE OF GEOLOGIC REPOSITORIES Literature Review

36 Subject Ind;x Temperature USl A 45 NUREG/CR-5118. LEAK AND STRUCTURAL TEST OF PERSONNEL NUREG/CR-5230. SHUTDOWN DECAY HEAT REMOVAL AIRLOCK FOR LWR CONTAINMENTS SUBJECTED TO PRESSURES ANALYSIS PLANT CASE STUDIES AND SPECIAL ISSUES Summary AND TEMPERATURES BEYOND DESIGN LIMITS. Report.

Temperature Measurement Unresolved Safety lasue A-17 NUREG/CR 4721: THE USE OF FIBER OPTICS FOR REMOTE TEM- NUREG-1174: EVALUATION OF SYSTEMS INTERACTIONS IN NUCLE.

PERATURE MEASUREMENT IN FISSION PRODUCT RELEASE AR POWER PLANTS. Technical Findings Related To Unresolved TESTS Safety issue A-17.

Thermal Shock Unsaturated Transport NUREG/CR-4219 VOS N2 HEAVY SECTION STEEL TECHNOLOGY VARIABLY SATURATED ANALYSIS NUREG/CR-5352: VAM2D PROGRAM.Semaannual Progress Report For April. September 1988 MODEL IN TWO DIMENSIONS. Version 5 0 With Hysteresis And NUREG/CR 5350 MISSION SURVEY FOR THE PRESSURE VESSEL Chained Decay Transport Documentation And User s Guide.

RESE ARCH USERS' FACILITY (PVRUF).

Thermal-Hydraulic VAM2D NUREG/CR-5274 NUMERICAL SIMULATION OF NATURAL CIRCULA- NUREG/CR 5352. VAM2D VARlABLY SATURATED ANALYSIS TION PHENOMENA IN A PWR DURING TMLB' TRANSIENTS PRIOR MODEL IN TWO DIMENSIONS. Version 5 0 With Hystereses And TO CURE DAMAGE. Chained Decay Transport Documentation And User's Guide.

Thermal-Mechanical Variable Amplitude NUREG/CR-5389. ANALYSIS OF ALTERNATIVE WASTE ' SOLATION NUREG/CR 4929 THE EFFECTS OF VARIABLE AMPLITUDE LOADING CONCEPTS ON A 533-B STEEL IN HIGH TEM"ERATURE AIR AND REACTOR Thermodynamic NUREG/CR-5235: THERMODYNAMICS OF TECHNETIUM RELATED vehicle Bomb TO NUCLEAR WASTE DISPOSAL.Solutahties of Tc(IV) Oxides And NUREG/CR-5246 A METHODOLOGY TO ASSIST IN CONTINGENCY The Electrode Potential Of The Tc(Vil)/Tc(IV)-Oxide Couple- PLANNING FOR PROTECTION OF NUCLEAR POWER PLANTS Thermoluminescent Doslmeter AGAINS1 LAND VEHICLE BOMBS.

NUREG 0837 V08 N04. NRC TLD DIRECT RADIATION MONITORING NE EVORK. Progress Report October December 1968. Vendor Inr ec pn Tit:e Liss SPE , TION STATUS REPORT. Quarterly Report. October-December NUREG d40 VII N01: TITLE LIST OF DOCUMENTS MADE PUBLICLY 19EJ (White Book)

AVAILABLE January 1 31,1989 NUREG 0540 VII NO2- TITLE LIST OF DOCUMENTS MADE PUBLICLY Vessel AVAILABLE February 1-28.1989 NUREG/CR-5193 MELPROG-PWR/ MOD 1: A TWO DIMENSIONAL, NUREG-0540 VII NO3. TITLE LIST OF DOCUMENTS MADE PUBLICLY MECHANISTIC CODE FOR ANALYSIS OF REACTOR CORE MELT AVAILABLE. March 1-31.1989 PROGRESSION AND VESSEL ATTACK UNDER SEVERE ACCIDENT NUREG 0540 VII N04: TITLE LIST OF DOCUMENTS MADE PUBLICLY CONDITIONS.

AVAILABLE. Apnl 1 30,1989.

Warm Prestress NUREG/CR-5208. WARM PRESTRESS MODELING. COMPARISON OF UR G/CR 252 AEROSOL SAMPLING AND TRANSPORT EFFICIEN- b^ '

CY CALCULATION (ASTEC) AND APPLICATION TO SURTSEY/DCH AEROSOL SAMPLING SYSTEM Code Version 1.0: Code Desenption Washits Valley Fault And User'* Manual- NUREG/CR-537 5 POST-PENNSYLVANIAN REACTIVATION ALONG THE WASHIT A VALLEY F AULT, SOUTHERN OKI AHOMA.

y,99 NUREG/CR-5336. SENSITIVITY OF THE STABILITY OF A WASTE EM-CEMEh DR TO VARIATION IN ASSUMED ROCK JOINT PA.

gE Ep RE CR-52B3. CLOSEOUT OF IE BULLETIN 79-03 LONGITUDINAL NUREG/CR 53B9 ANALYSIS OF ALTERNATIVE WASTE ISOLtTION WELD DEFECTS IN ASME 6A-312 TYPE 304 STAINLESS STEEL CONCEPTS PIPE SPOOLS MANUFACTURED BY YOiJNGSTOWN WELDING AND ENGINEERING COMPANY.

USl A-40 NUREG/CR-5284: CLOSEOUT OF IE BULLETIN 79-03A10NGITUDINAL NUREG/CR-5347: RECOMMENDATIONS FOR FIESOLUTION OF WELD DEFECTS IN ASME SA 312 TYPE 304 STAINLESS STEEL PUBLIC COMMENTS ON USl A 40. "SEtSMIC DESIGN CRITERIA." PIPE.

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NRC Originating Orgtnizction index (Steff Raports)

This index lists those NRC organizations that have published staff reports. The index is ar- .

ranged alphabetically by rnajor NRC organizations (e.g., program offices) and then by sub- I sections of these (e.g., divisions, branches) where appropriate. Each entry is followed by a NUREG number and title of the report (s), if further information is needed, refer to the main citation by NUREG number.

ADVtSORY COMMITTEE (S) - DIVISION OF FREEDOM OF INFORMATION & PUBLICATIONS SERV-ACRS ADVISORY COMMITTEE ON REACTOR SAFEGUARDS ICES (880515-8902 NUREG1125 V10. A COMPILATION OF REPORTS OF THE ADIV. NUREG-0540 V11 N01: TITLE LIST OF DOCUMENTS MADE PUBLIC-SORY COMMITTEE ON REACTOR SAFEGUARDS 1988 Annual. LY AVAILABLE, January 1 31,1989.

l' ATOMIC SAFETY BOARD (S) & PANEL (S) EDO -OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS ATOMIC SAFETY AND LICENSING BOARD PANEL DIVISION OF INDUSTRIAL & MEDICAL NUCLEAR SAFETY (POST NUREG 1363 V01: ATOMIC SAFETY AND LICENSINC BOARD 870729)

P%NEL ANNUAL REPORT FOR FISCAL YEAR 1988. NUREG-0904 S01 V01: SUPPLEMENT TO THE FINAL ENVIRONMEN-TAL STATEMENT RELATED TO THE DECOMMISSIONING OF THE OFFICE OF EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) RARE EARTHS FACILITY, WEST CHICAGO.lLLINOIS Volume 1-REGION 1. OFC OF THE DIRECTOR Main Text And Appendices A-G Docket No. 40-2061 NUREG-0837 V08 N04: NRC TLD DIRECT RADIATION MONITORING 'I NUREG-0904 601 V02: SUPPLEME.NT TO THE FINAL ENVIRONMEN.

