ML20080G511

Regulatory and Technical Reports (Abstract Index Journal). Compilation for Third Quarter 1994,July-September

ML20080G511
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Issue date:	12/31/1994
From:	NRC OFFICE OF ADMINISTRATION (ADM)
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References
NUREG-0304, NUREG-0304-V19-N03, NUREG-304, NUREG-304-V19-N3, NUDOCS 9502080121
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i NUREG-0304 Vol.19, No. 3 Regulatory and Technical Reports (Abstract Index Journal)

Compilation for Third Quarter 1994 July - September U.S. Nuclear Regulatory Commission Office of Administration a aro j

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r AVAILABILITY NOTICE Availability of Reference Materials Cited in NRC Publications Most documents cited in NRC publications will be available from one of the following sources:

1.

The NRC Public Document Room 2120 L Street, NW., Lower Level, Washington, DC 20555-0001 2.

The Superintendent of Documents, U.S. Government Printing Office, P. O. Box 37082, Washington, DC 20402-9328 3.

The National Technical information Service, Springfield, VA 22161-0002 Although the listing that follows represents the majority of documents cited in NRC publica-tions, it is not intended to be exhaustive.

Referenced documents available for inspection and copying for a fee from the NRC Public Document Room include NRC correspondence and intemal NRC memoranda NRC bulletins, circulars, information notices, inspection and investigation notices; licensee event reports; vendor repons and correspondence; Commission papers; and applicant and licensee docu-ments and correspondence.

The following documents in the NUREG series are available for purchase from the Govemment Printing Office: formal NRC staff and contractor reports NRC-sponsored conference pro-ceedings, international agreement reports, grantee repons, and NRC booklets and bro-chures. Also evailable are regulatory guides, NRC regulations in the Code of Federal Regula-tions, and Nuclear Regulatory Commission istuances.

Documents available from the National Technical Information Service include NUREG-series reports and technical reports prepared by other Federet agencies and reports prepared by the

)

Atomic Energy Commission, forerunner agency to the Nuclear Regulatory Commission.

Documents available from public and special technical libraries include all open literature items, such as books, joumal articles, and transactions. Federal Register notices, Federal and State legislation, and congressional reports can usually be obtained from these libraries.

Documents such as theses, dissertations, foreign reports and translations, and non-NRC con-forence proceedings are available for purchans from the organization sponsoring the publica-tion cited.

Single copies of NRC draft reports are available free, to the extent of supply, upon written request to the Office of Administration, Distribution and Mail Services Section, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, Copies of industry codes and standards used in a substantive manner in the NRC regulatory process are maintained at the NRC Library, Two White Flint North 11545 Rockville Pike, Rock-ville, MD 20852-2738, for use by the public. Codes and standards are usually copyrighted and may be purchased from the originating organization or, if they are American National Standards, f.om the American National Standards institute,1430 Broadway, New York, NY 10018-3308.

A year's subscription of this report consists of four quarterly issues.

NUREG-0304 Vol.19, No. 3 Regulatory and Technical Reports (Abstract Index Journal)

Compilation for Third Quarter 1994 July - September Date Published: December 1994 Regulatory Publications Branch Division of Freedom ofInformation and Publications Services Omcc of Administration U.S. Nuclear Regulatory Commission W:shington, DC 20555-0001 i

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Index Tab j

Main Citations and Abstracts......................................................... 1

• Staff Reports i

• Conference Proceedings

• Contractor Reports

• International ?.greement Reports l

Secondary Report Number index........................................................ 2 Personal Author inde x................................................................ 3 S u bject Inde x..................................................................... 4 NRC Originating Organization index (Staff Reports)........................................ 5 NRC Originating Organizstion index (International Agreements).............................. 6 NRC Contract Sponsor index (Contractor Reports)......................................... 7 Contractor index................................................................... 8 In'ernational Organization index........................................................ 9 Licensed Facility index................................................................... 10 I

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PREFACE This compilation consists of bibliographic data and abstracts fe,r the formal regulatory and technical reports issued by the U.S. Nuclear Regulatory Commission (NRC) Etaff and its contractors. It is NRC's intention to publish this compilation quarterly and to cumulate it an.1ually. Your comments will be ap-preciated. Please send them to:

Technical Publications Section Publications Branch Division of 7reedom of Information and Publications Services T-6 E7 U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 The main citations and abstracts in this compilation are listed in NUREG number order: NUREG-XXXX, NUREG/CP-XXXX, NUREG/CR-XXXX, and NUREG/lA-XXXX. These precede the following indexes:

Secondary Report Number index Personal Author Index Subject index 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 each iridex.

The bibliographic elements of the main citations are the following:

Staff Report NUREG-0808: MARK ll 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, (8) the microfiche address (for internal NRC use).

Conference Report NUREG/CP-0017: EXECUTIVE SEMINAR ON THE FUTURE ROLE OF RISK ASSESSMENT AND RELIABILITY ENf31NEERING 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 accession number, (8) the report number of the originating organization, (9) the microfiche address (for NRC internal use).

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

Sandia Laboratories. May 1981.100 pp. 8107010449. S AND80-0929. 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 numtv, (8) the report number of the originating organization (if given), and (9) the microfiche address (for NRC internal use).

v

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

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

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

ADD

- addendum APP

- appendix DRFT - draft ERR

- errata N - number R - revision S - supplement V - vo' urn 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 Service, Springfield, Virginia 22161. To purchase documents from the GPO, send a check or money order, payable to the Superintendent of Documents, to the following address:

Superintendent of Documents U.S. Government Printing Office Post Office Box 37082 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. aport 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.

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

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

1 vi

Main Citations and Abstracts i

The report listings in this compilation are arranged by report number, where NUREG XXXX is

[

cn NRC staff-onginated report, NUREG/CP-XXXX is an NRC-sponsored conference report, NUREG/CR-XXXX is an NRC contractor 9repared report, and NUREG/lA-XXXX is an inter-n tional agreement reaort The bibliographic information (see Preface for details) is followed b a brief abstract of t1is report.

f NUREG-0090 V17 N01: REPORT TO CONGRESS ON ABNOR-cause of the pubic interest, the MiscPflaneous category also in-MAL OCCURRENCES. January-March 1994.

• Offee for Analy-cludes events reported involving source material, byproduct ma-sis & Evaluation of Operatonal Data Director. August 1994.

tenal, and natural uranium, whch are exempt from safeguards 33pp. 9409090134. 80817:073.

requirements. Intornaten in the event descriptions was ob-Section 208 of the Energy Reorganizaten Act of 1974 identi-tained from offic%i NRC sources.

fees an abnormal occurrence (AO) as an unscheduled incident or event that the Nuclear Regulatory Commission determines to NUREG-0540 V16 N05: TITLE LIST OF DOCUMENTS MADE i

b2 signifcant from the standpoint of pubhc health or safety and PUBLICLY AVAILABLE.May 1-31, 1994.

• Division of Freedom requires a quarterty report of such events to be made to Crn-of Information & Publications Services (Post 940714). July 1994.

gress. This report provides a descnpton of those events *,nat 325pp. 9407250168. 80327:001, h;ve been determined to be abnormal occurrences dunng the This document is a monthly pubication containing desenp-penod of January 1 through March 31, 1994. This report ad.

tions of informaton received and generated by the U.S. Nuclear dresses seven AOs at NRC-icensed freilities. One involved in.

Regulatory Commisson (NRC). This informaton includes (1) operable main steam isolaton valves at a boiling water reactor, docketed matenal associated with civilian nuclear power plants four involved medcal brachytherapy misadministrations, one in-and other uses of radioactive matenals, and (2) nondocketed volved a medcal teletherapy misadministration, and one in.

matenal received and generated by NRC pertinent to its role as 1

volved four lost reference sources. One AO that was reported a regulatory agency. The following indexes are included: Per-l by an Agreement State rs also discussed; the informaton is cur-sonal Author Corporate Source, Report Number, and Cross rInt as of Apnl 25,1994. This event involved a therapeutic re-Reference of Enclosures to Pnncipal Documents.

diopharmaceutcal misadministration. The report also contains NUREG-0711: HUMAN FACTORS ENGINEERING PROGRAM updates on seven abnormal occurrences previously rep 1rted by NRC licensees and one abnormal occurrence previously report-REVIEW MODEL. O'HARAaJ.M.; HIGGINS.J.C.; STUBLER,W.F/'.

et al. Brookhaven National Laboratory. July 1994. 97pp ed by an Agreement State Icensee. For the penod January 1 to a'te to a t T s of the u at Regulatory Commission is performing ed ar u apeu c isa strat o e ou y reported as an "Other Event of interest" is included.

nuclea, power plant design certsfcaten reviews based or a design process plan that desenbes the human factors engineer.

NUREG-0304 V19 N01: REGULATORY AND TECHNICAL RE-ing (HFE) program elements that are necessary and sufficient to PORTS (ABSTRACT INDEX JOURNAL). Compilation For First develop an acceptable detailed design specifcation and an ac-Quarter 1994, January March.

• Drvision of Freedom of informa-ceptable implemented design. There are two pnncipal reasons ton & Pubicatons Servces (890206-940714). June 1994. 48pp.

for this approach. First, the initial design certification applea.

9407250316. 80328:300.

tons submitted for stcff review did not include detailed design This joumal includes all formal reports in the NUREG series informaton. Second, since human performance hterature and in-prepared by the NRC staff and contractors, proceedings of co'>

dustry experiences have shown that many signifcant human ferences and workshops, grants, ar.d intemational agreement factors issues arise early in the design process, review of the reports. The entnes in this compilation are indexed for access design process activities and results is important to the evalua-by title and abstract, secondary report number, personal author.

tion of an overall design. However, current regulatons and guid-l subject. NRC organization for staff and intemational agree-ance documents do not address the entena for design process ments contractor, internatsonal organizaton, and licensed facili-review. Therefore, the HFE Program Review Model (HFE :PRM) ty was developed as a basis for performing design certifcatcm re.

NUREG-0304 V19 N02: REGULATORY AND TECHNICAL RE-V'ews that include design process evaluations as well as Feview PORTS (ABSTRACT INDEX JOURNAL). Compilaton For of the final design. A central tenet of the HFE PRM is that the Second Quarter 1994, April-June.

• Division of Freedom of Infor.

HFE aspects of the plant should be develored, designed, and maton & Pubicatons Services (Post 940714). September 1994.

evaluated on the basis of a structured top-down system analysis 46pp. 9410130043. 81264:001.

using accepted HFE pnnciples. The HFE PRM consists of ten i

See NUREG-0304,'. #9,N01 abstract.

component elements. Each element is divided into four sec.

i tons: Background, Objective, Appleant Submittels, and Review NUREG 0525 V02 R02: SAFEGUARDS

SUMMARY

EVENT LIST Cntena. This report describes the development of the HFE PRM (SSEL). January 1,

1990 Through December 31, 1993.

and gives & detailed descripton of each HFE review element.

FADDEN.M.; YARDUMIAN.J. Operatons Branch. July 1994.

12 pp. 9410130051. 81264:047.

NUREG-0750 V37: NUCLEAR REGULATORY COMMISSION The Safeguards Summary Event List provides bnel summa-ISSUANCES. Opinions And Decisions Of The Nuclear Regula-ties of hundreds of safeguards-related events involving nuclear tory Commission With Selected Orders. January-June 1993.

• Di-matenal or facilities regulated by the U.S. Nuclear Regulatory vision of Freedom of informaton & Pubicatons Services Corvsson. Events are described under the categones: Bomb-(890206-94071d). June 1994. 572pp. 9409010177. 80723:001.

rr % mtruson, Missing / Allegedly Stolen, Transportation-relat-Lega! issuances of the Commission, the Atomic Safety and Li-ed 's menng/ Vandalism, Arson, Firearms-related, Radologeal censing Board Panel, the Administrative Law Judges, and NRC Sabotap, Non-radiologeal Sabotage, and Miscellaneous. Be-Program Offces are presented.

1

~ ~ _ _ _ _

2 Main Citations and Abstracts NUREG-0750 V38: NUCLEAR REGULATORY COMMISSION NUREG-0940 V13N01P01: ENFORCEMENT ACTIONS: SIGNIFl-ISSUANCES. Opinions And Decisions Of The Nuclear Regula-CANT ACTIONS RESOLVED REACTOR LICENSEES.Quarterty tory Commisson With Selected Orders. July-December 1993.

• Progress Report. January-March 1994.

• Ofc of Enforcement 1

Divson of Freedom of informaton & Pubications Services (Post 870413). June 1994. 210pp. 9407260127. 80345:099.

(890206-940714). June 1994. 436pp. 94C9010179. 80724:208.

This compilation summanzes signifcant enforcement actions See NUREG-0750,V37 abstract.

that have been resolved during one quarterly period (January -

March 1994) and includes copies of letters, Notees, and Orders NUREG-0750 V39101: INDEXES TO NUCLEAR REGULATORY sent b N ear Wa% hnissa 2 mam h@

COMMISSION ISSUANCES. January -March 1994.

• Division of ees with respect to these enforcement actons. It is antcipated Freedom of information & Publicatons Servces (Post 940714).

that the informaton in this pubicaten will be widely dissemine July 1994. 41pp. 9408150162. 80537.291.

Digests and indexes for issuances of the Commission, the ed to managers and employees engaged in activities licensed Atomic Safety and Licensing Board Panel, the Administrative by the NRC, so that actions can be taken to improve safety by avodng future volatons sMar to hse hnW in Ws pus Law Judges, the Directors' Decisons, and the Denials of Peti-caton.

tons for Rulemaking are presented.

NUREG-0750 V39102: INDEXES TO NUCLEAR REGULATORY NUREG-0940 V13N01P02: ENFORCEMENT ACTIONS: SIGNIF1-COMMISSION ISSUANOES. January June 1994.

• Division of CANT ACTIONS RESOLVED MEDICAL LICENSEESQuarterly Freedom of Information & Pubicatons Seryces (Post 940714).

Progress Report. January-March 1994.

• Ofc of Enforcement September 1994. 68pp. 9410130089. 81266:182.

(Post 870413). June 1994.145pp. 9407260176. 80346:001.

See NUREG-0750,V39,01 abstract See NUREG-0940,V13,N01,P01 abstract.

NUREG-0750 V39 N05: NUCLEAR REGULATORY COMMISSION NUREG-0940 V13N01P03: ENFORCEMENT ACTIONS: SIGNIFI-ISSUANCES FOR MAY 1994.Pages 249-284

• Division of CANT ACTIONS RESOLVED INDUSTRIAL Freedom of informaton & Pubications Servces (Post 940714).

LICENSEES.Ouarterly Progress Report January-March 1994.

• July 1994. 42pp. 9407250180. 80327.324.

Ofc of Enforcement (Post 870413). June 1994. 118pp.

See NUREG-0750,V37 abstract.

9407260183. 80346.146 j

NUREG-0750 V39 N06: NUCLEAR REGULATORY COMMISSION ISSUANCES FOR JUNE 1994.Pages 285-390.

• Divison of NUREG-0940 V13N02P01: ENFORCEMENT ACTIONS: SIGNIFI-Freedom of Informaton & Publicatons Seryces (Post 940714).

CANT ACTIONS RESOLVED REACTOR LICENSEES.Ouarterly August 1994.112pp. 9408250025. 80660:001.

Progreas Report, April June 1994.

• Ofc of Enforcement (Post See NUREG-0750,V37 abstract.

870413). August 1994. 200pp. 9409270322. 8'046:108.

This compilaton summanzes signifcant enforcement actons NUREG-0750 V40 N01: NUCLEAR REGULATORY COMMISSION that have been resolved dunng one quarterly penod (April -

e ISSUANCES FOR JULY 1994.Pages 1-41.

• Division of Free-June 1994) and includes copes of letters, Notees, and Orders l

dom of informaton & Pubications Servces (Post 940714). Sep-sent by the Nucler flegulatory Commission to reactor Icens-tember 1994. 48pp. 9410130023. 81262:307.

ees with respect tr Ose enforcement actons. It is antcipated See NUREG-0750,V37 abstract.

that the information in this pubication will be widely disseminat-NUREG-0637 V14 N01: NRC TLD DIRECT RADIATION MONi-ed to managers and employees engaged in activites leensed TORING NETWORK. Progress Report. January-March 1994.

by the NRC, so that actons can be taken to improve safety by STRUCKMEYER.R. Region 1 (Post 820201). June 1994. 231pp.

avoiding future volations similar to those desenbed in this puble-9407250293. 80329 001.

cation.

This report provides the status and results of the NRC Ther-J NUREG-0940 V13N02P02: ENFORCEMENT ACTIONS: SIGNIF1-moluminescant posimeter (TLD) Direct Radiation Monitonng i

CANT ACTIONS RESOLVED MEDICAL LICENSEES.Ouarterly Network Il preserHS the radiation levels measured in the vicinity Progress Report.Apni-June 1994.

• Ofc of Enforcement (Post of NRC licensed facilities throughout the country for the first 870413). August 1994. 354pp. 9410130039 81263 001.

guarter of 1994.

See NUREG-0940,V13.N02,P01 abstract.

NUREIG-0837 V14 N02: NRC TLD DIRECT RAC'ATION MONI-TCRING NETWCFtK. Progress Report. Apnt-June 1994.

NUREG-0940 V13N02P03: ENFORCEMENT ACTIONS. SIGNIFi-STNUCKMEYERR Regon 1 (Post 820201). August 1994.

CANT ACTIONS RESOLVED INDUSTRIAL 231pp 9409260062. 81042:112.

LICENSEES Quarterly Progress Report Apnt-June 1994.

• Ofc of Enforcement (Post 870413). August 1994. 177pp.

This teport provides the status and results of the NRC Ther, moluminescent Dosimeter (TLD) Direct Radiation Mor tonng 9410070244. 81230 001.

Network. It presents the radiaton levels measured in the vicinity See NUREG-0940,V13.N02.P01 abstract.

j of NRC Icensed facilities throughout the country for the second NUREG-1145 V10: U.S. NUCLEAR REGULATORY COMMISSION quarter of 1994.

j 1993 ANNUAL REPORT.

• Offee of Administraton, Director NUREG-0936 V13 N01: NRC REGULATORY AGENDA.Ouarterly (Post 940714). September 1994. 306pp. 9410130036.

Report, January-March 1994.

• Division of Freedom of fntorma-81262:001.

tion & Pubications Servces (890206-940714) June 1994. 58pp.

This report covers the major activities, events, decisons, and 9407250298. 80328.235.

planning that took place dunng Fiscal Year 1993 within the U S.

i The NRC Regulatory Agenda is a compilation of all rules on Nuclear Aegulatory Commission (NRC) or involving the NRC.

which the NRC has recently completed action, or has proposed NUREG-1242 V03 PT01: NRC REVIEW OF ELECTRIC POWER action, or is considenng action, and aff petitons for rulemaking RESEARCH INSTITUTE'S ADVANCED LIGHT WATER REAC-which have been received by the Commission and are pending TOR UTILITY REQUIREMENTS DOCUMENTS. Passive Plant disposition by the Commisson. The Regulatory Agenda is up.

Designs. Chapter 1. Project Number 669

• Associate Director for dated and issued each quarter.

Advanced Reactors & Lcense Renewal (Post 910918). August I

NUEG-0936 V13 NO2: NRC REGULATORY AGENDA Ouarterly 1994. 450pp. 9410060313. 81222 001.

Report. April-June 1994

• Division of Freedom of informaton &

The staff of the U S. Nuclear Regulatory Commisson has pre-Publicatons Services (Post 940714) August 1994 68pp.

pared Volume 3 (Parts 1 and 2) of a safety evaluaton report 9410060320. 81223 167.

(SER). "NRC Review of Electnc Power Research Institute's Ad-See NUREG-0936 V13.N01 abstract vanced Light Water Reactor Utility Requirements - Passive Plant 1

l

3 Main Citations and Abstracts f

Designs," to document the results of its review of the Electrc in the case of progress reports of multi-faceted programs), but Power Research institute's " Advanced Light Water Reactor Util-is listed under only one tope. Therefore, in searching for reports sty Requirements Document." This SER gives the results of the on a specific topic, other related topic areas should be checked staff's review of Volume lif of the Requirements Document for miso. The previous volume to this report covers the penod 1965 passive plant designs, which consists of 13 chapters and con-1990.

tains utility design requerernents for nuclear power plants for whch passive features will be used in their design (approxi-NUREG-1460 R01: GUIDE TO NRC REPORTING AND RECORD-mately 600 megawatts-electr:).

KEEPING REQUIREMENTS. Compiled From Requirements in Title 10 Of The U S. Code Of Fejeral Regulations As Codified j

NUREG-1242 V03 PT02: NRt; REVIEW OF ELECTRIC POWER On December 31,1993. COLLINS,M.; SHELTON.B. Office of in-RESEARCH INSTITUTE'S ADVANCED LIGHT WATER REAC-formaton Resources Management Post 890205L Juh M TOR UTILITY REQUIREMENTS DOCUMENT.Passve Plant Designs. Chapters 2-13. Project Number 669.

• Associate Direc-254kp940 e9 n i n

es the first two sectons the report-ing and recordkeeping requirements appleable to U.S. Nuclear Augu t 642 9 1007024 230 0 See NUREG 1242,V03 P01 abstract.

Regulatory Commission (NRC) Icensees and applicants and to members of the pubic. It includes those requirements codified MUREG-1307 R04:

REPORT ON WASTE BURIAL en Title 10 of the Code of Federal Regulatons. Chapter I, on

[

CHARGES Escalation Of Decommissoning Waste Disposal December 31,1993. It also includes, sn a separate section, any Costs At Low-Level Waste Bunal Facilities.

• Division of Regula-of those requirements that were superseded or discontinued be-tory Applicatons (Post 870413). June 1994. 54pp. C #8250008.

tween January 1992 and December 1993. Finally, the appendix 80658:306-hsts mailing and delivery addresses for NRC Headquarters and One of the requirements placed upon nuclear power reactor Regional Offces mentioned in the compilation.

1:censees by the U.S. Nuclear Regulatory Commission (NRC) #s for the Icensees to penodcally adjust the estimate of the cost NUREG 1462 V01: FINAL SAFETY EVALUATION REPORT RE-of decommissoning their plants, in dollars of the current year, LATED TO THE CERTIFICATION OF THE SYSTEM 80+

Es part of the process to provide reasonable assurance that DESIGN Chapters 1 14. Docket No. 52 002. (Asea Brown Edequate funds for decommissioning will be available when Boven-Combustion Engineenng)

• Associate Director for Ad-needed This report, whch is scheduled to be revised penudi-vanced Reactors & Lcense Renewal (Post 910918). hgust csily, contains the development of a formuft for escalating de-1994. 583pp. 9409200306 80953:001.

I commissioning cost estimates that is acceptable to the NRC, This final safety evaluation report (FSER) documents the and contains values for the escalaton of radcactive waste techncal review of the System 80+ standard design by the bunal costs, by site and by year. The heensees may use the for-U S Nuclear Regulatory Commission (NRC) staff. The applca-mula, the coeffecients, and the bunal escalaton from this report tion for the System 80+ design was submitted by Combuston in their escalaton analyses, or they rnay use an escalation rate Engineenng. Inc., now Asea Brown Boven-Combuston Engi-Et least equal to the esca:ation appf oach presented herein.

neenng (ABB-CE) as an appleaton for desigr, approval and NUREG-1415 V06 N02: OFFICE OF THE INSPECTOR subsequent design certifcaton pursuant to 10 CFR 5 52.45, GENERAL. Semiannual Report. October 1, 1993 - March 31, System 804 is a pressurized water reactor with a rated power i

1994. NORTON.L; BARCHl.T.; HUBER.D. Office of the inspec.

of 3914 megawatts thermal (MWt) and a design power of 3992 tor General (Post 890417). Apnf 1994. 46pp 9409200338.

MWt at which accidents are analyzed. Many itstures of the 80954:277.

System 80+ are similar to those of ABB-CE s System 80 The inspector General is required by the IG Act of 1978, as d*S'gn from whch it evolved. Unique features of the System j

tmended, to prepare a semiannual report to Congress which 00 + design include: a large sphercal, steel containment; an in-l summanzes program activities. The 6 month reporting pennd containment refueling water storage tank; a reactor cavity flood-ends March 31 and September 30th. The IG's report is submit.

Ing system, hydrogen ignitors, and a safety depressunzaton ted to the Chairman of tne NRC not later than April 30 and Oc.

system for severe accident mitigation; a combuston gas turbine tober 31, respectively. The Chairman comments on the IG's for an alternate aC source; and an advanced digitally based report and prepares his own. as required by the Act, and sub.

control room. On the basis of its evaluaton and independent mits both reports to Congress no later than November 30 and analyses, the NRC staff concludes that ABB-CE's appleation May 31, respectively.

for design certifcation meets the requirements of Subpart B of 10 CFR Part $2 that are appleable and technically relevant to t

NUREG-1426 V02: COMPILATION OF REPORTS FROM RE-the System 80 + standard design.

SEARCH SUPPORTED BY THE MATERIALS ENGINEERIN(.i BRANCH. DIVISION OF ENGINEERING 1991 1993. HISER,A.L NUREG-1462 V02: FINAL SAFETY EVALUATION REPORT RE-Divison of Engineenng (Post 870413) June 1994. 39pp-LATED TO THE CERTIFICATION OF THE SYSTEM 80+

9408030136. 80425:196.

DESIGN. Chapters 15-22 And Appendees. Docket No. 52-Since 1%5, the Matenals Engineenng Branch, Divison of En-002.(Asea Brown Boveri-Combuston Engineenng)

• Associate gineenng. of the Nuclear Regulatory Commission's Office of Nu-Director for Advanced Reactors & License Renewal (Post clear Regulatory Research, and its predecessors dating back to 910918). August 1994. 557pp. 9409200314. 80956:001.

l the Atomic Energy Commisson (AEC), has sponsored research See NUREG-1462,V01 abstract.

programs concerning the integnty of the primary system pres-sure boundary of light water reactors. The components of con-NUREG-1470 V03: FINANCIAL STATEMENT FOR FISCAL YEAR cern en these research programs have included the reactor 1993.

• Office of the Controller (Post 890205). August 1994.

pressure vessel (RPV), steam generators, and the piping These 110pp. 9409090026. 80816 001.

research programs have covered a broad range of topics, in-The Chief Financial Offcers Act of 1990 requires the NRC cluding fracture mechanics analysis and expenmental work fu.

Chief Financial Offcer to prepare and submit an annual financial RPV ard p9 sng appleatens, inspecton rnethod development statement to the Director of the Offee of Management and and qualifcaton, and evaluation of irradiation effects to RPV Budget (OMB). The OMB has replaced the requirement for the steels This report provides as complete a listing as practcal of CFO's Annual Report with the annual financial statement. The formal techncal reports submitted to the NRC by the investiga-annual financial statement was previously included in the Chief tors working on these research programs. This listing includes Financial Offcer's Annual Report. This report is the third annual topical, final and progress reports, and is segmented by topic report for the NRC and includes an overview of the NRC, the grea in many cases a report will cover several topics (such as audited pnncipal financial statements and audit reports for fiscal

1 i

1 4

Main Citations and Abstracts l

year 1993, and supplemental financial and management infor-the effect of their ac*cns on the environment. To futfill NRC's matort responsibilities under NEPA, the Commission is prepanng this NUREG-1478: NON-POWER REACTOR OPERATOR LICENSING GEIS whch analyzes alternative courses of acton and the EXAMINER STANDARDS.

• Division of Reactor Controls &

costs and impacts associated with those alternatwes. In prepar-Human Factors (Post 921004). June 1994. 200pp 9408030122.

ing the GEIS, the following approach was taken: (1) a hsting 80424:001.

was developed of regulatory alternatives for estabhshing rado-Tho Non-Power Reactor Operator Licensing Examiner Stand-logcal cnteria for decommissioning; (2) for each attemative, a ards provide polcy and guidance to NRC examiners and estab-detailed analysis and companson of incremental impacts, both hsh the procedures and practces for examining heensees and radiological and nonradological, to workers, members of the apphcants for NRC operator Icenses pursuant to Part 55 of pubic, and the environment, and costs, was performed; and (3)

Title 10 of the Code of Federal Regulations (10 CFR Part 55).

based on the analysis of impacts and costs, preliminary recom-They are intended to assist NRC examiners and facihty hcens.

mendatons were provided. Recommendatens contained in the ees to better understand the examination process and to GEIS include those related to the definiton of decommissioning, ensure the equitable and consistent administraton of examina.

the scope of rulemaking, the radologcal cnteria, rebtnctons on tions to all appleants. These standards are not a substitute for use, citizen participaton, use of the GEIS in site specife cases, the operator Icensing regulatons and are subject to revision or and minimi7ation of contaminaten.

other intemal operator examinaton licensing polcy changes. As NUREG-1496 V2 DRF FC: GENERIC ENVIRONMENTAL IMPACT appropnate, these standards will be revised penodcally to ac-STATEMENT IN SUPPORT OF RULEMAKING ON RADIOLOG-commodate comments and reflect new informaton or experi-ICAL CRITERIA FOR DECOMMISSIONING OF NRC-LICENSED NUCLEAR FACILITIES.Appendees. Draft Report For Comment.

NUREG-1484 V01: FINAL ENVIRONMENTAL IMPACT STATE-

• Divison of Regulatory Appleations (Post 870413). August MENT FOR THE CONSTRUCTION AND OPERATION OF CLAl-1994. 600pp. 9408300006. 80698:001.

BORNE ENRICHMENT CENTER, HOMER, LOUIStANA. Docket See NUREG-1496,V01.DRF FC abstract.

J No. 70-3070. Louisiana Energy Services, L.P. Environmental impact Statement ZEITOUN.A. Science Apphcations interna-NUREG-1500: WORKING DRAFT REGULATORY GUIDE ON RE-

~

tonal Corp. (formerty Science Appications, inc). August 1994.

LEASE CRITERIA FOR DECOMMISSIONING: NRC STAFF'S i

DRAFT FOR COMMENT.

DAILY.M.C.;

HUFFERT A.M.:

390pp. 9409070096. 80790:001,.

CARDILE.F.; et al. Divison of Regulatory Apphcations (Post This Final Environmental Impact Statement (FEIS) was pre-pared by the Nuclear Regulatory Commisson in accordance 870413). August 1994.168pp. 9490130081. 81264:171.

with NRC regulatson 10 CFR Part 51, whch implements the Na-The Nuclear Regulatory Commission's (NRC) regulatons i'i tonal Environmental Pohey Act (NEPA), to assess the potential 10 CFR Part 20 are being amended to include radiologeal ente-environmental impacts of the constructon and operation of a na for decommissioning of lands and structures at nuclear facili-proposed gaseous centnfuge ennchment facihty to be built in ties. it' CFR Part 20 Subpart E estabhshes entena for the re-Claibome Pansh, LA. The proposed facihty will have a produc-mediat w of contaminated sites or facihties that will allow their ton capacity of about 866 tonnes annually of up to 5 percent release for future use with or with-out restrctons. The entena i

enrched UF(6), using a proven centnfuge technology. Included include a Total Effective Dose Equivalent (TEDE)

.1st of 15 in the assessment are construction, both normal operations and mrem / year (0.15 mSv/y) that should not be exceeded by an av-potential accidents (intemal and external events), and the even-erage individual among those who could potentially receive the

[

tual decontaminaton and decommissoning of the site. In order greatest exposure from any residual activity within a facihty or to help assure that releases from the operaton of the facility on a site. The enteria also require a heensee to reduce any re-and potential impacts on the pubic are as low as reasonably sidual radioactivity to as-low-as-reasonably achievable (ALARA) achievable, an environmental monitoring program was devel-levels. This staff draft guide desenbes acceptable procedures oped to detect signifcant changes in the background levels of for determining the predicted dose level (PDL) from any residual uranium around the site. Other issues addressed include the radioactivity at the site, it describes the base features of the purpose and need for the facility, the attematwes to the pro-calculatonal models and the associated default assumptons posed action, the site selection process, environmental justce, and parameter values the NRC staff would find acceptable in and tails dispositen. The NRC concludes that the facihty can be Calculating PDLs. Appendces A, B, and C provide numercal constructed and operated with small and acceptable impacts on values that can be used to estimate the dose from residual ra-the pubhc and the environment. The FEIS supports Icensing.

dioactsvity remaining at a site. Since 10 CFR Part 20, Subpart E NUREG-1484 V02: FINAL ENVIRONMENTAL IMPACT STATE-introduces several new concepts, definitens and discussions MENT FOR THE CONSTRUCTION AND OPERATION OF CLAl-are included in a regulatory positen concepts secton of the BORNE ENRICHMENT CENTER, HOMER, LOUISlANA. Docket guide to assist hcensees in understanding some of the philoso-No. 70 3070 Louisiana Energy Services, L.P. Comments And phy undertying the rule.

Responses. ZEITOUN.A. Scence Apphcations intemational NUREG-1501 DRFT: BACKGROUND AS A RESIDUAL RAD 10AC.

r Corp. (formerly Science Apphcations, Inc.). August 1994.480pp.

TlVITY CRITERION FOR DECOMMISSIONING. Appendix A To 9409070125. 80792:001.

The Draft Generic Environmental impact Statement in Support Volume 2 contains the comments received on the Draft EIS Of Rulemaking On Radologeal Critena For Decommissioning

]

and the responses to those comments.

Of NRC... HUFFERT,A.M.; MECK.R.A. Division of Regulatory J

NUREG-1496 V1 DRF FC: GENERIC ENVIRONMENTAL IMPACT Apphcatons (Post 870413). MILLER,K.M. Energy, Dept.of, Envi-STATEMENT IN SUPPORT OF RULEMAKING ON RADIOLOG-ronmental Measurements Laboratory. August 1994, 100pp.

ICAL CRITERIA FOR DECOMMISSIONING OF NRC-LICENSED 9408250012. 80659-001.

NUCLEAR FACILITIES. Main Report. Draft Report For Comment.

This report was originally pubhshed as an appendix to the

• Divison of Regulatory Apphcatons (Post 870413). August oraft U.S. Nuclear Regulatory Commission (NRC) document en-1994.170pp. 9408300003. 80700.001.

titled, "Generc Environmental impact Statement in Support of The acton being considered in this Draft Generic Environ-Flulemaking on Radiological Cnteria for Decommissioning of mental impact Statement (GEIS) is an amerdment to the Nucle-NRC-Licensed Nuclear Facilities." Because of the great interest er Regulatory Commisson's (NRO regulatons in 10 CFR Part in this report by members of the public, citizen and environmen-20 to include radiological entena for decommissioning of lands tal organizatons, academicians, licensees, and regulators, the and structures at nuclear facshties. Under the Natonal Environ-NRC staff is pubhshing this report separately, so that it can be mental Pokey Act (NEPA), all Federal agencies must consider readily available to a diverse audience. This report was created l

's~-"'

=

5 Main Citations and Abstracts to assist both the NRC staff and interested memuers of the The 1994 Symposium on Valve and Pump Testing, jointly pubic in evaluating background radiaton (background) as a de-sponsored by the Board of Nuclear Codes and Standards of the comNssoning cntenon, by serving as a pnmer on background Amercan Society of Mechanical Er'gineers and by the Nuclear and providing informaton on the existing applications of back-Regulatory Commission, provides a forum for the discussion of I

ground in regulatory entena and standards. This report also de-current programs and methods for inservce testing and motor.

]

cusses some of the methods available to measure and dista-operated valve testing at nuclear power plants. The symposium guish between the very low radiation levels associated voth also provdes an opportunit/ to discuss the need to improve background and man-made sources of radiaton. Two approtich-that testing in order to help ensure the reliable performance of es are considered for applying background as a decommission-pumps and valves. The participation of industry representatives, eng cntenon; these are the use of background dose rates and regulators, and consultants results in the discussion of a broad background radionucide concentrations. This report concludes spectrum of ideas and perspectives regarding the improvement that the temporal and spatial vanability of background produces of inservice testing of pumps and valves at nuclear power a wde rar'ge of doses to United States residents, which pre-plants.

vents the application of background dose rates as a decommis-NUREG/CP-0137 V02: PROCEEDINGS OF THE THIRD NRC/

sioning cnlerion. Instead, this report recommends that local ASME SYMPOSIUM ON VALVE AND PUMP TESTING Held At

'ackground radonocide concentratons serve as a benchmark The Hyatt Regency Motel, Washington.DC. July 18--21, for decommissioning cntena, while taking into account the con-cept of reducing resdual radioactivity to a level as low as is rea-1994.Sesson 3A -Session 48.