OFC F N OR ENT POS 704 ) *NUNCODM "

. NUREG-0940 V08 N01: ENFORCEMENT ACTIONS SIGNIFICANT AC- RARE EARTHS FACILITY, WEST CHICAGOJLLINOISVolume 2: Ap-TIONS RESOLVED.Ouarterly Progress Report. January-March 1989, pendix H. Docket No. 40-2061.

EDO OFFICE OF ADMINISTRATION (PRE 870413 & POST 890205) U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF ADMINISTRATION (POST 890205) OFFICE OF THE GENERAL COUNSEL (POST 860701)

NUREG 1145 V05: U.S. NUCLEAR REGULATORY COMMISSION NUREG-0386 DOS: UNITED STATES NUCLEAR REGULATORY COM-1988 ANNUAL REPORT. MISSION STAFF PRACTICE AND PROCEDURE DIVISION OF FREEDOM OF INFORMATION & PISLICATIONS SERV. DIGEST. Commission, Appeal Board And Licensing Board ICES (POST 890205 Decisions. July 1972 - June 1988.

NUREG-0304 V13 N04: REGULATORY ANC ,aNs .L REPORTS NUREG-0386 DOS R01; UNITED STATES NUCLEAR REGULATORY (ABSTRACT INDEX JOURNAL). Annual Compilahon For 1988. COMMISSION STAFF PRACTICE AND PROCEDURE NUREG-0540 V11 NO2: TITLE LIST OF DOCUMENTS MADE PUBLIC- DIGEST.Commismon, Appeal Board And - Licensing Board LY AVAILABLE. February 1 28,1989. Decisions July 1972 - September 1988.

NUREG-0540 V11 NO3. TITLE LIST OF DOCUMENTS MADE PUBLIC. NRC-. NO DETAILED AFFILIATION GIVEN LY AVAILABLE March 1 31.1989. NUREG 1251 VOI: IMPLICATIONS OF THE ACCIDENT AT CHERNO.

NUREG 0540 V11 N04: TITLE LIST OF DOCUMENTS MADE PUBLIC- BYL FOR SAFETY REGULATION OF COMMERCIAL NUCLEAR -

LY AVAILABLE April t 30,1989. POWEA PLANTS IN THE UNITED STATES. Final ReportMain NUREG 0750 V28102; INDEXES TO NUCLEAR REGULATORY COM- Report.

MISSIOM ISSUANCES. July December 1988 NUREG-1251 vfl IMPLICATIONS OF THE ACCIDENT AT CHERNO-NUREG 0750 V29 NO2. NUCLEAR REGULATORY COMMISSION IS- BYL FOR SAFETY REGULATION OF COMMERCIAL NUCLEAR SUANCES FOR FEBRI.lARY 1989 Pages89-209 POWER PLANTS IN THE UNITED STATES Final Report. Appendix -

NUREG-0750 V29 NO3. iiUCLE AR REGULATORY C,0MMISSION IS- Public Comments And Their Disposition.

SUANCES FOR MARCH 1961 Pages 211-343. NUREG/CR-3950 V05' FUEL PERFORMANCE ANNUAL REPORT NUREG 0750 V29 N04. NUCLEAR REGU! ATORY COMMISSION IS- FOR 1967.

SUANCES FOR APRIL 1989_ Pages 345 393 NUREG/CR 5353' INHALED (147)PM AND/OR TOTAL-BODY NUREG 0936 V00 N01; NRC REGULATORY AGENDA.Ouarterly GAMMA RADIATION E ARLY MORTALITY AND MORBIDITY IN Report. January March 1989- RATS EDO- OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL EDO - OFFICE OF NUCLEAR REGULATORY RESEARCH (POST 820405)

OFF CE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA, DI.

l 607 )

^

NURE -0000 V11 N04: REPORT TO CONGRESS ON ABNORMAL U 9B DMS N OF A Y R S(bS 8 0413)

NUREG 1275 V05. OPERATING EXPERIENCE FEEDBACK REPORT -

PROGRESS IN SCRAM REDUCTION Commercial Power Reactors NUREG/ 0097 02.PR EDINGS OF HE' SIXTEENTH WATER REACTOR SAFETY INFORMATION MEETING.

NUREG/CP-0007 V03. PROCEEDINGS OF THE SIXTEENTH WATER OFFICE OF GOVERNMENTAL & PUBLIC AFFAIRS (POST 870413)

INTERNATIONAL PROGRAMS REACTOR SAFETY INFORMATION MEETING NUREG 1348: REPORT ON THE VISIT OF U S. NUCLEAR SAFETY NUREG/CP-0097 V04: PROCEEDINGS OF THE SIXTEENTH WATER DELEGATION TO THE SOVIET UNION, AUGUST 19-31,1988 REACTOR SAFETY INFORMATION MEETING.

NUREG/CP 0097 V05: PROCEEDINGS OF THE SIXTEENTH WATER EDO OFFICE OF INFORMATION RESOURCES MANAGEMENT & ARM REACTOR SAFETY INFORMATION MEETING (870413-890204) NUREGICP-0100. PROCEEDINGS OF THE INTERNATIONAL NUCLE.

DIVISION OF COMPUTER a VECOMMUNICATIONS SERVICES AR POWER PLANT AGING SYMPOSIUM.

(POST 890205) DMSiON OF ENGINEERING (POST 870413)

NUR5G-0020 V13 NO3: Lib AD OPERATlW ' REACTORS ST ATUS NUREG-0975 V07; COMPILATION OF CONTRACT RESEARCH FOR

SUMMARY

REPORT Data As Of February 28.1989 (Gray Book 1) THE MATERIALS ENGINEERING BRANCH, DIVISION OF NUREG-0020 V13 N04 LICENSED OPERATING REACTORS STATUS ENGINEERING Annual Report For FY 1968.

SUMMARY

REPORT. Data As Of March 31.1989 (Gray Book 1) DfVlSION OF REGULATORY APPLICATIONS (POST B70413)

NUREG 0020 V13 NOS. LICENSED OPERATING REACTORS ST ATUS NUREG 0933 SO9 A PRIORITIZATION OF GENERIC SAFET7

SUMMARY

REPORT. Data As Of Apnl 30,1989 (Gray Bocrk I) ISSUES 37 j

38 NRC Origin: ting Organir. tun Ind;x (St:ff R: ports)

DIVISION OF SAFETY ISSUE RESOLUTION (POST 883717) NUREG-1357: TECHNICAL SPECIFICATIONS FOR SHOREHAM NU-NUREG 1174. EVALUATION OF SYSTEMS INTERACTIONS IN NU- CLEAR POWER STATION. UNIT 1. Docket No. 50-322(Long Island CLEAR POWER PLANTS. Technical Findings Related To UnresoNed Lighting Company)

Safety issue A-17. NUREG 1360: TECHNICAL SPECIFICATIONS FOR LIMERICK GEN-NUREG 1341: REGULATORY ANALYSIS FOR THE RESOLUTION OF ERATING STATION, UNIT 2. Docket No. 50 383 (Philadelphia Electne GENERIC ISSUE 115. ENHANCEMENT OF THE RELIABILITY OF Company)

THE WESTINGHOUSE SOLID STATE PROTECTION SYSTEM STANDARDIZATION & NON. POWER REACTOR PROJECT DIRECTOR.

NUREG 1353: REGULATORY ANALYSIS FOR THE RESOLUTION OF ATE GENERIC ISSUE 82, "BEYOND DFSIGN BASIS ACCIDENTS IN NUREG-1312: SAFETY EVALUATION REPORT RELATED TO THE SPENT FUEL POOLS? RENEWAL OF THE FACILITY LICENSE FOR THE RESEARCH RE.

ACTOR AT THE DOW CHEMICAL COMPANY.

EDO - OFFICE OF NUCLEAR REACTOR REGULATION (POST 4/28/80) TVA PROJECTS DIVISION OFFICE OF NUCiEAR REACTOR REGULATION, DIRECTOR (POST NUREG 1232 V03: SAFETY EVALUATION REPORT ON TENNESSEE 870411) VALLEY AUTHORITY: BROWNS FERRY NUCLEAR PERFORM-NUREG-0797 S21: SAFETY EVALUATION REPORT RELATED TO ANCE PLAN Browns Ferry Unit 2 Restart.

THE OPERATION OF COMANCHE PEAK STEAM ELECTRIC DIVISION OF ENGINEERING & SYSTEMS TECHNOLOGY { POST TION.UN TS 1 A 2. Docket Nos. 50-445 And 50 446(Texas NU G 1344. EROSION / CORROSION-INDUCED PIPE WALL THIN-DIVISION OF REACT R PROJECTS - 1/II (POST B70411) NING IN U S. NUCLEAR POWER PLANTS NUREG 0420 S10 SAFETY EVALUATION REPORT RELATED TO DIVISION OF REACTOR INSPECTION & SAFEGUARDS (POST THE OPERATION OF SHOREHAM NUCLEAR POWER N STATION, UNIT 1 Docket No. 50-322. (Long Island Ughting Compa- G- 40 V12 N04 LICENSEE CONTRACTOR AND VENDOR IN-SPECTION STATUS REPORT. Quarterty Report. October-December NUREG-0896 SOB: SAFETY EVA UATION REPORT RELATED TO N THE OPERATION OF SEABROOK STATION, UNIT 1 Docket No. 50- G0 0 VI t 01: LICENSEE CONTRACTOR AND VENDOR IN-443 (Publ:c Service Company Of New Hampshire) SPECTION STATUS REPORT. Quarterly Report, January-March NUREG 0991 S07: SAFETY EVALUATION REPORT RELATED TO 1989 (White Book)

THE OPERATION OF UMERICK GENERATING STATION, UNITS 1 NUREG 1349 COMPILATION OF FASTENER TESTING DATA RE.

AND 2. Docket Nos 50 352 And 50 353 (Ph!!adelptua Electnc Com- CEIVED IN RESPONSE TO NRC COMPLIANCE BULLETIN 87-02.

pan NUREG 1354: FITNESS FOR DUTY IN THE NUCLEAR POWER INDUSTRY: RESPONSES TO PUBLIC COMMENTS NUREG-0991 S08. SAFETY EVALUATION REPORT RELATED TO DIVISION OF LICENSEE PERFORMANCE & QUALITY EVALUATION THE OPERATION OF UMERICK GENERATING STATION, UNITS 1 (POST 870411)

AND 2 Docket Nos 50-352 And 50 353 (Philadelphia Electnc Com- NUREG-1342: A STATUS REPORT REGARDING INDUSTRY IMPLE-pany) MENTATION OF SAFETY PARAMETER DISPLAY SYSTEMS NUREG-1331: TECHNICAL SPECIFICATIONS FOR SEABROOK STA- NUREG-1358. LESSONS LEARNED FROM THE SPECIAL INSPEC-TION, UNIT 1. Anr'endix "A" To Ucense No. NPF-67. Docket No 50- TlON PROGRAM FOR EMERGENCY OPERATING 443.(Public Service Company Of New Hampshire) PROCEDURES. Conducted March October 1988.

6 l

NRC Originating Organization Index (International Agreements)

This index lists those NRC organizations that have published international a ports. The index is arranged alphabetically by major NRC organizations pr e.g.,greemen fices) and then by subsections of these (e.g., divisions, branches) where (appropn,og ate. Each Cntry 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.

There were no NUREG/lA reports for this quarter.

I l

i i

39 l

1

I 1

I

NRC Centreet Spanzer Ind3x_(Centreetcr Reports) l

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) arepared by that organi-zation. If further information is needed, refer to the main citation by t le NUREG/CR number.

EDO . OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL NUREG/CR-5237. USE OF LINEAR REDUCECTSTlFFNESS ANALYTI.

DATA CAL MODELS TO PREDICT SEISMIC RESPONSE OF DAMAGED OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA. Dl- CONCRETE STRUCTURES.

. RECTOR NUREG/CR-5238, DEVELOPMENT OF AN ENGINEERING DEFINI-NUREG/CR-2000 V08 N2. LICENSEE EVENT REPORT (LER) TION OF THE EXTENT OF J SINGULARITY CONTROLLED CRACK l COMPILATION For Month Of February 1989- GRONTH.

NUREG/CR-2000 V08 N3: LICENSEE EVENT REPORT (LER) NUREG/CR-5257: FURTHER NEOTECTONIC STUDIES OF EARTH-COMPILATION.For Month Of March 1989. QUAKE ZONES IN THE EASTERN UNITED STATES.

NUREG/CR-2000 V08 N4: LICENSEE EVENT REPORT (LER) NUREG/CR-5268: AGING STUDY OF BOILING WATER REACTOR COMPILATION For Month Of Apnl 1989. RESIDUAL HEAT REMOVAL SYSTEM. j NUREG/CR-2000 V08 NS: LICENSEE EVENT REPORT (LER) NUREG/CR-5279: SULFATE-ATTACK FIESISTANCE AND GAMMA-IR-COMPILATION For Month Of May 1989. RADIATION RESISTANCE OF SOME PORTLAND CEMENT BASED MORTARS D VIS N OF SA E U DS & TRAN RTATION (POS 870 13) IOR IN 152-MM THICK SEN WIDE PLATES OF QUENCHED AND NUREGICR-5081: TACTICAL EXERCISE PLANNING ' HANDBOOK.

NUREG/CR 5172: TACTICAL TRAINING REFERENCE MANUAL. TEMPERED A 533 GRADE B CLASS 1 STEEL DIVISION OF HIGH LEVEL WASTE MANAGEMENT (POST 870413) NUREG/CR 5350 MISSION SURVEY FOR THE PRESSURE VESSEL NUREG/CR-3964 V01: TECHNIQUES FOR DETERMINING PROB. RESEARCH USERS' FACILITY (PVRUF).

ABILITIES OF EVENTS AND PROCESSES AFFECTING THE PER. NUREG/CR-5352: VAM2D - VARIABLY SATURATED ANALYSIS FORMANCE OF GEOLOGIC REPOSITORIES Literature Review. MODEL IN TWO DIMtLNSIONS Vorwon 5.0 With Hysteresis And NUREG/CR.5089: NUMERICAL MODELING OF GROUND WATER Chained Decay Transport Documentation And User's Guide.

FLOW SYSTEMS IN THE VICINITY OF THE REFERENCE REPOSI. NUREG/CR-5357: AN EXPLORATORY STUDY OF ELEMENT INTER.