• EG&G Idaho, Inc. July 1994.

sonably achievable.

387pp. 9408030114. EGG-2742. 80424:197, See NUREG/CP-0137,V01 abstract.

l NUREG 1502: ASSESSMENT OF DATABASES AND MODELING I

CAPABILITIES FOR THE CANDU 3 DESIGN. CARLSON D.E.;

NUREG/CR 3950 V09: FUEL PERFORMANCE REPORT FOR I

MEYER,R.O. Divison of Systems Research (Post 880717). July 1991. PAINTER,C.L.; ALVIS,J M.; BEYER.C E.; et al. Battelle l

1994.107pp. 9408220041. 80637:099.

Memorial Institute, Pacife Northwest Laboratory. August 1994.

As part of the research program associated with the prelim,.

123pp. 9409200326. PNL-5210. 80963:162.

nary review of the CANDU 3 deiJan, the NRC Offee of hciear This annual report, the fourteenth in a senes, provdes a bnef Regulatory Research (RES) has rampleted an assessment of description of fuel performance dunng 1991 in commercial nu-databases and modeling capabillt'es that might be needed to clear power plants and an indication of trends. Onef summanes support the CANDU 3 design To ensure full coverage of the of fuel operating expenence, fuel dessgn changes, fuel surveil-design, a detailed assessmen' methodology was developed by lance programs, hegtFbumup expenence, problem areas, and the RES staff and wa ;mplemented with help from research stems of general signifcance are provded. References to more projects at three national laboratones. This report integrates detailed information and related U.S. Nuclear Regulatory Com-l and summanzes the database and modeling assessments, in.

mission evaluations are included.

Cluding major contnbutions from these laboratones.

NUREG/CR-4219 V10 N1: HEAVY SECTION STEEL TECHNOL-NUREG-1503 V01: FINAL SAFETY EVALUATION REPORT RE-OGY PROGRAM. Semiannual Progress Report For October LATED TO THE CERTIFICATION OF THE ADVANCED BOIL-1992 - March 1993. PENNELL.W.E. Oak Rdge Natonal Labora-l lNG WATER REACTOR DESIGN Docket No. 52401.(General tory. September 1994.149pp. 9410120224. ORNL/TM-9593 Electre Nuclear Energy)

• Associate Director for Advanced Re-81254:001.

actors & License Renewal (Post 910918). July 1994. 876pp.

The Heavy-Secton Steel Technology (HSST) Program is con-l 9408260011.80681:001.

ducted for the Nuclear Regulatory Commission by Oak Rdge This Safety Evaluation Report (SER) documents the technical National Laboratory (ORNL). The program focus is on the de-review of the U.S. Advanced Boiling Water Reactor (ABWR) velopment and validation of technology for the assessment of standard design by the U.S. Nuclear Regulatory Commission fracture-preventon margins in commercial nuclear reactor pres-(NRC) staff. The application for the ABWR design was submit-sure vessels. The HSST Program is organized in 12 tasks: (1) ted by GE Nuclear Energy. The NRC staff concludes that, sub.

program management, (2) fracture methodology and analysis, lect to satisfactory resoluton of the confirmatory stems identified (3) material charactenzaten and properties. (4) special techncal in Section 1.8 of this SER, GE's applicaton for design certifca-assistance (5) fracture analysis computer programs, (6) cleav-ton meets the requirements of Subpart B of 10 CFR Part 52 age-crack initiation, (7) cladding evaluations, (8) pressunzed-that are applicable and technically relevant to the U.S. ABWR thermal shock technology, (9) analysis methods validation, (10) standard design.

fracture evaluations, (11) warm prest?essing, and (12) biaxial I a ng e s.

e pr ge tasks have Wn SMM to NUREG-1503 V02: FINAL SAFETY EVALUATION REPORT RE-pla e emphasis on the sesolution fracture issues with near-term LATED TO THE CERTIFICATION OF THE ADVANCED BOIL-

'*"*'"O ING WATER REACTOR DESIGN. Appendices. Docket No. 52-are drawn fr m ORN'L with subcontract support from universi-001.(General Electnc Nuclear Energy)

• Associate Director for Advanced Resctors & License Renewal (Post 910918) July tained with the sister Heavy-Secton Steel irradiation Program at l

1$84ju$kG 1503 V hs States and abroad. This report provdes an overview of principal 59 098 ORNL and with related research programs both in the United l

NUREG-1504: REVIEW CRITERIA FOR THE PHYSICAL FITNESS developments in each of the 12 program tasks from October TRAINING REQUIREMENTS IN 10 CFR PART 73. BROWN C.

1992 to March 1993.

• • "[9 8

NUREG/CR-4513 R01: ESTIMATION OF FRACTURE TOUGH-3 4 33 302 8 78 081 This document provides review cntens tha't will be used in re-US N DEM SMS N" DNA AGING IN LWR SYSTEMS. CHOPRA,0.K. Argonne Natonal viewing and approving revisod pnysical secunty plans submitted o

August 1994. 83pp. 9409230297. ANL-93/22.

by heensees which are required to meet the physical fitness re-Querements in 10 CFR Part 73.

This report presents a revision of the procedure and correla-NUREG/CP-0137 V01: PROCEEDINGS OF THE THIRD NRC/

tions presented earlier in NUREG/CR 4513. ANL-90/42 (June ASME SYMPOSIUM ON VALVE AND PUMP TESTING. Held At 1991) for predicting the change in mechanical properties of cast The Hyatt Regency Hotel, Washington.DC. July 18-21, stainless steel components due to thermal aging dunng service 1994.Sesson 1 A - Sessen 2C.

• EG&G Idaho. Inc. July 1994.

in light water reactors at 280 330 degrees C (535-625 degrees 570pp. 9408250007. EGG-2742. 80657:001.

F). The correlations presented in this report tre based on an

I 6

Main Citations and Abstracts expanded database and have been optimized with mechanical-the replacement energy costs associated with short-term shut.

property data on cast stainless steels aged up to =58,000 h at downs or deratings of one or more nuclear reactors. The calcu-290-350 degrees C (554-633 degrees F). The correlatons for lates are based on the setisonal, unit-specsfic cost estimates estimatsng the change in tensile stress, including the Ramberg/

for 1993-1996 prevously published in NRC Report NUREGiCri-Osgood parameters for strain hardening, are also desenbed.

4012, Vol. 3 (1992), for all 112 U S. reactors. Because the The fracture toughness J-R curve, tensile stress, and Charpy-RECAP program is menu-dnven, the user c 2n define specif6 impact energy of aged cast stainless steels are estimated from case studies in terms of such parameters as the units to be in-known matenal information. Mechanical properties of a specific cluded, the length and timing of the shutdown or d6ating cast stainless steel are estimated from the extent and kinetics pered, the unit capacity factors, and the reference year for re-of thermal embnttlement. Embnttlement of cast stainless steels port.ng cost results. In additon to simultaneous shutdown i

is charactenred in terms of room-temperature Charpy-impact cases, more comphcated situations, such as overlapping shut-energy. The extent or degree of thermal embnttlement at "satu-down penods or shutdowns that occur in different years, can be raton," i.e., the minimum impact energy that can be achieved examined through the use of a present-worth calculation opton.

for a matenal after long-term aging, is determined from the i

chemical compositen of the steel. Charpy-impact energy as a NUREG/CR 5535 V07:

RELAPS/ MOD 3 CODE functon of time and temperature of reactor service is estimated MANUAL.Summanes And Reviews Of Independent Code As-from the kinetics of thermal embrittlement, which are also deter-sessrnent Reports. SLOAN.S.M.; SCHULTZ,R R.; WILSON,G.E.

l noned from the chemical compositon. The initial impact unergy EG&G Idaho, Inc. June 1994.120pp. 9407260037. EGG 2596.

of the unaged steelis required for these estimations.

80344:207.

i NUREG/CR-4639 V5R4P2: NUCLEAR COMPUTERIZED Lt.

Summanes of RELAPS/ MOD 3 code assessments..a listing of BRARY FOR ASSESSING REACTOR RELIABILITY the assessrr ent matnx, and a chronology of the vanous ver-l (NUCLARR) Volume 5: Data Manual.Part 2: Human Error Proba.

sons of the code are given. Results from these code assess-bility (HEP) Data. REECE.W.J.: GILBERT,8 G.; RICHARDS.R E ments have been used to formulate a compilaten of some of EG8G Idaho, Irc September 1994. 453pp. 9410130115 EGG-the strengths and weaknesses of the code, These results are 2458. 81265-00t documented in the report Volume 7 was designed to be updat-This data manual contains a hard copy of the information in ed perodically and to include the results of the latest codt as-the Nuclear Cornputenred Library for Assessing Reactor Rell-sessments as they become available. Consequently the user of ability (NUCLARR) Verson 3.5 database, which is sf onsored by Volume 7 should check that the latest revison is available.

the U S Nuclear Regulatory Commission. NUCLAHR was de-signed as a tool for nsk analysis. Many of the nudear reactors NUREG/CR-5591 V02 N1: HEAVY SECTION STEEL IRRADIA.

in the U.S. and several outsde the U S. are represented in the TlON PROGRAM. Semiannual Progress Report For October NUCLARR database. NUCLARR includes both human error 1990 - March 1991 CORWIN,W.R. Oak Rdge National Labora-probability estimates for workers at the plants and hardware farl-tory. July 1994. 36pp. 9408180191. ORNL/TM-11508.

ure data for nuclear reactor equipment Aggregatons of these 80613 001.

data yield valuable reliability estimates for probabilistic nsk as-The pnmary goal of the Heavy-Section Steel irradiaton Pro-sessments and human reliability analyses. The data manual is gram is to provda a thorough, quantitative assessment of the organized to permit manual searches of the information of the effects of neutron irradiaton on the matenal behavior, and in computenzed verson is not available-particular the fracture toughness properties, of typical pressure NUREG/CR-4639 V5R4P3: NUCLEAR COMPUTERIZED Lt.

vessel steels as they relate to light water reactor pressure-BRARY FOR ASSESSING REACTOR REllABILITY vessel integnty. Effects of specimen size, matenal chemistry, (NUCLARR) Volume 5: Data ManualPart 3: Hardware Compo, product form and microstructure, irradiation fluence, flux, tem-nent Failure Data. REECE.W.J.; GILBERT.B G.; RICHARDS R E, perature and spectrum, and post-irradiation annealing are being EG&G Idaho, Inc. September 1994 186pp. 9410130099 EGG-examined on a wde range of fracture properties. Anafyses of 2458.81267.001, precleavage stable ductile teanng of high-copper welds 72W See NUREG/CR 4639,V05,R04,P02 abstract.

and 73W demonstrated that the size effects observed in the ansdon mgon am nd due to shantial hms in &cW NUREG/CR-5128 Rot: EVALUATION AND REFINEMENT OF teanng behavor. Drop-weight tests, Charpy impact tests, and LEAK-RATE ESTIMATION MODELS PAUL.D D, AHMAD.J4 chemical analyses of the Midland reactor low upper shelf welds SCOTT P.M.; et al. Battelle Memonal Institute, Calumbus Lab-were completed showing large vanations in bulk copper con-oratones June 1994. 97pp. 9407260077. BMI-21ri4. 80345 001.

tent. transition temperature, and upper-shelf energy. Atom probe Lsak-rate estimaton models are important ele nents in devel-field ion microscopy analyses revealed no evdence of fine openg a leak-before-break methodology in papirg integnty and copper precipitates or clusters en the unerradiated M diend welds safety analyses. Existing thermal-hydraulic and crack-opening-but a substantial depletion in the copper concentraton in the area models used in current leak rate estimations have been in-matnx corporated into a single computer code for leak-rate estimaton The code is called SOUIRT, which stands for Seepage Ouantif'-

NUREG/CR-5726: REVIEW OF THE DIABLO CANYON PROB-caton of Upsets in Reactor Tubes. The SOUIRT program has ABILISTIC RISK ASSESSMENT.

BOZOKI G E.;

been vaindated by companng its thermal-hydraulic predictions FITZPATRICK,R. Brookhaven Natonal Laboratory. BOHN.M P.;

with the limited expenmental data that have been published on et at. Sandia National Laboratones. August 1994. 500pp.

two-phase flow through slits and cracks, and by companng its 9409260069 BNL NUREG-52288. 81028.001.

crack-opening-area predictions with data from the Degraded This report details the review of the Diablo Canyon Probabilis.

Piping Program. In additon, leak. rate expenments were con.

• c Risk Assessment (DCPRA). The study was performed under ducted to obtain validation data for a circumferential fatigue contract from the Probabilistic Risk Analysis Branch, Office of crack in a carbon steel pipe girth weld Nuclear Reactor Research, USNRC by Brookhaven National NUREG/CR 5344 Rot: REPLACEMENT ENERGY COST ANALY-Laboratory The DCPRA is a full scope Level i effort and al-SIS PACKAGE (RECAP). USER'S GUIDE. VANKUtKEN.J C.,

though the review touched on all aspects of the PRA, the inter.

WILLING.D.L Argonne National Laboratory July 1994. 54pp.

nal events and seismic events received the vast majonty of the 9407250267. ANL/EES.TM 364 80328141.

review effort The report includes a number of independent sys-A microcomputer p.ogram called the Replacement Energy tems analyses, sensitivity studies. Importance analyses as well Cost Analysis Package (RECAP) has been developed to assist as conclusions on the adequacy of the DCPRA for use in the the U S Nuclear Regulatory Commiss on (NRC) in determining Diablo Canyon Long Term Seismic Program.

7 Main Citations and Abstracts NUREG/CR-5758 V04: FITNESS FOR DUTY IN THE NUCLEAR advanced systems This two-volume report provides the results POWER INDUSTRY. Annual Summary Of Program Performance of the project. Volume 1 descnbes the development of the Ad-Reports CY 1993 WESTRA.C.; FORSLUND C.; FIELD,1.; et al-vanced HSI Design Review Guideline (DRG) including (1) its Battelle Memonal Institute, Pacific Northwest Laboratory August theoretical and technical foundation, (2) a general model for the 1994.101pp. 9409230281. PNL-9985. 81006.184-review of advanced HSis, (3) guideline development in both This report summanzes the data from the semiannual reports hard-copy and computer-based versions, and (4) the tests and on Fitness for Duty programs submitted to the NRC by utilities evaluations performed to develop and validate the DRG.

for two reporting penods: January 1 through June 30,1993,and Volume 1 also includes a discusson of the gaps in available July 1 through December 31,1993. Dunng 1993, licensees re.

guidance and a methodology for addressing them Volume 2 ported that they had conducted 242,966 tests for the presence rovides the guideline to be used for advanced HSI review and of illegal drugs and alcohol. Of these tests, 1,512 (62%) were the procedures for their use' confirmed positive. Positive test results vaned by category of test and category of worker The majonty of positive test results NUREG/CR-5908 V02: ADVANCED HUMAN-SYSTEM INTEAl-(952) were obtained through pre access training Of tests con-FACE DESIGN REVIEW GUIDELINE. Evaluaton Procedures.

ducted on workers having access to the protected area there And Guidelines For Human Factors Engineenng Reviews.

were 341 positive tests from random testing and 163 pumtive O'HARA.J M ; BROWN,W.S Brookhaven National Laboratm tests from for-cause testing. Follow-up testing of workers wh BAKER,C C.; et al Affiliaton Not Assigned July 1994 PUpp i

had premously tested positive resulted in 56 positive tests For-9408250004. BNL-NUREG-52333. 80656:001*

cause inting resulted in the highest percentage of positive tests about 22 percent of for cause tests were positive This See NUREG/CR-5908,V01 abstract compares with a positive test rate of 104 percent of pre-access NUREG/CR-5965: MODELING FIELD SCALE UNSATURATED tests and 23 percent of random tests. Positive test rates also FLOW AND TRANSPORT PROCESSES. GELHAR.L.W.;

vaned by category of worker. When all types of tests are com-CELIA.M A ; MCLAUGLIN D Massachusetts Institute of Tech-bened (pre-access, random, for cause, and follow-up testing).

short-term contractor personnel had the highest positive test nology, Cambridge, MA. August 1994. 82pp. 9409230273.

rate at.97 percent. Licensee employees and long-term contrac.

81006 001.

tors had lower combined positive test rates ( 25% and.21 %, re.

A stochastic theory desenbing unsaturated flow and contame spectively) Of the substances tested, manguana was responsi-naton transport in naturally hemerogeneous soils has been en-ble for the highest percentage of positive test results (49 56%),

hanced by adopting a more realistic charactenzation of soil van-followed by cocaine (23 41%) and alenhol (22.65%)

ability The enhanced theory is used to predict field-scale effec-tive properties and vanances of tension and moisture content.

NUREG/CR 5861: CRACK-SPEED RELATIONS INFERRED Applications illustrate the important effects of small-scale het-FROM LARGE SINGLE-EDGE-NOTCHED SPECIMENS OF A 533 B STEEL. SCHWARTZ,C W. Oak Ridge National Laborato-erogene@ on largescaW anisotg, and hystecsjs and demon-ry-July 1994 32pp 9408180237. ORNLSUB79 77789.

strate the feasibit:S! M ;,T.uiating two-dimensionai flow systems 80595 312.

at time and space scales of interest in radioactrve waste dispos-A relatonship between instantaneous crack-tip velocity, a dy.

al investigations. Numencal algonthms for predicting idt se&

namic stress intensity factor,K(!), and temperature T for A 533 B unsaturated flow and contaminant transport have been im-steel is estimated using dynamic crack position vs time data proved by requinng them to respect fundamental physical pnnci-measured in a senes of very large-scale crack-arrest tests. The pies such as mass conservaton These algonthms are able to corresponding dynamic stress intensity vs time history and the provide realistic simulations of systems with very dry initial con-dynamic-arrest toughness for each test are obtained from gen-ditions and high degrees of heterogeneity. Numencal simulaton eration-mode elastodynamic snalyses based on cubic polynome of the simultaneous movement of water and air in unsaturated al lits to the discrete crack-position data points. Applicaton soils has demonstrated the importance of air pathways for con-mode elastodynamic analytical predicatons based on the pro.

taminant transport The stochastic flow and transport theory has posed a-K(')-T relation are within 7% of expenmentally meas-been used to develop a systematic approach to performance ured arrested crack lengths and within 50% of measured arrest assessment and site characterization. Prediction uncertainties times. These predictions represent significant improvements have been quantified by considenng the role of both natural het-over results obtained using previous preliminary estimates of erogeneity and measurement error. Hypothesis-testing tech-the a-K(1) T relation for A 533 B steel. The influence of nonlin-niques have been used to determine whether model predictions ear matenal behavior on the results is also evaluated are consistent with observed data.

NUREG/CR-5908 V01: ADVANCED HUMAN-SYSTEM INTER-NUREG/CR-5973 R01: CODES AND STANDARDS AND OTHER F/ CE DESIGN REVIEW GUIDELINE. General Evaluation GUIDANCE CITEC IN REGULATORY DOCUMENTS.

Model. Technical Development, And Guidefine Desenption.

ANKRUM,A.R.; NICKOLAUS.J.R.; VINTHER,R.W.; et al. Battelle O'HARA.J M.

Brookhaven National Laboratory July 1994 Memonal Institute, Pacific Northwest Laboratory. August 1994.

140pp 9408250026 BNL-NUREG-52333 80660115-398pp. 9409230271. PNL-8462. 81009:001.

i Advanced control rooms will use advanced human-system interface (HSI) technologies that may have significant impica.

As part of the U.S. Nuclear Regulatory Commission (NRC) tions for plant safety in that they will affect the operator's over.

Standard Review Plan Update and Development Program, Pa-all role in the system, the method of information presentation, cific Northwest Laboratory developed a listing of industry con-and the ways in which operators interact with the system. The sensus codes and standards and other government and indus-U S. Nuclear Regulatory Commisson (NRC) reviews the HSI as.

try guidance referred to in regulatory documents. In additon to pects of control rooms to ensure that they are designed to good updating prevous information, Revison 1 adds citations from human factors engineenng pnnciples and that operator perform-the NRC inspection Manual and the improved Standard Techni-ance and reliability are appropnately supported to protect public cal Specifications This listing identifies the version of the code health and safety. The pnncipal guidance available to the NRC, or standard cited in the regulatory document, and the current however, was developed more than ten years ago, well before version of the code or standard. It also provides a summary these technological changes Accordingly, the human factys charactenzation of the nature of the citaton. This listing was de-guidance needs to be updated to serve as the basis for NRC veloped from electronic searches of the Code of Federal Regu-review of 1hese advanced designs. The purpose of this protect latons and the NRC's Bulletins, Information Notees, Circulars, was to develop a general approach to advanced HSt review and Genenc Letters. Policy Statements. Regulatory Guides, and the the human factors guidelines to support NRC safety reviews of Standard Review Plan (NUREG-0800).

1 8

Main Citations and Abstracts NUREG/CR-6093: AN ANALYSIS OF OPERATIONAL EXPERS-graphical fault tree construction to cut set generation and quan-ENCE DURING LOW POWER AND SHUTDOWN AND A PLAN tification to report generation. Version 5 0 of IRRAS provides FOR ADDRESSING HUMAN RELIABILITY ASSESSMENT the same Capabilities as earlier versions and adds the abilrty to ISSUES. BARRIERE.M.; LUCKAS,W. Brookhaven National Lab-perform location transformations, seismic analysis, and provides oratory. WHITEHEAD.D.; et al. Sandia National Laboratones.

enhancements to the user interface as well as improved algo-J June 1994.

200pp 9408030127. BNL NUREG-52388.

nthm performance Additionally, version 5 0 contains new alpha-i 80431:107.

numenc fault tree and event tree editors, and a powerful set of Recent nuclear power plant events (e g. Chernobyl, Diablo macro-based rule editors. These editors are used for event tree Canyon, and Vogtle) and U S. Nuclear Regulatory Commission rules, recovery rules, and end state partitioning.

1 (NRC) reports (e.g. NUREG-1449) have led to concerns regard-ing human rehability during low power and shutdown (LP&S)

NUREG/CR-6116 V03: SYSTEMS ANALYSIS PROGRAMS FOR conditions and limitations of human reliability analysis (HRA)

HANDS-ON INTEGRATED RELIABILITY EVALUATIONS (SA-methodologies in adequately representing the LP&S environ-PHIRE) VERSION 5.0. Integrated Reliability And Risk Analysis meit. As a result of these concerns, the NRC enitiated two par-System (IRRAS)

Tutonal Manual.

VANHORN.R L; allel research projects to assess the influence of LP&S condi-RUSSELL,K.D.; SKINNER,N L EG&G idaho, Inc. July 1994.

tions on human reliability through an analysis of operational ex-174pp. 9408150049. EGG-2716. 80544:106.

penence at pressunrod water reactors (PWRs) and boiling The Systems Analysis Programs for Hart-on integrated Rele water reactors (BWRs). These research projects, performed by ability Evaluatons (SAPHIRE) refers to a set of several micro-Brookhaven National Laboratory for PWRs, and Sandia National computer programs that were developed to create and analyze Laboratones for BW6 Mentified unique aspects of human per-probabilistic nsk assessments (PRAs), pnmanly for nuclear formance dunng LP&S conditions and provided a program plan power plants. This volume is the tutonal manual for the Integrat-for research and developmere necessary to improve existing ed Reliability and Risk Analysis System (IRRAS) Version 5.0, a HRA methodologies. This report documents the results of the state-of-the-art, microcomputer-based probabilistic risk assess-analysis of LP&S operating expenence and desenbes the im-ment (PRA) model development and analysis tool to address proved HRA program p;an.

key nuclear plant safety issues. IRRAS is an integra%d software NUREG/CR-6116 V01: SYSTEMS ANALYSIS PROGRAMS FOR tool that gives the user the ability to create and analyre fault HANDS-ON INTEGRATED RELIABILITY EVALUATIONS (SA-trees and accident sequences using a microcomputer. A senes PHIRE)

VERSION 5.0. Technical Reference Manual.

of lessons is provided that guides the user through basic steps RUSSELL,K D.; ATWOOD.C L.; GALYEAN,W.J.; et al. EG&G common to most analyses performed with IRRAS. The tutorial is Idaho, Inc. July 1994. 131pp. 9408120223 EGG 2716.

divided into two maior sectons: basic and additorial features.

The basic section contains lessons that lead the student 80517:001.

The Systems Analysis Programs for Hands-on Integrated Rel,.

through development of a very simple problem an IRRAS, high-ability Evaluations (SAPHIRE) refers to a set of several micro-lighting the program's most basic features. The additonal fea-computer programs that were developed to create and anatyre tures section contains lessons that expand on basic analysis probabilistic nsk assessments (PRAs), pnmanly for nuclear features of lRRAS 5 0.

j NUREG/CR-6116 V04: SYSTEMS ANALYSIS PROGRAMS FOR power plants. This volume provides information on the pnnci-pies used in the construction and operation of Version 5.0 of HANDS-ON INTEGRATED RELIABILITY EVALUATIONS (SA-the Integrated Reliability and Risk Analysis System (IRRAS) and PHIRE) VERSION 5.0. Systems Analysis And Risk Assessment the System Analysis and Risk Assessment (SARA) system. It (SARA) Reference Manual. RUSSELL,K.D.; KVARFORDT,K.Ja summanzes the fundamental mathematical concepts of sets SKINNER.N.La et al. EG&G Idaho, Inc. July 1994. 291pp.

and logic, fault trees, and probability. This volume then de-9408150057. EGG-2716. 80541:105 scnbes the algonthms that these programs use to construct a The Systems Analysis Programs for Hands-on Integrated Reli-fault tree and to obtain the minimal cut sets. It gives the formu-las used to obtain the probability of the top event from the mini-Computer programs that were develope 1 to create and analy2e mal cut sets, ano the formulas for probabilities that are appro-Probabilistic nsk assessments (PRAs), pnmanly for nuclear pnate under vanous assumptions concerning repairability and power plants. This volume is the reference manual for the Sys-mission time. It defines the measures of basic event importance tems Analysis and Risk Assessment (SARA) System Verson that these programs can calculate. This volume gives an over-5.0, a microcomputer based system used to analyze the safety view of uncertainty analysis using simple Monte Carlo sampling ssues of a Namily" [i e., a power plant, a manufactonng faci! sty, or Latin Hypercube sampling, and states the algonthms used by any facility on which a probabilistic nsk assessment (PRA) might these programs to generate random-basic event probabilities be performed]. The SARA database contains PRA data pnmanly from vanous distnbutions Further references are given, and a for the dominant accident sequences of a family and desenptive detailed example of the reducten and quantification of a simple information about the family including event trees, fault trees, fault tree is provided in an appendix.

and system model diagrams. To simulate changes to family sys-NUREG/CR 6116 V02: SYSTEMS ANALYSIS PROGRAMS FOR tems, SARA users change the failure rates of initiating and HANDS-ON INTEGRATED RELIABILITY EVALUATIONS (SA-basic events and/or modify the structure of the cut sets that PHIRE) VERSION 5 0. Integrated Reliability And Risk Analysis make up the event trees, fault trees, and systems. The user System (IRRAS)

Reference Manual.

RUSSELL,K.D.;

then evaluates the effects of these changes through the recal-KVARFORDT.K.J ; SKINNER.N.La et al. EG&G idaho, Inc. July culaton of the resultant accident sequence probabilities and sm-1994 422pp 9408150043. EGG-2716. 80542 032.

portance measures. The results are displayed in tables and The Systems Analysis Programs for Hands-on Integrated Reli-graphs that may be pnnted for reports.

ability Evaluations (SAPHIRE) refers to a set of several micro-computer programs that were developed to create and analyze NUREG/CR-6116 V05: SYSTEMS ANALYSIS PROGRAMS FOR probabilistic nsk assessments (PRAs), pnmanly for nuclear HANDS ON INTEGRATED RELIABILITY EVALUATIONS (SA-powor plants. The integrated Reliability arid Risk Analysis PHIRE) VERSION 5 0. Systems Analysis And Risk Assessment System (IRRAS) is a state-of-the art, microcomputer based (SARA) Tutonal Manual. SATTISON,M B.; RUSSEL L,K.D.;

probabelistic nsk assessment (PRA) model development and SKINNER,N L.

EG&G Idaho, Inc. July 1994.

110pp.

analysis tool to address key nuclear plant safety issues IRRAS 9408150072. EGG-2716. 80544:001.

is an integrated software tool that gives the user the ability to The Systems Analysis Programs for Hands-on Integrated Reli-create and analyze fault trees and accident sequences using a ability Evaluations (SAPHIRE) refers to a set of several micro-l microcomputer. This program provides functons that range from computer programs that were developed to create and analyte

=

1 9

Main Citations and Abstracts probabihstic nsk assessments (PRAs), pnmarily for nuclear NUREG/CR-6121: COMPONENT EVALUATION FOR INTERSYS-power plants. This volume is the tutorial manual for the Systems TEM LOSS OF-COOLANT ACCIDENTS IN ADVANCED LIGHT Analysis and Risk Assessment (SARA) System Version 5.0, a WATER REACTORS. WARE A.G. EG&G Idaho, Inc. July 1994.

microcomputer based system used to analyze the safety issues 113pp. 9408250010. EGG 2717. 80658:177, of a " family" [i.e., a power plant, a manufactunng facility, any Using the methodology outlined in NUREG/CR-5603 this f:cility on which a probabiliste nsk assessment (PRA) might be report evaluates (on a probabihste basis) design rules for com-performed). A senes of lessons is provided that guides the user ponents in ALWRs that could be subjected to intersystem loss-through some base steps common to most analyses performed of-coolant accidents (ISLOCAs). The methodology is intended with SARA. The example problems presented in the lessons for piping elements, flange connections, on-line pumps and build on one another, and in combination, lead the user through til aspects of SARA sensitivity analysis capabilitses.

valves, and heat exchangers. The NRC has directed that the design rules be evaluated for BWR pressures of 7.04 MPa NUREG/CR-6116 V07: SYSTEMS ANALYSIS PROGRAMS FOR (1025 psig), PWR pressures of 15.4 MPa (2235 psig), and 177 HANDS-ON INTEGRATED RELIABILITY EVALUATIONS (SA.

degrees C (350 degrees F), and has established a goal of 90%

PHIRE) VERSION 5.0. Fault Tree, Event Tree, And Piping & In.

probability that system rupture will not occur dunng an ISLOCA strumentation Diagram (FEP) Editors Reference Manual, event. The results of the calculations in this report show that i

MCKAY,M K.; SKINNER,N.L.; WOOD.S.T. EG&G ldaho, Inc.

components designed for a pressure of 0.4 of the reactor cool-July 1994.147pp. 9408150081. EGG-2716. 80537:144.

ant system operating pressure will satisfy the NRC survival goal The Systems Analysis Programs for Hands-on integrated Reh-in most cases. Specific recommendations for component ability Evaluations (SAPHIRE) refers to a set of several micro-strengths for BWR and PWR appications are made in the computer programs that were developed to create and analyze report. A peer review panel of nationally recognized experts was probabilistic nsk assessments (PRAs), pnmarily for nuclear selected to review and critique the initial results of this program.

power plants. The Fault Tree, Event Tree, and Piping & Instru-mentation Diagram (FEP) editors allow the user to graphcally NUREG/CR-6127: THE EFFECTS OF STRESS ON NUCLEAR build and edit fault trees, event trees, and piping & instrumenta, POWER PLANT OPERATIONAL DECISION MAKING AND ten diagrams (P&lDs). The software is designed to enable the TRAINING APPROACHES TO REDUCE STRESS EFFECTS.

independent use of the graphical. based editors found in the In-MUMAW,R.J. Westinghouse Electnc Corp. August 1994. 43pp.

tegrated Reliability and Risk Assessment System (IRRAS). FEP 9408250017. 80656:278.

is compnsed of three separate editors (Fault Tree, Event Tree.

Operational personnel may be exposed to signifcantly levels and Piping & Instrumentation Diagram) and a utility module. This of stress dunng unexpected changes in plant state and plant i

reference manual prov6 des a screen-by-screen guide of the emergencies. The decision making that identifies operational ac-entire FEP System.

tions, which is strongly determined by procedures, may be af-NUREG/CR 6116 VOS: SYSTEMS ANALYSIS PROGRAMS FOR fected by stress, and performance may be impaired. This report HANDS-ON INTEGRATED RELIABILITY EVALUATIONS (SA-analyzes potential effects of stress in nuclear power plant (NPP)

PHIRE) VERSION 50.Models And Results Database (MAR-D) settings, especially in the context of severe accident manage-Reference Manual. RUSSELL,K.D.; SKINNER,N L EG&G Idaho, ment (SAM) First, potential sources of stress in the NPP setting Inc. July 1994.134pp. 9408150094. EGG-2716. 80544:280.

are identified. This analysis is followed by a review of the ways The Systems Analysis Programs for Hands-on Integrated Reh.

in which stress is likely to affect performance, with an emphasis abihty Evaluations (SAPHIRE) refers to a set of several micro.

on performance of cognitive skihs that are linked to operational computer programs that were developed to create and analyze decision making. Finally, potential training approaches for reduc-probabiliste nsk assessments (PRAs), primanly for nuclear ing or eliminating stress affects are identified. Several training power plants. The pnmary function of MAR-D is to create a data approaches have the potential to ehminate or mitigate stress ef-repository for completed PRAs and Individual Plant Examina-fects on cognitive skill performance. First, the use of simulated i

tions (IPEs) by providing input, conversion, and output capabih-events for training can reduce the novelty and uncertenty that ties for data used by IRRAS, SARA, SETS, and FRANTIC soft-can lead to stress and performance impairments. Second, train-ware. As probabihste risk assessments and individual plant ex-ing to make cognitive processing more effcient and less rehant (minations are submitted to the NRC for review, MAR-D can be on attention and memory resources can offset the reductions in used to convert the models and results from the study for use these resources that occur under stressful conditions. Third, with IRRAS and SARA. Then, these data can be easily ac*

training that targets crew communcations skills can reduce the cIssed by future studies and will be in a form that will enhance likelihood that communications will fail under stress.

the analysis process. This reference manual provides an over-view of the functions available within MAR-D and step-by-step NUREG/CR-6120: PIPING BENCHMARK PROBLEMS FOR THE operating instructions-ABB/CE SYSTEM 80+ STANDARDIZED PLANT. BEZLER.P.;

DEGRASSI,D.; BRAVERMAN J.; et al. Brookhaven National NUREG/CR-6120: CONTROLLED FIELD STUDY FOR VALIDA-TION OF VADOSE ZONE TRANSPORT MODELS.

Laboratory. July 1994. 234pp. 9408150117. BNL-NUREG.

WlERENGA,P.J.; WARRICK,A.W.; et al. Anzona, Univ. of, 52396. 80543:090.

Tucson, AZ. HILLS R.G. New Mexico State Univ., Las Cruces.

To satisfy the need for venfcation of the computer programs NM. August 1994, 27pp. 9409060223. 80785:001.

and modehng techniques that will be used to perform the final Predction of radionuchde migration through soil and ground.

piping analysis for the ABB/ Combustion Engineenng System water requires models which have been tested under a variety 80+ Standardized Plant, three benchmark problems were de-of conditions. Unfortunately, many of the existing models have veloped. The problems are representatwe piping systems sub-r:ot been tested in the field, partly because such testing requires jected to representative dynamic loads with solutions developed s.ccurate arvi representative data. This report provides the using the methods being proposed for analysis for the System 1

design of a large scale field expenment representatwo, in terms 80+ standard design. It will be required that the combined h-of surface area and depth of vadose zone, of an actual disposal cense Icensees demonstrate that their solutions to these prob-crea Expenments are proposed which will yield documented lems are in agreement with the benchmark problem set.

data, of sufficient scale, to allow testing of a variety of models including effective media stochaste models and deterministic NUREG/CR-6143 V02P1A: EVALUATION OF POTENTIAL models. Details of the methodology and procedures to be used SEVERE ACCIDENTS DURING LOW POWER AND SHUT-in the expenment are presented.

l

~

r

10 Main Citations and Abstracts DOWN OPERATIONS AT GRAND GULF, UNIT 1. Analysis Of NUREG/CR4143 V02PT4: EVALUATION OF POTENTIAL Core Damage Frequency From internal Events For Plant Oper-SEVERE ACCIDENTS DURING LOW POWER AND SHUT-atonal State 5 Dunng A Refueling Outage. Sections 19.