TORY LOCATION.HANFORD, WASHINGTON. ACTIONS AND COMPOSITION DEPENDENCIES IN RADIATION NUREG/CR-5336: SENSITIVITY OF THE STABILJY OF A WASTE SENSITIVITY DEVELOPMENT. Final Report.

EMPLACEMENT DRIFT TO VARIATION IN ASSUMED ROCK JOINT NUREG/CR-5375: POST-PENNSYLVANIAN REACTIVATION ALONG PARAMETERS IN WELDED TUFF. THE WACHITA VALLEY FAULT,SOLrTHERN OKLAHOMA.

NUREG/CR-5389: ANALYSIS OF ALTERNATIVE WASTE ISOLATION NUREG/CR-5379 V01: NUCLEAR PLANT SERVtCE WATER SYSTEM CONCEPTS. AGING DEGRADATION ASSESSMENT Phase !.

NUREG/CR-5383. EFFECT OF AGING ON F'ESPONSE TIME OF NU-EDO - OFFICE OF NUCLEAR REGULATORY RESE ARCH (POST 820405) CLEAR PLANT PRESSURE SENSORS.

OFFICE OF NUCLEAR REGULATORY RESEARCH, DIRECTOR (POST NUREG/CR-5391: FLOW OF GROUNDWATER AND TRANSPORT OF 860720) CONTAMINANTS THROUGH SATURATED FRACTURED GEOLOG-NUREG/CR-5274 NUMERICAL SIMULATION OF NATURAL CIRCU- IC MEDIA.

LATION PHENOMENA IN A PWR DURING TMLB' TRANSIENTS MECHANICAL ENGINEERING BRANCH (870413 880716)

PRIOR TO CORE DAMAGE. NUREG/CR-5356: IMPROVED MODEL FOR PREDICTING JR DIVISION OF ENGINEERING (POST 870413) CURVES FROM CHARPY DAT t Phase i Final Report NUREG/CR4082 V07; DEGRADED PIPING PROGRAM FHASE DIVISION OF REGULATORY APPLICATIONS (POST 870413) li. Seventh Program Report October 1987 + January 1989. NUREG/CR-3469 V04: OCCUPATIONAL DOSE REDUCTION AT NU.

NUREG/CR-4082 V0B. DEGRADED PIPING PROGRAM - PHASE CLEAR POWER PLANTS: ANNOTATED BIBLIOGRAPHY OF SE-II. Summary Of Technical Results And Their Significance To Leak- LECTED READINGS IN RADIATION PROTECTION AND ALARA Before-Breal And IrvService Flaw Acceptance Criter?a. March 1984 - NUREG/CR-4214 Pil R1: HEALTH EFFECTS MODELS FOR NUCLE.

January 1989. AR POWER PLANT ACCIDENT CONSEQUENCE ANALYSIS. Low NUREG/CR-4219 V05 N2: HEAVY-SECTION STEEL TECHNOLOGY LET Radiation.Part 11. Scientihc Bases For Health Effects Models PROGRAM Semiannual Progress Report For Apnt September 1980. NUREG/CR 4409 V03: DATA BASE ON DOSE REDUCTION RE-NUREG/CR4759: DEMONSTRATION OF A PERFORMANCE AS- SEARCH PROJECTS FOR NUCLEAR POWER PLANTS.

SESSMENT METHODOLOGY FOR HIGH-LEVEL RADIOACTIVE NUREG/CR-5261: SAFETY EVALUATION OF MHTGR LICENSING WASTE DISPOSAL IN BASALT FORMATIONS. BASIS ACCIDENT SCENARIOS NUREG/CR4929: THE EFFECTS OF VAR 1ABLE AMPLITUDE LOAD- NUREG/CR-5344. REPLACEMENT ENERGY COST ANALYSIS PACK-ING ON A 533-B STEEL IN HIGH-TEMPERATURE AIR AND REAO. AGE (RECAP) USER'S GUIDE.

TOR WATER ENVIRONMENTS NUREG/CR 5351: MODELS FOR PULMONARY LETHALITY AND NUREGICR-5087: STEAM GENERATOR GROUP PROJECT. Task 7 MORBtDITY AFTER 1RRADIATION FROM IfCERNAL AND EXTER-Final Report: Post-Service Baseline Eddy Cunent Examinaton NAL SOURCES.

NUREG/CR 5118: LEAK AND STRUCTURAL TEST OF PERSONNEL NUREG/CR-5353 INHALED (147)PM AND/OR TOTAL-BODY AIRLOCK FOR LWR CONTAINMENTS SUBJECTED TO PRES- GAMMA RADIATION EARLY MORTALITY AND MORBIDITY IN SURES AND TEMPERATURES BEYOND DESIGN LIMITS. RATS.

NUREGICR 5208 WARM PRESTRESS MODELING:COMPAR$0N NUREG/CR.5355: HTGR INGRESS ANALYSIS USING MINET.

OF MODELS AND EXPERIMENTAL PESULTS DIVISION OF SAF ETY ISSUE RESOLUTION (POST 880717)

NUREC/CIN 5216- POST-IRRADIATION FRACTURE TOUGHNESS NUREG/CR-5230: SHUTDOWN DECAY HEAT REMOVAL I CHARACTERIZATION OF FOUR LAB-MELT PLATES. ANALYSIS PLANT CASE STUDIES AND SPECIAL ISSUES Summary l NUREG/CR-5216 RO1; POST IRRADIATION FRACTURE TOUGH- Report.

NESS CHARACTERIZATION OF FOUR LAB-MELT PLATES. NUREG/CR-5281: VALUEllMPACT ANALYSES OF ACCIDENT PRE-NUREG/CR-5222: STATIC LOAD CYCLE TESTING OF A LOW- VENTIVE AND MITIGATIVE OPTIONS FOR SPENT FUEL POOLS. ,

ASPECT-RATIO SIX-INCH WALL TRG-TYPE STRUCTURE TRG-4-6 NUREGICR-5332

SUMMARY

AND ANALYSIS OF PUBLIC COM- l (1.0. 025). MENTS ON NUREG-1317 REGULATORY OPTIONS FOR NUCLE. i NUREG/CR 5235. THERMODYNAMICS OF TECHNETIUM RELATED AR PLANT LICENSE RENEWAL Final Report TO NUCLEAR WASTE DISPOSAL Solutahties of Tc(IV) Oxides Ahd NUREG/CR 5347: RECOMMENDATIONS FOR RESOLUTION OF The Electrode Potential Of The Tc(Vil)/Tct!V)-Oxide 'souple. PUBLIC COMMENTS ON USI A 40, " SEISMIC DESIGN CRITERIA" 41

42 NRC C:ntr:ct Sp nsor Index OlVISION OF SYSTEMS RESEARCH (POST 880717) NUREG/CR-5264: CLOSEOUT OF IE BULLETIN 79-NUREG/CR 4550 V02: ANALYSIS OF CORE DAMAGE FREQUENCY 03A: LONGITUDINAL WELD DEFECTS IN ASME SA 312 TYPE 304 FROM INTERNAL EVENTS: EXPERT JUDGMENT STAINLESS STEEL PIPE.

ELICITATION.Part 1: Expert Panel Results. Part 2: Feoject Staff Re- NUREG/CR-529t CLOSEOUT OF IE BULLETIN 80-09 HYDRAMO-suits. TOR ACTUATOR DEFICIENCIES.

NUREG/CR 4675: IN. PILE OBSERVATION OF FUEL AND CLAD RE- NUREG/CR-5293: CLOSEOUT OF IE BULLETIN 86-01: MINIMUM LOCATION DURING LMFBR CORE DISRUPTIVE ACCIDENTS. FLOW LOGIC PROBLEMS THAT COULD DISABLE RESIDUAL NUREG/CR-4721: THE USE OF FIBER OPTICS FOR REMOTE TEM- HEAT REMOVAL PUMPS.

PERATURE MEASUREMENT IN FISSION PRODUCT RELEASE DIVISION OF ENGINEERING & SYSTEMS TECHNOLOGY (POST TESTS 870411)

NUREG/CR-4960 A

SUMMARY

OF HYDROGEN-AIR DETONATION NUREG/CR 3950 V05: FUEL PERFORMANCE ANNUAL REPORT EXPERIMENTS. FOR 1987.

NUREG/CR-4994: CORE CONCRETE INTERACTIONS USING NUREG/CR-5244: EVALUATION OF NON-RADIOLOGICAL WATER MOLTEN STEEL WITH ZlRCONIUM ON A BASALTIC CHEMISTRY AT POWER REACTORS.

BASEMAT:THE SURC 4 EXPERIMENT. NUREG/CR-5349. STEAM GENERATOR OPERATING NUREG/CR-5163 POWER BURST FACILfTY (PBF) SEVERE FUEL EXPERIENCE. UPDATE FOR 1987-1988.

DAMAGE TEST 14 TEST RESULTS REPORT. DIVISION OF REACTOR INSPECTION & SAFEGUARDS (POST NUREG/CR-5193: MELPROG-PWR/ MOD 1: A TWO-DIMENSIONAL. 870411)

MECHANISTIC CODE FOR ANALYSIS OF REACTOR CORE MELT NUREG/CR-5227 S01: FITNESS FOR DUTY IN THE NUCLEAR PROGRESSION AND VESSEL ATTACK UNDER SEVERE ACCI- POWER INDL,,TRY:A REVIEW OF TECHNICAL ISSUES.

DENT CONDITIONS. NUREG/CR4246; A METHODOLOGY TO ASSIST IN CONTINGENCY NUREG/CR-5252: AEROSOL SAMPLING AND TRANSPORT EFF1- PLANNING FOR PROTECTION OF NUCLEAR POWER PLANTS CIENCY CALCULATION (ASTEC) AND APPUCATION TO SURT- AGAINST LANC VEHICLE BOMBS.

SEY/DCH AEROSOL SAMPLING SYSTEM. Code Version 10: Code DIVISION OF RADIATION PROTECTION & EMERGENCY PREPARED-Description And User's Manual. NESS (POST 870411)

NUREG/CR-5275: FLAME FACILITY.The Effect Of Obstacles And NUREG/CR-5187: PRA APPLICATIONS PROGRAM FOR INSPEC-Transverse Venting On Flarne Acceleration And Transition To Deto- TION AT CALVERT CLIFFS UNIT 1 NUCLEAR POWER PLANT.

nation For Hydrogen-Air Mixtures At Large Scale. NUREG/CR-5319: RISK SENSITIVITY TO HUMAN ERROR.

NUREG/CR-5371: DEVELOPl/ENT AND USE OF RISKED-BASED IN-EDO - OFFICE OF NUCLEAR REACTOR REGULATION (POST 4/28/80) SPECTION GulDES.

DIVISION OF OPERATIONAL EVENTS ASSESSMENT (POST B70411) DIVISION OF LICENSEE PERFORMANCE & OUAUTY EVALUATION NUREG/CR-4934: CLOSEOUT OF IE BULLETIN 83 06.Nonconforrrung (POST 870411)

Materials Supplied By Tube Une Corporation Facilities At Long Island NUREG/CR-5228 VO1: TECHNIOUES FOR PREPARING FLOW-City. New Yoric Houston Texas: And Carol Strearn. Illinois. CHART FORMAT EMERGENCY OPERATING NUREG/CR 5283. CIOSEOUT OF IE BULLETIN 79 03:LONGITUDI- PROCEDURES. Background (Sections 1.0-9.0).

NAL WELD DEFECTS IN ASME SA-312 TYPE 304 STAINLESS NUREG/CR-5220 V02; TECHNIQUES FOR PREPARING F LOW-i STEEL PIPE SPOOLS MANUFACTURED BY YOUNGSTOWN CHART-FORMAT EMERGENCY OPERATING PROCEDURES.Usy's l WELDING AND ENGINEERING COMPANY. Manual (Sections 10.0-17.0).

l 1

Centrcctor Index i

This index lists, in alphabetical order, the contractors that prepared the NUREG/CR reports 1

. listed in this compilation. Listed below each contractor are the NUREG/CR numbers and l titles of their reports. If further information is needed, refer to the main citation by the NUREG/CR number.

i l

ANALYSIS & MEASUREMENT SERVICES CORP. NUREG/CR 3469 V04: OCCUPATIONAL DOSE REDUCTION AT NU-NUREG/CR-5383: EFFECT OF AGING ON RESPONSE TIME OF NU- CLEAR POWER PLANTS. ANNOTATED BIBLIOGRAPHY OF SELECT.

CLEAR PLANT PRESSt'RE SENSORS.. ED READINGS IN RADIATION PROTECTION AND ALARA.

NUREG/CR-4409 V03: DATA BASE ON DOSE REDUCTION RE-ARGONNE NATIONAL LABORATORY SEARCH PROJECTS FOR NUCLEAR POWER PLANTS.

NUREG/CR-5274: NUMERICAL SIMULATION OF NATURAL CIRCULA- NUREG/CR 5244: EVALUATION OF NON-RADIOLOGICAL WATER TION PHENOMENA IN A PWR DURING TMLB' TRANSIENTS PRIOR CHEMISTRY AT POWER REACTORS.

TO CORE DAMAGE. NUREG/CR-5261: SAFETY EVALUATION OF MHTGR LICENSING NUREG/CR-5344: REPLACEMENT ENERGY COST ANALYSl$ PACK- BASIS ACCIDENT SCENARIOS.

AGE (RECAP). USER'S GUIDE. NUREG/CR-5268: AGING STUDY OF BOILING WATER REACTOR RE- I SIDUAL HEAT REMOVAL SYSTEM.

ARK ANSAS. UNIV. OF, F AYETTEVILLE, AR NUREG/CR-5279: SULFATE ATTACK RESISTANCE AND GAMMA-IR-NUREG/CR-5375: POST PENNSYLVANIAN REACTIVATION ALONG RADIATION RESISTANCE OF SOME PORTLAND CEMENT BASED THE WASHITA VALLEY FAULT. SOUTHERN OKLAHOMA. MORTARS.

NUREG/CR-528t: VALUE/ IMPACT ANALYSES OF ACCIDENT PRE.

EATTELLE HUMAN AFFAIRS RESEARCH CENTERS VENTIVE AND MITlGATIVE OPTIONS FOR SPENT FUEL POOLS.

NUREG/CR-5227 S01: FITNESS FOR DUTY IN THE NUCLEAR POWER NUREG/CR-5319: RISK SENSITIVITY TO HUMAN ERROR.

INDUSTRY.A REVIEW OF TECHNICAL ISSUES. NUREG/CR 5347; RECOMMENDATIONS FOR RESOLUTION OF NUREG/CR-5228 V01: TECHNIOUES FOR PREPARING FLOWCHART

• PUBLIC COMMENTS ON USl A-40 " SEISMIC DESIGN CRITERIA."