DOWN OPERATIONS AT GRAND GULF, UNIT 1. Analysis Of WHITEHEAD.D. Sandia National Laboratones. DARBY,J. Sci.

Core Damage Frequency From intemal Events For Plant Oper-

)

ence & Eng.neenng Associates, Inc. YAKLE.J.; et at Science ational State 5 Dunng A Refueling Outage. Internal Applications international Corp. (formerty Science Applicatons, FORESTER,1 Science Applications inte natonal Corp. (formerly Inc.).

June 1994. 284pp. 9408030161, SAND 93-2440.

Science Applications, Inc.). WHITEHr;AD,D. Sandia Natonal 80442:001, Laboratones. DARBY,J.; et al. Goerse & Engineenng Associ-This document contains the accident sequence analysis of in.

ates, Inc. June 1994. 889pp. M 08030243. SAND 93-2440.

ternally initiated events for Grand Gulf. Unit 1 as it opvates in 80439 001.

the Low Power and Shutdown Plant Operational State 5 dunng See NUREG/CR 6143,V02,PT3 abstract.

a refueling outage. The report documents the methodology NUREG/CR4143 V03: EVALUATION OF POTENTIAL SEVERE used dunng the analysis, desenbes the results from the applica-ACCIDENTS DUR NG LOW POWER AND SHUTDOWN OPER-tion of the methodology, and compares the results with the re-ATIONS AT GRAND GULF UNIT 1. Analysis Of Core Damage suits from two full power analyses performed on Grand Gulf.

Frequency From Internal Events For Plant Operational State 5 un A

ing u age.

a a Nawal NUREG/CR4 43 V02P18: EVALUATION OF POTENTIAL "9'"**""9 SEVERE / OCIDENTS DURING LOW POWER AND SHUT-

• • • • 'ncJJy' 1994.112pp 9408180206. SANDC3-2440.

,I DOWN OERATIONS AT GRAND GULF, UNIT 1. Analysis Of 244 Core Da,iage Frequency From Internal Events For Plant Oper-This report presents the details of the analysis of core ation# State 5 Dunng A Refueling Outage.Section 10 damage frequency due to fire dunng shutdown Plant Operaton-Y W fEHEAD.D. Sandia Natonal Laboratones. DARBY,J Sci-al State 5 at the Grand Gulf Nuclear Staten. Insights from pre-ence & Engineenng Associates, Inc. YAKLE,J.; et al. Science vious fire analyses (Peach Bottom, Surry, LaSalle) were used to Appiscations international Corp. (formerly Science Applications-the greatest extent possible in this analysis. The fire analysis Inc ).

June 1994. 997pp 9408030170. SAND 93-2440.

was fully integrated utilizing the same event trees and fault 80426-001-trees that were used in the internal events analysis In assess-Sta NUREG/CR-61a3,V02 P1 A abstract eng shutdown nsk due to fine at Grand Gulf, a detailed screening was performed which included the following elements. (a) Com-NUREG/CR-6143 V02PIC: EVALUATION OF POTENTIAL puter aided vital area analysis (b) Plant inspections, (c) Credit SEVERE ACCIDENTS DURING LOW POWER AND SHUT.

for automatic fire protection systems (d) Recovery of random DOWN OPERATIONS AT GRAND GULF, UNIT 1. Analysis Of failures, and (e) Detailed fire propagation modeling. This screen-Core Damage e requency From internal Events For Plant Oper-ing process revealed that all plant areas had a negligible atonal State 5 Dunng A Refueling Outage Main Report.

(< l.0E-8 per year) contnbution to fire-induced core damage WHITEHEAD.D. Sandia National Laboratones. DARBY,J. Sci-frequency, ence & Engineenng Associates, Inc. YAKLE,J.; et al. Science Applicatons International Corp (formerly Science Applications, NUREG/CR-6143 V04: EVALU ATION OF POTENTIAL SEVERE inc.).

June 1994. 373pp. 9408030176. SAND 93 2440.

ACCIDENTS DURING LOW POWEH AND SHilTDCWN OPER-80443.001.

ATIONS AT GRAND GULF. UNIT 1. Analysis Of Core Damage See NUREG/CR-6143,V02,P1 A abstract.

Frequency From Internally induced Flooding Events For Plant Operational State 5 Dunng a Refueling..

DANDINI,V.;

NUREG/CR-6143 V02PT2: EVALUATION OF POTENTIAL STAPLE,84 et al. Sandia National Laboratones FORESTER,J.

SEVERE ACCIDENTS DURING LOW POWER AND SHUT.

Science Applications internatonal Corp. (formerly Science Ap-DOWN OPERATIONS AT GRAND GULF, UNIT 1. Analysis Of pl' cations, Inc ). July 1994. 472pp. 9409070061 SAND 93-2440.

Core Damage Frequency From Internal Events For Plant Oper.

80787.001.

ational State 5 Dunng Refueling Outage. Internal. DARBY,J.

An estimate of the contnbution of intemal flooding to the Science & Engineenng Associates, Inc. WHITEHEAD.D.;

mean core damage frequency at the Grand Gulf Nuclear Station STAPLE B.; et at Sandia Nahonal Laboratores June 1994.

was calculated for Plant Operational State 5 dunng a refueling 609pp. 9408030187. SAND 33-2440. 80432.001.

outage Pursuant to this objective, flood zones and sources This document contains the accident sequence analysis of in-were identified and flood volumes were calcu'ated. Equipment ternally initiated events for Grand Gulf, Unit 1 as it operates in necessary fu the maintenance of plant safety was identified the Low Power and Shutdown Plant Operational State 5 dunng and its vulnerability to flooding was determined. Event trees and fauH Ws wee Md a hW as rqM, aM N a refueling outage. The report documents the methodology quantifcaton was pMarnM using h MS cd he mean used dunng the analysis, describes the results from the applica-c e amage Muscy eMak W %% &nng M $ was tion of the methodology, and compares the results with the re-found to be 2.3 E-8 per year.

suits from two full power analyses performed on Grand Gulf.

NUREG/CR-6143 V05: EVALUATION OF POTENTIAL SEVERE NUREG/CR-6143 V02PT3: EVALUATION OF POTENTIAL ACCIDENTS DURING LOW F'OWER AND SHUTDOWN OPER-SEVERE ACCtDENTS DURING LOW POWER AND SHUT.

AT!ONS AT GRAND GULF, UNIT 1. Analysis Of Core Damage DOWN OPERATIONS AT GRAND GULF, UNIT 1. Analysis Of Frequency From Seismic Events Dunng Mid Loop Core Damage Frequency From internal Events For Plant Oper-Operatons Main Report. BUDNITZ.R.J. Future Resources Asso-ational State 5 Dunng A Refueling Outage internal.. YAKLE.J ciates, Inc. DAVIS,P R. PRD Corsulting RAVINDRA.M.K.; et al.

Science Applications international Corp (formerly Science Ap-EOE, Inc. August 1994 110pp 9409230278. 81006 083 plications, Inc ) DARBY,J Science & Engineenng Associates, Dunng 1989, the Nuclear Regulatory Commission (NRC) inits-inc. WHITEHEAD.D; et al Sandia Natonal Laboratones. June ated an es;ensive program to carefully examine the potential 1994. 834pp. 9408030235. SAND 93-2440 80429 001.

risks dunng low power and shutdown operations The program This report provides supporting documentation for vanous includes two paralle! projects being performed by Brooktiaven tasks associated with the performance of the probabilistic nsk National Laboratory (BNL) and Sandia National Laboratones assessment for Plant Operatonal State 5 dunng a refueling (SNL) Two plants, Surry (pressunred water reactor) and Grand outage at Grand Gulf, Unit I as documented in Volume 2, Part 1 Julf (boiling water reactor). were selected as the plants to be of NUREG/CR-6143 studied The objectives of the program are to asse% the nsks I

l

v i

11 Main Citations and Abstracts of severe accidents initiated during plant operational states SEVERE ACCIDENTS DURING LOW POWER AND SHUT.

other than full power operation and to compare the estimated DOWN OPERATIONS AT SURRY, UNIT 1. Analysis Of Core core damage frequencies, important accident sequences and Damage Frequency Fron, internal Events Dunng Mid Loop other qualitatrse and quantitatwe results with those accidents Operations. Appendices E (Sections E.9.E.16).

CHU,T.L; initiated dunng full power operation as assessed in NUREG.

MUSICKI,Z.; KOHUT,P.; et al. Brookhaven National Laboratory.

1150. The objectve of thes report is to document the approach June 1994.

502pp. 9408150234.

BNL-NUREG-52399.

utilized in the Grand Gutt plant and discusa *he results obtained.

80556:202.

A parallel report for the Surry plant is prepared by SNL.

See NUREG/CR-6144,V02.P1 A abstract.

NUREG/CR4144 V02P4: EVALUATION OF' POTENTIAL NUREG/CR4144 V02P1A: EVALUATION OF POTENTIAL SEVERE ACCIDENTS DURING LOW POWER AND SHUT-SEVERE ACCIDENTS DURING LOW POWER AND SHUT-DOWN OPERATIONS AT SURRY, UNIT 1. Analysis Of Core DOWN OPERATIONS AT SURRY, UNIT 1. Analysis Of Core Damage Frequency From internal Events Dunng Mid-Loop Damage Frequency From Intemal Events Dunng Mid-Loop Operations. Appendices F-H. CHU,T.L; MUSICKl,Z.; KOHUT,P.;

Operations. Main Report (Chapters 1-6). CHU,T.L.; MUSICKl.Z.;

et al. Brookhaven National Laboratory. June 1994. 612pp.

XOHUT,P,; et at Brookhaven National Labotatory. June 1994.

9408150246. BNL NUREG 52399. 80559:001.

j 494pp.9408120219. BNL-NUREG-52399. 80515:001.

See NUREG/CR-6144,V02.P1 A abstract.

t Dunng 1989, the Nuclear Regulatory Commission (NRC) initi.

NUREG/CR-6144 V02P5: EVALUATION OF POTENTIAL ated an extensive program to carefully examine the potential SEVERE ACCIDENTS DURING LOW POWER AND SHUT-i nsks during low power and shutdown operations. The program includes two parallel projects being performed by Brookhaven DOWN OPERATIONS AT SURRY, UNIT 1. Analysis Of Core 1

National Laboratory (BNL) and Sandia National Laboratones Damage Frequency From Internal Events Dunng Mid-Loop Operations. Appendices 1. CHU,T.L; MUSICXl,Z.; KOHUT,P.; et (SNL). Two plants Surry (pressunzed water reactor) and Grand al. Brookhaven National Laboratory. June 1994. 313pp.

Gulf (boiling water reactor), were selected as the plants to be 9408150284. BNL-NUREG-52399. 80558:001, studied. The objectrves of the program are to assess the nsks See NUREG/CR-6144,V02,PI A abstract.

of severe accidents initiated during plant operational states i

other than full power operation and to compare the estimated NUREG/CR-6144 V03 P1: EVALUATION OF POTENTIAL core damage frequencies, important accident sequences and SEVERE ACCIDENTS DURING LOW POWER AND SHUT-other quaktatsve and quantitative results with those accidents DOWN OPERATIONS AT SURRY, UNIT 1. Analysis Of Core initiated dunng full power operation as assessed in NUREG-Damage Frequency From internal Fires During Mid. Loop 1150. The objective of this report is to document the approach Operatons. Main Report. MUSICKI,Z.; CHU,T.L Brookhaven Na-utshzed in the Surry plant and d!scuss the results obtained. A bonal Lawatoy HO,W m at M. Inc 5%

ad, parallel report for the Grand Gulf plant is prepared by SNL This NURE 5 9 18 083 study shows that the core-damage frequency dunng mid-loop See NUREG/CR-6144,V02,PI A abstract.

operation at the Surry plant is comparable to that of power op-eration. We recognize that there is very large uncertainty in the NUREG/CR-6144 V03 P2: EVALUATION OF POTENTIAL 1

human error probabilities in this study. This study identified that SEVERE ACCIDENTS DURING LOW POWER AND SHUT-only a few procedures are available for mitigating accidents that DOWN OPERATIONS AT SURRY, UNIT 1. Analysis Of Core may occur dunng shutdown. Procedures wntten specifically for Damage Frequency From intemal Fires Dunng Mid-Loop shutdown accidents would be useful.

Operations. Appendices. MUSIOKI,Z.; CHU,T.L Brookhaven Na-tional Laboratory. HO,V.; et al. PLG, Inc. (formerly Pickard, NUREG/CR-6144 V02P18: EVALUATION OF POTENTIAL Lowe & Gsmck, Inc.). Juty *1994. 400pp. 9408180149. BNL-SEVERE ACCIDENTS DURING LOW POWER AND SHUT.

NUREG-52339. 80616:001, DOWN OPERATIONS AT SURRY, UNIT 1. Analysis Of Core See NUREG/CR 6144,V02.P1 A abstrr.:t.

i Damage Frequency From intemal Events During Mid Loop NUREG/CR-6144 V04: EVALUATION 07 POTENTIAL SEVERE Operations. Main Report (Chapters 7-12). CHU T.L.; MUSICKI,Z.;

ACCIDENTS DURING LOW POWER AlJD SHUTDOWN OPER-KOHUT,P.; et al Brookhaven National Laboratory. June 1994.

ATIONS AT SURRY, UNIT 1. Analysis Of C, ore Damage Frequen.

630pp.9408150181. BNL-NUREG-52399. 80538:001.

cy From Internal Floods Dunng Mid-Loop Operatioris. KOHUT,P.

See NUREG/CR-6144,V02,P1 A abstract.

Brookhaven National Laboratory. July 1994.

200pp.

9408180160. BNL NUREG-52399. 80614:060.

NUREG/CR-6544 V02P2: EVALUATION OF POTENTIAL See NUREG/CR-6144,V02,P1 A abstract.

SEVERE ACCIDENTS DURING LOW POWER AND SHUT-DOWN OPERATIONS AT SURRY, UNIT 1. Analysis Of Core NUREG/CR-6144 V05: EVALUATION OF POTENTIAL SEVERE Damage Frequency From internal Events Dunng Mid-Loop ACCIDENTS DURING LOW POWER AND SHUTDOWN OPER-Operations. Appendices A-D. CHU,T.L.; MUSICKI,Z.; KOHUT,P.;

ATIONS AT SURRY, UNIT 1. Analysis Of Core Damage Fre-quency un Sesmk Events Dunng MW OpwatonsMain et at Brookhaven Natonal Laboratory. June 1994. 468pp.

9408150192. BNL-NUREG-52399. 80540:001.

Report. BUDNITZ,R.J. Future Resources Associates, Inc.

See NUREG/CR 6144,V02 P1 A abstract.

DAVIS,P.R. PRD Consutting. RAVINDRA,M.K.; et al EOE, Inc.

August 1994.114pp. 9409230293. 81010:116.

"9 NUREG/CR 6144 V02P3A: EVALUATION OF POTENTIAL ated an exten'sive program to carefully examine the potentiaf 1

SEVERE ACCIDENTS DURING LOW POWER AND SHUT.

4 GOWN OPERATIONS AT SURRY. UNIT 1. Analysis Of Core nsks dunng low power and shutdown operatens. The program Damage Frequency From Internal Events During Mid-Loop includes two parallel projects being performed by Brookhaven Nationat Laboratory (BNL) and Sandra National Laboratories Operations. Appendices E (Sections E.1 -E.8).

CHU T.L (SNL). Two plants, Surry (pressurized water reactor) and Grand MUSICK1,Z.; KOHUT.P.; et al. Brookhaven National Laboratory.

Gulf (boihng water reactor), were selected as the plants to be June 1994.

560pp.

9408150228.

BNL-NUREG-52399.

studied. The objectives of the program are to assess the risks B0555:001.

of severe accidents initiated dunng plant operational states i

See NUREG/CR-6144,V02,P1 A abstract.

other than full power operaton and to compare the estimated i

core damage frequencies, important accident sequences and NUREG/CR-6144 V02P38: EVALUATION OF POTENTIAL other quaktative and quantitative results with those accidents

_ - ~..-

12 Main Citations and Abstracts initiated dunng full power operation as assessed in NUREG-pnor to cleavage. Ductile crack extensions of 10-15 x the initial 1150. The obective of this report is to document the approach crack tip opening displacement at initiation are considered in l

utilized in the Surry plant and discuss the results obtained. A plane-strain, finite element computations. The finite element re-parallel report for the Grand Gulf plant is prepared by SNL suits demonstrate a significant elevation in crack-tip constraint NUREG/CR 6151: FEASIBILITY OF DEVELOPING RISK-BASED due to macroscopic " sharpening" of the extending tip relative to RANKINGS OF PRESSURE BOUNDARY SYSTEMS FOR IN-the blunt tip at the initiation of growth. However this effect is SERVICE INSPECTION. VO,T.V.; SMITH.B.W.; SIMONEN.F.A.;

offset partially by the additional plastic deformation associated j

et al. Battelle Memorial institute, Pacific Northwest Laboratory.

with the increased apphed J required to grow the crack. The ini-August 1994. 86pp. 9410130086. PNL-8912. 81266:091.

tial a/W ratio, teanng modulus, strain hardening exponent and 1

I Goals of the Nondestructive Evaluation Rehabihty Program specimen size interact in a complex manner to define the evolv.

sponsored by the NRC at PNL are to 1) assess current inspec-ing near tip conditions for cleavage fracture. The paper explores tion techniques and requirements of all pressure boundary sys-development of the new model, provides necessary graphs and 1

I tems and components, 2) determine if improvements are procedures for its application ar;d demonstrates the effects of needed, and 3) if necessary, develop recommendations for re.

the model on fracture data sets for two pressure vessel steels vising the applicable ASME Codes and regulatory requirements.

(A5338 and A515).

In evaluating approaches that could be used to provide a tech-NUREG/CR-6168: DIRECT CONTAINMENT HEATING INTEGRAL nical basis for improved inservice inspection (ISI) plans, PNL EFFECTS TESTS AT 1/40 SCALE IN ZION NUCLEAR POWER has developed and applied a method that uses results of prob.

PLANT GEOMETRY.

BINDER,J L.;

MCUMBER.L.M.;

abilistic nsk assessment (PRA) to rank pressure boundary sys-tems for ISI. In the PNL program, the feasibility of developing SPENCER.B.W. Argonne National Laboratory. September 1994.

nsk-based genenc ISI requirements is being conducted in two 112pp. 9410120216. ANL-94/18. 81254.150.

phases. Phase i involves identifying and pnontizing the systems The results of Direct Containment Heating (DCH) integral ex-most relevant to plant safety. The results of these evaluations penments are presented. The expenments simulated a high will be consolidated into requirements for comprehensive piping pressure melt ejection in the Zion Nuclear Power Plant. Expen-system inspections that will be developed in Phase ll. This ments were conducted in a 1/40 scale model of the Zion con-report presents the Phase i results of evaluations for eight se.

tainment. The model included the vessel lower head, cavity and lected plant PRAs. Based on the results of this study, it appears instrument tunnel, and the lower containment structures. The t

that there are generic insights that can be extrapolated from the melt elections were driven by steam. There were two main ob-selected plants to specific classes of hght water reactors.

jectives of these expenments. The first was to investigate the i

NUREG/CR-6152: EXPERIMENTS TO INVESTIGATE DIRECT CONTAINMENT HEATING PHENOMENA WITH SCALED scale fa ility at Argonne Natonal Laboratory and in a 1/10 MODELS OF THE SURRY NUCLEAR POWER PLANT BLANCHAT.T.K.; Al.LEN.M.D.; PILCH,M M.; et al. Sandia Na$

tional Laboratones June 1994. 206pp. 9407260019. SAND 93-test series. The second object:ye was to address potential ex.

5 t

2519. 80344 00, The Contaament Technology Test Facihty (CTTF) and the aWmina hme W mnd @w was md in N U Surtsey Test Facihty at Sandia National Laboratones are used seres of tests which utilized a prototypic core melt. Corium ex-r to perform s :aled expenments that simulate High Pressure Melt penments were conducted that wore counterpart to the IET-Ejection accidents in a nuclear power plant (NPP). These ex.

1RR and IET 6 iron / alumina tests.

penments are designed to investigate the effects of direct con-tainment h9ating (DCH) phenomena on the containment load.

NUREG/CR-6178: LABORATORY CHARACTERIZATION 'OF High-temperature, chemically reactsve melt (thermite) is ejected ROCK JOINTS. HSIUNG,S.M.; KANA.D.D.; AHOLA,M.P.; et al.

by h:gn-pressure steam into a scale model of a reactor cavity.

Center for Nuclear Waste Regulatory Analyses. May 1994, Debns is entrained by the steam blowdown into a containment 240pp. 9407260012. CNWRA 93-013. 80342:001.

e model where specific phenomena, such as the effect of sub-A laboratory characterization of the Apache Leap tuff joints I

compartment structures, prototypic air / steam / hydrogen atmos-under cyche pseudostatic and dynamic loads has been under-pheres, and hydrogen generation and combustion, can be stud-taken to obtain a better understanding of dynamic joint shear r

ied. Four integral Effects Tests (IETs) have been performed behavior and to generate a complete data set that can be used w'th scale models of the Surry NPP to investigate DCH phe-i for validation of existing rock-joint models. Study has indicated I

nomena. The 1/6 scale Integral Effects Tests (IET-9, IET-10, that available methods for determining joint roughness coeffi-and IET-11) were conducted in CTTF, which is a 1/6(th) scale cient (JRC) significantly underestimate the roughness coefficient i

model of the Surry reactor containment building (RCB). The 1/

of the Apache Leap tuff joints, that will lead to an underestima-10(th) scale IET test (lET-12) was performed in the Surtsey ton of the joint shear strength. The results of the direct shear vessel, which had been configured as a 1/10 scale Surry RCB.

tests have indicated that both under cyche pseudostatic and dy-Scale models were constructed in each of the facihties of the hMmmpmuh%s Sorry structures, including the reactor pressure vessel, reactor smaller than that of forward sheanng and the joint dilation re-support skirt, control rod dove missile shield, biological shield sulting from forward sheanng recovers dunng reverse sheanng.

wall, cavity, instrument tunnel, residual heat removal platform g

g and heat exchangers, seal table room and seal table, operating I

tests, the sheanng velocity effect on rock-joint behavior seems i

to be minor, and no noticeable effect on the peak joint shear eves the esu ts strength and the joint shear strength for the reverse shearing is NUREG/CR-6162: EFFECTS OF PRIOR DUCTILE TEARING ON observed.

CLEAVAGE FRACTURE TOUGHNESS IN THE TRANSITION REGION. DOODS.R.H.; TANG,M. liknois, Univ. of, Urbana, IL.

NUREG/CR-6181: A PILOT APPLICATION OF RISK-BASED ANDERSON,T.L. Texas A&M Univ., College Station, TX. June METHODS TO ESTABLISH INSERVICE INSPECTION PRIOR-1994.45pp.9407250325. UILU-ENG93-2014. 80329.232.

ITIES FOR NUCLEAR COMPONENTS AT SURRY UNIT 1 NU.

Previous work by the authors descnbed a micromechanis CLEAR POWER STATION.

VO,T.V.;

GORE.B F.;

fracture model to correct measured J(c)-values for the mecha.

SIMONEN,F.A.; et al. Battelle Memonal Institute, Pacific North-nistic effects of large-scale yielding. This new work extends the west Laboratory. August 1994. 72pp. 9409090115. PNL-9020.

model to also include the influence of ductile crack extension 80817:001.

t E

~_

_m

13 Main Citations and Abstracts As part of the NDE Reliability Program sponsored by the NUREG/CR-6190 V02: PROTECTION AGAINST MALEVOLENT NRC, PNL is developing a method that uses nsk-based ap.

USE OF VEHICLES AT NUCLEAR POWER PLANTS Vehicle i

proaches to establish inservice anspection plans for nuclear Barner System Siting Guidance For Blast Protection.

l power plant components. This method uses probabiliste risk as-NEBUDA.D.T. Army, Dept. of Corps of Engineers. August 1994.

i sessment (PRA) results and failure Modes and Effects Analysis 41pp. 9409200303. 80954:236.

l techniques to identify and pnontire the most nsk-important sys-See NUREG/CR-6190,V01 abstract.

tems and components for inspection. The Surry Nuclear Power NUREG/CR-6203: VALIDATION STUDIES FOR ASSESFING UN-Staten Unit 1 was selected for pilot appleatons of this method.

SATURATED FLOW AND TRANSPORT THROUGd FRAC-The specife systems addressed in this report are the reactor TURED ROCK.

BASSETT R.L; NEUMAN,S.P.;

pressure vessel, reactor coolant, low-pressure injection, and RASMUSSEN.T.C.; et al. Anzona, Univ. of, Tucson, AZ. August auxiliar1 feedwater. The results provide a nsk-based ranking of 1994. 219pp. 9409090105. 80816:111, components within these systems and relate the target nsk to The objectives of this contract are to examine hypotheses target failure probabihty values for individual components. These and conceptual models conceming unsaturated flow and trans-results will be used to gude the development of improved in-port through heterogeneous fractured rock and to design and spection plans for,uclear power plants. To develop inspection execute confirmatory field and laboratory experiments to test p ans, the acceptable level of nsk from structural failure for im-these hypotheses and conceptual models. Important new infor-portant systems and components will be apportioned as a small maton is presented such as the application and evaluaton of fracton of the total PRA-estimated nsk for core damage. This procedures for estimating hydraulic, pneumate, and solute process will determine acceptable target nsk and target failure transport coeffcients for a range of thermal regimes. A field probability values for indivdual components. Inspecten require-heater expenment was des #gned that focused on edentifying the ments will be set at levels to assure that acceptable failure suitability of existing monitonng equipment to obtain required probabilities are maintained.

data. A reliable method was developed for conducting and inter.

preting tests for air permeability using a straddle-packer ar-NUREG/CR-6183: PEER REVIEW OF THE TMI-2 VESSEL IN-rangement. Detailed studies of fracture flow from Queen Creek VESTIGATION PROJECT METALLURGICAL EXAMINATIONS.

into the Magma Copper Company ore haulage tunnel have BOHL,R.W.; GAYDOS,R.G ; VANDER VOORT,G.; et al. Ar-been initiated. These studies will provide data on travel time for gonne National Laboratory. July 1994. 45pp. 9408220048. ANL-transport of water and solute in unsaturated tuff. The collection 94/3. 80637.206.

of rainfall, runoff, and infiltraton data at two small watersheds at Fifteen samples recovered from the lower head of the Three the Apache Leap Tuff Site enabled us to evaluate the quantity Mile Island (TMI) Unit 2 nuclear reactor pressure vessel were and rate of water infiltrating into the subsurface via either frac-subjected to detailed metallurgical examinatons by the Idaho tures or matnx. Charactenzaton methods for hydraulic param-Natonal Engineenng Laboratory. Argonne National Laboratory eters relevant to high-level waste transport, including fracture apertures, transmisswity, matnx porosity, and fracture wetting (ANL) and several of the European partcipants. These exami-ont propagabon velocites, wwe Mo#

nations determined that a portion of the lower head reached temperatures as high as 1100 degrees C dunng the accident NUREG/CR-6206: TRANSPORT CALCULATIONS OF RADI-and cooled from these temperatures at =I0-100 degrees C/

ATION EXPOSURE TO VESSEL SUPPORT STRUCTURES IN min. The remainder of the lower head was found to have re-THE TROJAN REACTOR. ASGARI.M.; WILLIAMS,M L. Louisi-mained below 727 degrees C. A panel of three outside peer re-ana State Univ., Baton Rouge, LA. KAM.F.B.K.; et al. Oak R dge viewers was formed to conduct an independent review of this National Laboratory. July 1994. 74pp. 9412020031. ORNL/TM-metallurgical analyses. This review determined that the conclu-12693. 81941:001.

sions resulting from the INEL study were fundamentally correct.

Compansons of transport calculatons of the dosimeter activi-in partcular, the panel recffirmed that four lower head samples ties with the expenmental measurements shows that the values attained temperatures as high as 1100 degrees C, and perhaps obtained with ENDF/B-VI cross-section data overestimate the es high as 1150 1200 degrees C in one case, dunng the acci.

measured results for high-energy-threshold reactions in the dent. They concluded that these samples subsequently cooled cavity by up to 41% and thermal reactons by up to a factor of at a rate of =50-125 degrees C/ min in the temperature range 3.0. The transport calculations performed with the onginal of 600-400 degrees C. The reviewers also agreed that the re-SAILOR cross-secten library (based on ENDF/B-IV data) over-mainder of the lower head samples had not exceeded 727 de-estimate measured threshold reactions by only 15% and the grees C dunng the accident and suggested several refinements thermal reactions by about a factor of 2.50. These results are inconsistent with those obtained in earlier studes that com-and attemative procedures that could have been employed in pared transport calculations done with SAILOR vs ENDF/B-VI, the onginal analysis.

which indicate that SAILOR tends to underestimate cavity activi-ties for tnreshold reactons, while the ENDF/B Vi values usually NUREG/CR-6190 V01: PROTECTION AGAINST MALEVOLENT USE OF VEHICLES AT NUCLEAR POWER PLANTS.Vehele agree better with experimental results. One factor that probably contnbutes to the rather large discrepancy between the comput-Bamer System Siting Guidance For Blast Protection, ed and measud actwes is N cm poww esNon used NEBUDA,D.T. Army, Dept. of, Corps of Engineers. August 1994, in the calculations. Because of unavailability of plant-specifc 18pp. 9409200299. 80954 218.

data, a genenc power distnbution provided by Westingtouse This manual provides for determining the minimum safe was used. Since the calculated cavity flux levels appear to be standoff distance between vital safety related equipment and over-estimated, the results estimated for the exposure to the the design basis vehicle bomb threat adopted by the U.S. Nu-support structure should be conservative.

clear Regulatory Commission. Vital safety related equipment should survive t',e design basis vehicle bomb attack when the NUREG/CR-6208: AN EMPIRICAL INVESTIGATION OF OPERA-minimum safe standoff distance is provided. Guidance is provid-TOR PERFORMANCE IN COGNITIVELY DEMANDING SIMU-ed for exposed vital safety related equipment and for equipment LATED EMERGENCIES. ROTH,E M.; MUMAW,R.J. Westing-housed within vital area bamers. The types of vital area bamers house Electnc Corp. LEWIS P.M. Human Factors Branch July cddressed are 12,18, 24, and 30 inch-thick reinforced con-1994.143pp. 9407250208. 80328:005.

crete slabs with reinforcing ratios of 0.2, 0 4. 0 6. 0.8,1.0 per.

Thes report documents the results of an empincal Study of nu-cent.

clear power plant operator performance in cognitively demand-ing simulated emergencies. Dunng emergencies operators

14 Main Citations and Abstracts follow highly presenptive wntten procedures. The objectives of head spin, decreased from 15 percent hydrogen at 300K down the study were to understand and document what role higher-to between 9 and 10 percent hydrogen at 050K.

level cognitive activities such as diagnosis, or more generally

' situation assessment', play in guiding operator performance, NUREG/CR-6218: A REVIEW OF THE TECHNICAL ISSUES OF given that operators utilize procedures in responding to the AIR INGRESSION DURING SEVERE REACTOR ACCIDENTS.

events. The study examined crew performance in vanants of POWERS,D A.; KMETYK L.N.; SCHMIDT,R.C. Sandia National two emergencies: (1) an Interfacing System Loss of Coolant Ac.

Laboratones. September 1994. 84pp. 9409270204. SAND 94-cadent and (2) a Loss of Heat Sink scenario. Data on operator 0731. 81046 023.

performance were collected using training simulators at two Severe reactor accident scenanos involving air ingression into plant sites. Up to 11 crews from each plant participated in each the reactor coolant system are desenbed. Evidence from of two simulated emergencies for a total of 38 cases. Crew per.

modern reactor accident analyses and from the accident at formance was videotaped and partial transcnpts were produced Three Mile Island shows residual fuel will be present in the core and analyzed. The results sevealed a number of instances region when air ingression is possible. This residual fuel can where higher-level cognitive activities such as situation assess.

interact with the air. Exploratory calculations with the MELCOR ment and response planning enabled crews to handie aspects code of station blackout accidents dunng shutdown conditions of the situation that were not fully addressed by the procedures and dunng operations are used to examine clad oxidation by air This report documents these cases and discusses their implica-and ruthenium release from fuel in air. Extensive ruthenium re-tions for the development and evaluation of training and Control lease is predicted when air ingression rates exceed about 10 room a'ds, as well as for human reliability analyses.

moles /s. Past studies of air interactions with irradiated reactor fuel are reviewed. Effects air ingression may have on fissson NUREG/CR-6212: VALUE OF PUBLIC HEALTH AND SAFETY product release, transport, deposition, and revapontation are ACTIONS AND RADIATION DOSE AVOIDED BAUM J W.

discussed Perhaps the most important effects of air 'ngression i

Brookhaven National Laboratory. May 1994.54pp.9407260025.

are expected to be enhanced release of rJthenium from the fuel BNL-NUREG-52413. 80342 241.

and the formation of copious amounts of aerosol from uranium The values judged best to reflect the willingness of society to oxide vapors. Revaponzation of iodine and tellunum retained in pay for the avoidance or reduction of nsli were deduced from the reactor coolant system might be expected.

studies of costs of health care, transportation safety, consumer product safety, government agency actions, wage-nsk compen.

NUREG/CR-6224 DRF FC: PARAMETRIC STUDY OF THE PO-sation, consumer behavior (market) stLdies, and willingness-to.

TENTIAL FOR BWR ECCS STRAINER BLOCKAGE DUE TO pay surveys. The results ranged from $1,400,000 to $2.700.000 LOCA GENERATED DEBRIS. Draft For Comment. ZlCLER,G.;

per life saved Applying the mean of these values ($2.100.000)

BEATY,R.; BRIDEAU J ; et al. Science & Engineenng Associ-and the latest nsk per unit dose coefficients used by the ICRP ates, Inc. August 1994. 238pp. 9408310226 SEA 93-554 06-A1.

(1991), which take into account nsks to the general public, in-80719 001.

ciuding genetic effects and non-fatal cancers, yields a value of This report documents a plant-specific study for a BWR 4 dose avoided of $750 to $1.500 per person-cSv for public expo-with Mark I containment, that evaluated LOCA-generated debns sures. The lower value applies if adjustments are made for phenomena and the potential for losing recirculation cooling ca-years of life lost per fatality A nominal value of $1,000 per pability due to ECCS pump suction strainer clogging and loss of person-cSv seems appropnate in light of the many uncertainties net positive suction head (NPSH) margin The maior elements j

involved in deducing these values. These values are consistent of the study were: (1) acquisition of data from a reference BWR; with values recommended by several European countnes for in.

(2) analysis of weld failure frequencies to estimate the LOCA dividual doses in the region of 1 mSv/y (100 mrem /y) Below frequency; (3) development of BWR debns generation and this dose rate, most countnes have values a factor of 7 to 10 debns transport models; (4) modeling debns transport in the lower, based on the assumption that society is less concemed suppression pool. (5) estimation of strainer blockage frequency with fatality nsks below about 10(-4)/y.

and loss of NPSH margin; and (6) estimation of core damage frequency attnbutable to a loss of ECCS foilowing a large NUREG/CR-6213: HIGH-TEMPERATURE HYDROGEN-AIR-LOCA. A point estimate overall DEGB pipe break frequency (per STEAM DETONATION EXPERIMENTS IN THE BNL SMALL-Rx year) of 1.6E-04 was calculated with a corresponding overall SCALE DEVELOPMENT APPARATUS. CICCARELLI.G.;

DCCS loss of NPSH frequency (per Rx year) of 1.5E 04. The GINSBURG,T.; BOCCIO.J.; et al. Brookhaven National Labora-point estimate of core damage frequency (per Rx year) due to tory. August 1994 99pp. 9409230300. BNL-NUREG-52414-blockage-related accident sequences for the reference plant 81011-001.

ranged from 4.2E-06 to 2 SE-05. The results of this study show The Small-Scale Development Apparatus (SSDA) was con-that severe strainer blockage and loss of NPSH can occur structed to provido a preliminary set of expenmental data to within the first 30 minutes of the LOCA if particulates are charactenze the effect of temperature on the ability of hydro-present in addition to the LOCA generated debns This study it-gen-air steam mixtures to undergo detonations and, equally im-lustrates the Competing effects of debns settling versus turbu-portant, to support design of the larger scale High-Temperature lence effects, which can take place in the suppression pool.