FORMAT EMERGENCY OPERATING PROCEDURES Background NUREGICR-5355: HTGR INGRESS ANALYSIS USING MINET.

(Sections 1.0-9.0L NUREG/CR-5371: DEVELOPMENT AND USE OF RISKED-BASED IN-NUREG/CR-5228 V02: TECHNIQUES FOR PREPARING FLOWCHART. SPECTION GULDES.

FORMAT EMERGENCY OPERATING PROCEDURES User's Manual (Sections 10.0-t 7.0). CBI RESEARCH CORP.

NUREG/CR 5118: LEAK AND STRUCTURAL TEST OF PERSONNEL SATTELLE MEMORIAL INSTITUTE, COLUMBUS LABORATORIES AIRLOCK FOR LWR CONTAINMENTS SUBJECTED TO PRESSURES NUREG/CR-4082 V07: DEGRADED PIPING PROGRAM - PHASE AND TEMPERATURES BEYOND DESIGN LIMITS.

II. Seventh Program Report. October 1987 January 1989.

NUREG/CR 4082 V08: DEGRADED PIPING PROGRAM - PHASE DAVID W. TAYLOR NAVAL RESEARCH & DEVELOPMENT CENTER ll. Summary Of Technical Results And Their Significance To Leak- NUREG/CR-5238 DEVELOPMENT OF AN ENGINEERING DEFINITION Before-Break And in-Service Flaw Acceptance Cnteria, March 1984

• OF THE EXTENT OF J SINGULARITY CONTROLLED CRACK NU / 081: TACTICAL EXERCISE PLANNING HANDBOOK.

NUREG/CR-5172: TACTICAL TRAINING REFERENCE MANUAL. EG&G IDAHO, INC, (SUBS. OF EG&G, INC.)

BATTELLE MEMORIAL INSTITUTE, PACIFIC NORTHWEST NUREG/CR-5163 POWER BURST FACILITY (PBF) SEVERE FUEL LABORATORY DAMAGE TEST 14 TEST RESULTS REPORT.

'G/CR-3950 V05: FUEL PERFORMANCE ANNUAL REPORT FOR FR ACTURESEARCH, INC.

NI G/CR 5087: STEAM GENERATOR GROUP PROJECT. Task 7 4921 M W M & W M M M M N W Final Report Post Service Baseline Eddy Current Examination. ON A 533-B STEEL W HWEWAM M M UN NUREG/CR 5167: PRA APPLICATIONS PROGRAM FOR INSPECTION WATER ENVIRONMENTS.

NUREG/ R 22 0 FT HARVARD SCHOOL OF PUBLIC HEALTH, BOSTON, MA SF DUT N E L' EAR POWER NUREG/CP 0098 V01: PROCEEDINGS OF THE 20TH DOE /NRC NU-INDUSTRY:A REVIEW OF TECHNICAL ISSUES l NUREG/CR-5228 V01: TECHNIQUES FOR PREPARING FLOWCHART- CLEAR AIR CLEANING CONFERENCE. Sections 1 5. Held in Boston, F E GENCY OPERATING PRC"EDURES. Background NUREYCP- 8 Vo I E INGS OF THE 20TH DOE /NRC NU.

NUREC/CR-5228 V02: TECHNIOUES FOR PREPARING FLOWCHART. CLEAR AIR CLEANING CONFERENCE. Sessions 6 15. held in FORMAT EMERGENCY OPERATING PROCEDURES. User's Manual Boston, Massachusetts. August 22 25,1988.

(Sections 100170 HYDROGE OGIC, INC NUREG/CR-5351; M DELS FOR PULMONARY LETHALITY AND MOR-B TY AFTER IRRADIATION FROM INTERNAL AND EXTERNAL MODEL IN TWO DIMENSIONS. Version 5 0 With Hysteresis And NUREG/CR-5353: INHALED (147)PM AND/OR TOTAL-BODY GAMMA Chained Decay Transport Documentation And User's Guide.

RADIATION.EARLY MORTALITY AND MORBIDITY IN RATS,

^

AG N DEG DATI ASSESSME T Ph NUR G/CR 3'954 VO EC INIOUES FOR DETERMINING PROBABIL.

ITIES OF EVENTS AND PROCESSES AFFECTING THE PERFORM-EROOKHAVEN NATIONAL LABORATORY ANCE OF GEOLOGIC REPOSITORIES Literature Review.

NUREG/CP 0097 V01: PROCEEDINGS OF THE SIXTEENTH WATER REACTOR SAFETY INFORMATION MEETING. IN-SITU, INC.

NUREG/CP 0097 V02: PROCEEDINGS OF THE SIXTEENTH WATER NUREG/CR-5391. FLOW OF GROUNDWATER AND TRANSPORT OF ,

FIEACTOR SAFETY INFORMATION MEETING CONTAMINANTS THROUGH SATURATED FRACTURED GEOLOGIC  !

NUREGICP 0097 V03: PROCEEDINGS OF THE SIXTEENTH WATER MEDIA.

REACTOR SAFETY INFORMATION MEETING NUREG/CP-0097 V04. PROCEEDINGS OF THE SIXTEENTH WATER INHALATION TOXICOLOGY RESEARCH INSTITUTE REACTOR SAFETY INFORMATION MEETING. NUREG/CR-535*: MODELS FOR PULMONARY LETHALITY AND MOR-NUREG/CP 0097 V05: PROCEEDINGS OF THE SIXTEENTH WATER BIDITY AFTER 1RRADIATION FROM INTERNAL AND EXTERNAL REACTOR SAFETY INFORMATION MEETING SOURCES.  :

43

44 C:ntr:ct:r Ind:x ITASCA CONSULTING G3OUP, INC. NUREG/CR 4219 VOS N2: HEAVY SECTION STEEL TECHNOLOGY NUREG/CR-5336. SENSITIVITY OF THE STABUTY OF A WASTE EM. PROGRAM Semiannual Progress Report For Apol. September 1988 PLACEMENT DRIFT TO VARIATION IN ASSUMED ROCK JOINT PA. NUREG/CR-4721 THE USE OF FIBER OPTICS FOR REMOTE TEM-RAMETERS IN WELDED TUFF. PERATURE MEASUREMENT IN FISSION PRODUCT RELEASE NUREG/CR 5389 ANALYSIS OF ALTERNATIVE WASTE ISOLATION TESTS.

CONCEPTS. NUREG/CR-5235' THERMODYNAMICS OF TECHNETIUM RELATED TO NUCLEAR WASTE DISPOSAL Solubehties of Tc(IV) Oxides And JAPAN ATOMIC ENERGY RESEARCH INSTITUTE The Electrode Potential Of The Tc(VIO/Tc(IV)-Oxide Couple.

NUREG/CR-5252: AEROSOL SAMPLING AND TRANSPORT EFFICIEN- NURE G/CR-5330: HIGH-TEMPERATURE CRACK ARREST BEHAvlOR CY CALCULATION (ASTEC) AND APPLICATION TO SURTSEY/DCH IN 152 MM THICK SEN WIDE PLATES OF OUENCHED AND TEM-AEROSOL SAMPLING SYSTEM. Code Version 1.0: Code Desenption PERED A 533 GRADE B CLASS 1 STEEL.