Combustion Facihty (HTCF) by providing a test bed for solution of a number of high-temperature design and operational prob-NUREG/CR-6233 V01: STABILITY OF CRACKED PIPE UNDER lems. The SSDA, the central element of which is a 10-cm inside INERTIAL STRESSES Subtask 1.1 Final Report SCOTT P.M.;

diameter,61 m long tubular test vessel designed to permit det-WILSON.M.; OLSON R.J.; et al. Battelle Memonal Institute, Co.

onation expenments at temperatures up to 700K, was employed lumbus Laboratones August 1994.195pp. 9409260057. BMI-to study self-sustained detonations in gaseous mixtures of hy.

2177. B1043 001.

drogen, air, and steam at temperatures between 300K and This report presents the results of the pipe fracture experi-650K at a fixed initial pressure of 0.1 MPa. Detonation cell size ments, analyses, and matenal characten2ation efforts performed measurements provide clear evidence that the effect of hydro-within Subtask 1.1 of the IPIRG Program. The objectwe of Sub-gen-air gas mwture temperature, in the range 300K 650K, is to task 1.1 was to experimentally venfy the analysis methodologies decrease cell size and, hence to increase the sensitivity of the for circumferentially cracked pipe subjected pnmarily to inertial mixture to undergo detonations The effect of steam content, at stresses. Eight cracked pipe expenments were conducted on 6-any given temperature, is to increase the cell size and. thereby, anch nominal diameter TP304 and A1068 pipe. The expenmen-to decrease the sensitivity of stoichiometnc hydrogen-air mix-tal procedure was developed using nonlinear time-history finite tures The hydrogen-air detonability limits for the 10-cm inside element analyses which included the nonlinear behavior due to diameter SSDA test vessel, based upon the onset of single-the crack. The model did an excellent Job of predicting the dis-

15 Miin Cit:ti:ns and Abstracts placements, forces. and times to maximum moment. The com-shifts to higher frequencies, while the response of tanks /ves-panson of the expenmen%i loads to the predicted loads by the sels depended rnainly on their support conditions. The evalua-Net-Section-Collapse (hZ), Dimensionless Plastic Zone Pa-tion of various piping support configurations demonstrated that rameter, J-estimation schemes, R6, and ASME Section XI in-proper system design (for a given spectrum) rather than number service Haw assessment crrena tended to underpredict the of supports or system stiffness is important to hmiting pipe measured bending moments except for the NSC analysis of the stresses Fiping at loads exceeding the DBE eightfold still had A1068 pipe. The effects of ilaw geometry and loading history significant margins and failure is improbable in spite of multiple on toughness were evaluated by calculating the toughness from support failures. The mean value for pipe damping, even under the pipe tests and companng these results to C(T) values.

extreme loads, was found to be about 4% Companson of knear These effects were found to be vanable. The surface crack ge-and nonlinear computational results with piping response meas-ometry tended to increase the toughness (relative to C(T) re-urements showed that predictions have a wide scatter and do sults), whereas a negative load ratio significantly decreased the not necessanly yield conservative responses underpredicting, in TP304 stainless steel surface-cracked pipe apparent toughness particular, peak support forces. For the soil / structure system The inertial expenments tended to achieve complete failure the quality of the predictions did not depend so much on the within a few cycles after reaching maximum load in these rela-complexity of the modehng. but rather on whether the model tively small diameter pipe expenments Hence, a load-controlled captured the sahent features and nonhneanties of the system.

fracture mechanics Nysis may be more appropnate than a displacement-contr<

analysis for these tests NUREG/CR-6237

STATISTICAL ANALYSIS OF FATIGUE NUREG/CR-6234: VALIDATION OF ANALYSIS METHODS FOR STRAIN-LIFE DATA FOR CARBON AND LOW-ALLOY STEELS.

ASSESSING FLAWED PIPING SUBJECTED TO DYNAMIC KEISLER.J.; pHOPRA,0 K ; SHACK,W.J. Argonne National Lab-LOADING OLSON R J ; WOLTERMAN,R L, WILKOWSKI,G M ;

oratory. August 1994. 52pp. 9409260059 ANL-94 /21 8 43M et al. Battelle MemonalInstitute Columbus Laboratones. August 1994 68pp 9409060227. ANL-94/22 80785 028.

The existing fatigue strain vs life (S N) data, foreign and do-Argonne National Laboratory and Battelle have pntly con-mestic, for camon and lomaHoy sWs M in N consuum ducted a research program for the USNRC to evaluate the abih-of nuclear power plant components have been compiled and ty of current engineenng analysis methods and one state-of-the-categorized according to matenat, loading, and environmental art analysis method to predict the behavior of circumferentially conditions A statistical model has been developed for estimat-surface cracked pipe system water-hammer expenments. The ing the effects of the vanous test conditions on fatigue life. The expenmental data used in the evaluahon were from the HDR results of a ngorous statistical analysis have been used to esti-Test Group E31 senes conducted by the Kernforschungszen.

mate the probability of initiating a fatigue crack. Data in the liter-trum Karlsruhe (kfK) in Germany. The incentive for this evalua.

ature were reviewed to evaluate the effects of sire, geometry, tion was that simphfied engineenng methods, as well as newer and surface finish of a component on its fatigue hfe. The fatigue

" state-otthe art" fracture analysis methods, have been typically 6-N curves for components have been determined by applying vahdated only with static expenmental data Hence these dy.

design margins for size, geometry, and surface finish to crack namic expenments were of high interest High-rate dynamic initiation curves estimated from the model. The significance of loading can be classified as either repeating, e g, seismic, or the effect of environment on the current Code design cerve and nonrepeating e.g. water hammer Development of expenmental on the proposed intenrn design curves for carbon and low-alloy data and validation of cracked pipe analyses under seismic steels presented in NUREG/CR-5999 is discussed.

loading (repeating dynamic loads) are being pursued separately within the NRC s international Piping Integnty Research Group NUREG/CR-6250:

SUMMARY

OF COMMENTS RECEIVED ON (IPIRG) program This report desenbed developmental and vali-STAFF DRAFT PROPOSED RULE ON RA'ilOLOGICAL CRITE-dation efforts to predict crack stabihty under water-hammer R!A FOR DECOMMISSIONING. CAPLIN,J.; ' AGE,G.; SMITH.D.;

loading. as well as compansons using currently used analysis et al. Advanced Systems Technology, Inc. August 1994.123pp.

procedures Current fracture analysis methods use the elastic 9409060247. 80786 001 stress analysis loads decoupled from the fracture mechanics The Nuclear Regulatory Commission (NRC) is conducting an analysis, while state-of the-art methods employ nonhnt3r enhanced participatory rulemaking to estabhsh radiological ente-cracked pipe time history finite element analyses The results ria for the decommissioning of NRC-licensed facilities. The NRC showed that the currtent decoupled methods were conservative obtained comments on the scope, issues, and approaches in their predictions. whereas the cracked pipe finite element through a senes of workshops (57 FR 58727), Genenc Environ-mental Impact Statement (GEIS) scoping meetings (58 FR analyses were more accurate, yet slightly conservative. The nonhnear time. history cracked pipe finite element analyses con, 33570), a dedicated electronic bulletin board system (50 FR ducted in this program were also attractive in that they were 37760), and written submissions. A summary of workshop and done on a small Apollo DN5500 workstation, whereas other scope-meeting comments was pubhshed as NUREG/CR-6156.

cracked pipe dynamic analyses conducted in Europe on the On February 2,1994, the Commission pubhshed in the Federal same expenments required the use of a CRAY2 supercomputer, Register (59 FR 4868) a notice that the NRC staff had prepared and were less accurate.

a " staff draft" proposed rule on radiological enteria for decom-missioning Copies of the staff draft were distributed to the NUREG/CR-6236: SEISMIC INVESTIGATIONS OF THE HDR Agreement States, participants in the earher meetings, and SAFETY PROGRAM Summary Report MALCHER L.;

other interested parties for comment. This report summanzes SCHRAMMEL.D.; STEINHILBER H : et al. Germany, Federal the comments identified from the 96 docketed letters received Republic of August 1994 95pp 9409060242 ANL-94 /20.

on the staff draft. No analysis or response is included in this 80785.249.

report. The comments reflect a broad spectrum of viewpoints.

The pnmary objective of the seismic investigations, performed Two subjects on which the commenters were in general agree-at the HDR facihty in Kahl/ Main, FRG was to vahdate calcula-ment were (1) that the enhanced participatory rulemaking tional methods for the seismic evaluation of nuclear reactor sys-should proceed, and (2) that the forthcoming GEIS and guid-tems, using expenmental data from an actual nuclear plant.

ance documents are needed for better understanding of the Using eccentne mass shaker excitation the HDR soil / structure draft rule system was tested to incipient f ailure, exhibitsng highly nonhnear response and demonstrating that structures not seismically de-NUREG/CR-6252: LESSONS LEARNED FROM THtE THREE signed can sustain loads equivalent to a design basis earth.

MILE ISLAND-UNIT 2 ADVISORY PANEL, LACH.D.;

quake (DBE) Load transmission from the structure to piping /

BOLTON.P.; DURBIN,N.; et al. Batte!Ie Seattle Research equipment indicated significant response amphfications and Center. August 1994. 53pp. 9409060253 PNL-9871. 80786:124.

16 M in Citatirns and Abstracts In response to public concern about the cleanup of the Three This document presents a top level dasign of an Open Archi-Mile Island, Unit 2 (TMI-2) facility after an accident on March tecture Seismic Monitonng (OASM) system intended to auto-28, 1979 involving a loss of reactor coolant and subsequent matically mcnitor local and regional seismic activities. The damage to the reactor fuel, twelve cit >zens were asked to serve system is designed to process single and three component data on an independent Advisory Panel to consult with the Nuclear similar to those recorded by the U S National Seismic Network i

Regulatory Commission (NRC) on the decontamination and and local stations operated by academic and research institu-cleanup of the facility. The panel met 78 times over a period of tions. The main components of the system are time senes proc-E thirteen years, holding public meetings in the vicinity of TMI-2 essing, event formation, event classification, and hazard as-and meeting regularly with NRC Commissioners in Washington, sessment. These fully independent modules are complemented D C. This report desenbes the results of a project designed to by operational and research databases Signal detection, onset identify and descnbe the lessons learned from the Advisory Panel and place those lessons an the context of what we gener-time estimation and signal charactenzation are functions of the ally know about citizen advisory groups. A summary of the em-time senes module. Signal association and event location are pocal literature on cit: zen advisory panels is followed by a bnef erformed in the event formation module. The seismic source is history of the TMI-2 Advisory Panel The body of the report con-charactenzed in the event classification module. The seismic tains the analysis of the lessons learned, preliminary conclu-hazard assessment module estimates basic parameters for use sions about the effectiveness of the Panel, and implications for m seismic nsk analysis. The operational database acts as the the NRC in the use of advisory panels. Data for the report in-central faCality through which access to the seismic data and clude meeting transcnpts and interviews with past and present communication between the system s modules are accom-Panel participants.

phshed. The function of the research database is to provide a

• " " " * *9 *"

NUREG/CR-6254: SOUTHERN APPALACHIAN RECT IAL SEIS-MIC NETWORK. CHlU.S-C.C.; JOHNSTON.A.; CL ' M. Mem-NUREG/GR-0013: APPLICATIONS OF A NEW MAGNETIC MON-phis State Univ, Memphis, TN August 94 81pp ITORING TECHNIOUE TO IN SITU EVALUATION OF FATIQUE 9409230288. 81010 035 DAMAGE IN CERROUS COMPONENTS.

JILES.D C.;

Memphis State University has monitored tne sesmicity of the BlNER.S B ; GOVINDARAJU,M.; et al lowa State Univ, Ames, southern Appalachian area since late 1979 by means of the IA June 1994 41pp 94072502B6. 80328195-Southern Appalachian Regional Seismic Network (SARSN),

which has provided good spatial coverage for earthquake loca-The work undertaken in this project consisted of research into tion Activity is more heavily concentrated in the Valley and the use of magnetsC inspection methods for the estimation of fa-Ridge province (VR) of eastern Tennessee than in the Blue tigue hfe of nuclear pressure vessel steel The rationale for this Ridoe (ER) or Piedmont (P). The major:ty of these events lie be.

work was that the mechanical and magnetic properties of ferro-tween the New York-Alabama and the Clingman/Ocoee linea-magnetic matenals are closely interrelated, and therefore the monts, magnetic anomalies of deep-seated baseinent struc.

measurements of the magnetic properties could be used to tures Thus, SARSN has been able to define the first order monitor the evolution of fatigue damage in these specimens as charactenstics of the Southern Appalachian seismic zone. The they were subjected to Cyclic loading The results of the work focal depths of the earthquakes are concentrated between 8 have shown that it is possible to monitor the fatigue damage and 16 km, pnncipally beneath the Appalachian overthrust in nondestructively by magnetic techniques For example, in load-Cross section the average seismicity is shallower beneath the controlled high cycle fatigue tests, it has been found that the BR and P provinces than the VR and North American craton plastic strain and coercivity accumulate loganthmically dunng Results of focal mechanism studies for events that occurred be-the fatigue process. Thus a quantitative relationship between tween October 1986 and December 1991, indicate that the coercivity and the number of fatigue cycles could be established basement of the VR province is under honzontal, NE-SW com-based on two empincal coefficients, which can be determined pressive stress Right-lateral stnke-slip faulting on nearly N S from the test conditions and matenal properties. Also it was faults is preferred as it agrees with tne trend of the regional found that prediction of the onset of fatigue failure in steels was magnetic anomaly pattern possible under certain conditions in strain-controlled low cycle NUREG/CR-6255: DESIGN OF AN OPEN ARCHITECTURE SEIS.

fatigue, entical changes in Barkhausen emissions. coerCivity and MIC MONITORING SYSTEM GHAllB.H A.; LEONARD.S K.;

hysteresis loss occurred in the last ten to twenty percent of fa-KRAFT,G D

ENSCO, Inc September 1994 125pp.

tigue hfe 9410060315 DCS-94-024 81223 235 l

Secondary Report Number Index This index lists, in alphabetical order, the performing organization-issued report codes for the NRC contractor and international agreement reports in this compilation. Each code is cross-r@ferenced to the NUREG r: umber for the report and to the 10-digit NRC Document Control System accession number.

SECONDARY REPORT NUMBER REPORT NUMBER SECONDARY REPORT NUMBER REPORT NUMBER ANL-93/22 NUREG/CR-4513 Rot EGG-2596 NUREG/CR-5535 V07 ANL-94 /18 NUREG/CR4168 EGG 2716 NUREG/CR-6116 V01 ANL-94/20 NUREG/CR4236 EGG-2716 I4UREG/CR4116 V02 ANL-94/21 NUREG/CR-6237 EGG-2716 NUREG/CR-6116 V03 QNL-94/22 NUREG/CR-6234 EGG-2716 NUREG/CR-6116 V04 CML 94/3 NUREG/CR-6183 EGG-2716 NUREG/CR 6116 V05

,$ h ANL/EES-TM 364 NUREG/CR-5344 ROI BMi-2164 NUREG/CR4128 R01 EGG-2717 NUREG/CR4121 BMI 2177 NUREG/CR-6233 V01 EGG-2742 NUREG/CP-0137 V02 BMI-2178 NUREG/CR-6234 EGG-2742 NUREG/CP-0137 V01 BNL-NUREG 52288 NUREG/CR-5726 KFK/PHDR 99E 91 NUREG/CR4236 i

BML-NUREGS2333 NUREG/CR 5908 V02 ORNL/TM-11568 NUREG/CR4591 V02 N1 i

BML NUREG-52333 NUREG/CR 5908 V01 ORNL/TM-126if3 NUREG/CR-6206 BNL NUREG-52388 NUREG/CR4093 ORNL/TM-9593 NUREG/CR 4219 V10 N1 BNL-NUREG42396 NUREG/CR-6128 ORNLSUB79-77789 NUREG/CR-5861 6

BNL-NUREG-52399 NUREG/CR-6144 V02P1 A PNL 5210 NUREG/CR-3950 V09 BNL-NUREG 52399 NUREG/CR-6144 V02P1B PNL4462 NUREG/CR4973 RO' 3NL-NUREG 52399 NUREG/CR4144 V02P2 PNL-8912 NUREG/CR 6151 BNL-NUREG-52399 NUREG/CR-6144 V02P3A PNL-9020 NUREG/CR-6181 BNL-NUREG 52399 NUREG/CR4144 V02P3B PNL-9871 NUREG/CR4252 BNL-NUREG-52399 NUREG/CR-6144 V02P4 PNL-9985 NUREG/CR-5758 V04 i

BML NUREG-52399 NUREG/CR-6144 V02P5 SAND 931804 NUREG/CR-6093 i

BML-NUREG 52399 NUREG/CR-6144 V03 P1 A

6 V

BNL NUREG42399 NUREG/CR4144 V03 P2 SAND 93 2440 NUREG/CR-6143 V02P1C BNL NUREG-52399 NUREG/CR-6144 V04 SAND 93-2440 NUREG/CR4143 V02PT2 I

BNL-NUREG 52413 NUREG/CR4212 SAND 93-2440 NUREG/CR4143 V02PT3 BNL NUREG424l4 NUREG/CA-6213 SAND 93-2440 NUREG/CR-6143 V02PT4 BSRC-700/94/016 NUREG/CR-5758 V04 SAND 93-2440 NUREG/CR4143 V03 BSRC-800/94/014 NUREG/CR-6252 SAND 93-2440 NUREG/CR-6143 V04 CMWRA 93 013 NUREG/CR4178 SAND 93 2519 NUREG/CR-6152 DCS 94 024 NUREG/CR 6255 SAND 94-0731 NUREG/CR-6218 EGG 2458 NUREG/CR-4639 V5R4P3 SEA 93454-06 A1 NUREG/CR-6224 ORF FC EGG-2458 NUREG/CR-4639 V5R4P2 UILU-ENG93-2014 NUREG/CR-6162 i

4 l

6 i

17

)

I b

i m

J_

r

.N

_..i e

Personal Author Index 4

i This index lists the personal authors of NRC staff, contractor, and international agreement t

reports in alphabetical order. Each name is followed by the NUREG number and the title of tha report (s) prepared by the author. If further information is needed, refer to the main cita-

{

tion by the NUREG number.

l AHMAD.J.

ternal Events For Plant Operatonal State 5 Dunng A Refuehng NUREG/CR-5128 RO1: EVALUATION AND REFINEMENT OF LEAK.

Outage Section 10.

RATE ESilMATION MODELS_

NUREG/CR4143 V02P1C: EVALUATION OF POTENTIAL SEVERE AC-C CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT AHOLA,M.P.

GRAND GULF, UNIT 1. Analysis Of Core Damage Frequency From in-NUREG/CR.6178. LABORATORY CHARACTERIZATION OF ROCK tornal Events For Plant Operational State 5 Dunng A Refuehng JOINTS Outage Main Report.

ALLEN,M.D.

BEYER C.E NUREG/CR4152: EXPERIMENTS TO INVESTIGATE DIRECT CON-TAINMENT HEATING PHENOMENA WITH SCALED MODELS OF THE NUREG/CR-3950 V09. FUEL PERFORMANCE REPORT FOR 1991.

SURRY NUCLEAR POWER PLANT.

BEZLER,P.

ALVIS,J.M NUREG/CR-6128: PIPING BENCHMARK PROBLEMS FOR THE ABB/

NUREG/CR-3950 V09. FUEL PERFORMANCE REPORT FOR 1991-CE SYSTEM 80+ STANDARDIZED PLANT.

ANDERSON.T.L BINDER,J.L NUREG/CR4162: EFFECTS OF PRIOR DUCTILE TEARING ON CLEAV-NUREG/CR4168. DIRECT CONTAINMENT HEATING INTEGRAL EF.

AGE FRACTURE TOUGHNESS IN THE TRANSITION REGION FECTS TESTS AT 1/40 SCALE IN ZION NUCLEAR POWER PLANT GEOMETRY.

ANKRUM,A.R.

NUREG/CR-5973 Rol: CODES AND STANDARDS AND OTHER GUID-BINER,S.B.

ANCE CITED IN REGULATORY DOCUMENTS.

NUREG/GR 0013: APPLICATIONS OF A NEW MAGNETIC MONITOR-ING TECHNIQUE TO IN SITU EVALUATION OF FATIQUE DAMAGE ASCARI.M.

IN FERROUS COMPONENTS.

I NUREG/CR-6206: TRANSPORT CALCULATIONS OF RADIATION EX-

"OSURE TO VESSEL SUPPORT STRUCTURES IN THE TROJAN RE.

BLANCHAT,T.K.

ACTOR.

NUREG/CR4152' EXPERIMENTS TO INVESTIGATE DIRECT CON-TAiNMENT HEATING PHENOMENA WITH SCALED MODELS OF THE ATWOOD,C.L SURRY NUCLEAR POWER PLANT.

NUREG/CR-6116 V01: SYSTEMS ANALYSIS PROGRAMS FOR HANDSON INTEGRATED REllABILITY EVALLATIONS (SAPHIRE)

BLEY,D.

VERSION 5.0. Technical Reference Manual, NUREG/CR-6144 V02P1 A. EVALUATION OF POTENTIAL SEVERE AC-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT BAKER C.C.

SURRY, UNIT 1. Analysis Of Core Damage Frequency From Internal NUREG/CR.6908 V02: ADVANCED HUMAN-SYSTEM INTERFACE Events Dunng Md-Loop Operatons Main Report (Chapters 16)

DESIGN REVIEW GUIDELINE. Evaluaton Procedures And Gudehnes NUREG/CR-6144 V02P18: EVALUATION OF POTENTIAL SEVERE AC.

For Human Factors Engineenng Reviews, CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT BARCHI,T.

SURRY, UNIT 1. Analysis Of Core Damage Frequency From Internal Events Dunng Mid-Loop Operatons Main Report (Chapters 712L F

NUREG 1415 V06 NO2: OFFICE OF THE INSPECTOR NUREG/CR 6144 V02P2: EVALUATION OF POTENTIAL SEVERE ACCl-GENERALSemiannual Report,0ctober 1,1993 - March 31,1994.

DENTS DURING LOW POWEFI AND SHUTDOWN OPERATIONS AT I

SURRWN41.Anahsis Of Core Damage Frequency From Internal BARRIERE M'4093 AN ANALYSIS OF OPERATIONAL EXPERIENCE NUREG/CR b2 A A

T Tl NTIAL SEVERE AC-NU C

144 DURING LOW POWER AND SHUTDOWN AND A PLAN FOR AD-DRESSING HUMAN RELIABILITY ASSESSMENT ISSUES.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SURRY. UNIT 1. Analysts Of Core Damage Frequency From Internal CASSETT,R.L Events Dunng M4-Loop Operatons Appendices E (Sectons E.1-E 8).

NUREG/CR4203: VAllDATION STUDIES FOR ASSESSING UNSATU-NUREG/CR4144 V02P3B. EVALUATION OF POTENTIAL SEVERE AC-RATED FLOW AND TRANSPORT THROUGH FRACTURED ROCK.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SURRY. UNIT 1. Analysis Of Core Damage Frequency From internal CAUM.J.W.

Events Dunng Md-Loop Operatons.Apperdices E (Sectons E.9.E.16).

NUREG/CR4212: VALLE OF PUBLIC HEALTH AND SAFETY ACTIONS NUREG/CR4144 V02P4: EVALUATION OF POTENTIAL SEVERE ACCl-AND RADIATION DOSE AVOIDED.

DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SURRY. UNIT 1. Analysis Of Core Damage Frequency From Internal BEATY,R.

Events Dunng Md-Loop Operatons. Appendices F.H NUREG/CR4224 DRF FC-PARAMETRIC STUDY OF THE POTENTIAL NUREG/CR4144 V02P5: EVALUATION OF POTENTIAL SEVERE ACCl.

FOR BWR ECCS STRAINER BLOCKAGE DUE TO LOCA GENERAT.

DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT ED DEBRIS. Draft For Comment.

SURRY. UNIT 1 Analysis Of Core Damage Frequency From internal Events Dunng Mid-Loop Operatons Appendices L NUREG/CR4143 V02P1 A: EVALUATION OF POTENTIAL SEVERE AC-BOCCIO.J.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR 6213:

HIGH. TEMPERATURE HYDROGEN.AlR-STEAM GRAND GULF UNIT 1. Analysis Of Core Damage Frequency From In-DETONATION EXPERIMENTS IN THE BNL SMALL SCALE DEVELOP.

ternal Events For Plant Operatonal State 5 Dunng A Refuehng MENT APPARATUS Outage Sect ons 1-9 NUREG/CR4143 V02P18. EVALUATION OF POTENTIAL SEVERE AC.

BOHL.R.W.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR-6183: PEER REVIEW OF THE TMI 2 VESSEL INVESTIGA-GRAND GULF, UNIT 1. Analysis Of Core Damage Frequency From in.

TION PROJECT METALLURGICAL EXAMINATIONS.

19 w

r-

20 Personal Author index BOHN,M.P.

BUDNITZ,R.J.

NUREG/CR-5726 REVIEW OF THE DIABLO CANYON PROBABILISTIC NUREG/CR-6143 VOS: EVALUATION OF POTENTIAL SEVERE ACCl-R)SK ASSESSMENT.

DENTS DURING LOW POWER AND SHUTDOWN OPERATONS AT BOLTON,P.

GRAND GULF, UNIT 1. Analysis Of Core Damage Frequency From Seisme Events Dunng Md Loop Operatons Main Report.

NUREG/CRs t. LESSONS LEARNED FROM THE THREE MILE NUREG/CR4144 V05. EVALUATON OF POTENTIAL SEVERE ACCI-ISLAND-UNIT 2 ADVISORY PANEL DENTS DURING LOW POWER AND SHUTDOWN OPERATONS AT SURRY. UNIT 1. Analysis Of Core Damage Frequency From Seisme n

unng WW Wons hn Re UREG 07 HUMAN FACTORS ENGINEERING PROGRAM REVIEW MODEL CAPLIN.J.

NUREG/CR4250:

SUMMARY

OF COMMENTS RECEIVED ON STAFF NURE /C 5726: REVIEW OF THE DIABLO CANYON PROBABILtSTIC M SS ON G RISK ASSESSMENT.

NUREG/CR4144 V02P1 A: EVALUATION OF POTENTIAL SEVERE AC-CARDILE,F.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG 1500: WORKING DRAFT REGULATORY GUOE ON RELEASE SURRY. UNIT 1.Anatysis Of Core Damage Frequency From internal CRITERIA FOR DECOMMISSIONING NRC STAFF'S DRAFT FOR Events Dunng M4 Loop Operatons Main Report (Chapters 14)

COMMENT' NUREG/CR-6144 V02PIB. EVALUATION OF POTENTIAL SEVERE AC.

COENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT CARLSON,0.E.

SURRY. UNIT 1. Analysis Of Core Damage Frequency From internal NUREG-1502: ASSESSMENT OF DATABASES AND MODELING CAPA-Events Dunng M4 Loop Operations Main Report (Chapters 712)

BILITIES FOR THE CANDU 3 DESIGN.

NUREG/CR4144 V02P2. EVALUATION OF POTENTIAL SEVERE ACCl-DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT CELIA.M.A.

SURRY. UNIT 1. Analysis Of Core Damage Frequency From Internal NUREG/CR-5965: MODELING FIELD SCALE UNSATURATED FLOW Events Dunng Mid-Loop Oper*tions Appendices A-D.

AND TRANSPORT PROCESSES.

NUREG/CR4144 V02P3A: EVALUATION OF POTENTIAL SEVERE AC-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT CHEN,Z.J.

SURRY. UNIT 1. Analysis Of Core Damage Frequency From Internal NUREG/GR-0013. APPLICATONS OF A NEW MAGNETIC MONITOR.

Events Dunng M4 Loop Operatens Appendices E (Sectons E 1 E 8).

ING TECHNIQUE TO IN SITU EVALUATION OF FATIOUE DAMAGE NUREG/CR4144 V02P38. EVALUATION OF POTENTIAL SEVERE AC-Irv.7RROUS COMPONENTS CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SURRY. UNIT 1. Analysis Of Core Damage Frequency From Intemal CHlU,J M.

Events Dunng M4 Loop Operatons. Appendices E (Sections E 9-E.16)

NUREG/CR-6254 SOUTHERN APPALACHIAN REGIONAL SEISMIC NUREG/CR4144 V02P4. EVALUATION OF POTENTIAL SEVERE ACCl-NETWORK.

DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SURRY. UNIT 1. Analysis Of Core Damage Frequency From internal CHlu,S-C.C.

Events Dunng M4 Loop Operatons Appendices F-H NUREG/CR.6254. SOUTHERN APPALACHIAN REGIONAL SEISMIC NUREG/CR4144 V02P5 EVALUATION OF POTENTIAL SEVERE ACCI.

NETWORK.

DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SURRY. UNIT 1. Analyses Of Core Damage Frequency From Internal CHOPRA.O.K.

Events Dunng M4 Loop Operatons. Appendices 1.

NUREG/CR 4513 ROI: ESDMATION OF FRACTURE TOUGHNESS OF CAST STAINLESS STEELS DURING THERMAL AGING IN LWR SYS-BRAVERMANJ.

TEMS.

NUREG/CR4128 PIPING BENCHMARK PROBLEMS FOR THE ABB/

NUREG/CR-6237. STATISTICAL ANALYSIS OF FATIGUE STRAIN LIFE CE SYSTEM 80+ STANDARDIZED PLANT.

DATA FOR CARBON AND LOW-ALLOY STEELS.

BRIDEAU,J.

CHOWDHURY,A.H.

NUREG/CR4224 DRF FC: PARAMETRIC STUDY OF THE POTENTIAL NUREG/CR-6178: LABORATORY CHARACTERIZATION OF ROCK FOR BWR ECCS STRAINER BLOCKAGE DUE TO LOCA GENERAT.

JOINTS.

ED DEBRIS. Draft For Comment.

CHu,T.L BROWN C.

NUREG/CR-6144 V02P1 A: EVALUATION OF POTENTIAL SEVERE AC.

NUREG 1504 REVIEW CRITERIA FOR THE PHYSICAL FITNESS CIDENTS DURING LOW POWER Ai40 SHUTDOWN OPERATIONS AT TRAIN!NG REQUIREMENTS IN 10 CF PART 73 SURRY, UNIT 1. Analysis Of Core Damage Frequency From Intemal Ekar;ts Dunng M4 Loop Operations Main Report (Chapters 16)

BROWN,T.

NUREG/CR-6144 V02P18. EVALUATION OF POTENTIAL SEVERE AC-NUREG/CR4143 V02P1 A' EVALUATION OF POTENTIAL SEVERE AC-COENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT CIDENTS DURING LOW POWER AND SHUTDOWN OPERATONS AT SURRY, UNIT 1. Analysis Of Core Damage Frequency From Intnmal GRAND GULF. UNIT 1. Analysis Of Core Damage Frequency From In-Events Dunng M4 Loop Operatons Maen Report (Chapters 712).

temal Events For Plant Operational State 5 Dunng A Refuehng NUREG/CR-6144 V02P2. EVALUATON OF POTENTIAL SEVERE ACCI-Outage Sectons 19 DENTS DURING LOW POWER AND SHUTDOWN OPERATONS AT NUREG/CR4143 V02P18. EVALUATION OF POTENTIAL SEVERE AC-SURRY. UNIT 1. Analysis Of Core Damage Frequency From intemal COENTS DURING LOW POWER AND SHUTDOWN OPERATONS AT Events Dunng M4 Loop Operatons. Appendices A D GRAND GULF. UNIT 1. Analysis Of Core Damage Frequency From In-NUREG/CR-6144 V02P3A: EVALUATION OF POTENTIAL SEVERE AC-temal Events For Plant Operatonal State 5 Dunng A Refueling CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT Outage Secten 10 SURRY. UNIT 1. Analysis Of Core Damage Frequency From Intemal NUREG/CR4143 V02PIC: EVALUATION OF POTENTIAL SEVERE AC-Events Dunng M4 Loop Operatons Appendees E (Sectons E.1-E 8)

COENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR4144 V02P38-EVALUATION OF POTENTIAL SEVERE AC-GRAND GULF, UNIT 1 Anal sis Of Core Damage Frequency From in.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT

/

temal Events For Plant Operatonal State 5 Dunng A Refusting SURRY. UNIT 1. Analyses Of Core Damage Frequency From Intemal Outage Main Report Events Dunng M4 Loop Operatons Appendices E (Sectons E.9-E.16)

NUREG/CR-6143 V02PT4 EVALUATION OF POTENTIAL SEVERE AC-NUREG/CR-6144 V02P4 EVALUATION OF POTENTIAL SEVERE ACCl-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATONS AT DENTS DURING LOW POWER AND SHUTDOWN OPERATONS AT GRAND GULF. UNIT 1.Aralyses Of Core Damage Frequency From In-SURRY. UNIT 1. Analysis Of Core Damage Frequency From Intemal temat Events For P' ant Operatonal State 5 Dunng A Refuehng Events Dunng M4 Loop Operatons. Appendices F.H Outage intemal..

NUREG/CR-6144 V02P5 EVALUATION OF POTENTIAL SEVERE ACCl-DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT BROWN.W.S.

SURRY UNIT 1 Analysis Of Core Damage Frequency From intemal NUREG/CR-5908 V02. ADVANCED HUMAN-SYSTEM INTERFACE Events Dunng M4 Loop Operatons Appendeces I DESIGN REVIEW GUIDELINE Evaluaton Procedures And Guidehnes NUREG/CR-6t44 V03 P1: EVALUATION OF POTENTIAL SEVERE AC-For Human Factors Engmenng Reviews CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT y

Personal Author Index 21 SURRY, UNIT 1.Analyms Of Core Damage Frequency From internal NUREG/CR-6144 V02P5: EVALUATION OF POTENTIAL SEVERE ACCI-Fres Dunng M4 Loop Operations Main Report DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR-6144 V03 P2: EVALUATION OF POTENTIAL SEVERE AC-SURRY. UNIT 1. Analysis Of Core Damage Frequency From Intemal CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT Events Dunng M4 Loop Operatons.ApWces 1.

SURRY, UNIT 1. Analysis Of Core Damage Frequency From internal Fres Dunng M4 Loop Operatons. Appendices.

DANIEL.S.

NUREG/CR-6143 V02P1A. EVALUATION OF POTENTIAL SEVERE AC-

^

N 6213.

HIGH-TEMPERATURE HYDROGEN. AIR. STEAM DETONATION EXPERIMENTS IN THE BNL SMALL-SCALE DEVELOP.

ternal Events 6 Rant Operatonal State 5 Dunng A RMing MENT APPARATUS Outage Sect ons 1-9 l

COLLINS,M.

NUREG/CR 6143 V02PIB: EVALUATION OF POTENTIAL SEVERE AC-I NUREG 1460 RO1: GUIDE TO NRC REPORTING AND RECORDKEEP-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT ING REQUIREMENTS. Compiled From Requirements in Title 10 Of GRAND GULF, UNIT 1.Analyms Of Core Da.nage Frequency From In-The U S. Code Of Federal Regulations As Codified On December 31, ternal Events For Plant Operatonal State 5 Dunng A Refuehng 1993' Outage Secton 10.

NUREG/CR-6143 V02PIC: EVALUATION OF POTENTIAL SEVERE AC-COMES,L CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR-6224 DRF FC: PARAMETRIC STUDY OF THE POTENTIAL GRAND GL'LF, UNIT 1, Analysis Of Core Damage Frequency From In-FOR BWR ECCS STRAINER BLOCKAGE DUE TO LOCA GENERAT.

temal Events For Plant Operatonal State 5 Dunng A Refuehng ED DEBRIS. Draft For Comment.