And Uber's Manual- NUREG/CR 5350- M:SSION SURVEY FOR THE PRESSURE VESSEL KTECH CORP.

A I O NUREG/CR 4994. CORE-CONCRETE INTERACTIONS USING MOLTEN P ARAMETER. INC.

STEEL WITH ZlRCONIUM ON A BASALTIC BASEMAT:THE SURC 4 NUREG/CR-4934. CLOSEOUT OF IE BULLETIN 83 06 Nonconforming EXPERIMENT-Matenals Supplied By Tube-Line Corporation Facilities At Long Island LOS ALAMOS NATIONAL LABORATORY City. New Yoric Houston, Texas. And Carol Stream. Illinois.

NUREG/CR 5222: STATIC LOAD CYCLE TESTING OF A LOW-ASPECT. NUREG/CR 5283. CLOSEOUT OF IE BULLETIN 79-03 LONGITUD:NAL WELD DEFECTS IN ASME SA-312 TYPE 304 STAINLESS STEEL RATIO SIX lNCH WALL TRG-TYPE STRUCTURE TAG-4-6 (10. 0 25)

NUREG/CR 5237 USE OF LINEAR REDUCED-STIFFNESS ANALYTI- PIPE SPOOLS MANUFACTURED BY YOUNGSTOWN WELDING AND CLM ELS TO FRED CT SEISMIC RESPONSE OF DAMAGED NURE 5 84 CLOS OU'T OF IE BULLETIN 79-03A LONGITUD!NAL WELD DEFECTS IN ASME SA-312 TYPE 304 STAINLESS STEEL LOVELACE DIOMED & ENVIRONMENTAL RESEARCH INSTITUTE PIPE.

NUREG/CR-5351: MODELS FOR PULMONARY LETHALITY AND MOR. NUREG/CR 5291 CLOSEOUT OF IE BULLETIN 80-09 HYDRAMOTOR BIDITY AFTER 1RRADIATION FROM INTERNAL AND EXTERNAL ACTUATOR DEFICIENCIES.

SOURCES NUREG/CR-5293: CLOSEOUT OF IE BULLETIN 06 01. MINIMUM FLOW NUREG/CR-6353: INHALED (147)PM AND/OR TOTAL-BODY GAMMA LOGIC PROBLEMS THAT COULD DISABLE RESIDUAL HEAT RE-RADIATION EARLY MORTALITY AND MORBIDITY IN RATS. MOVAL PUMPS.

MATERIALS ENGINEERING ASSOCIATES,INC. SANDIA NATIONAL LABORATORIES NUREG/CR-4929. THE EFFECTS OF VARIABLE AMPLITUDE LOADING NUREG/CR 3964 V01: TECHNIOUES FOR DETERMINING PROBABIL- l ON A 533-B STEEL IN HIGH-TEMPERATURE AIR AND REACTOR ITIES OF EVENTS AND PROCESSES AFFECTING THE PERFORM-  ;

WATER E ENVIRONMENTS ANCE OF GEOLOGIC REPOSITORIES Uterature Review l NUREG/CR-6208: WARM PRESTRESS MODELING: COMPARISON OF NUREG/CR-4214 Pil RI: HEALTH EFFECTS MODELS FOR NUCLEAR MODELS AND EXPL.% MENTAL RESULTS POWER PLANT ACCIDENT CONSEQUENCE ANALYSIS. Low LET NUREG/CR-5216: POST IRRADIATION FRACTURE TOUGHNESS Radiation Part II: Scientihc Bases For Health Effects Models.

CHARACTERIZATION OF FOUR LAB-MELT PLATES NUREG/CR-4550 V02. ANALYSIS OF CORE DAMAGE FREQUENCY NUREG/CR-5216 RO1: POST-IRRADIATION FRACTURE TOUGHNESS FROM INTERNAL EVENTS. EXPERT JUDGMENT ELICITATION Part CHARACTERIZATION OF FOUR LAB-MELT PLATES NUREG/CR-5357: AN EXPLORATORY STUDY OF ELEMENT INTERAC-N /CR 57 IN IL SER T FF AND CLAD RELO.

TIONS AND COMPOSITION DEPENDENCIES IN RADIATION SENSI-TIVITY DEVELOPMENT. Final Report. CATION DURING LMFBR CORE DISRUPTIVE ACCIDENTS NUREG/CR 4759 DEMONSTRATION OF A PERFORMANCE ASSESS-MCGILL UNIV., MONTREAL, CANADA MENT METHODOLOGY FOR HIGH-LEVEL RADIOACTIVE WASTE NUREG/CR-4961: A

SUMMARY

OF HYDROGEN-AIR DETONATION EX. DISPOSAL IN BASALT FORMATIONS.

PER!MENTS. NUREG/CR 4961: A

SUMMARY

OF HYDROGEN. AIR DETONATION EX.

PERIMENTS.

MITRE CORP. NUREG/CR-4994: CORECONCRETE INTERACTIONS USING MOLTEN NUREG/CR-5332.

SUMMARY

AND ANALYSIS OF PUBLIC COMMENTS STEEL WITH ZlRCONIUM ON A BASALTIC BASEMAT.THE SURC 4 ON NUREG 1317; REGULATORY OPTIONS FOR NUCLEAR PLANT EXPE RIMENT.

LICENSE RENEWAL. Final Report. NUREG/CR-5089: NUMERICAL MODELING OF GROUND-WAT ER FLOW SYSTEMS IN THE VICINITY OF THE REFERENCE REPOSI-MODELING & COMPUTER SERVICES TORY LOCATION.HANFORD. WASHINGTON NUREG/CR-5356. IMPROVED MODEL FOR PREDICTING J-R CURVES NUREG/CR-5118: LEAK AND STRUCTURAL TEST OF PERSONNEL FROM CHARPY DATA Phase i Final Report. AIRLOCK FOR LWR CONTAINMENTS SUBJECTED TO PRESSURES AND TEMPERATURES BEYOND DESIGN LIMITS.

NATIONAL INSTITUTE OF STANDARDS & TECHNOLOGY (FORMERLY NUREG/CR-5193- MELPROG PWR/ MOD 1: A TWO-DIMENSIONAL, NATIONAL BUREAU OF MECHANISTIC CODE FOR ANALYSIS OF PEACTOR CORE MELT NUREG/CR-5330: HIGH-TEMPERATURE CRACK ARREST BEHAVIOR PROGRESSION AND VESSEL ATTACK UNDER SEVERE ACCIDENT IN 152 MM-THICK SEN WIDE PLATES OF OUENCHED AND TEM- CONDITIONS.

PERED A 533 GRADE D CLASS 1 STEEL- NUREG/CR-5230. SHUTDOWN DECAY HEAT REMOVAL NEW MEKlCO, UNIV OF, ALBUQUERQUE, NM ^ ^ ^ ^ "

NUREG/CR-5222. STATIC LOAD CYCLE TESTING OF A LOW-ASPECT- NURE CR-5252 AEROSOL SAMPLING AND TRANSPORT EFFICIEN-RATIO SIX-INCH WALL TRG-TYPE STRUCTURE TRG-4-6 (1.0,0.25)

CY CALCULATION (ASTEC) AND APPLICATION TO SURTSEY/DCH OAK RIDGE ASSOCIATED UNIVS. AEROSOL SAMPLING SYSTEM Code Version 1.0. Code Desenption NUREG/CP-0101: PROCEEDINGS OF THE WORKSHOP ON RULES And User's Manual.