Outage. Main Report.

CORWIN,W.R.

DARBY,J, NUREG/CR-5591 V02 N1: HEAVY-SECTION STEEL IRRADIATION NUREG/CR-6143 V02P1 A. EVALUATION OF POTENTIAL SEVERE AC-PROGRAM. Semiannual Progress Report For October 1990 March CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT 1991.

GRAND GULF, UNIT 1. Analysis Of Core Damage Frequency From In-ternal Evems 6 Rant hatonal MaM 5 Dunng A Refuehng DAILY,M.C'500: WORKING DRAFT REGULATORY GUIDE ON RELEASE NUREG1 NU C 143 VU PIB: EVALUATION OF POTENTIAL SEVERE AC.

l CRITERIA FOR DECOMMISSIONING: NRC STAFF'S DRAFT FOR CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT COMMENT.

GRAND GULF, UNIT 1. Analysis Of Core Damage Frequency From In-DANDINI,V.

ternal Events For Plant Operatonal State 5 Dunng A Refuehng NUREG/CR-6143 V02P1 A: EVALUATION OF POTENTIAL SEVERE AC-Outage Secten 10.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR4143 V02P1C: EVALUATION OF POTENTIAL SEVERE AC-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT GRAND GULF, UNIT 1.Analyms Of Core Damage Frequency From In-ternal Events For Plant Operational State 5 Dunng A Refuehng GRAND GULF UNIT 1. Analysis Of Core Damage Frequency From In-

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Outage. Sections 1-9 temal Events For Ptsnt Operatonal State 5 Dunng A Refuehng NUREG/CR4143 V02P18. EVALUATION OF POTENTIAL SEVERE AC.

Outage Main Report.

CiDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR-6143 V02PT2: EVALUATION OF POTENTIAL SEVERE AC-GRAND GULF. UNIT 1.Analyms Of Core Damage Frequency From in.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT ternal Events For Plant Operational State 5 Eunng A Refuehng GRAND GULF. UNIT 1.Ar,alysis Of Cure Damage Frequency From In-Outage.Secton 10 temal Events For Plant Operatonal State 5 Dunng Refuehng j

NUREG/CR4143 V02P1C: EVALUATION OF POTENTIAL SEVERE AC-Outage intemeL.

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CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR-6143 V02PT3: EVALUATION OF POTENTIAL SEVERE AC.

GRAND GULF,UNii 1.Analyms Of Core Damage Frequency From in.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT temal Events For Plant Operationa! State 5 Dunng A Refuehng GRAND GULF. UNIT 1. Analysis Of Core Damage Frequency From In-Outage Man Report temal Events For Plant Operatonal State 5 Dunng A Refueling WUREG/CR4143 V02PT2 EVALUAllON OF POTENTIAL SEVERE AC-Outage Internal..

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR-6143 V02PT4. EVALUATION OF POTENTIAL SEVERE AC-GRAND GULF, UNIT 1. Analysis Of Core Damage Frequency From in.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATION 3 AT ternal Events For Plant Operational State 5 Dunng Refueling GRAND GULF, UNIT 1. Analysis Of Core Damage Frequency From In-Outage internal..

temal Events For Plant Operatonal State 5 Dunng A Refuehng NUREG/CR-6143 V04. EVALUATION OF POTENTIAL SEVERE ACCl-Outage.tntemaL DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT GRAND GULF. UNIT 1. Analysis Of Core Damage Frequency From In-DAVIDSON G.R.

tomally induced Flooding Events For Plant Opera 9onal State S Dunng NUREG/CR-6203: VALIDATION STUDIES FOR ASSESSING UNSATU-j a Refuehng..

RATED FLOW AND TRANSPORT THROUGH FRACTURED ROCK.

l DANG,V.

DAVIS,P.R.

l NUREG/CR-6144 V02PI A: EVALUATION OF POTENTIAL SEVERE AC-NUREG/CR-6143 V05: EVALUATION OF POTENTIAL SEVERE ACCl-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SURRY, UNIT 1.Analyss Of Core Damage Frequency From intemal GRAND GULF, UNIT 1.Analyss Of Core Damage Frequency From Events Dunno M4 Loop Operations Mam Report (Chapters 16)

Seismic Events Durmg M4 Loop Operations Main Report.

NUREG/CR4144 V02PIB. EVALUATION OF POTENTIAL SEVERE AC-NUREG/CR-6144 V05: EVALUATION OF POTENTIAL SEVERE ACCI-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SURRY, UNIT 1.Analyss Of Core Damage Frequency From Intemal SURRY, UNIT 1. Analysis Of Core Dama6e Freauency From Seismc Events Dunng M4 Loop Operatens Man Report (Chapters 7-12)

Events Dunng M4 Loop Operatons Main Report NUREG/OR4144 V02P2: EVALUATION OF POTENTIAL SEVERE ACCl-DENTS DURING LOW POWER AND SHUTDOWN OPERAllONS AT DEGRASSI,D.

l SURRY. UNIT 1. Analysis Of Core Damage Frequency From intemal NUREG/CR4128. PIPING BENCHMARK PROBLEMS FOR THE ABB/

Events Dunng MdLoop Operations Appendices A-D CE SYSTEM 80+ STANDARDIZED PLANT.

NUREG/CR-6144 V02P3A: EVALUATION OF POTENTIAL SEVERE AC-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT DIAMOND,D.J.

SURRY, UNIT 1. Analysis Of Core Damage Frequency From Intemal NUREG/CR4144 V02P1 A: EVALUATION OF POTENTIAL SEVERE AC.

Events Durmg M4 Loop Operations.Appendees E Sections E.1-E 8)

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT MUREG/CR4144 V02P38: EVALUATION OF POTE(NTIAL SEVERE AC-SURRY, UNIT 1 Analysis Of Core Damage Frequency From Intemal CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT Events Dunng M6 Loop Operatons Main Report (Chapters 14).

SURRY. UNIT 1.Analyss Of Core Damage Frequency From intamal NUREG/CR 6144 V02P10: EVALUATION OF POTENTIAL SEVERE AC-Events Dunno Mid-toop Operations Appendees E (Sections E 9-E.16.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR-6144 V02P4 EVALUATION OF POTENTIAL SEVERE ACC)-

l SURRY, UNIT 1.Anatysis Of Core Damage Frequency From Intemal DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT Events Dunng M4 Loop Operations Mam Report (Chapters 712).

SURRY. UNIT 1. Analysis Of Core Damage Frequency From Intemal NUREG/CR4144 V02P2: EVALUATION OF POTENTIAL SEVERE ACCI-Events Dunng Mid Loop Operatons.Appendcas F-H.

DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT

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22 Personal Author Index SURRY. UNIT 1 Analysis Of Core Damage Frequen6, From internat NUREGICR-6143 V02PT4 EVALUATION OF POTENTIAL SEVERE AC-Events Dunng M4 Loop Operations Appendices A-D.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR-6144 V02P3A. EVALUATION OF POTENTIAL SEVERE AC-GRAND GULF. UNIT 1 Analysis Of Core Damage Frequency From In-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT ternal Events For P! ant Operational State 5 Dunng A Refueling SURRY. UNIT 1. Analysis Of Core Damage Frequency From Internal Outage internal,

Events Dunng M4 Loop Operat ons Appendices E (Sections E 1-E 8)

NUREG/CR 6143 V04 EVALUATION OF POTENTIAL SEVERE ACC NUREGICR6144 V02P39. EVALUATION OF POTENTIAL SEVERE AC-DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS

.f CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT GRAND GULF. UNIT 1. Analysis Of Core Damage Frequency from +

SURRY UNIT 1. Analysis Of Core Damage Frequency From Internal ternally induced Flooding Events For Plant Operationai State 5 Dur ig Events Dunng M4 Loop O ations Appendices E (Sectr>ns E 9-E 16)

NUREG/CR-6144 V02P4 ENUATION OF POTENTIAL SEVERE ACCl-a Muehng _

DENTS DURING LOW POWER Aru) SHUTDOWN OPERATIONS AT ns dL Opee a ions e ce -

N REG /CR 5758 V04 FITNESS FOR DUTY IN THE NUCLE AR POWER NUREG/CR-6144 V02P5. EVALUATION OF POTENTIAL SEVERE ACCI.

INDUSTRY Annual Summary Of Program Performance Reports CY DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT 1993 SURRY. UNIT 1. Analysis Of Core Damage Frequency From internal Events Dunng M4 Loop Operations Appendices i GALLETTI.G.S.

NUREG0711 HUMAN FACTORS ENGINEERING PROGRAM REVIEW DIEFICKS.D.R.

MODEL NUREG/CR 6183 PEER REVIEW OF THE TMI-2 VESSEL INVESTIGA.

TION PROJECT METALLURGICAL EXAMINATIONS GALYE AN.W.J.

DOCTOR.S.

NUREG/CR 6116 VOI SYSTEMS ANALYSIS PROGRAMS FOR NUREG/CR 6181: A PILOT APPLICATION OF RISK-BASED METHODS HANDS-ON INTEGRAT ED REllABILITY EVALUATIONS (SAPHIRE)

TO ESTABLISH INSERVICE INSPECTION PRIORITIES FOR NUCLE.

VERSION 5 0 Technical Jeterence Manual AR COMPONENTS AT SURRY UNIT 1 NUCLEAR POWER STATION GAYDOS.R.G.

DODD3.R.H.

NUREG/CR 6183 PEER REVIEW OF THE TMI-2 VESSEL INVESilGA.

NUREG/CR 6162 EFFECTS OF PRIOR DUCTILE TEARING ON CLEAV-TION PROJECT METALLURGICAL EXAMINATIONS AGE FRACTURE TOUGHNESS IN THE TRANSITION REGION GE LH AR.LW.

/ R-5758 V04 FITNESS FOH DUTY IN THE NUCLEAR POWER N

C D

S R R SSE INDUSTRY Annual Summary Of Program Performance Reports CY N EG[CR 6213 HIGH-TEMPER ATURE HYDROGE N-AIR-ST E AM S ND UN T 2 ADV S R P DETONATION EXPERIMENTS IN THE BNL SMALL-SCALE DEVELOP.

ECKENRODE.R.J.

MENT APPARATUS NUREG-0711. HUMAN F AC10RS ENGINEERING PROGRAM REVIEW MODE L-GHAllB.H A.

NUREG/CR-6255 DESIGN OF AN OPEN ARCHITECTURE SEISMIC E CONOMOS.C.

MONITORING SYSTEM NUREG/CR 6213 HIGH TEMPERATURE HYDROGEN AIR-STEAM DETONATION EXPERIMENTS IN THE BNL SMALL SCALE DEVELOP.

GHOSH,A.

MENT APPARATUS NUREG/CR 6178 LABORATORY CHARACTERIZATION OF ROCK FADDEN.M.

JOINTS NUREG-0525 V02 R02 SAFEGUARDS

SUMMARY

EVENT LIST G

R G

(SSEL) January 1.1990 Through December 31 1993 FIELD.I.

ASSESSING REACTOR RELIABILITY (NUCLARR) Volume 5 Data NUREG/CR 5758 V04 FITNESS FOR DUTY IN THE NUCLEAR POWER Manual Part 2. Human Error Probabihty sHEP) Data 1

INDUSTRY Annual Summary Of Program Performance Reports CY NUREG/CR~4639 V5R4P3 NUCL EAR COMPUTERIZED LIBRARY FOR 1993 ASSESSING REACTOR REllABILITY (NUCLARR) Volume 5 Data Manual Part 3. Hardware Component Failure Data p

NUREG/CR 6213 HIGH-TE MPE R ATURE HYDROGEN A!R STEAM GINSBURG.T.

1 DETONATION EXPERIMENTS IN THE BNL SMALL-SCALE DEVELOP.

NUREG/CR-6213 HIGH TEMPERATURE HYDROGEN AIR STEAM MENT APPARATUS DETONATION EXPER!MENTS IN THE BNL SMALL-SCALE DEVELOP-FITZPATRICK.R.

MENT APPARATUS NUREG/CR 5726 REVIEW OF THE DIABLO CANYON PROBABILISTIC RISK ASSESSMENT GOODMAN.C.

FLANIGAN.LF.

MDL NUREG/CR 5128 ROI. EVALUATION AND REFINEMENT OF LEAK.

RATE ESTIMATION MODELS GORE.B F.

NUREG/CR-6151 FEASIBillTY OF DEVELOPING RISK-BASED RANK-

]

FORESTER.J INGS OF PRESSURE BOUNDARY SYSTEMS FOR INSERVICE IN-NUREG/CR 6143 V02P1 A EVALUATION OF POTE NTIAL SEVERE AC-SPECTION CIDE NTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR 6181. A PILOT APPLICATION OF RISK BASED METHODS GRAND GULF. UNIT 1 Analyses Of Core Damage Frequency From In-TO ESTABLISH INSERVICE INSPECTION PRIORITIEC FOR NUCLE.

tornal Events For Plant Operational State 5 Dunng A Refuehng AR COMPONENTS AT SURRY UNIT 1 NUCLEAR POWER ST ATION Outaje Sections 1-9 NUREu/CR-6143 V02P1B EVALUATION OF POTENTIAL SEVERE AC-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT GOVINDARAJU.M.

GRAND GULF, UNIT 1 Analysis Of Core Damage Frequency From in.

NUREG/GR-0013 APPLICATIONS OF A NE W MAGNETIC MONITOR-ternal Evens For Plant Operational State 5 Dunng A Refueling ING TECHNIOUE TO IN SITU EVALUATION OF F ATIOUE DAMAGE Outage Section 10 IN FERROUS COMPONENTS NUREG/CR 6143 V02PIC EVALUATION OF POTENTIAL SEVERE AC-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT GR ANDA,T.M.

GRAND GULF. UNIT t Analysis Of Core Damage Frequency From in-NURE G/CR 5908 V02 ADV ANCE D HUM AN-SYSTE M INTERFACE terna 5 vents For Plani Operationai State 5 Dunrg A Refuehng DESIGN REVIEW GUIDELINE Evc.luation Procedures And Gt.J hnes Outage Main Report Fn# Human Factors Engineenng Reviews

e Person:I Author index 23 l

GRANT,T.

HSIUNG,S.M.

NUREG/CR-5758 V04-FITNESS FOR DUTY IN THE NUCLEAR POWER NUREG/CR-6178 LABORATORY CHARACTERIZATION OF ROCK INDUSTRY Annual Summary Of Program Performance Reports CY JOINTS 1993 NR /CR-6144 V02P1 A: EVALUATION OF POTENTIAL SEVERE AC-NUREG/C' 5758 V04 FITNESS FOR DUTY IN THE NUCLEAR POV f*

R CIDENTS DUR!NG LOW POWER AND SHUTDOWN OPERATIONS AT IND STRY. Annual Sumrnary Of Program Performance Reports t 'Y S'JRRY. UNIT LAnalysis Of Core Damage Frequency From internal Events Dunng M4 Loop Operatons Main Report (Chapters 14).

CUZMAN,A.

NUREG/CR-6144 V02P18 EVALUATION OF POTENTIAL SEVERE AC-NUREG/CR-6203 VALIDATION STUDIES FOR ASSESSING UNSATU-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT RATED FLOW AND TRANSPORT THROUGH FRACTURED ROCK SURRY. UNIT 1. Analysis Of Core Damage Frequency From Internal Events Dunno Mid Loup Operations Main Report (Chapters 712)

HAMMER,J.A.

NUREG/CR-6144 V02P2' EVALUATION OF POTENTIAL SEVERE ACCl-NUREG/CR-5973 R01 CODES AND STANDARDS AND OTHER GUID-DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT ANCE CITED IN REGULATORY DOCUMENTS SURRY. UNIT 1.Analyws Of Core Damage Frequency From Internal Events Dunng M4 Loop Operatons Appendices A-D.

HARTY,R.

NUREG/CR-6144 V02P3A EVALUATION OF POTENTIAL SEVERE AC.

NUREG/CR-6252 LESSONS LEARNED FROM THE THREE MILE CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT ICLAND. UNIT 2 ADVISORY PANEL SURRY, UNIT 1. Analysis Of Core Damage Frequency From Internal vents Dunng mm Opwatons Appendees E (Sedons EM 8)

HIGGINS f.C*

NUREG/CR-6144 V02P3B EVALUATION OF POTENTIAL SEVERE AC-HURE G-0711: HUMAN FACTORS ENGINEERING PROGRAM REVIEW SIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT MODEL.

SURRY, UNIT 1. Analysis Of Core Damage Frequency From internal HILLS R.G.

Events Dunng M4 Loop Operatons Appendees E (Sectons E.9-E 16).

NUNEG/CR4144 V02P4 EVALUATION OF POTENTIAL SEVERE ACCl-NUREG/CR-6120. CONTROLLED FIELD STUDY FOR VALIDATION OF DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT VADOSE ZONE TRANSPORT MODELS SURRY UNIT 1. Analysis Of Core Damage Frequency From internal HISER,A.L.

Events Dunng Mid Loop Operations Appendees F-H.

NUREG 1426 V02. COMPILATION OT REPORTS FROM RESEARCH NUREG/CR-6144 V02P5: EVALUATION OF POTENTIAL SEVERE ACCI-SUPPORTED BY THE MATERIALS ENGINEERING DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT BRANCH. DIVISION OF ENGINEERING 1991 1993 SURRY, UNIT 1 Analysis Of Core Damage Frequency From Internal Events Dunng M4 Loop Operatons Appendices I.

HO,V, NUREG/CR4144 V03 P1: EVALUATIJN OF POTENTIAL SEVERE AC.

HUBER.D.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG 1415 VO6 NO2.

OFFLE OF THE INSPECTOR SURRY, UNIT 1. Analysis Of Core Damage Frequency From internal GENERAL. Semiannual Report. October 1,1993 March 31,1994.

Fres Dunng M4 Loop Operatons Main Report NUREG/CR-6144 V03 P2. EVALUATION OF POTENTIAL SEVERE AC.

HUFFERT,A.M.

CIDENTS DURING LOW POWER AND SHUTOUWN OPERATIONS AT NUREG 1500. WORKING DRAFT REGULATORY GUIDE ON RELEASE SURRY, UNIT 1. Analysis Of Core Damage Frequency From Internal CRITERIA FOR DECOMMISSIONING NRC STAFF'S DRAFT FOR Fres Dunng M4 Loop Operatons Appendices COMMENT.

NUREG-1501 DRFT: BACKGROUND AS A RESIDUAL RADIOACTIVITY HOLMES.B.

CRITERION FC7 DECOMMISSIONING Appendix A To The Draft Ge-NUREG/CR-6144 V02PI A. EVALUATION OF ( nTENTIAL SEVERE AC-nere Envronmental Impact Statement in Support Of Rutemaking On CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT Radiologeal Cntena For Decommessening Of NRC..

SURRY. UNIT 1. Analysis C: Core Damage Frequency From internal Events Dunng M4 Loop Operations Mam Report (Chapters 1-6)

ILBERG,D.

NUREG/CR-6144 V02PIB EVALUATION OF POTENTIAL SEVERE AC*

NUREG/CR-6144 V02P1A EVALUATION OF POTENTIAL SE /ERE AC-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SURRY, UNIT 1 Anatyss Of Core Damage Frequency From Internal SURRY. UNIT 1.Analyss Of Core Damage Frequency From Interna!

Events Dur ng iwJ Loop Operations Main Report (Chapters 7-12)

Events Dunng M4 Loop Operatons Main Fleport (Chapters 1-6)

NUREG/CR4144 V02P2. EVALUATION OF POTENTIAL SEVERE ACCl-NUREG/CR-6144 V02P1B EVALUATION OF POTENTIAL SEVERE AC-DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT CIDENTS DURING LOW POWER AND SHUTDOWN OPERAtlONS A i SURRY,0 NIT 1 Analyss Of Core Damage Frequency From Internal SURRV. UNIT 1 Analyss Of Core Damage craa ency From Internal NUI C

44 02 A A UAT O NTE TIAL SEVERE AC-n ng oop Opmamns Main NW Kmam W NUREG/CR-6144 V02P2. EVALUATION OF POTENTIAL SEVERE ACCI-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT DENTS NRM LOW NW AW SHWOOWN NNS M SURRY, UNIT 1. Analysis Of Core Damage Frequency From internal SUR NR LAnahss Of Cme Damage Requency From intenal Events Dunno M4 Loop Operatens.Appendees E (Sections E 1-F 8)

NUREG/CR4144 ' 02P38. EVALUATION OF POTENTIAL SEVERE AC-Events Dunng M4 Loop Operatons Appendces A-D.

NUREG/CR-6144 V02P3A. EVALUATION OF POTENTIAL SEVERE AC-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SURRY, UNIT 1. Analysis Of Core Damage Frequency From internal SURRY. UNIT 1. Analysts Of Core Damage Frequercy From internal Fvents Dunno M4 Loop Operatons.Appaidees E (Sectons E 9-E 16)

NUREG/CR414e V02P4 EVALUATION OF POTENTIAL SEVERE ACCl.

Events Dunng M d Loop Operatons Appendees E (Sectons E.1-E 8)

NUREG/CR-6144 V02P38. EVALUATION OF POTENTIAL SEVERE AC-DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SURRY. UNIT 1. Analysis Of Cose Damage Frequency From internal Events Dunng M4 Loop Operatons Appenclices F-H SURRY. UNIT 1. Analysis Of Core Damage Frequency From intemmi NUREG/CR-6144 V02P5. EVALUATION OF POTENTIAL SEVERE ACCI.

Events Dunng M4 Loop Operatons Appendees E (Sect.ons E 9 E.16t DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR-6144 V02P4 EVALUATION OF POTENTIAL SEVERE ACCI-SURRY, UNIT 1.Analvm Of Core Damage Frequency Frou internal DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT Events Dunng Mid loop Operatons. Append ces i.

SURRY UNIT f Analysis Of Core Damage Frequency From internal Events Dunng M4 Loop Operations Appendices F-H HOU,Y.-M.

NUREG/CR-6144 V02P5 EVALUATION OF POTENTIAL SEVERE ACCl-NUREJ/CR-6144 V03 P1: EVALUATION OF POTENTIAL SEVERE AC-DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT CIDENTS fSRING LOW POWER AND SHUTDOWN OPERATIONS AT SURRY, UNIT 1 Analyss Of Core Damage Frequency From Internal SURRY. UNIT 1.Analyss Of Core Damage Frequency From Internal Events Dunng M4 Loop Operatons Appendices 1.

Fres Dunno M4 Loop Operatons Main Report NUREG/CR4144 V03 P2. EVALUATION OF POTENTIAL SEVERE AC.

JiLES.D.C.

CIDENTS DURING LOW POWD1 AND SHUTDOWN OPERATIONS AT NUREG/GR-0013 APPLICATIONS OF A NEW MAGN! TIC MONITOR-SORY,0 NIT 1.Anatyais Of Core Damage Frequency From internal SNG TECHNIOUE TO IN SITU EVALUATION OF FATIOUE DAMAGE Fsw Dunng M4 Loop Operatons.Appendees IN FERROUS COMPONENTS.

24 Personal Author inder JOHNSON,0.

KOHUT,P.

NUREC/CR.6144 VC2PI A. EVALUnTION OF POTENTIAL SEVERE AC-NUREG/CR4144 V02P1 A EVALUATION OF POTENTIAL SEVERE AC.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT CIDENT S DURING LOW POWER AND SHUTDOWN OPERATIONS AT SURRY. UNIT 1 Analysis Of Core Damage Frequexy From internal SURRY. UNIT 1. Analysis Of Core Damage Frequency From internal Events Dunng Md Loop Operat ons Main Report (Chapters 141 Events Dunng M d-Loop Operatons Main Report (Chapters 14).

NUREG/CR-6144 V02P1B EVALUATION OF POTENTIAL SEVERE AC-NUREG/CR4144 V02P1B EVALUATION OF POTENTIAL SEVERE AC-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SURRY. UNIT 1 Analysis Of Core Damage Frequency From Internal SURRY, UNIT 1. Analysis Of Core Damage Frequency From intemal Events Dunng Md-Loop Operations Main Report (Chapters 7.12).

Events Dunng Md-Loop Operatons Vain Report (Chapters 712)

NUREGICR4144 V02P2 EVALUATON OF POTENTIAL SEVERE ACCl-NUREG/CR-6144 V02P2. EVALUATION OF POTENTIAL SEVERE ACCI-DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SURRY. UNIT 1 Analysis Of Core Damage Frequency From Internal SURRY UNIT 1. Analysis Of Core Damage Frequency From internal Events Durno M4 Loop Operatons Appendices A-D Events Dunng Md Loop Operations Appendices A-D.

NUREG/CR-6144 V02P3A EVALUATION OF POTENTIAL SEVERE AC-NUREG/CR4144 V02P3A. EVALUATK d OF POTENTIAL SEVERE AC-CMENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SURRY, UNIT 1. Analysis Of Core Damage Frequency From Internal SURRY, UNIT 1. Analysis Of Core Damage Frequency From Internal Fuents Dur no Mid Loop Operatens Appendices E (Sectons E 1-E 8)-

Events Dunng Md-Loop Operatons. Appendices E (Sectons E.1.E.8)

NUREG/CR 614 V02P3B EVALUATION OF POTENTIAL SEVERE AC-NUREG/CR-6144 V02P3B EVALUATION OF POTENTIAL SEVE3E AC-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SURRY UNIT 1 Analysis Of Core Dr.%ge Frequency From Internal SURRY, UNIT 1.Anatysis Of Core Damage Frequency From internal 114 Vb2P7E L AT N F ENTI SIVE NUREG/CR-6144 V02P4 EVALUATON OF i C TENTIAL SEVERE ACCl-Events Dunng Md Loop Operatons Appent*es E (Sectons E 9-E.16).

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SURRY, UNIT 1 Analysis Of Core Damage Frequency From Internal naWs G Gm Damage Renn % internal Events Dunng Md-Loop Operations Appendices F.H NUREG/CR 6144 V02P5 EVALUATION OF POTENTIAL SEVERE ACCl-Events Dunng Md-Loop Operatons Apperdices F H NUREG/CR 6144 V02P5. EVALUATION OF POTENTIAL SEVERE ACCl.

DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SURRY. UNIT 1. Analysis Of Core Damage Frequency From internal R NR 1 Analysis Of Core Damage Frequency From Internal Events Dunng Mid-Loop Operations Appendices 1.

Events Dunng Mid Loop Operatons. Appendices 1.

I JOHNSON J.J.

NUREG/CR4144 V04 EVALUATION OF POTENTIAL SEVERE ACCl-NUREG/CR-5726 REVIEW OF THE DIABLO CANYON PROBABILISTIC DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT RISK ASSESSMENT.

SURRY. UNIT 1 Analysis Of Core Damage Frequency From internal Floods Dunng Md-Loop Operatons.

JOHNSTON.A.

NUREG/CR-6254 SOUTHERN APPALACHIAN REGIONAL SEISMIC KOT,C.A.

NETWORK.

NUREG/CR4234 VALIDATION OF ANALYSIS METHODS FOR AS-SESSING FLAWED PIPING SUBJECTED TO DYNAMIC LOADING K AM.F.B.K.

NUREG/CR-6236 SEISMIC INVESTIGATIONS OF THE HDR SAFETY NURE G/CR4206 TRANSPORT CALCULATIONS OF RADIATION Ex-PROGRAM Summary Report POSURE TO VESSEL SUPPORT STRUCTURES IN THE TROJAN RE.

ACTOR KRAFT,G.D.

NUREG/CR 4255 DEslGN OF AN OPEN ARCHITECTURE SEISMIC KANA.D.D.

MONITORING SYSTEM NUREG/UR * '8 LABORATORY CHARACTERl; ATION OF ROCK JOINTS KVARFORDT,K.J.

NUREG/CR 6116 V02 SYSTEMS ANAYSIS PROGRAMS FOR KEISLER.J.

HANDSON INTEGRATED RELIABILITY EVALUATIONS (SAPHIRE)

NUREG/CR4237 STATISTICAL ANALYSIS OF FATIGUE STRAIN-LIFE VERSION 5 J integrated Reliability And Risk Anatysis System (IRRAS) l OATA FOR CARBON AND LOW-ALLOY STEELS Reference Manual NUREG/CR4116 V04 SYSTEMS ANALYSIS PROGRAMS FOR KENDRICK,E.D.

HANDS ON INTEGRATED RELIABil.lTY EVALUAflONS (SAPHIRE)

NUREG/CR-3950 V09 FUEL PERFORMANCE REPORT FOR 1991.

VERSION 5 0 Systems Analysis And Risk Assessment (SARA) Refer.

KINOSHITA.M.

ence Manual NUREG/CR-6213 HIGH. TEMPERATURE HYDROGEN AIR STEAM DETONATION EXPERIMENTS IN THE BNL SMALL-SCALE DEVELOP.

LACH,D.

MENT APPARATUS NUREG/CR.6252 LESSONS LEARNED FROM THE THREE MILE ISLAND UNIT 2 ADVISORY PANEL.

KIRK.H.

NUREG/CR-6143 V02P1 A. EVALUATION OF POTENTIAL SEVERE AG.

LAMBRIGHT.J.

CIDENTS DURING LOW POWER AND SHUTDOWN O,'ERATIONS AT NUREG/CR 6143 V03 EVALUATION OF POTENTIAL SEVERE ACCl-GRAND GULF, UNIT 1 Analysis Of Core Damage Frequency From in.

DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT ternal Events For Plant Operational State 5 Dunng A Refueling QAND GULF UNIT 1. Analysis Of Core Damage Frequency From In-Outage Sectons 1-9 ternal Events For Plant Operational State 5 Dunng A Refueling Outage.

NURf G/CR-6143 V02P1B EVALUATION OF POTENTIAL SEVERE AC.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT LEONARD S.K.

GRAND GULF. UNIT 1. Analysis Of Core Damage Frequency From in.

NUREG/CR4255 DESIGN OF AN OPEN ARCHITECTURE SEISMIC ternal Events For Plant Operatonal State 5 Dunng A Refueling MONITORING SYSTEM Outage Secton to NUREG/CR4143 V02P1C: EVALUATION OF POTENTIAL SEVERE AC.

LE WIS,P.M.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR-6208 AN EMPIRICAL INVESTIGATION OF OPERA 10R GRAND GULF. UNIT 1. Analysis Of Co'e Damage Frequency From in PERFORMANCE IN COGNITIVELY DEMANDING SIMULATED EMER.

ternal Events For Plant Operatonal State 5 Dunng A Refueling GENCIES Outape Main Report.

NUREG/CR4143 V04 EVALUATION OF POTENTIAL SEVERE ACCl.

LIN,J.

DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR-6144 V02P1A EVALVAllON OF POTENTIAL SEVERE AC-GRAND GULF. UNIT 1 Analysis Of Core Damage Frequency From in.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT ternally Induced Flooding Events For Plant Operatonal State 5 Dunng SURRY. UNIT 1 Analysis Of Core Damage Frequency From internal a Refueling..

Events Dunng Mc-Loop Operatons Main Report (Chapters 1-6)

NUREG/CR4144 V02P1B EVALUATION OF POTENTIAL SEVERE AC-KMETYK.LN.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR 6218 A REVIEW OF THE TECHNICAL ISSUES OF AIR IN-SURRV. UNIT 1 Analysis Of Core Damage Frequency From internal GRESSION DURING SEVERE REACTOR ACCIDENTS Events Dunng Md Loop Operatons Main Report (Chapters 7-12)

Personal Author Index 25 l

NUREG/CR-6144 VD2P2: EVALUATION OF POTr_NTIAL SEVERE ACCl-nenc Envronmental impact Statement in Support Of Rulemalung On DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT Radiological Cntena For Decommissioning Of NRC-.

i SURRY. UNIT 1.AnaYam Of Cnre Damage Frequency From Internal Events Dunng Md Loop Operatons Appendices A D MEYER.R.O.

NUREG/CR4144 V02P3A. EVALUATION OF POTENTIAL SEVERE AC-NUREG-1502. ASSESSMENT OF DATABASES AND MODELING CAPA-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT BILmES FOR THE CANDU 3 DESIGN.

SURRY.UN1" 1 An" 4 Of Core Damage Frequency From Intemal Events Dunng Md-LL.p Operations Appendna E (Sections E 1-E 8)

MILLERE.M.

NUREG/CR4144 V02P3B EVALUATION OF POTENTIAL SEVERE AC-NUREG-1501 DRFT. BACKGROUND AS A RESIDUAL RADIOACTIVITY CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT CRITERION FOR DECOMMISSIONING. Appendix A To The Draft Go-SURRY, UNIT 1. Analysis Of Core Damage Frequency From inter.al nenc Environmental Impact Statement in Sur. ' Of Rulemaking On NL R CR 4 Vb2P E A$

FPO SYVE T

DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT MILLER S.

SURRY. UNIT 1. Analysis Of Core Damage Frequency From internal NUREG/CR-6143 V02P1A. EVALUATION OF POTENTIAL SEVERE AC.

Events Dunng Md-Loop Operatons Appe* dices F-H NUREG/CR4144 V02P5; EVALUATION OF POTENTIAL SEVERE ACCI' CIDENTS DURING LOW POWER AND SHiiTDOWN OPERATIONS AT DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT GRAND GULF. UNIT 1. Analysis Of Core Lamage Frequency From In-

,,,nal Events For Plant Operatonal State 5 Dunng A Refuehng SURRY, UNIT 1. Analysis Of Core Damage Frequency From Internal Outa Sectons 1-9 NURE CR4143 V02PIB. EVALUATION OF POTENTIAL SEVERE AC-Nt I C

144 0 LU l O

TENTIAL SEVERE AC.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SURRY, UNIT 1. Analysis Of Core Damage Frequency From Internal nahsis G h Damage Requency %n in.

Fres Dun Mid>.oop Operatons Main Re ternal Events For Plant Operatonal State 5 Dunng A Refuehng NUREG/CRl144 V03 P2-EVALUATION O POTENTIAL SEVERE AC.

Outage Secton 10.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR4143 V02P1C: EVALUATION OF POTENTIAL SEVERE AC-SURRY, UNIT 1. Analysis Of Core Damage Frequency From Ir ternal CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT Fires Dunng Md-Loop Operatons Appendices.

GRAND GULF, UNIT 1. Analysis Of Core Damage Frequency From In-ternal Events For Plant Operatonal State 5 Dunng A Refueling LOHRSTORFER.C.

Outage Main Report f4UREG/CR4203. VALIDATION STUDIES FOR ASSESSING UNSATU-RATED FLOW AND TRANSPORT THROUGH FRACTURED ROCK MITCHELL.D.

NUREG/CR-6143 V02P1 A. EVALUATION OF POTENTIAL SEVERE AC.

LUCKAS,W.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR-6093 AN ANALYSIS OF OPERATIONAL EXPERIENCE DURING LOW POWER AND SHUTDOWN AND A PLAN FOR AD-GRAND GULF, UNIT 1. Analysis Of Core Damage Frequency From In-tornal Events For Plant Operatonal State 5 Dunng A Refueleng DRESSING HUMAN RELIABILITY ASSESSMENT ISSUES.

Outage Sections 1-9 NUREG/CR4143 V02PIB EVALUAilON OF POTENTIAL SEVERE AC-NUREG/CR-6143 V03 EVALUATION OF POTENTIAL SEVERE ACCl-CIDENTS DURING LOW POWER ANG SHUTDOWN OPERATIONS AT DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT GRAND GULF. UNIT 1. Analysis Of Core Damage Frequency From In-GRAND GULF,UNti 1. Analysis Of Core Damage Frequency From In-ternal Events For Plant Operatonal State 5 Dunng A Refuehng ternal Events For Plant Operatonal State 5 Dunng A Refuehng Outage NU E C 1 3 Vd2PIC: EVALUATION OF POTENTIAt. SEVERE AC-CATUIRE-MOFFITT CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT fdVREG/CR 5973 RO1: CODES AND STANDARDS AND OTHER GUID-GRAND GULF, UNIT 1.Analysss Of Core Damage Frequency F!cm in-ANCE CITED IN REGULATORY DOCUMENTE ternal Events For Plant Operational State 5 Dunng A Gofuehng Outage Main Report.

CALARO.J.C.

NUREG-1500 WORKING DRAFT REGULATORY GUIDE ON RELEASE MOFFITT,R.

CRITERIA FOR DECOMMISSIONING NRC STAFF'S DRAFT FOR NUREG/CR-5758 V04. FITNESS FOR DUTY IN THE NUCLEAR POWER COMMENT.

INDUSTRY Ar.nual Summary Of Program Performance Reports CY 1993.

CALCHER,L.

NUREG/CR-6236. SEISMIC INVESTIGATIONS OF THE HDR SAFETY MUM A W,R.J.

PROGRAM Summary Report.

NUREG/CR4127. THE EFFECTS OF STRESS ON NUCLEAR POWER MARIAN,A.L.

PLANT CPERATIONAL DECISION MAKING AND TRAINING AP.

NUREG/CR-3950 V09 FUEL PERFORMANCE REPORT FOR 1991.

NUREG/CR AN P CAL NVESTI ATION OF OPERATOR MARSCHALL,C.

PERFORMANCE IN COGNITIVELY DEMANDING SIMULATED EMER.

NUREG/CR-6233 V01. STABILITY OF CRACKED PIPE UNDER INER.

GENCiES TIAL STRESSES Subtask 1.1 Final Report.

MCGARRY.E D.

NUREG/CR-6144 V02P1A: EVALUATION OF POTENTIAL SEVERE AC-NUREG/CR4206: TRANSPORT CALCULATIONS OF RADIATION Ex-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT POSURE TO VESSEL SUPPORT STRUCTURES IN THE TROJAN RE.

SURRY LNIT 1.Anatysis Of Core Damage Frequency From internal ACTOR.

Evants Dunng Md-Loop Operatons Main Report (Chapters 14).

NUREG/CR-6144 V02P18: EVALUATION OF POTENTIAL SEVERE AC-(

MCKAY,M.K.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT l

NUREGICA 6116 VO7: SYSTEMS ANALYSIS PROGRAMS FOR SURRY,UNfT 1. Analysis Of Core Damage Frequency From Internal

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HANDS-ON INTEGRATED RELIABILITY EVALUATIONS (SAPHIRE)

Events Dunng bd-loop Operatons Main Report (Chapters 7-12).

VERSION 5 0 Fault Tree, Event Tree, And Apeng & Instrumentaton NUREG/CR4144 V02P2: EVALUATION OF POTENTIAL SEVERE ACCI-

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Diagram (FEP) Editoes Reference Manual.

DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT I

MCLAUGLIN.D SURRY, UNIT 1.Anatysis Of Core Damage Frequency From internal NUREG/CR 5965. MODELING FIELD SCALE UNSATURATED FLOW NU C

44 VO A A

OF POTENTIAL SEVERE AC.

AND TRANSPORT PROCESSES.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT MCUMBERLM.

SURRY,UN:T 1. Analysis Of Core Damage Frequency From Internal NUREG/CR 6168 DIRECT CONTAINMENT HEATING INTEGRAL EF.

Events Dunno M,d Loop Operatons. Appendices E (Sectors E.1-E 8) l FECTS TESTS AT 1/40 SCALE IN ZION NUCLEAR POWER PLANT NUREG/CR4144 V02P30 EVALUATION OF POTENTIAL SEVERE AC-GEOMETRY.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT l

SURRY, UNIT 1. Analysis Of Core Damage Frequency From internal l

MECK R.A.

Events Dunng Md-Loop Operatons Apperdice= E (Sectons E 9-E.16).

NUREG-1501 DRFT: BACKGROUND AS A RESIDUAL RADIOACTIVITY NUREG/CR4144 V02P4. EVALUATION OF POTENTIAL SEVERE ACCl-CRITERION FOR DECOMM:SSiONING Appendm A To The Draft Go-DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT l

t L

26 Personal Author Index SURRY,U" J 1. Analysis Of Core Damage Frequency From internal RAMEY SMITH,A.

Events Dunng Mid-Loop Operatons Appendices F-H NUREG/CR-6093 AN ANALYSIS OF OPERATIONAL EXPERIENCE NUREG/CR4144 V02P5. EVALUATION OF POTENTIAL SEVERE ACCl-DURING LOW POWER AND SHUTDOWN AND A PLAN FOR AD-DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT t/RESSING HUMAN RELIABILITY ASSESSMENT ISSUES SURRY. UNIT 1. Analysis Of Core Damage Frequency From internal Events Dunng Med. Loop Operations Appendices i R AO,D.V.

NUREG/CR4144 V03 P1-EVALUATION OF POTENTIAL SEVERE AC-NUREG/CR-6224 DRF FC. PARAMETRIC STUDY OF THE POTf NTIAL CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT FOR BWR ECCS STRAINER BLOCKAGE DUE TO LOCA GENERAT.

SURRY, UNIT 1. Analysis Of Core Damage Frequency From Internal ED DEBRIS Draft For Comment Fres Dunng Mid Loop Operatens Main Report.

NURCG/CR-6144 V03 P2-EVALUATION OF POTENTIAL SEVERE AC.

RASMUSON,D.M.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR-6116 VOI: SYSTEMS ANALYSIS PROGRAMS FOR SURRY, UNIT 1 Analysis Of Core Damage frequency From intemal HANDS ON INTEGRATED RELIABILITY EVALUATIONS (SAPHIRE)

Fres Dunng Mid-Loop Operatons Appendices VERSION 5 0 Technical Reference Manual.

NUREG/rR4116 V02. SYSTEMS ANALYSIS PROGRAMS FOR NEBUDA.D.T.

HANC.

'N INTEGRATED RELIABILITY EVALUATIONS (SAPHIRE)

NUREG/CR4190 V01. PROTECTION AGAINST MALEVOLENT USE OF VERSION 5 0lntegrated Rehabihty And Risk Analysis System (IRRAS)

VEHICLES AT NUCLEAR POWER PLANTS Vathicle Bamer System Reference Manual Siting Guidance For Blast Protection.

NUREG/CR-6190 V02. PROTECTION AGAINST MALEVOLENT USE OF RASMUSSEN.T.C.

VEHICLES AT NUCLEAR POWER PLANTS Vehicle Barner System NUREG/CR-6203 VALIDATION STUDIES FOR ASSESSING UNSATU-Siting Guidance For Blast Protection RATED FLOW AND TRANSPORT THROUGH FAACTURED ROCK NEUM AN,S.P.

RA'elNDRA M.K.

NUREG/CR4203 VALIDATION STUDIES FOR ASSES $1NG UNSATU-NUREG/CR-5726. REVIEW OF THE DIABLO CANYON PROBABILISTIC RATED FLOW AND TRANSPORT THROUGH FRACTURED ROCK.

RISK ASSESSMENT.

NUREG/CR-6143 V05 EVALUATION OF POTENTIAL SEVFRE ACCI-NICHOLS R.T.

DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR-6152 EXPERIMENTS TO INVESTIGATE DIRECT CON-GRAND GULF. UNIT 1 Analysis Of Core Damage Frequency From TAINMENT HEATING PHENOMENA WITH SCALED MODELS OF THE Seismic Evente Dunng Mid Loop Operations Main Report SURRY NUCLE AR POWEP

• ANT.

NUREG/CR-6144 V05 EVALUATION OF POTENTIAL SEVERE ACCl-DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT HICKOLAUS.J.R.

SURRY UNIT 1 Analysis Of Core Damage Frequency From Seismic NUREG/CR 5973 R01. CODES AND STANDARDS AND OTHER GUID-Events Dunng Mid-loop Operations Main Report.

ANCE CITED IN REGULATORY DOCUMENTS R E E C E.W.J.

NORTON,L NUREG/CR-4639 V5R4P2: NUCLEAR COMPUTERIZED LIBRARY FOR NUREG 1415 V06 NO2:

OF FICE OF THE INSPECTOR ASSESSING REACTOR RELIABILITY (NUCLARR) Volume 5. Data GENERAL. Semiannual Report. October 1.1993 - March 31,1994 Manual Part 2. Human Error Probability (HEP) Data NUREG/CR-4639 V5R4P3 NUCLEAR COMPUTERIZED LIBRARY FOR O'H AR A.JM-ASSESSING REACTOR RELIABILITY (NUCLARR) Volume 5 Data NUREG-0711. HUMAN FACTORS ENGINEERING PROGRAM REVIEW Manual Part 3. Hardware Component Failure Data MODEL NUREG/CR 5908 V01: ADVANCED HUMAN SYSTEM INT E RF ACE RICHARDS,R.E.

DESIGN REVIEW GUIDELINE. General Evaluation Model. Technical i4UREG/CR-4639 V5R4P2 NUCLEAR COMPUTERIZED LIBRARY FOR Development. And Guideline Desenption ASSESSING REACTOR RELIABILITY (NUCLARR) Volume 5 Data NUREG/CR-5908 V02 ADVANCED HUMAN SYSTEM INTERFACE Manual Part 2 Human Error Probability (HEP) Data DESIGN REVIEW GUIDELINE. Evaluation Procedures And Guidehnes NUREG/CR-4639 V5R4P3 NUCLEAR COMPUTERIZED LIBRARY FOR For Human f actors Engineenng Reviews ASSESSING REACTOR REllABILITY (NUCLARR) Volume 5 Data Manual Part 3 Hardware Component Failure Cota OLSON.R.J.

NUREG/CR 0233 V01: STABILITY OF CRACKED PIPE UNDER INER-pogg,g, TIAL STRESSES Subtask 11 F,nal Report NUREG/CR-6143 V03 EVALUATION OF POTENTIAL SEVERE ACCl-NUREG/CR 6234 VAllDATION OF ANALYSIS METHODS FOR AS.

DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SE SSING FLAWED PIPING SUBJECTED TO DYNAMIC LOADING GRAND G'.'LF. UNIT 1. Analysis Of Core Damage Frequency From In-ternal Events For Plant Operational State 5 Dunng A Refuehng Outage.

PAGLG.

NUREG/CR-6250

SUMMARY

OF COMMENTS RECElVED ON STAFF ROTH.E.M.

DRAFT PROPOSED RULE ON RADIOLOGICAL CRITERIA FOR DE-NUREG/CR-6208 AN EMPIRICAL INVESTIGATION OF OPERATOR COMMISSIONING PERFORMANCE IN COGNITIVELY DEMANDING SIMULATED EMER-GENCIES PAINTER,C.L NUREG/CR 3950 V09 FUEL PERFORMANCE REPORT FOR 1991.

RUtZ N.

NUREG/CR-6224 DRF FC PARAMETRIC STUDY OF THE POTENTIAL PAUL D.D.

FOR BWR ECCS STRAINER BLOCKAGE DUE TO LOCA GENERAT.

NUREG/CR 5128 R01' EVALUATION AND REFINEMENT OF LEAK.

ED DEBRIS Draft For Comment RATE ESTIMATION MODELS RUSSELL,K.D.

P AYNE.G. A.

NUREG/CR-6116 V01-SYSTEMS ANALYSIS PROGRAMS FOR NUREG/CR-3950 V09 FUEL PERFORMANCE REPORT FOR 199f.

HANDS-ON INTEGRATED RELIABILITY EVALUATIONS (SAPHIRE)

P[NNELL W.E.

VERSION 5 0 Technical Reference Manual NUREG/CR-4219 V10 N' HEAVY SECTION STEEL TECHNOLOGY NUREG/CR4116 V02 SYSTEMS ANALYSIS PROGRAMS FOR HANDS ON INTEGRATED RELIABILITY EVALUATIONS (SAPHIRE)

PROGRAM Semiannual Progress Report for October 1992 - March VERSION 5 0 Integrated Rehabahty And Risk Analysis System (IRRAS) 1993 Reference Manual PILCH.M M.

NUREG/CR-6116 V03 SYSTEMS.iNALYSIS PROGRAMS FOR NURE GICR-6152 EXPERIMENTS TO INVESTIGATE Dl!4ECT CON.

HANDS-ON INTEGRATED RELIABILITY EVALUATIONS (SAPHIRE)

TAINMENT HE ATING PHENOMENA WITH SCALED MODELS OF THE VERSION 5 0 Integrated Rehabshty And Risk Analytos System (IRRAS)

SURRY NUCLEAR POWER PLANT Tutonal Manual NUREG/CR-6116 V04 SYSTEMS ANALYSIS PROGRAMS FOR POWERS.D.A.

HANDS-ON INTEGRATED RELIABILITY EVALUATIONS (SAPHIRE)

NUREGICR 6218 A REVIEW OF THE TE CHNiCAL ISSUES OF AIR IN VERSION 5 0 Systems Analysis And Risk Assessment (SARA) Refer-GRESSION DURING SEVERE REACTOR ACCIDENTS ence Manual

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Personal Auth:r index 27 NUREG/CR4116 V05: SYSTEMS ANALYSIS PROGRAMS FOR SIU,N.

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VERSION 5 0 Systems Analysis And Risk Assessment (SARA) Tutonal CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT i

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NUREG/CR4116 V08. SYSTEMS ANALYSIS PROGRAMS FOR Events Dunng Mid Loop Operations Main Report (Chapters 14).

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NUREG/CR4144 V02PIB EVALUATION OF POTENTIAL SEVERE AC-VERSION 5 0 Models And Results Database (MAR D) Reference CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT i

Manual.

SURRY, UNIT 1 Analysis Of Core Damage Frequency From internal l

SAeEK,M.G..

Events Dunno Md-Loop Operatons. Main Report (Chapters 712).

l NUREG/CR-6144 VC2P2: EVALUATION OF POTENTIAL SEVERE ACCl-NUREG/CR4726' REVIEW OF THE DIABLO CANYON PROBABILISTIC DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT RISK ASSESSMENT.

SURRY. UNIT 1. Analysis Of Core Damage Frequency From intemal Events Dunng Moop Operatons Appeneces AO j

SATO'K'G/CR-6213.

NUREG/CR4144 V02P3A: EVALUATION OF POTENTIAL SEVERE AC.

NURE HIGH-TEMPERATURE HYDROGEN AtR-STEAM CIDENTS DURtNG LOW POWER AND SHUTDOWN CPERATIONS AT DETONATION EXPERIMENTS IN THE BNL SMALL-SCALE DEVELOP.

MENT APPARATUS SURRY, UNIT 1. Analysis Of Core Damage Frequency From Intema!

Events Dunng Md-Loop Operatens Appendices E (Soctons E.1 E 8).

SATTISON M.8 NUREG/CR4144 V02P38: EVALUATION OF POTENTIAL SEVERE AC-b NUREG/CR4116 VOI:. SYSTEMS ANALYSIS PROGRAMS FOR HANDS ON INTEGRATED RELIABILITY EVALUATIONS (SAPHIRE)

SURRWNR LAnaYsis C - ]amage Requency Rom inWnal Events Dunng Mid-Loop C~

ppendicos E (Sectons E.9-E.16).

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V S TE S A YSIS PROGRAMS FOR DENTS DURING LOW FC.

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VERSION 5 0 Systems Analysis And Risk Assessme91 (SARA) Tutonal SURRY. UNIT 1. Analysis On r

ManuW Events Dunng Md-Loop Op Appendices F.H.

j NUREG/CR 6144 V02P5 EV+

.rDN OF POTENTIAL SEVERE ACCI-SCHMIDT,R.

DENTS DURING LOW POWtH AND SHUTDOWN OPERATIONS AT NUREG/CR-6233 V01: STABILITY OF CRACKED PIPE UNDER INER.

SURRY, UNIT 1. Analysis Of Core Damage Frequency From Internal TIAL STRESSES Subtask 11 Final Report Events Dunng Md-Loop Operatons. Appendices 1.

NUREG/CR4144 V03 P1: EVALUATION OF POTENTIAL SEVERE AC-SCHM4DT,R.C.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR4218 A REVIEW OF TH6 TECHNICAL ISSUES OF AIR IN-SURRY, UNIT 1. Analysis Of Core Damage Frequency From internal i

GRESSION DURING SEVERE REACTOR ACCIDENTS.

Fires Dunng Md-loop Operatons Main Report NUREG/CR4144 V03 P2. EVALUATION OF POTENTIAL SEVERE AC-SCHRAMMEL,0.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR4236. SEISMiG INVESTIGATIONS OF THE HDR SAFETY SURRY, UNIT 1. Analysis Of Core Damage Frequency From intemat i

PROGRAM. Summary Report Fires Dunns Mid Loop Operatons. Appendices.

SCHULTZ,R R.

SKINNER.N.L.

NUREG/CR4535 V07: RELAPS/ MOD 3 CODE MANUALSummanes And NUREG/CR4116 V02: SYSTEMS ANALYSIS PROGRAMS FOR Reviews Of Independent Code Assessment Repo ts.

HANDS-ON INTEGRATED RELIABILITY EVALUATIONS (SAPHIRE) r VERSION 5.0 Integrated Rehabihty And Rsk Analysis System (IRRAS)

I SCHWARTZ,C.W.

Reference Manual.

NUREG/CR-5861: CRACK SPEED RELATIONS INFERRED FROM NUREG/CR4116 V03: SYSTEMS ANALYSIS PROGRAMS FOR LARGE SINGLE-EDGE-NOTCHED SPECIMENS OF A 533 B STEEL HANDS ON INTEGRATED RELLABILITY EVALUATIONS (SAPHIRE) i VERSION 5 0. Integrated Rehatulity And Rsk Analysis System (IRRAS) f SCIACCA.F.

Tutonal Manual NUREG/CR-6224 DRF FC: PARAMETRIC STUDY OF THE POTENTIAL NUREG/CR-6116' V04 SYSTEMS ANALYSIS PROGRAMS FOR 1

FOR BWR ECCS STRAINER BLOCKAGE DUE TO LOCA GENERAT.

HANDS-ON INTEGRATED RELIABILITY EVALUATIONS (SAPHIRE)

I ED DEBRIS Draft For Comment.

VERSION 5.0 Systems Analysis And Risk Assessment (SARA) Refer-ence Manual.

I

^

NU EG CR-5128 R01: EVALUATION AND RFFINEMENT OF LEAK.

NDS N NTE R TED R B Y UTOS PH R NURE /

33 01 S ABI TY OF CRACKED PIPE UNDER 'NER.

VERSION 5.0 Systems Analysis And Risk Assessment (SARA) Tutonal I

TIAL STRESSES Subtask 1.1 Final Report NURE CR-6116 VC7: SYSTEMS ANALYSIS PROGRAMS FOR i

SHACK,W.J.

HANDS-ON INTEGRATED RELIABILITY EVALUATIONS (SAPHIRE)

NUREG/CR-6237: STATISTICAL ANALYSIS OF FATIGUE STRAIN-LIFE VE~ISION 5 0 Fault Tree, Event Tree, And Piping & Instrumentation j

DATA FOR CARBON AND LOW ALLOY STEELS.

Diagram (FEP) Edstors Reference Manual.

NUREG/CR-6116 V08-SYSTEMS ANALYSIS PHOGRAMS FOR

{

SHAFFER.C.

HANDS-ON INTEGRATED RELIABILITY EVALUATIONS (SAPHIRE)

NUREG/CR 6224 DRF FC: PARAMETRIC STUDY OF THE POTENTIAL VERSION 5 0 Models And Results Database (MAR-D) Reference.

FOR BWR ECCS STRAINER BLOCKAGE DUE TO LOCA GENERAT.

Manual.

ED DEBRIS. Draft For Comment.

SHELTON,8.

NUREG/CR-5535 V07; RELAP5/ MOD 3 CODE MANUAL.Summanes And p

NUREG 1400 RO1: GUIDE TO NRC REPORTING AND RECORDKEEP.

Reviews Of Incspendent Code Assessrnent Reports.

(NG REQUIREMENTS Compled From Requirements in Title 10 Of The U S. Code Of Fe.%rral Regulatons As Codified On December 31 SMITH,8.W.

[

1993 NUREG/CR4151: FEASIBILITY OF DEVELOPING RISK-BASED RANK.

(

INGS OF PRESSURE BOUNDARY SYSTEMS FOR INSERVICE IN-SHERFEY,L.L SPECTION l

NUREG/CR4973 Rot: CODES AND STANDARDS AND OTHER GUID-

?

ANCE CITED IN REGULATORY DOCUMENTS.

SMITH,D.

I NUREG/CR-6250:

SUMMARY

OF COMMENTS RECEIVED ON STAFF SIMONEN,F.A.

DRAFT PROPOSED RULE ON RADIOLOGICAL CRITERIA FOR DE-I NUREG/CR4151: FEASIBILITY OF DEVELOPING RISK BASED RANK-COMMISSIONING.

INGS OF PRESSURE BOUNDARY SYSTEMS FOR INSERVICE IN-l SPECTION SPENCER,8.W.

NUREG/CR4181: A PILOT APPLICATION OF RISK-BASED METHODS NUREG/CR-6168. DIRECT CONTAINMENT HEATING INTEGRAL EF.

[

TO ESTABLISH INSERVICE INSPECTION PRIORITIES FOR NUCLE-FECTS TESTS AT 1/40 SCALE IN ZION NUCLEAR POWER PLANT 1

AA COMPONENTS AT SURRY UNIT 1 NUCLEAR POWER STATION GEOMETRY.

6 I

E I

.e

28 Person:t Author Index STAPLE.8.

THOMAS.W.

NUREG/CFI 6143 V02P1 A EVALUATION OF POTENTIAL SEVERE AC-NUREG/CR-6224 DRF FC: PARAMETRIC STUDY OF THE POTENTIAL CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT FOR BWR ECCS STRAINER BLOCKAGE DUE TO LOCA GENERAT-GRAND GULF. UNIT 1. Analysis Of Core Damage Frequency From In-ED DEBRIS. Draft For Comment.

ternal Events For Plant Operator.al State 5 Dunng A Refueling Outage Sectons 1-9 TONG,W.H.

NUREG/CR4143 V02PIB-EVALUATION OF POTENTIAL SEVERE AC-NUREG/CR4143 V05: FVALUATION OF POTENTIAL SEVERE ACCl-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT DENTS DURING LOW POWER AND SHUTDCWN OPERATIONS AT GRAND GULF. UNIT 1. Analysis Of Core Damage Frequency From In-GRAND GULF. UNIT 1. Analyses Of Core Damage Frequency From ternal Events For Plant Operatonal State 5 Dunng A Refueling se,smic Events Dunng Mid-Loop Opere*. ins Main Report Outage Secten 10 NUREG/CR-6144 V05: EVALUATION OF POTENTIAL SEVERE ACCl-NUREG/CR 6143 V02P1C. EVALUATION OF POTENTIAL SEVERE AC.

DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT 1

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SURRY, UNIT 1. Analysis Of Core Damage Frequency From Seismic i

GRAND GULF. UNIT 1.Analys:s Of Core Damage Frequency Frorn in-Events Dunng Md-Loop Operations Main Report.

ternal Events For Plant Operatonal State 5 Dunng A Flefuehng Outage Man Report-VANDER VOORT,G NUREG/CR-6143 V02PT2. EVALUATION OF POTENTIAL SEVERE AC.

NUREG/CR-6183 PEER REVIEW OF THE TMI-2 VESSEL INVESTIGA-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT TION PROJECT METALLURGICAL EXAMINATIONS.

GRAND GULF. UNIT 1. Analyses Of Core Damage Frequency From In-ternal Events For Plant Operatonal State 5 Dunng Refueling VANHORN.R.L.

NUEd/

1 'UO2PT3. EVALUATION OF POTENTIAL SEVERE AC-NUREG/CR-6116 V03. SYSTEMS ANALYSIS P 4 GRAMS FOR CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT HANDS ON INTEGRATED RELIABILITY EVALUA flONS (SAPHIRE)

GRAND GULF. UNIT 1. Analysis Of Core Damage Frequency Frorn in-VERSION 5.Olntegrated Rehability And Risk Analysis System (IRRAS)

Tutonal Manual temal Events For Plant Operatonal State 5 Dunng A Refuelmg NU Ed/C 614 UO2PT4 EVALUATION OF POTENTIAL SEVERE AC-VANKUlKEN J.C.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR-5344 RO1: REPLACEMENT ENERGY COST ANALYSIS GRAND GULF. UNIT 1. Analysis Of Core Damage Frequency From in.

PACKAGE (RECAP) USER'S GUIDE.

al vents For Plant Operatonal State 5 Dunng A Refuehng y

NUREd/CR-61431/04. EVALUATION OF POTENTIAL SEVERE ACCI-NUREG/CR 5908 V02-ADVANCED HUMAN. SYSTEM INTERFACE DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT DESIGN REVIEW GUIDELINE. Evaluaton Procedures And Guidelines GRAND GULF. UNIT 1. Analysis Of Core Damage Frequency From in.

For Human Factors Engineenng Reviews ternally induced Flooding Events For Plant Operatonal State 5 Dunng a Refueling _

VINTHER,R.W.

NUREG/CR-5973 RO1: CODES AND STANDARDS AND OTHER GUID-STEINHILBER.H.

ANCE CITED IN REGULATORY DOCUMENTS.

NUREGICR-6236. SEtSMIC INVESTIGATIONS OF THE HDR SAFETY I

PROGRAM Summary Report VO.T.V.

NUREG/CR-6151: FEASIBILITY OF DEVELOPING RISK-BASED RANK +

i (TRUCKMEYER.R.

INGS OF PRESSURE BOUNDARY SYSTEMS FOR INSERVICE IN-NUREG 0A37 V14 N01. NRC TLD DIRECT RADIATION MONITOR!NG SPECTION NETWORK Progress Report. January-March 1994-NUREG/CR 6181; A PILOT APPLICATION OF RISK-BASED METHODS NUREG-0837 V14 NO2. NRC TLD DIRECT RADIATION MONITORING TO ESTABLISH INSERVICE INSPECTION PRIORITIES FOR NUCLE-NETWORK. Progress Report. Apr4-June 1994.

AR COMPONENTS AT SURRY UNIT 1 NUCLEAR POWER STATION.

STUBLER,W.F.

NUREG 711: HUMAN FACTORS ENGINEERING PROGRAM REVIEW

• A E /CR-6143 V02P1A. EVALUATION OF POTENTIAL SEVERE AC.

~

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SU.R.F.

GRAND GULF. UNIT 1. Analyse Of Core Damage Frequency From In-NUREG/CR-6144 V02PI A EVALUATION OF POTENTIAL SEVERE AC-terna! Events For Plant Operatonal State 5 Dunng A Refuehng a

4 CIDENTS DUNNG LOW POWER AND SHUTDOWN OPERATIONS AT Outage Sectons 19 SURRY. UNIT 1. Analysis Of Core Damage Frequency From Intemal NUREG/CR4143 V02P1B EVALUATION OF POTENTIAL %EVERE AC-Events Dunno Mid-Loop Operatens Main Report (Chapters 16)

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR-6144 V0?PtB EVALUATION OF POTENTIAL SEVERE AC-GRAND GULF. UNIT 1. Analysis Of Core Damage Frequency From In-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT ternal Events For Plant Operational State 5 Dunng A Refueling SURRY, UNIT 1. Analysis Of Core Damage Frequency From Internal Outage Secton 10 Events Dunng Mid-Loop Operatons Main Report (Chaptors 712)

NUREG/CR 6143 V02PIC EVALUATION OF POTENTIAL SEVERE AC-NUREG/CR-6144 V02P2. EVALUATION OF POTENTIAL SEVERE ACCI-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT GRAND GULF. UNIT 1. Analysis Of Core Damage Frequency From In-SURRY.UND 1.Anatysis Of Core Damage Frequency From Intemal temal Events For Plant Operatonal State 5 Dunng A Refueling Events Dunng Mid-loop Operatons Appendices A-D Outage Main Report.

NUREG/CR-6144 V02P3A: EVALUATION OF POTENTIAL SEVERE AC-NUREG/CR 6143 V02PT4 EVALUATION OF POTENTIAL SEVERE AC-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SURRY. UNIT 1 Analysis Of Core Damage Frequency From Internal GRAND GULF. UNIT 1. Analysis Of Core Damage Frequency From In-NUR C

44 02 30 A AT N OF TEN SE E AC-ternal Events For Plant Operational State 5 Dunng A Refuehng CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT Outage internal SURRY. UNIT 1. Analysis Of Core Damage Frequency From internal WALSH,R.

NR C

4 0P E AL A P E Tl SEVERE NUREG/CR-6224 DRF FC: PARAMETRIC STUDY OF THE POTENTIAL DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT FOR BWR ECCS STRAINER BLOCKAGE DUE TO LOCA GENERAT.

ED DEBRIS Dratt For Comment.

SURRY. UNIT 1. Analysis Of Core Damage Frequency From Internal Events Dunng Mid-Loop Operatons Appendices F H NUREG/CR-6144 V02P5 EVALUATION OF POTENTIAL SEVERE ACCl-gggg*y g*

DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR 6128 PIP!NG BENCHMARK PROBLEMS FOR THE ABB/

SURRY. UNIT 1. Analysis Of Core Damage Frequency From Internal CE SYSTEM 604 STANDARDIZED PLANT.

Events " Jnng Mid-Loop Operatens Appendices 1 MEM TANO.M.

NUREG/CR 6121 COMPONENT EVALUATION FOR INTERSYSTEM NUREG/CR 6162. UFECTS OF PRIOR DUCTILE TEARING ON CLEAV-LOSS OF. COOLANT ACCIDENTS IN ADVANCED LIGHT WATER RE.

AGE FRACTURE TOUGHNESS IN THE TRANSITION REGION ACTOR $

~

P:rsonal Author Index 29 L

CARNER,R.D.

WILSON,G.E.

NUREG/CR-5973 A01: CODES AND STANDARDS AND OTHER GUO.

NUREG/CR 5535 V07. RELAP5/ MOD 3 CODE MANUAL.Summanes And ANCE CITED IN REGULATORY DOCUMENTS.

Reviews Of Independent Ccde Assessment Reports.

WARRICK.A.W.

WILSON.M.

NUREG/CR4120. CONTROLLED FIELD STUDY FOR VALIDATION OF NUREG/CR-6233 V01: STABluTY OF CRACKED PIPE UNDER INER.

VADOSE ZONE TRANSPORT MODELS.

TIAL STRESSES Subtask 1.1 F nal Report.

i.

l

[

WELCH.D.L WOLTERMAN,R.L l

NUREG/CR-5908 V02: ADVANCED HUMAN-SYSTEM INTERFACE NUREG/CR-6234. VALIDATON OF ANALYSIS METHODS FOR AS-j DESIGN REVIEW GUCEUNE, Evaluaton Procedures And Guidehnes SESSING FLAWED PIPING SUBJECTED TO DYNAMIC LOADING.

For Humar* Factors Engmeenng Reviews.

WONG.SR WESTRA,C.

NUREG/CR-6144 V02P1 A. EVALUATION OF POTENTIAL SEVERE AC-NUREG/CR-5758 V04 FITNESS FOR DUTY IN THE NUCLEAR POWER CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT r

INDUSTRY Annual Summary Of Program Performance Reports CY SURRY, UNIT 1.Analyms Of Core Damage Frequency From Intemat 1993.

Events Dunng Md Loop Operations Man Report (Chapters 14)

NUREG/CR-6144 V02P18. EVALUATION OF POTENTIAL SEVERE AC-WHITEHEAD D-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATONS AT NUREG/CR-6093. AN ANALYSIS OF OPERATIONAL EXPERIENCE SURRY. UNIT 1. Analysis Of Core Damage Frequency From internal DURING LOW POWER AND SHUTDOWN AND A PLAN FOR AD-Events Dunng Md-Loop Operations Man Report (Chapters 712).

DRESSING HUMAN REttABluTY ASSESSMENT ISSUES.

NUREG/CR-6144 V02P2: EVALUATION OF POTENTIAL SEVERE ACCl-NUREG/CR4143 V02P1 A EVALUATION OF POTENTIAL SEVERE AC' DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SURRY. UNIT 1. Analysis Of Core Damage Frequency From Internal GRAND GULF. UNIT 1.Anafysis Of Core Damage Frequency From l*

Events Dunng Md-Loop Operatons. Appendices A-D.

temal Events For Plant Operational State 5 Dunng A Refuelm9 NUREG/CR.6144 V02P3A: EVALUATION OF POTENTIAL SEVERE AC-l Outage Sectons 1-9 CIDENTS DURING LOW POWER AND SHUTDOWN OPERATONS AT NUREG/CR4143 V02P18. EVALUATON OF POTENTIAL SEVERE AC-SURRY. UNIT 1.Analyss Of Core Damage Frequency From Internal i

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT Events Dunng Md-Loop Operatons Appendices E (Sectons E.1-E.8)

GRAND GULF. UNIT 1. Analysis Of Core Damage Frequency From l*

NUREG/CR4144 V02P3B: EVALUATION OF POTENTIAL SEVERE AC-temal Events For Plant Operatonal State 5 Dunng A Refuelin9 COENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT Outage.Secten 10-SURRY, UNIT 1. Analysis Of Core Damagc Frequency From internal NUREG/CR4143 V02P1C: EVALUATION OF POTENTIAL SEVERF AC-Events Dunng Md-Loop Operatons Appendices E (Sectons E.9-E.16)

COENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR4144 V02P4 EVALUATION OF POTENTIAL SEVERE ACCI-GRAND GULF, UNIT 1.Analysin Of Core Damage Frequency From l*

DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT tornal Events For Plant Operatonal State 5 Durmg A Refuelm9 SURRY, UNIT 1. Analysis Of Core Damage Frequency From internal Outage Mam Report-Events Dunno Mid-Loop Operatons Appenances F-H.

NUREG/CR4143 V02PT2: EVALUATION OF POTENTIAL SEVEP.E AC-NUREG/CR-6144 V02P5. EVALUATION OF POTENTIAL SEVERE ACCl-COENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT GRAND GULF, UNIT 1. Analysis Of Core Damage Frequency From l*

SURRY. UNIT 1. Analysis Of Core Damage Frequency From Internal tornal Events for Plant Operatonal State 5 Dunng Refuelin9 Events Dunng Md-Loop Operations Appendices I.

Outage.IntemaL..

NUREG/CR4143 V02PT3: EVALUATOt. OF POTENTIAL SEVERE AC.

WOOD,5.T.

COENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR4116 V02: SYSTEMS ANALYSIS PROGRAMS FOR GRAND GULF. UNIT 1. Analysis Of Core Damage Frequency From trk HANDS-ON INTEGRATED REUABluTY EVALUATONS (SAPHIRE)

Isrnal Events For Plant Operational State 5 Durmg A Refuelin9 VERSION 5.Olntegrated Rehatxhty And Risk Analysis System (IRRAS)

Outage. internal....

Reference Manual.

NUREG/CR4143 V02PT4. EPALUATION OF POTENTIAL SEVERE AC-NUREG/CR-6116 V04: SYSTEMS ANALYSl$ PROGRAMS FOR CWNTS DURING LOW POWER AND SHUTDOWN OPERATONS AT HANDSON INTEGRATED RELIAB!UTY EVALUATONS (SAPHIRE)

GRAND GULF, UNIT 1 Analysis Of Core Damage Frequency From l'b VERSION 5 0. Systems Analysis And Risk Assessment (SARA) Refer-temal Events For Plant Operational State 5 Durmg A Refuelmg once Manual.

Outage lntemaL NUREG/CR4116 V07. SYSTEMS ANALYSIS PROGRAMS FOR l

NUREG/CR4143 V04: EVALUATON OF POTENTIAL SEVERE ACCl' HANDS-ON INTEGRATED REUABILITY EVALUATIONS (SAPHIRE)

DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT VERSION 5.0 Fault Tree, Event Tree, And Piping & Instrumentaten GRAND GULF. UNIT 1. Analyses Of Core Damage Frequency From In-Diagram (FEP) Editors Reference Manual.

temally induced Flooding Events For Plant Operatonal State 5 Dunng a Refueling..

YAKLE,J.

I NUREG/CR4143 V02P1A: EVALUATON OF POTENTIAL SEVERE AC-t WisLIN.C.

COENTS DURING LOW POWER AND SHUTDOWN OPERATONS AT NUREG/CR4250.

SUMMARY

OF COMMENTS RECEIVED ON STAFF GRAND GULF, UNIT 1. Analysis Of Core Damage Frequency From tr>

i DRAFT PROPOSED RULE ON RADIOLOGICAL CRITERLA FOR DE-temat Events For Plant Operational State 5 Dunng A Refueling COMMISSIONING-Outage Sectons 1-9.