FOR EXEMPTION FROM REGULATORY CC JROL. NUREG/CR 5275 FLAME FACILITY.The Effect Of Obstacles And Trans-verse Venting On Flame Acceleration And Transition To Detonation For

+ 06 K RIDGE NATIONAL LABORATORY Hydrogen Air Mmtures At Large Scale.

NUREG/CP 0098 V03 PROCEEDINGS OF THE 20TH DOE /NRC NU-CLEAR AIR CLEANING CONFERENCE.An Inder To The 1st Through SCIENCE APPLICATIONS INTERNATIONAL CORP. (FORMERLY th AEC/ERDA/ DOE And DOE /NRC Nuclear Air Cleaning Confer. S E APP R Cg ,6 ETHbDOLOGY TO ASSIST IN CONTINGENCY NUREG/CR-2000 V00 N2. LICENSEE EVENT REPORT (L ER) PLANNING FOR PROTECTION OF NUCLEAR POWER PLANTS COMPILATION For Month Of February 1989 AGAINST LAND VEHICLE BOMBS NUREG/CR-2000 V0B N3- LICENSEE EVENT REPORT (LER) NUREG/CR-5349 STEAM GENERATOR OPERATING COMPILATION For Month Of March 1989 EXPERIENCE. UPDATE FOR 1987 1968 NUREG/CR-2000 V0B N4. LICENSEE EVENT REPORT (LER) I COMPIL ATION For Month Of Apal 1989. SOUTH CAROLINA, UNIV. OF, COLUMBIA, SC  !

NUREG/CR-2000 V08 NS- LICENSEE EVENT REPORT (L ER) NURE G/CR-5257 FURTHER NEOTECTONIC STUDIES OF EARTH-COMPILATION For Month Of May 1989 OUAKE ZONES IN THE E ASTERN UNITED STATES i

l

C:ntr:ct:r Ind;x 45 U.S.HAVAL ACADEMY, ANNAPOLIS,MD NUREG/GR-5299 DEVELOPMENT OF AN ENGINEERING DEFINfTION OF THE EXTENT OF J SINGULARITY CONTROLLED CRACK

. GROWTH.

i l

internation:I Organizati:n Ind:x This index lists, in alphabetical order, the countries and performing organizations that pre-pared the NUREG/lA reports listed in this compilation. Listed below each country and per-forming organization are the NUREG/lA numbers and titles of their reports. If further infor-mation is needed, refer to the main citation by the NUREG/lA number.

- There were no NUREG/lA reports for this quarter.

l l

47 j l

Licano d Fccility Indsx This index lists the facilities that were the subject of NRC staff or contractor reports. The facility names are arranged in alphabetical order. They are preceded by their Docket number  ;

cnd followed by the report number. If further information is needed, refer to the main citation l l by the NUREG number. i li 50 424 AMn W Vogtle Nuclear Plant Urut 1, Georgs NUREG-1359 ERR W352 Limenck Generatng Stabon, Urut 1. PMadelpNa NUREG 0991 SOS Power Co Electre Co.

S 425 An W vogtle Nuclear Plant, Unit 2, Georpa NUREG 1359 ERR 50-353 Limerck Generating Stahon. Urut 2, Ptviadelphe NUREGJa91 S07 Power CD Electre Co.

50 260 Browns Feny Naciew Power Statm Um 2, NUREG-1232 VD3 W353 Limerch Gene +abng Statm Urut 2, PNadegtua NUREG 0991 SOB Tennessee valley Auhon Elecinc Co.  ;

50 317 Calvert Cliffs Nuclear Power Plant Urut 1, NUREG/CR-5*87 M443 Seabrook Nuclear Staten, Unit 1, Pubhc Sennce NUREG 0896 S08 i Bartmore Gas & Electre Co of New Hampstw j R445 Comanche Peak Steam Electre Staton, Urut 1, N'JREG4797 S21 W443 Seabrook Nuclear Staton, Unit 1. Pubhc Sennce NUREG 1331 1 Texas Utshes Electr Co of New Hampstm

$0 446 Carranche Peak Steam Electrc Staton, Umt 2, NUREG4797 S21 Shoreham Nuclear Power Statm Long Island NUREG 0420 S10

% 322 Tesas utsties E!ec8 Lehng Co 322 m ear Poww Staba W lsW HUREM357 2061 M meal Corp., West Chcago, IL, S01 v01

[ 52 in e n ,'u t 1 s[  % 383 Wa'i Generating Statm Umt 4, Loaraana NUREG 1360 Power & Light Co.

E m Co.

l 49 l

N:iC FORu 335 - U,S. NUCLE AR REGUL ATOR Y COMMISSION 1. RE PORT NUMBE R L% 1102, "

o Icam NumtYrs r5 vY' 3201.2202 BIBLIOGRAPHIC DATA SHEET

. an,mtrua,om or,ir,a anorus NUREG-0304 2.mLE AND SUBM LE Vol .14, No. 2 Regulatory and Technical Reports (Abstract Index Journal) y 3,,,,,, ,,, ,,3n,o ous s ,. u .~

Compilation for Second Quarter 1989 August l 1989 April - June 4 ,,N OR GRANT Nuvet R

5. AUTHORISI 6. TYPE OF REPOHT Reference

7. PE HIOD COVE R E D rsarr aswe Dere6r April - June 1989

8. PE R F ORMING ORGANIZ AT TON - N AME AND ADDR ESS to* Nac. orovoor onvssoon. orrece ar negron, v.s Nuther Resuserary comvroowon. end mentonn eaaren os contractor. orove .

numa and mentong addresL} l Division of Freedom of Information and Publications Services Office qf Administration U.S.' Nuclear Regulatory Commission Washington, DC 20555

9. SFONSORING ORG ANf 2AT SON - N AM E AND ADDR ESS ut NRc. tvor ~some es above . tr ontractor. c orovrete v, Rc Dwhoon. coroce or Rey,on. v s. Nucker negaterore commowan.

and meitmo address 1

'Same as 8, above.

10. SUPPLEME NTARY NOTES 1L ABSTRACT (200 worm or ess!

This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors; proceedings of conferences 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, international organization, and licensed facility.

12. KE Y WORDS/DE SCH:PT ORS IL est worm or phress's ther weti ess,vr researrirers in smering ene report.1 13 AV Aet AbaLil v bi A It Mirv i Unlimited I compilation muu~, n mus ,<. nu,,

abstract index g ,,,, %,

Unclassified ir..,~,,,,,,,

Unclassified Ib. NUMBER OF FAGE S

\b VHICE l

NRC FORM 33t (2 891 t

l

guct3AR sige LA Y Miesg3 NT e aN E WASHINGTON, D.C. 20005 usN?4 Z murr no. w C penal 77 is uno a E

E Main Citations 1 1ANIACt9tigo $

and Abstracts 120555139531 hy"h! PUBLICATIONS SVCS /*

,TPS PDR-NUREG [

DC 20555 **

h[skNGTON Secondary Report i Number index i Personal Author index.

E!

o!

C b

Subject index oj o

Ddl NRC Originating Organization p

• @l Index (Staff Reports) i3 wg]!

E t-Mml 55i eOl 8

NRC Originating Organization Index (International Agreements) dyl el w

NRC Contractor SponsorIndex

@f zi l

. Contractor Index international Organization y index g e.

W G'

8 Licensed Facility Index

_ _ _ _ _ -