NUREG/CR4143 V02P18: EVALUATION OF POTENTIAL SEVERE AC.

WlEEENGA P.J.

COENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR4120. CONTROLLED FIELD STUDY FOR VALCATION OF GRAND GULF. UNIT 1.Anatysis Of Core Damage Frequency From Ir>

+

VADOSE ZONE TRANSPORT MODELS-temal Events For Plant Operational State 5 Dunng A Refuelm0 Outage.Secton 10.

MLKNIM NUREG/CR-6143 V02P1C: EVALUATION OF POTENTIAL SEVERE AC-NUREG/CR-5128 RO1: EVALUATION AND REFINEMENT or LEAK-COEN1S DURING LOW POWER AND SHUTDOWN OPERATIONS AT GRAND GULF, UNIT 1. Analyses Of Core Damage Frequency From In-NURE /

33 V 1 1B TY OF CRAMED PIPE UNDER INER-temal Events For Plant Operational State 5 Dunng A Refuelin0 TIAL STRESSES Subtask 1.1 Fmal Repart.

NUREG/CR4234 VAllDATION OF ANALwlS METHODS FOR AS.

NU C 4143 PT3: EVALUATION OF POTENTIAL SEVERE AC-SESSING FLAWED PIPING SUBJECTED TO DYNAMIC LOADING.

I CIDENTS D8) RING LOW POWER AND SHUTDOWN OPFRATIONS AT mLLiggggyt, GRAND GULF, UNIT 1. Analysis Of Core Damage Fregoency From in.

NUREG/CR4206: TRANSPORT CALCULATIONS OF RADIATON EX.

temal Events For Plant Operatonal State 5 Dunne A Refuelmg S E TO VESSEL SUPPORT STRUCTURES IN THE TROJAN RE.

gter.

COENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT WILLING.D.L.

GRAND GULF UNIT 1. Analyses Of Core Damage Frequency From In-NUREG/CR-5344 R01: REPLACEMENT ENERGY COST ANALYSIS temal Events For Plant Operatonal State 5 Dunng A Refueling PACKAGE (RECAP): USER'S GUOE.

Outage intamaL-

1 1

30 PCrsonal Author index NUREGICR-6143 V0J EVALUATION OF POTENTIAL SEVERE ACCI-SURRY. UNIT 1 Analysis Of Core Damage Frequency From interna!

DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT Events Dunng Md Loop Operatons Appendices i GRAND GULF. UNIT 1. Analysis Of Core Damage Frequency From In-NUREG/CR 6144 V03 P1. EVALUATION OF POTENTIAL SEVERE AC-ternal Events For Plant Operatonal State 5 Dunng A Refueling Outage CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT VANG.J.

SURREUNIT 1 Analysis Of Core Damage Frequency From Internal Fres Dunng Md-Loop Operatons Main Report NUREG/GR-6144 V02P1 A EVALUATION OF POTENTIAL SEVERE AC-NUREG/CR-6144 V03 P2 EVALUATION OF POTENTIAL SE' VERE AC.

CIDENTS DURING LOW POWEn AND SHUTDOWN OPERATIONS AT CIDENTS DURING LOW POWER AND SHUTDOV 4 OPERATIONS AT SURRY. UNIT 1. Analysis Of Core Damage Frequency From internal SURRY. UNIT 1 Anatysis Of Core Damage Frequency From Internal Events Dunng Md-Loop Operations Marn Report (Chapters 1-6)

Fres Dunng Md-Loop Operatons Appendeces NUREG/CR-6144 V02PIB EVALUATION OF POTENTIAL SEVERE AC-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT Y ARDUMI AN.J.

SURRY, UNIT 1. Analysis Of Core Damage Frequency From Internal NUREG-0525 V02 R02. SAFEGUARDS

SUMMARY

EVENT LIST Events Dunng Md-Loop Operations Main Report (Chapters 7-12)

(SSEL). January 1,1990 Through December 31,1993 NUREG/CR-6144 V02P2-EVALUATION OF POTENTIAL SEVERE ACCI-DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT YEH T'C SURRY, UNIT 1. Analysis Of Core Damage Frequency from Internal N$ REG /CR-6120. CONTROLLED FIELD STUDY FOR VALIDATION OF Events Dunng Md-Loop Operatons Appendices A D.

VADOSE ZONE TRANSPORT MODELS NUREG/CA.6144 V02P3A. EVALUATION OF POTENTIAL SEVERE AC-ZEITOUN.A.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NURE G 1484 V01: FINAL ENVIRONMENT AL IMPACT STATEMENT SURRY. UNIT 1 Analysis Of Core Damage Frequency Frnm internal FOR THE CONSTRUCTION AND OPERATION OF CLAIBORNE EN-Events Dunng Mid Loop Operatons Appendices E (Sectons E.1 E 5')

NUREG/CR 6144 V02P3B EVALUATION OF POTENTIAL SEVERE AC-RICHMENT CENTER, HOMER. LOUISlANA Docket No 70-3070 Louess-ana Eneroy Services. L P Envronmental impact Statement CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG 1444 V02 FINAL ENVIRONMENTAL IMPACT ST ATE ME NT SURRY UNIT 1 Analyses Of Core Damage Frequency From internal FOR THE CONSTRUCTION AND OPERATION OF CLAIBORNE EN-Events Dunng Md-Loop Operations Appendices E (sections E 9-E 16)

RICHMENT CENTER. HOMER. LOUISLANA Docket No 70-3070 Louise NUREG/CR 6144 V02P4. EVALUATION OF POTENTIAL SEVERE ACCl-J DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT ana Energy Services. L P Comments And Responses SURRY. UNIT 1 Analysis Of Core Damage Frequency From internal ZiGLER,G.

Events Dunng Mid Loop Operatens Appendces F-H NUREG/CR-6224 DAF FC PAR AMETRIC STUDY OF THE POTE NTIAL NUREG/CH 6144 V02P5 EVALUATON OF POTENTIAL SEVERE ACCl-FOR BWR ECCS STRAINER BLOCKAGE DUE TO LOCA GENERAT-DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT ED DEBRIS Draft For Commer.t.

i Subject index This index was developed from keywords and word strings in titles and abstracts. During this t

l-development period, there will be some redundancy, which will be removed later when a rea-l sonable thesaurus has been developed through experience. Suggestions for improvements l

cro welcome.

l l

A 533 8 Steel Automat 6c Detect 6on NUREG/CR 5861: CRACK-SPEED RELATIONS INFERRED FROM NUREG/CR 62b5 DESIGN OF AN OPEN ARCHITECTURE SEISMIC LARGE SINGLE-EDGE-NOTCHED SPECIMENS OF A 533 B STEEL-MONITORING SYSTEM.

A!WR BWR NUREG-1503 V01: FINAL SAFETY EVALUATION REPORT RELATED NUREG/CR4143 V02PI A. EVALUATION OF POTENTIAL SEVERE AC-i TO THE CERTIFICATION OF THE ADVANCED BOILING WATER RE' CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT l

ACTOR DESIGN Docket No. 52 001(General Electnc Nuclear Energy)

GRAND GULF, UNIT 1. Analysis Of Core Damage Frequency From In-s NUREG-1503 V02. FINAL SAFETY EVALUATION REPORT RELATED temal Events For Plant Operational State 5 Dunng A Refuehng TO THE CERTIFICATION OF THE ADVANCED BOILING WATER RE' Outage. Sections 19.

ACTOR DESIGN Appendices Docket No. 52 001.(General Electre Nu-NUREG/CR4143 V02P18. EVALUATION OF POTENTIAL SEVERE AC-f clear Evergy)

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT GRAND GULF, UNIT 1. Analysis Of Core Damage Frequency From In-ALWR

"" ^

NUREG/CR-6121 COMPONENT EVALUATION FOR INTERSYSTrA Out LOSS-OF. COOLANT ACCIDENTS IN ADVANCED LIGHT WATF3 RE.

NUREG/CR4143 Vd2P1C: EVALUATION OF POTENTIAL SEVERE AC-

}

ACTORS CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT Atmumal Occurrence GRAND GULF,0 NIT 1. Analyses Of Core Damage Frequency From In-temal Events For Piant Operational State 5 Dunng A Refueling NUREG-0090 Vl? N01. REPORT TO CONGRESS ON ABNORMAL COCURRENCES January-March 1994 NU E CR 143 2PT2: EVALUATION OF POTENTIAL SEVERE AC.

Afranced Boiling Water Reactor CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT l

NUREG-1503 V01: FINAL SAFETY EVALUATION REPORT RELATED GRAND GULF. UNIT 1. Analysis Of Core Damage Frequency From In-TO THE CERTIF4 CATION OF THE ADVANCED BOILING WATER RE.

temal Events For Plant Operational State 5 Dunng Refuehng ACTOR DESIGN Docket No 52-001 (General Electnc Nuclear Fnergy)

Outage Intemal-NUREG-1503 V02: FINAL SAFETY EVALUATION REPORT RELATED NUREG/CR4143 V02PT3. EVALUATION OF POTENTIAL SEVERE AC-t TO THE CERTIFICATION OF THE ADVANCED BOILING WATER RE.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT ACTOR DESIGN Appendices. Docket No. 52 001 (General Electne Nu.

GRAND GULF, UNIT 1. Analysis Of Core Damage Frequency From In-clear Energy) ternal Neats For Plant Operational State 5 Dunng A Refueling j

Outage. Internal.

Att:nced Light Water Reactor NUREG/CR4143 V02PT4 EVALUATION OF POTENTIAL SEVERE AC-NUREG 1242 V03 P101: NRC REVIEW OF ELECTRIC POWER RE.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SEARCH INSTITUTE'S ADVANCED LIGHT WATER PEACTOR UTILi-GRAND GULF, UNIT 1. Analysis Of Core Damage Frequency From In-t TY REQUIREMENTS DOCUMENTS Passwa Plant Designs Chapter temal Events For Plant Operational State 5 Dunng A Refuehng 1 Protect Number 669 Outage.imemaL.

NUREG 1242 V03 PT02: NRC REVIEW OF ELECTRIC POWER RE-NUREG/CR4224 DRF FC: PARAMETRIC STUDY OF THE POTENTIAL l

SEARCH INSTITUTE'S ADVANCED LIGHT WATER RFACTOR UTIL1-FOR BWR ECCS STRAINER BLOCKAGE DUE TO LOCA GENERAT.

TY REQUIREMENTS DOCUMENT Passive Plant DesignsChapters 2-ED DEBRIS Dratt For Comment.

[

13 Protect Number 669 NUREG/CR4121 COMPONENT EVALUATION FOR INTERSYSTEM Blast Protect 6on

't LOSS-OF COOLANT ACCIDENTS IN ADVANCED LIGHT WATER RE-NUREG/CR-6190 V01; PROTECTION AGAINST MALEVOLENT USE OF ACTORS.

VEHICLES AT NUCLEAR POWER PLANTSVehele Bamer System i

Siting Guidance For Blast Protection.

Advanced Reactors System 80 +

NUREG/CR4190 V02: PROTECTION AGAINST MALEVOLENT USE OF i

NURE G/CR4128 PIPING BENCHMARK PROBLEMS FOR THE ABB/

VEHICLES AT NUCLEAR POWER PLANTS. Vehicle Bamer System CE SYSTEM 804 STANDARDIZED PLANT-Siting Guidance For Diast Protection.

Adylsory Panet Boiling Water Reactor l

NUREG/CR4252 LESSONS LEARNED FROM THE THREE MILE NUREG/CR 6143 V02PtA EVALUATION OF POTENTIAL SEVERE AC-i ISLAND UNIT 2 ADVISORY PANEL.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT 1

GRAND GULF, UNIT 1.Anatysis Of Core Damage Frequency From In-4 Air ingress 6on nel Nnts 6 Nnt Opmatonal Staw 5 Nnng A N#ng l

NUREG/CR4218 A REVIEW OF THE TECHNICAL ISSUES OF AIR IN-GRESSION DURING SEVERE REACTOR ACCIDENTS NU GC 13 2P1B EVALUATION OF POTENTIAL SEVERE AC-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT Air Permeability NUREG/CR4203. VALIDATION STUDIES FOR ASSESSING UNSATU.

GRAND GULF, UNIT 1. Analysis Of Core Dama0e Frequency From in-l RATED FLOW AND TRANSPORT THROUGH FRACTURED ROCK.

terra Events For Plant Operational State 5 Dunng A Refuehng Outage Section 10.

AirCsture NUREG/CR4143 V02P1C: EVALUATION OF POTENTIAL SEVERE AC-NUREG/CR 4213; HIGH-TEMPERATURE HYDROGEN. AIR-STEAM CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT DETONATION EXPERIMENTS IN THE BNL SMALL-SCALE DEVELOP.

GRAND GULF. UNIT 1.Ana'ysts Of Core Damage Frequency From In-

?

MENT APPARATUS temal Events For Plant Oparational State 5 Dunng A Refueling Outage Main Report Annual Report NUREG/CR4143 V02PT2 EVALUATION OF POTENTIAL SEVERE AC.

NUREG-1145 V10. O S NUCLEAR REGULATORY COMMISSION 1993 CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT ANNUAL REPORT.

GRAND GULF, UNIT 1. Analysis Of Core Damage Frequency From In-31 l

i l

1

32 Subject index temal Events For Plant Operatonal State 5 Dunng Refueling SURRY UNIT 1. Analysis Of Core Damage Frecuency From intemal Outage internal...

Events Dunng M4Looo Operatons Main Report (Chapters 712).

NUREG/CR4143 V02PT3: EVALUATION OF POTENTIAL SEVERE AC-NUREG/CR-6144 V02P2: EVALUATION OF POTENTIAL SEVERE ACCI-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT GRAND GULF. UNIT 1. Analysis Of Core Damage Frequency From In-SURRY UNIT 1 Analysis Of Core Damage Frequency From Internal tornal Events For Plant Operatonal State 5 Dunng A Refueling Events Dunng M4 Loop Operatons.Appendees A-D.

Outage intemal.

NUREG/CR4144 V02P3A: EVALUATION OF POTENTIAL SEVERE AC-NUREG/CR4143 V02PT4. EVALUATION OF POTENTIAL SEVERE AC.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SURRY UNIT 1. Analysis Of Core Damage Frequency From intemal GRAND GULF. UNIT 1 Analysis Of Core Damage Frequency From In-Events Dunng M4 Loop Operatons Appendees E (Sectons E.1 E.8).

ternal Events For Plant Operatonal State 5 Dunng A Refueling NUREG/CR-6144 V02P38. EVALUATION OF POTENTIAL SEVERE AC-Outage internal CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR4224 DAF FC: PARAMETRIC STUDY OF THE POTENTIAL SURRY UNIT 1. Analysis Of Core Damage Frequency From intemal FOR BWR ECCS STRAINER BLOCKAGE DUE TO LOCA GENERAT-Events Dunng M4 Loop Operatons.Appendees E (Sectons E 9-E.16).

ED DEBRIS Draft For Comment.

NUREG/CR-6144 V02P4. EVALUATION OF POTENTIAL SEVERE ACCl-DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT O'

NU E O ASSESSMENT OF DATABASES AND MODELING CAPA-Events Dunng Mid-Loop Operatons.Appendees F-H.

BILITIES FOR THE CANDU 3 DESIGN NUREG/CR4144 V02P5: EVALUATION OF POTENTIAL SEVED5 ACCI-DENTS DURING LOW POWER AND SHUTDOWN OPERA *.h)NS AT Claiborne Enrichment Center NUREG 1484 vot: FINAL ENVIRONMENTAL IMPACT STATEMENT SURRY. UNIT 1. Analysis Of Core Damage Frequency From intemal FOR THE CONSTRUCTION AND OPERATION OF CLAIBORf6 EN.

Events Dunng M4 Loop Operatons.Appendees 1.

NUREG/CR4144 V03 P1: EVALUATION OF POTENTIAL SEVERE AC-RICHMENT CENTER HOMER. LOUISIANA Docket No. 70-3070.Lourss-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT ana Energy Servces. L P. Environmental Impact Statement NUREG 1484 V02: FINAL ENVIRONMENTAL IMPACT STATEMENT SURRY. UNIT 1. Analysis Of Core Damage Frequency From Intemal FOR THE CONSTRUCTION AND OPERATION OF CLAIBORNE EN.

Fires Dunng M4 Loop Operatons Main Report.

NUREG/CR-6144 V03 P2: EVALUATION OF POTENTIAL SEVERE AC-RICHMENT CENTER, HOMER. LOUISLANA. Docket No. 70-3070 Louis.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT ana Energy Services. LP. Comments And Responses.

SURRY. UNIT 1. Analysis Of Core Damage Frequency From Internal Code F6res Dunng M4 Loop Operatons.Appendees.

NUREG/CR 5973 R01: CODES AND STANDARDS AND OTHER GUID-NUREG/CR4144 V04. EVALUATION OF POTENTIAL SEVERE ACCI-ANCE CITED IN REGULATORY DOCUMENTS.

DENTS DURING LOW POWER AND SHUTDOWN OPERAllONS AT SURRY UNIT 1. Analysis Of Core Damage Frequency From intemal Cognitive Skill Floods Dunng M4 Loop Operatons.

NUREGICA-6127. THE EFFECTS OF STRESS ON NUCLEAR POWER NUREG/CR4144 V05: EVALUATION OF POTENTIAL SEVERE ACCI-PLANT OPERATIONAL DECISION MAKING AND TRAINING AP.

DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT PROACHES TO REDUCE STRESS EFFECTS.

SURRY. UNIT 1. Analysis Of Core Damage Frequency From Seisme Events Dunng M4 Loop Operatons. Main Report.

NUREG/CR-6128. PIPING BENCHMARK PROBLEMS FOR THE ABB/

Core Degradation CE SYSTEM 80 + STANDARDIZED PLANT.

NUREG/CR4218: A REVIEW OF THE TECHNICAL ISSUES OF AIR IN-GRESSION DURING SEVERE REACTOR ACCIDENTS Concrete Cracking NUREG/CR-6236. SEISMIC INVESTIGATIONS OF THE HDR SAFETY Crack i

PROGRAM Summary Report-NUREG/CR 5128 R01. EVALUATION AND REFINEMENT OF LEAK-RATE ESTIMATION MODELS.

Containment NUREG/CR-6213 HIGH-TEMPERATURE HYDROGEN-AIR STEAM O'

DET NAT EXPERIMENTS IN THE BNL SMALL-SCALE DEVELOP-NUR R-5591 V02 N1: HEAVY SECTION STEEL IRRADIATION PROGRAM Semiannual Progress Report For October 1990 - March Containment Heating 1991.

NUREG/CR4152. EXPERIMENTS TO INVESTIGATE DIRECT CON-Crack Growth TAINMENT HEATING PHENOMENA WITH SCALED MODELS OF THE NUREG/CR-6162 EFFECTS OF PRIOFi OUCTILE TEARING ON CLEAV-SURRY NUCLEAR POWER PLANT.

AGE FRACTURE TOUGHNESS IN THE TRANSITION REGtON.

Control Room NUREG/CR 5908 V01: ADVANCED HUMAN-SYSTEM INTERFACE Crack Statdlity DESIGN REVIEW GUIDELINE. General Evaluaten Model. Techncal NUREG/CR4234. VALIDATION OF ANALYSIS METHODS FOR AS-Development. And Guideline Desenpton.

SESSING FLAWED PIPING SUBJECTED TO DYNAMIC LOADING.

NUREG/CR 5908 V02. ADVANCED HUMAN-SYSTEM INTERFACE DESIGN REVIEW GUIDELINE. Evaluaton Procedures And Guidelines Cracked Pipe For Human Factors Engineenng Reviews NOREG/CR4233 V01: STABILITY OF CRACKED PIPE UNDER INER-r TIAL STRESSES Subtask 1.1 Final Report.

Core Damage NUREG/CR-6143 V03. EVALUATION OF POTENTIAL SEVERE ACCl-Database DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG-1502: ASSESSMENT OF DATABASES AND MODELING CAPA-GRAND GULF. UNIT 1 Analysis Of Core Damage Frequency From in-BILITIES FOR THE CANDU 3 DESIGN.

temal Events F or Plant Operatonal State 5 Dunng A Refueling Outane.

NUREG/CR 6143 V04: EVALUATION OF POTErolAL SEVERE ACDl-Detwte DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR4224 DAF FC: PARAMETRIC STUDY OF THE POTENTIAL GRAND GULF. UNIT 1. Analysis Of Core Damage Frequency From In-FOR BWR ECCS STRAINER BLOCKAGE DUE TO LOCA GENERAT.

temally Inrtuced Flooding Events For Plant Operatonal State 5 Dunng ED DEBRIS. Draft For Comment, a Refueling --

NUREG/CR4143 V05: EVALUATION OF POTENTIAL SEVERE ACCl.

Decomnweeloning DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG-1307 R04: FIEPORT ON WASTE BURtAL CHARGES Escalaton GRAND GULF. UNIT 1 Analysis Of Core Damage Frequency From Of Decommissorung Waste Disposal Costs At Low-Level Waste Bunal Seisme Events Dunng M4 Loop Operatons Main Report.

Facilities.

NUREG/CR4144 V02PI A: EVALUATION OF POTENTIAL SEVERE AC.

NUREG 1496 V1 DRF FC: GENERIC ENVIRONMENTAL IMFACT CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT STATEMENT IN SUPPORT OF RULEMAKING ON RADIOLOGICAL SURRY UNIT 1. Analysis Of Core Damage Frequency From intemal CRITERIA FOR DECOMMISSIONING OF NRCLICENSED NUCLEAR Events Dunno M4 Loop Operations Main Report (Chapters 14)

FACILITIES Main Report Draft Report For Comment.

NUREG/CR 6144 V02P10. EVALUATION OF POTENTIAL SEVERE AC-NUREG 1496 V2 DAF FC: GENERIC ENVIRONMENTAL IMPACT CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT STATEMENT IN SUPERT OF RULEMAKING ON RADIOLOGICAL

.. ~

Subject index 33 j

CRITERIA FOR DECOMMISSIONING OF NRC. LICENSED NUCLEAR Event Tree FACILITIES Appendees Draft Report For Comment NUREG/CR 6116 V07: SYSTEMS ANALYSIS PF4;CTL"!,3 FOR NUREG 1500: WORKING t RAFT REGULATORY GUIDE ON RELEASE HANDS-ON INTEGRATED RELIABILITY EVALUATIONS (SAPHIRE)

CRITERIA FOR DECOMt4!SSIONING NRC STAFF'S DRAFT FOR VERSION 5.0. Fault Tree, Event Tree, And Ppng & Instrumentation NU 1

DRFT: BACKGROUND AS A RESIDUAL RADIOACTIVITY CRITERION FOR DECOMMISSIONING Appenda A To The Draft Go-Eseminor Stenderd nere Envronmental Impact Statement in Support Of Rulemaking On NUREG 1478. NON-POWER REACTOR OPERATOR LICENSING EXAM-Radiolopcal Critena For Decommisssoning Of NRC....

INER STANDARDS.

NUREG/GR4250:

SUMMARY

OF COMMENTS RECEIVED ON STAFF DRAFT PROPOSED RULE ON RADIOLOGICAL CRITERIA FOR DE.

FEP COMMISSIONING NUREG/CR-6116 VOT: SYSTEMS ANALYSIS PROGRAMS FOR HANDS-ON INTEGRATED REUABILITY EVALUATIONS (SAPHIRE)

Detonationo-Esperimental Date VERSION 5.0. Fault Tree. Event Tree. And Peng & Instrumentation NUREG/CR-6213.

HIGH. TEMPERATURE HYDROGEN AIR-STEAM Diagram (F EP) Editors Reference Manual.

DETONATION EXPERIMENTS IN THE BNL SMALL SCALE DEVELOP-MENT APPARATUS.

Fe%ue NUREG 1426 V02. COMPILATION OF REPORTS FROM RESEARCH Direct Containment Heat 6ng SUPPORTED BY THE MATERIALS ENGINEERING WUREG/CR4168 DIRECT CONTAINMENT HEATING INTEGRAL EF-BRANCH. DIVISION OF ENGINEERING.1991-1993.

FECTS TESTS AT 1/40 SCALE IN ZION NUCLEAR POWER PLANT GEOMETRY.

Fatigue Crack init6etion

+

NUREG/CR4237: STATISTICAL ANALYSIS OF FATIGUE STRAIN-LIFE Draft Proposed Rule DATA FOR CARBON AND LOW-ALLOY STEELS.

=

NUREG/CR4250

SUMMARY

OF COMMENTS RECEIVED ON STAFF DRAFT PROPOSED RULE ON RADIOLOGICAL CRITERIA FOR DE.

FeMue Damage COMMISSIONING.

NUREG/GR 0013 APPLICATIONS OF A NEW MAGNETIC MONITOR-ING TECHNIQUE TO IN SITU EVALUATION OF FATIQUE DAMAGE Draft Regu6 story Guide IN FERROUS COMPONENTS.

NUREG 1500. WORKING DRAFT REGULATORY GUIDE ON RELEASE CRITERIA FOR DECOMMISSIONING: NRC STAFF'S DRAFT FOR Fault Tree COMMENT.

NUREG/CR4116 V07. SYSTEMd ANALYSIS PROGRAMS FOR HANDS-ON INTEGRATED RELIABILITY EVALUATIONS (SAPHIRE) i Ductile Teer6ng VERSION 5.0. Fault Tree, Event Tree, And Pen 0 & Instrumentation NUREG/CR4162. EFFECTS OF PRIOR DUCTILE TEARING ON CLEAV-Diagram (FEP) Editors Reference Manual AGE FRACTURE TOUGHNESS IN THE TRANSITION REGION p

Dynamic Load NUREG 1460 R01: GUIDE TO NRC REPORTING AND RECORDKEEP-NUREG/CR4128 PIPING BENCHMARK PROBLEMS FOR THE ABR/

tNG REQUIREMENTS. Compded From Requirements in Title 10 Of CE SYSTEM 80+ STANDARDIZED PLANT.

The U S. Code Of Federal Regulations As Codified On December 31, 1993.

Dynamic Loading c

NUREG/CR4178 LABORATORY CHARACTERIZATION OF ROCK Felvous Component

'5 JOINTS NUREG/GR-0013. APPLICATIONS OF A NEW MAGNETIC MONITOR-NUREG'CR-6234 VALIDATION OF ANALYSIS METHODS FOR AS.

ING TECHNIQUE TO IN SITU EVALUATION OF FATIOUE DAMAGE SESSING FLAWED P1 PING SUBJECTED TO DYNAMIC LOADING IN FERROUS COMPONENTS.

Dynamic Arrest Toughnese Field Study i

NUREG/CR.5861: CRACK-SPEED RELATIONS INFERRED FROM NUREG/CR-6120: CONTROLLED FIELD STUDY FOR VALIDATION OF LANGE SINGLE-EDGE-NOTCHED SPECIMENS OF A 533 B STEEL VADOSE 2ONE TRANSPORT MODELS i

ECCs Final Design Approval i

NUREG/CR4224 DAF FC. PARAMETRIC STUDY OF THE POTENTIAL NUREG 1242 V03 PT01: NRC REVIEW OF ELECTRIC POWER RE-FOR BWR ECCS STRAINER BLOCKAGE DUE TO LOCA GENERAT-SEARCH INSTITUTE'S ADVANCED LIGHT WATER REACTOR UTILi-ED DEBRIS Draft For Comment TV REQUIREMENTS DOCUMENTSPassive Plant Designs Chapter 1 Project Number 669 Electodynamic NUREC-1242 V03 PT02: NRC REVIEW OF ELECTRIC POWER RE-NUREG/CR4861: CRACK SPEED RELATIONS INFERRED FROM SEARCH INSTITUTE'S ADVANCED LIGHT WATER REACTOR UTILt-LARGE SINGLE-EDGE NOTCHED SPECIMENS OF A 533 B STEEL.

TY REQUIREMENTS DOCUMENT. Passive Plant DesignsChapters 2 13 Project Number 669 Embrittlement NUREG 1462 V01: FINAL SAFETY EVALUATION REPORT RELATED

'i NUREG/CR-5591 V02 N1: HEAVY SECTION STEEL IRRADIATON TO THE CEFTIFICATION OF THE SYSTEM 80+ DESIGN Chapters 1 PROGRAM. Semiannual Progress Report For October 1990 March 14 Docket No. 52 002. (Asea Brown Boven-Combustion Engineenng) 1991.

NUREG 1462 V02: FINAL SAFETY EVALUATON REPORT RELATED TO THE CERTIFICATION OF THE SYSTEM 80+ DESIGN Chapters Enforcement Acteo" 15-22 And Appendices. Docket No.52-002(Anes Brown Boven-Com-NUREG-0940 V13N01P01: ENFORCEMENT ACTONS: SIGNIFICANT bustion Engineenng)

ACTIONS RESOLVED REACTOR LICENSEES Ouarterly Progress Report. January-March 1994 Final Env6ronmental Impact Statement NUREG-0940 V13N0tP02. ENFORCEMENT ACTIONS: SIGNIFICANT NUREG-1484 V01: FINAL ENVIRONMENTAL IMPACT STATEMENT ACTIONS RESOLVED MEDICAL LICENSEES Ouarterly Progress FOR THE CONSTRUCTION AND OPERATION OF CLAIBORNE EN-Report. January-March 1994 RICHMENT CENTER, HOMER. LOUISIANA. Docket No 70 3070,Louiso i.

RUREG 0940 V13N01P03. ENFORCEMENT ACTIONS. SIGNIFICANT ana Energy Servees. LP. Environmental Impact Statement ACTIONS RESOLVED INDUSTRIAL LICENSEESouarterly Progress NUREG 1484 V02 FINAL ENVIRONMENTAL IMPACT STATEMENT Report. January M. arch 1994 FOR THE CONSTRUCTION AND OPERATON OF CLAIBORNE EN-WUREG 0940 V13N0?P01' ENFORCEMENT ACTONS. SIGNIFICANT RICHMENT CENTER, HOMER. LOUISIANA. Docket No. 70 ~.,070.Louish i

i ACTIONS RESOLVED REACTOR LICENSEES Quarterly Psogress ana Energy Seryces, L P. Comments And Responses r'

Report Apreslune 1994 RUREG 0940 V13N0?P02: ENFORCEMENT ACTONS SIGNIFICAN T Final Safety Evaluat6on Report AC DONS RESOLVED MEDICAL LICENSEES ouarterty Progress NUREG-1462 V01. FINAL SAFETY EVALUATION REPORT RELATED Report.Aptd-June 1994 TO THE CERTIFICATION OF THE SYSTEM 80+ DESIGN Chapters 1-NUREG 0940 V13N0?P03 ENFORCEMENT ACTIONS SIGNIFICANT 14 Docket No. 52402 (Asea Brown BoverFCombustion Ergneenng)

ACTONS RESOLVED INDUSTRIAL LICENSEES Quarterly Progress NUREG-1462 V02 FINAL SAFETY EVALUATION REPORT RELATED I

Report,Aprd-June 1994 TO THE CERTIFICATION OF THE SYSTEM Ph DESIGNChapters f

{

(

i

.n..--

34 Subject index 15-22 And Appendices Docket No 52-002 (Asea Brown Boven Com-High Pressure Melt Election bustion Engineenng)

NUREG/CR 6152. EXPERIMENTS TO lNVESTIGATE DIRECT CON-NUREG 1503 V01: FINAL SAFETY EVALUATION REPORT RELATED TAINMENT HEATING PHENOMENA WITH SCALED MODELS OF THE TO THE CERTIFICATION OF THE ADVANCED BOILING WATER RE-SURRY NUCLEAR POWER PLANT.

ACTOR DESIGN Docket No.52-001 (General Electnc Nuclear Energy)

NUREG-1503 V02 FINAL SAFETY EVALUATION REPORT RELATED Human Error TO THE CERTIFICATION OF THE ADVANCED BOILING WATER RE-NUREG/CR 4639 V5R4P2: NUCLEAR COMPUTERIZED LIBRARY FOR ACTOR DESIGN Appendeces Docket No 52 001(General Electnc No-ASSESSING REACTOR REUABluTY (NUCLARR) Volume 5. Data clear Energy)

Manual Part 2: Human Error Probability (HEP) Data NUREG/CR-4639 V5R4P3. NUCLE AR COMPUTE Rl2ED LIBRARY FOR F6nancial Statement ASSESSING REACTOR REUABIUTY (NUCLARR) Volume 5: Data NUREG-1470 V03 FINANCIAL STATEMENT FOR FISCAL YEAR 1993 Manual Part 3 Hardware Component Failure Data NUREG/CR 6208 AN EMPIRICAL INVESTIGATION OF OPERATOR Fitness For Duty NUREG/CR-5758 V04 FITNESS FOR DUTY IN THE NUCLEAR POWER PERFORMANCE IN COGNITIVELY DEMANDING SIMULATED EMER-GENCIES INDUSTRY Annual Summary Of Program Performance Reports CY 1993.

Human Factors Engineer 6ng NUREG/CR-5908 V01. ADVANCED HUMAN SYST EM INTERFACE Fiswed Piping DESIGN REVIEW GUIDEUNE. General Evaluation Model, Technical NURE G/CR-0234. VALIDATION OF ANALYSIS METHODS FOR AS-SESSING FLAWED PlPING SUBJECTED 10 DYNAMIC LOADING Development, And Guideline Description.

NUREG/CR-5908 V02 ADVANCED HUMAN-SYSTEM INTERFACE Fracture Mechanics DESIGN REVIEW GUIDEUNE. Evaluation Procedures And Guidehnes NUREG 1426 V02 COMPILATION OF REPORTS FROM RESEARCH F or Human Factors Engineereng Reviews.

SUPPORTED BY THE MATERIALS ENGINEERING Human Factors Engineering Program BRANCH.DIVISLON OF ENGINEERING 1991 1993 NUREG 0711 HUMAN FACTORS ENGINEERING PROGRAM REVIEW NUREG/CR-4219 V10 N1: HEAVY SECTION STEEL TECHNOLOGY MODEL PROGRAM Semiannual Progress Report For October 1992 - March 1993 Human Retabnity NUREG/CR-5128 ROI EVALUATION AND REFINEMENT OF LEAK-NUREG/CR 6093 AN ANALYSIS OF OPERATIONAL EXPERIENCE RATE ESTIMATION MODELS DURING LOW POWER AND SHUTDOWN AND A PLAN FOR AD-NUREG/CR 5591 V02 N1 HEAVY-SECTION STEEL IRRADIATION DRESSING HUMAN REllABluTY ASSESSMENT ISSUES PROGRAM Semiannual Progress Repor1 f or October 1990 March NUREG/CR 6208 AN EMPIRICAL INVESTIGATION OF OPERATOR 1991.

PERFORMANCE IN COGNITIVELY DEMANDING blMULATED EMER-NUREG/CR 6233 V01: STABluTY OF CRACKED PIPE UNDER INER-GENCIES TIAL STRESSES Subtask 1.1 Final Report NUREG/CR 6234 VALIDATION OF ANALYSIS METHODS FOR AS-Human-System lnterf ace SESSING FLAWFD PIPING SUBJECTED TO DYNAMIC LOADING NUREG/CR 5908 V01: ADVANCED HUMAN SYSTEM INTERFACE Fracture Toughness DESIGN REVIEW GUIDELINE. General Evaeustion Model. Techrucal NUREG/CR 4513 RO1: ESilMATION OF FRACTURE TOUGHNESS OF NU 5 8 V2 H'UMAN-SYSTE M INTERFACE CAST STAINLESS STEELS DURING THERMAL AGING IN LWR SYS-DESIGN REVIEW GUIDELINE Evaluation Procedures And Guidelines NUREG/CR 6162 EFF ECTS OF PRIOR DUCTILE TEARING ON CLEAV-For Human Factors Engineenng Reviews AGE FRACTURE TOUGHNESS IN THE TRANSITION REGION 1RRAS Fractured Rock NUREG/CR-6116 V01: SYST EMS ANALYSIS PROGRAMS FOR NUREG/CR 6203 VALIDATION STUDIES FOR ASSESSING UNSATU-HANDSON INTEGRATED REUABluTY EVALUATIONS (SAPHIRE)

RATED FLOW AND TRANSPORT THROUGH F RACTURED ROCK VERSION 5 0 Technical Reference Manual NUREG/CR.6116 V02 SYSTE MS ANALYSIS PROGRAMS FOR Fuel Performance Report HANDS-ON INTEGRATED RELIABILITY EVALUATIONS (SAPHIRE)

NUREG/CR-3950 V09 FUEL PERFORMANCE REPORT FOR 1991.

VERSION 5 0lntegrated Rehabihty And Risk Analysis System (IRRAS)

Reference Manual.

Generalized Beamforming NUREG/CR-6116 V03-SYSTEMS ANALYSTS PROGRAMS FOR NUREG/CR 6255. DESIGN OF AN OPEN ARCHITECTURE SLISMIC HANDS-ON INTEGRATED REUABluTY EVALUATIONS (SAPHIRE)

MONITORING SYSTEM VERSION 5 0 integrated Rehability And Risk Analysis System (IRRAS)

Tutoral Manual Generic EnvironmentalImpact Statement NUREG 1496 V1 DRF FC GE NE RIC E NVIRONMENT AL IMPACT ISLOCA STATEMENT IN SUPPORT OF RULEMAKING ON RADIOLOGICAL NURE G/CR-6121: COMPONENT EVALUATION FOR INTERSYSTEM CRITERIA FOR DECOMMISSIONING OF NRC UCENSED NUCLEAR LOSS OF-COOLANT ACCIDENTS IN ADVANCED LIGHT WATER RE-F ACILITIES Main Repor1 Draft Report For Comment ACTORS NURE G-1496 V2 DRF F C.

GE NE RIC ENVIRONMENTAL IMPACT STATEMENT IN SUPPORT OF RULEMAKING ON RADIOLOGICAL Independent Code Assessment CRITERIA FOR DECOMMISSIONING OF NRC-LICENSED NUCLEAR NUREG/CR 5535 V07. RELAP5' MOD 3 CODE MANUALSummanes And FACIUTIES Apperdces Draft Report For Comment Reviews Of Independent Code Assessment Reports.

NUREG-1501 DRFT: BACAGROUND AS A RESIDUAL RADIOACTIVITY CRITERION FOR DECOMMISSIONING Appendix A To The Dratt Ge.

Inertial Stress nenc Environmental impact Statement in Support Of Rulemaking On NUREG/CR 6233 V01: STABILITY OF CRACKED PIPE UNDER INER, Radiological Cnlana For Decommissioning Of NRC..

TIAL ST RESSES Subtask 11 Final Report.

HDR Safety Program innervice inspection NUREG'CR 4236 SEISMIC INVESTIGATIONS OF THE HDR SAFETY NUREG/CR-6151: FEASIBlUTY OF DEVELOPING RISK BASED RANK-i PROGRAM Summary Fleport INGS OF PRESSURE BOUNDARY SYSTEMS FOR INSERVICE IN-i SPECTION Heavy Section Steel Technology Program NUREG/CR 6181: A PILOT APPUCATION OF RISK-BASED METHODS NUREC/CR-4219 V10 N1 HEAVY SECTION STEEL TECHNOLOGY TO ESTABUSH INSERVICE INSPECTION PR:ORITIES FOR NUCLE.

PROGRAM Semiannual Progress Report F or October 1992 - March AR COMPONFNTS AT SURRY UN!! 1 NUCLEAR POWER STATION 1993 Inservice Testing Heavy Section Steellrradtation Program NUREG/CP 0137 V01 PROCEEDINGS OF THE THIRD NRC/ASME NUREG/CR 5591 V02 N1 HE AVY-SE CTION STEEL 1RRADIATION SYMPOslUM ON VALVE AND PUMP TESTING He6d At The Hyatt Re-j PROGRAM Semannual Prorpess Report For Octobor 1990 March gency Hotel. Washington DC, July 18-21,1994 Session 1 A - Session i

1991 2C.

Subject index 35 NUREG/CP-0137 V02: PROCEEDINGS OF THE THIRD NRC/ASME NUREG 0750 V39102. INDEXES TO NUCLEAR REGULATORY COM-SYMPOSIUM ON VALVE AND PUMP TESTING Held At The Hyatt Re-MISSION ISSUANCES January-June 1994.

gency Hotei. Washengton.DC.suly 18-21, 1994Sesson 3A -Sessor, NUREG-0750 V39 N05: NUCLEAR REGULATORY COMMISSION IS-48.

SUANCES FOR MAY 1994 Pages 249-264 NUREG 0750 V39 N06. NUCLEAR REGULATORY COMMISSION IS-Internal Event SUANCES FOR JUNE 1994 Pages 285-390.

NUREG/CR-5726: REVIEW OF THE DIABLO CANYON PROBABILISTIC NUREG-0750 V40 N01: NUCLEAR REGULATORY COMMfSSION IS-RISK ASSESSMENT.

SUANCES FOR JULY 1994 Pages 141.

I NUREG/CR-6143 V03 EVALUATION OF POTENTIAL SEVERE ACCI-l DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT Lessons Learned GRAND GULF. UNIT 1. Analysis Of Core Damage Frequency From In-NUREG/CR-6252: LESSONS LEARNED FROM THE THREE MILE t

tornal Events For Plant Operatonal State 5 Dunno A Refuehng Outage ISLAND-UNIT 2 ADVISORY PANEL.

NUREG/CR-6144 V02P1 A EVALUATION OF POTENTIAL SEVERE AC.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT Light Water Reactor SURRY. UNIT 1. Analysis Of Core Damage Frequency From internal NUREG/CR 4513 RO1: ESTIMATION OF FRACTURE TOUGHNESS OF Events Dunno M4 Loop Operations Main Report (Chapters 16)

CAST STAINLESS STEELS DURING THERMAL AGING IN LWR SYS-NUREG/CR-6144 V02PIB EVALUATION OF POTENTIAL SEVERE AC-TEMS CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SURRY. UNIT 1. Analysis Of Core Damage Frequency From internal Loss-Of-Coolant Accident i

Events Dunng Md-Loop Operatons Main Report (Chapters 712]

NUREG/CR-6121: COMPONENT EVALUATION FOR INTERSYSTEM j

NUREG/CR4144 V02P2: EVALUATION OF POTENTIAL SEVERt: ACCl-LOSS-OF-COOLANT ACCIDENTS IN ADVANCED LIGHT WATER RE-DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT ACTORS SURRY. UNIT 1.Anatysis Of Core Damage Frequency From Internal Events Dunng Md-Loop Operatons Appendicos A-D Low Power i

NUREG/CR 6144 V02P3A. EVALUATION OF POTENTIAL SEVERE AC-NUREG/CR-6093. AN ANALYSIS OF OPERATIONAL EXPERIENCE CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT DURING LOW POWER AND SHUTDOWN AND A PLAN FOR AD-SURRY, UNIT 1.Analyss Of Core Damage Frequency From internal DRESSING HUMAN RELIABILITY ASSESSMENT ISSUES.

Event. Dunno M4 Loop Operatons Appendices E (Sections E 1 E B)

NUREG/CR 6143 V02P1 A EVALUATION OF POTENTIAL SEVERE AC-NUREG/CR 6144 V02P2B EVALUAllON OF POTENTIAL SEVERE AC-CIDENTS DUnlNG LOW POWER AND SHUTDOWN OPERATIONS AT CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT GRAND GULF, UNIT 1. Analysis Of Core Damago Frequency From In-SURRY, UNIT 1.Anatysis Of Core Damago Frequency From Internal ternal Events For Plant Operatonal State 5 Dunng A Refueleng Events Dunng M4 Loop Operations. Appendices E (Sectons E 9-E 16)

Outage Sectons 19 NUREG/CR-6144 V02P4 EVALUATION OF POTENTIAL SEVERE ACCI-NUREG/CR4143 V02P18. EVALUATION OF POTENTIAL SEVERE AC-DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SURRY, UNIT 1. Analysis Of Core Damage Freque icy From '9temal GRAND GULF. UNIT 1. Analysis Of Core Damage Frequency From In-temal Events For Plant Operatonal State 5 Dunng A Refuehng NU GC 6 44 Vb2 E L F

TE lAL SEVERE ACCl-DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NU

/C 143 Vd2P1C. EVALUATION OF POTENTIAL SEVERE AC-SURRY UNIT 1 Analysis Of Core Damage Frequency From Intemal CIDENTS DUnlNG LOW POWER AND SHUTDOWN OPERATIONS AT Events Dunny M4 Loop Operatons Appendices I.

GRAND GULF, UNIT 1. Analysis Of Core Damage Frequency From Irr internal F6re ternal Events For Plant Operatonal State 5 Dunng A Refueling NUREG/CR 6144 V03 PI: EVALUATION OF POTENTIAL SEVERE AC-Outage Mam Report CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR-6143 V02PT2: EVALUATION OF POTENTIAL SEVERE AC-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SURRY, UNIT 1 Analysis Of Core Damage Frequency From Internal Fwes Dur Mid Loop Operations Main Re GRAND GULF. UNIT 1 Analysis Of Core Damage Frequency From In-NUREGICR 144 V03 P2. EVALUATION O POTENTIAL SEVERE AC-ternal Events For Plant Operatonal State 5 Dunng Refueling CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT Outage Internal.-

NUREG/CR-6143 V02PT3 EVALUATION OF POTENTIAL SEVERE AC.

SURRY, UNIT 1. Analysis Of Core Damage Freauency From intemal Fires Dunng Mid Loop Operatons. Appendices CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT GRAND GULF, UNIT 1. Analysis Of Core Damage Frequency From In-Internal Flood temal Events For Plant Operatonal State 5 Dunng A Refuehng NUREG/CR 6144 V04 EVALUATION OF POTENTIAL SEVERE ACCl-Outage internal ~.

DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR-6143 V02PT4. EVALUATION OF POTENTIAL SEVERE AC-SURRY, UNIT 1 Analysis Of Core Damage Frequwncy From Internal CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT Floods Dunng MdLoop Operatons GRAND GULF, UNIT 1 Analysis Of Core Damage frequency From In-ternal Events For Plant Operational State 5 Dunng A Refuehng intirphase Drag Outage. internal.-.

NUREG/CR 5535 VOT RELAP5/ MOD 3 CODE MANUAL Summanes And NUREG/CR-6143 V03 EVALUATION OF POTENTIAL SEVERE ACCl-Reviews Of independent Code Assessment Reports.

DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT GRAND GULF,UNtT 1 Analysis Of Core Damage Frequency From In-WA temal Events For Plant Operatonal State 5 Dunng A Refuehng Outage.

NUREG/CR 6224 DAF FC PARAMETRIC STUDY OF THE POTENTIAL NUREG/CR 6143 V04. EVALUATION OF POTENTIAL SEVERE ACCl-FOR BWR ECCS STRAINER Bl.OCKAGE DUE TO LOCA GENERAT-DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT ED DEBRIS Draft For Comment GRAND GULF. UNIT 1. Analysis Of Core Damage Frequency From In-temally induced Fiooding Events For Plant Operatonai State 5 Dunng LWR NUREG/CR-45$3 ROI ESTIMATION OF FRACTURE TOUGHNESS OF NURE I43 V05 EVALUATION OF POTENTIAL SEVERE ACCl-CAST STAINLESS STEELS DURING THERMAL AGING IN LWR SYS DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT TEMS GRAND GULF, UNIT 1.Anatysis Of Core Damage Frequency From Lc9k Rate Seismic Events Dunng M4 Loop Operatons Mam Report.

NUREGICR 5128 RJ1 EVALUATION AND REFINEMENT OF lEAK.

NUREG/CR-6144 V02P1 A: EVALUATION OF POTENTIAL SEVERE AC.

RATE ESTIMATION MODELS CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SURRY. UNIT 1. Analysts Of Core Damage Frequency From Internal Legat issuances Events Dunng MdLoop Operations Main Report (Chapters 16)

NUREG-0750 V37.

NUCLEAR REGULATORY COMMISSION NUREG/CR 6144 V02P1B EVALUATION OF POTENTIAL SEVERE AC-ISSUANCES Opinons And Decisons Of The Nuclear Regulatory Com.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT mmaion with Selected Orders January-June 1993 SURRY. UNIT 1. Analyses Of Core Damage Frequency From Internal NUREG 0750 V38 NUCLEAR RE GULATOR Y COMMISSION Events Dunng MdLoop Operatons Main Repoit (Chapters 712)

ISSUANCES Opinions And Decisons Of The Nuclear Rogulatory Com.

NUREG/CR 6144 V02P2 EVALUATION OF POTENTIAL SEVERE ACCl-masson With Sc6ected Orders July-Decemtrer 1993 DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG 0750 V39101. INDEXES TO NUCLEAR REGULATORY COM-SURRY. UNIT 1 Analysis Of Core Damage Frequency From Intemal MISSION ISSUANCES January -March 1994 Events Dunng M4 Loop Operations Append *ces A-D

l l

36 SubDetInd;x NUREGICR-6144 V02P3A EVALUATION OF POTENTIAL SEVERE AC.

Nuclear Computertred L6brary CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR-4639 V5R4P2 NUCLEAR COMPUTERIZED LIBRARY FOR SURRV, UNIT 1 Analysis Of Core Damage Frequency From Internal ASSESSING REACTOR RELIABILITY (NUCLARR) Volume 5 Data Events Dunng Mid-Loop Operations Appendices F (Sections E 1-E B)

Manual Part 2. Human Error Probabihty (HEP) Data NUREG/CR 6144 V02P38. EVALUATION OF POTENTIAL SEVERE AC-NUREG/CR-4639 V5R4P3 NUCLEAR COMPUTERIZED LIBRARY FOR CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT ASSESSING REACTOR RELIABtttTY (NUCLARR) Volume 5 Data SURRY.UN!T 1 Analysis Of Core Damage Frequency From internal Manual Part 3 Hardware Component f ailure Data Events Dunng Med Loop Operations Appendices E (Sections E 9-E 16)

NUREG/CR-6144 V02P4 EVALUATION OF POTENTIAL SEVERE ACCl-Occupational Safety DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR 6212. VALUE OF PUBLIC HEALTH AND SAFETY ACTIONS SURRY. UNIT 1. Analysis Of Core Damage Frequency From Internal AND RADIATION DOSE AVOIDED Events Dunng Met oop Operations Appendices F-H NUREG/CR 6144 V02P5 EVALUATION OF POTENTIAL SEVERE ACCl-DENTS DUR!NG LOW POWER AND SHUTDOV/N OPERATIONS AT UR O

OF FIC OF THE INSPECTOR GENERAL Semiannual Report,0ctobe[E SURRY. UNIT 1 Analysis Of Core Damage Frequency From interne 1,1993 March 31,1994 Events Dunng Mid-Loop Operations Appendices i NUREGICR 6144 V03 P1 EVALUATION OF POTENTIAL SEVERE AC-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT Operational Lag-%nce SURRY. UNIT 1 Analysts Of Core Damage Frequency From Internal NUREG/CR-6093 AN ANALYSIS OF OPERATIONAL E XPERIENCE Fires Dunng Med L oop Operations Main Report DURING LOW POWER AND SHUTDOWN AND A PLAN FOR AD-NUREGICR 6144 V03 P2 EVALUATION OF POTENTIAL SEVERE AC.

DRESSING HUMAN RELIABILITY ASSESSMENT ISSUES CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SURRY. UNIT 1 Analysis Of Gore Damage Frequency From Internal Operator Performance Fires Dunng MdLoop Operations Appendices NUREG/CR-6127 THE EFFECTS OF STRESS ON NUCLEAR POWER NUREG/CR 6144 V04 EVALUATION OF POTENTIAL SEVERE ACCl-PLANT OPERATIONAL DECISION MAKING AND TRAINING AP.

DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT PROACHES TO REDUCE STRESS EFFECTS SURRY. UNIT 1 Anatys;s Of Core Damage Frequency From Internal NUREG/CR 6208 AN EMPIRICAL INVESTIGATION OF OPERATOR Floods Dunng Md Loop Operations PERFORMANCE IN COGNITIVELY DEMANDING SIMULATED EMER-NUREG/CR-6144 V05 EVALUATION OF POTENTIAL SEVERE ACCl-GENCIE S DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SURRY, UNIT 1 Analysis Of Core Damage Frequency From Seismic Peer Review Events Dunng Mid Loop Operations Main Report NUREG/CR-6183 PEER REVIEW OF THE TM1-2 VESSEL INVE STIGA-Low-Alloy Steet NUREG/CR 6237 STATISTICAL ANALYSIS OF FATIGUE STRAIN LIFE Performance Assessment DATA FOR CARBON AND LOW-ALLOY STEELS.

NUREG/CR-5965 MODELING FIELD SCALE UNSATURATED FLOW Low-Level Radioactive Waste AND TRANSPORT PROCESSES NUREG/CR 5965 MODELING FIELD SCALE UNSATURATED FLOW AND TRANSPORT PROCESSES Petit 6ons For Rulemaldng NUREG-0936 V13 N01. NRC REGULATORY AGENDA Ouarterly tiagnetic Measurement Report.Jantary-March 1994.

NUREG/GR-0013 APPLICATIONS OF A NEW MAGNETIC MONITOR NURE G-0936 V13 NO2 NRC REGULATORY AGENDA.Ouarterly ING TECHNIOUE TO IN SITU EVALUATION OF FATIOUE DAMAGE Report.Apnidune 1994 IN F ERROUS COMPONE NTS Physical Fitness trainmg Malevolent NURE G-1504 OEVIEW CRITERIA FOR THE PHYSICAL FITNESS NUREGICA-6190 VOf PROTECTION AGAINST MALEVOLENT USE OF TRAINING REOUIREME NTS IN 10 CFR FART 73 VEHICLES AT NUCLE AR POWER PL ANTS vehecle Bamer Syuem Siting Guidance For Blast Protection

pip, NUREG/CR-6190 V02 PROTECTION AGAINST MAL EVOLENT USE OF NURE GICR $128 Rei-EVALUATION AND F.EFINEMENT OF LE AK-VEHICLES AT NUCLE AR POAER PLANTS Vehicle Bamer System RATE ESTIMATION MODELS Siting Guidance For Blast Protection NUREG/CR-6128 PIPING BENCHMARK PROBLEMS FOR THE ABB/

Metaibrg6 cal Esamination CE SYSTEM 80 4 STANDARDtIED PLANT-NUREGrCR 6183 PEER REVIEW OF THE TMb2 VESSEL INVESTIGA.

TION PROJECT METALLURGICAL EXAMINATIONS Pipe Stress NUREG/C46236 SEISMIC INVESTIGATIONS OF THE HDR SAFETY Models And Results Datease PROGRAM Summary Report NUREG/CR6116 V08 SMTEMS AN ALY SIS PROGRAMS FOR HANDS-ON INTEGRATED REUABILITY EVALUATIONS (SAPHiRE)

Piping VE RSION $ 0 Models And Results Database (MAR D) Reference NUREG 1426 V02 COMPILATION OF REPORTS FROM RESEARCH Manual SUPPORTED BY THE M ATE RIALS ENGINEERING BRANCH. DIVISION OF ENGINEERING 1991-1993 Motor-Operated Valve NURE G/CR-6121 COMPONENT EVALUATION FOR INTERSYST EM NUREG/CP 0137 V01 PROCEEDINGS OF THE Th;RD NRC/ASME LOSS-OF-COOLANT ACCIDENTS IN ADVANCED LIGHT WATER RE-SYMPOSIUM ON VALVE AND PUMP TESTING Held Al The Hyatt Re.

ACTORS gency Hotel, Washington.DC, July 18-21. 1994Seswon 1 A - Session NUREG/CR 6181. A PILOT APPLICATION OF R:SK BASED METHODS TO EST ABLISH INSERVICE INSPECTION PRIORITIES FOR NUCLE-NU EG/CP-0137 V02 PROCEEDINGS OF THE THIRD NRC/ASME SYMPOSIUM ON VALVE AND PUMP TESTING Held At The Hyatt Re-rcy Hotel Wash'rigto%DC July 18--21,1594 Session 3A -Semon Piping System NUREG/CR-6151 FEASIBILITY OF DEVELOPING RISK BASED RANK.

INGS OF PRESSURE BOUNDARY SYSTEMS FOR INSERVICE IN-Nondestructive Evaluston NUREG/CR-6151. f EASIBillTY OF DEVELODING RISK-BASED RANK.

SPECTION INGS OF PRESSURE BOUNDARY Sv5TEMS FOR INSERVICE IN-Pressure Boundry System SPECTION NUREG/CR 6181. A PILOT APPLICATION OF RISCBASED METHODS NURE G/CR-6151 FE ASIBillTY OF DEVELOPING RISK-BASED RANK-TO ESTABLISH INSERVICE INSPECTION PRIORITIES FOR NUCLE.

INGS OF PRESSURE BOUNDARY SYSTEMS FOR INCERVICE IN-AR COMPONENTS AT SURRY UN!T 1 NUCLEAR POWER STATION SPE CTION NUREG/GR-0013 APPLICATIONS OF A NEW MAGNETIC MONrOR-NURE G /CR-3181.

PILOT APPLICATION OF RISK-BASED METHODS ING TECHNIQUE TO IN SITU EVALLlATION OF FATIQUE DAMAGE TO ESTABLISH INSERVICE INSPECTION PRIORfTIES FOR NUCLE-IN FERROUS COMPONENTS AR COMPONENTS AT SURRY UNIT 1 NUCLEAR POWER STATION

~

Subject Index 37 Pressure Vessel Radioiogical Criteria NUREG/CR-5591 V02 N1: HEAVY-SECTION STEEL IRRADIATION NUREG-1496 VI DRF FC: GENERIC ENVIRONMENTAL IMPACT PROGRAM Semiannual Progress Report For October 1990 March STATEMENT IN SUPPORT OF RULEMAKING ON RADIOLOGICAL 1991-CRITERIA FOR DECOMMISSIONING OF NRC-LICENSED NUCLEAR Pressurtred-Thermal Shock FACILITIES Main Report. Draft Report For Comment.

NUREG 1496 V2 DRF FC. GENERIC ENVIRONMENTAL IMPACT NUREG/CR-4211: V10 N1. HEAVY SECTION STEEL TECHNOLOGY PROGRAM Semiannual Progress Report for October 1992 March STATEMENT IN SUPPORT OF RULEMAKING ON RADIOLOGICAL 0 93 CRITERIA FOR DECOMMISSIONING OF NRC-LICENSED NUCLEAR FACILITIES. Appendices Draft Report For Comment.

Probabilistic Risk Assessment NUREG/CR-6250

SUMMARY

OF COMMENTS RECEIVED ON STAFF NUREG/CR-4639 V5R4P2 NUCLEAR COMPUTERIZED LIBRARY FOR DRAFT PROPOSED RULE ON RADIOLOGICAL CRITERIA FOR DE-ASSESSING REACTOR RELIABILITY (NUCLARR) Volume 5 Data COMMISSIONING.

M nnual.Part 2 Human Error Probabihty (HEP) Data NUREG/CR.4639 V5R4P3 NUCLEAR COMPUTERIZED LIBRARY FOR Reactor Accident ASSESSING REACTOR REllABILITY UCLARR) Volume 5 Data NUREG/CR-6144 V02P1A: EVALUATION OF POTENTIAL SEVERE AC.

Minual Part 3 Hardware Component Failure Data CIDENTS DURiNG LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR 5726 REVIEW OF THE DIABLO CANVON PROBABILISTIC SURRY, UNIT 1. Analysis Of Core Damage Frequency Frnm internal RISK ASSESSMENT.

Events Dunng Mid-Loop Operations Main Report (Chapters 16).

NUREG/CR 6116 V01: SYSTEMS ANALYSIS PROGRAMS FOR HANDSON INTEGRATED REL' ABILITY EVALUATIONS (SAPHIRE)

P* actor Operator VERSION 5 0. Technical Reference Manual NUREG/CR-5008 VOI: ADVANCED HUMAN-SYSTEM INTERFACE NUREG/CR 6116 V02 SYSTEMS ANALYSIS PROGRAMS FOR DESIGN REVIEW GUIDELINE. General Evaluation Model, Technical HANDS-ON INTEGRATED REllABILITY EVALUATIONS (SAPHIRE)

Development. And Guideline Desenption VERSION 5.Olntegrated Reliability And Risk Analysis System (IRRAS)

NUREG/CR-5908 V02. ADVANCED HUMAN-SYSTEM INTERFACE F.ference Manual DESIGN REVIEW GUIDELINE. Evaluation Procedures And Guidelines NUREG/CR-6116 V03 SYSTEMS ANALYSIS PROGRAMS FOR For Human Factors Engineenng Reviews.

HANDS-ON INTEGRATED RELIAGLITY EVALUATIONS (SAPHIRE)

VERSION 5 0 Integrated Reliability And Risk Analysis System (IRRAS)

Reactor Operator Licensing Tutonal Manual.

NUREG-1478 NON-POWER REACTOR OPERATOR LICENSING EXAM-NUREG/CR-6116 V04 SYSTEMS ANALYSIS PROGRAMS FOR INER STANDARDS.

HANDS-ON INTEGRATED RELIABILITY EVALUATIONS 'SAPHINE)

VERSION 5 0 Systems Analysis And Risk Assessment (SARA) Refer-Reactor Pressure vessel ence Manual NUREG-1426 V02: COMPILATION OF REPORTS FROM RESEARCH NUREG/CR-6116 V05 SYSTEMS ANALYSIS PROGRAMS FOR SUPPORTED BY THE MATERIALS ENGINEERING HANDS-ON INTEGRATED RELIABILITY EVALUATIONS (SAPHIRE)

BRANCH, DIVISION OF ENGINEERING 1991 1993 VERSION 5 0 Systems Analysis And Risk Assessment (SARA) Tutonal M rnual Reactor Reliability NUREG/CR4116 V07: SYSTEMS ANALYSIS PROGRAMS FOR HANDS-ON INTEGRATED RELIABILITY EVALUATIONS (SAPHIRE)

NUREG/CR-4639 V5R4P2 NUCLEAR COMPUTERIZED LIBRARY FOR VERSION 5 0 Fault Tree. Event Tree, And Piping & Instrumentation ASSESSING REACTOR RELIABILITY (NUCLARR) Volume 5 Data Dupram (FEP) Editors Reference Manual Manual Part 2. Human Error Probability (HEP) Data.

NUREG/CR-4639 V5R4P3 NUCLEAR COMPUTERIZED LIBRARY FOR NURLG/CR 6116 V08 SYSTEMS ANALYSIS PROGRAMS FOR HANDS ON INTEGRATED RELIABILITY EVALUATIONS (SAPHIRE)

ASSESSING REACTOR RELIABILITY (NUCLARR). Volume 5' Data Manual.Part 3 Hardware Component Failure Data VERSION 5 0 Mudels And Results Database (MAR-D) Reference M nwel NUREG/CR4181: A PILOT APPLICATION OF RISK-BASED METHODS Reactor Safety TO ESTABLISH INSERVICE INSPECTION PRIORITIES FOR NUCLE-NUREG/CR-6213 HIGH-TEMPERATURE HYDROGEN-AIR STEAM AR COMPONENTS AT SURRY UNIT 1 NUCLEAR POWER STATION DETONATION EXPERIMENTS IN THE BNL SMALL-SCALE DEVELOP-MENT APPARATUS Program Performance NUREG/CR-5758 V04 FITNESS FOR DUTY IN THE NUCLEAR POWER Reactor Shutdown i USTRY. Annual Summary Of Program Performance Reports CY

.g Public Health Recordkeeping Requirement NUREG/CR 6212. VALUE OF PUBLIC HEALTH AND SAFETY ACTIONS NUREG-1460 RO1: GUIDE TO NRC REPORTING AND RECOROKEEP-AND RADIATION DOSE AVOIDED ING REQUIREMENTS. Compiled From Requirements in Title 10 Of The U.S. Code Of Federal Regulations As Codified On December 31, Pump Testing 1993 NUREG/CP-0137 V02-PROCEEDINGS OF THE THIRD NRC/ASME SYMPOSIUM ON YALVE AND PUMP TESTING Held At The Hyatt Re-Refueling Outege gency Hotel, Washington.DC July 18 -21, 1994 Session 3A -Sesson NUREG/CR-6143 V04. EVALUATION OF POTENTIAL SEVERE ACCI-48 DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT GRAND GULF, UNIT 1. Analysis Of Core Damage Frequency From in.

NURE 5535 V07. RELAP5/ MOD 3 CODE MANUAL.Summanes And R) in '

Reviews Of Independent Code Assessment Reports Radiation Dose Regu atory Agenda NUREG'CR-6212 VALUE OF PUBLIC HL ALTH AND SAFETY ACTIONS NUREG-0936 V13 N01: NRC REGULATORY AGENDA Ouarterly AND RADIATION DOSE AVOIDED Reprt.Janur.ry March 1994.

NURE G-0936 V13 NO2 NRC REGULATORY AGENDA Ouarterly Radiation Embrittlement Report.Apni-June 1994.

NUREG 1426 V02. COMPILATION OF REPORTS FROM RESEARCH SUPPORTED BY THE MATERIALS ENGINEERING Regulatory And Techrncal Report BRANCH.DfVISION OF ENGINEERING 1991 1993 NUREG-0304 V19 N01. REGULATORY AND TECHNICAL REPORTS (ABSTRACT INDEX JOURNAL) Compilation For First Quarter Aadiation Esposure 1994. January March

. UREG/CR-6206 TRANSPORT CALCULATIONS OF RADIATION Ex.

NURE G-0304 V19 NO2. REGULATORY AND TECHNICAL REPORTS POSURE TO VESSEL SUPPORT STRUCTURES IN THE TROJAN RE.

(ABSTRACT INDEX JOURNAL) Compilation For Second Quarter ACTOR 1994.Apnt-June Cadution Protection Regulatory Stabilization NUREG/CR-6212 VALUE OF PUBLIC HEAllH AND SAFETY ACTIONS NUREG 1242 V03 PTC1: NRC REVIEW OF ELECTRIC POWER RE-AND RADIATION DOSE AVOIDED SEARCH INSTITUTE'S ADVANCED LIGHT WATER REACTOR UTill-

38 Subject index TV REOUIREMENTS DOCUMENTS Passsve Plant Desegns Chapter NUREG/CR-6116 V08 SYSTEMS ANALYS;S PROGRAMS FOR 1 Protec1 Nurnber 669 HANDS-ON INTEGRATED RELIABluTY EVALUATIONS (SAPHIRE)

NUREG-1242 V03 PT02: NRC REVIEW OF ELECTRIC POWER RE-VERSION 5 0 Models And Results Database (MAR D) Reference SE ARCH INSTITUTE'S ADVANCED LIGHT WATER REACTOR UTILI-Manual TY REQUIREMENTS DOCUMENTPassive Plant Designs Chapters 2-13 Protect Number 669 SARA Release Criteria NUREG/CR-6116 VO4 SYSTEMS ANALYSIS PROGRAMS FOR NUREG-1500 WORKING DRAFT REGULATORY GUIDE ON RELEASE HANDS-ON INTEGRATED RELIABILITY EVALUATIONS (SAPHIRE)

/ERSION 5 0 Systems Analysis And Risk Assessment (SARA) Refer.

CRITERIA FOR DECOMMISSIONING NRC STAFF'S DR/ET FOR COMMENT-ence Manual.

NUREG/CR-6116 V05-SYSTEMS ANALYSIS PROGRAMS FOR Fleplacement Energy Cost HANDS-ON INTEGRATED RELIABILITY EVALUATIONS (SAPHIRE)

NUREG/CR-5344 RO1; REPLACEMENT ENERGY COST ANALYSIS yste a Anahsis And Rsk 4sent @W Monal PACKAGE (HCAP) USER'S GUIDE.

Report To Congress Safeguards Summary Event List NUREG.0090 V17 NW REPORT TO CONGRESS ON ABNORMAL NUREG 0525 V02 R02. SAFEGUARDS

SUMMARY

EVENT LIST OCCURRENCES. January-March 1994.

(SSEL). January 1,1990 Through December 31,1993 Reporting Requ6rement Seism 6c Event NUREG-1460 RO1-GUIDE TO NRC REPORTING AND RECORDKEEP.

NUREG/CR-5726. REVIEW OF THE DIABLO CANYON PROBABILtSTIC ING REQUIREMENTS Compiled From Requirements in Titic.0 (Y RISK ASSESSMENT.

The U S Code Of Federal Regulations As Codified On December 31 NUREG/CR-6143 V05 EVALUATION OF POTENTIAL SEVERE ACCl-1993 DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT GRAND GULF, UNIT 1. Analysis Of Core Damage Frequency From Residual Radioactivity Seismic Events Dunng Med Loop Operations Main Report NUREG-1501 DRFT. BACKGROUND AS A RESIDUAL RADIOACTIVITY NUREG/CR-6144 V05 EVALUATION OF POTENTIAL SEVERE ACCI-CRITERlON FOR DECOMMISSIONING Appendix A To The Draft Ge-DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT nenc Environmental impact Statement in Support of Rulemaiung on SURRY. UNIT 1. Analysis Of Core Damage Frequency From Seismic Radological Critena For Decomminiorung Of NRC..

Events Dunng Mid Lenp Operatons Main Report.

Rev6ew Criterts Seismic Monitoring NURE G-1504 REVIEW CRITERIA FOR THE PHYSICAL FITNESS NUREG/CR-6254 SOUTHERN APPALACHIAN REGIONAL SEISMIC TRAINING REQUIREMENTS IN 10 CFR PART 73.

NETWORK.

NUREG/CR-6255. DESIGN OF AN OPEN ARCHITECTURE SEISMIC Rock Jo}nt MONI10 RING SYSTEM.

NUREG/CR 6176 LABORATORY CHARACTERIZATION OF ROCK j

JOINTS Seism 6c Network NUREG/CR-6254 SOUTHERN APPALACHIAN REGIONAL SElSMIC i

Rulemak.ing NETWORK.

I NUREG-1496 V1 DRF FC. GENERIC ENVIRONMENTAL IMPACT 1

STATEMENT IN SUPPORT OF RULEMAKING ON RADIOLOGICAL Selsmic Testing i

CRITERIA FOR DECOMMISSIONING OF NRC-LICENSED NUCLEAR NUREGICR.6236 SEISMIC INVESTIGATIONS OF THE HDR SAFETY FACILITIES Main Report Draft Report For Comment PROGRAM Summary Report.

NUREG-1496 V2 DAF FC; GENERIC ENVIRONMENTAL IMPACT STATEMENT IN SUPPORT OF RULEMAKING ON RADIOLOGICAL Sever Accident CRITERIA FOR DECOMMISSIONING OF NRC-LICENSED NUCLEAR NUREG/CR 6144 V02PIB EVALUATION OF POTENTIAL SEVERE AC-F ACILITIES Appendices Dratt Report For Comment.

NUREG-1501 DRFT. BACKGROUND AS A RESIDUAL RADIOACTIVITY CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT CRITERION FOR DECOMMISSIONING Appende A To The Draft Ge-SURRY. UNIT 1 Analysis Of Core Damage Frequency From Internat Events Dunng Mid-Loop Operations Main Report (Chapters 7-12) nenc Environniental impact Statement in Support Of Rulemaking On Radological Critena For Decommissiorung Of NRC.-

Severe Accident Rules NUREG 1502. ASSESSMENT OF DATABASES AND MODELING CAPA-BILITIES FOR THE CANDU 3 DESIGN NUREG-0936 V13 N01. NRC REGULATORY AGENDA Ouarterly NUREG/CR-6143 V02P1A. EVALUATION OF POTENTIAL SEVERE AC-NUR 36 13 02 NRC RE GULATORY AGENDA Quarterly CIDENTS DURtNG LOW POWER AND SHUTDOWN OPERATIONS AT Report.Apol June 1994 GRAND GULF, UNIT t. Analysis Of Core Damage Frequency From In-ternal Events For Plant Operational State 5 Dunng A Refueling SAPHIRE Outage Sections 19.

NUREG/CR-6116 V01: SYSTE MS ANALYSIS PROGRAMS FOR NUREG/CR-6143 V02P18. EVALUATION OF POTENTIAL SEVERE AC-HANDS-ON INTEGRATED RELIABILITY EVALUATIONS (SAPHIRE)

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT VERSION 5 0 Technical Reference Manual.

GRAND GULF, UNIT 1. Analysis Of Core Damage Frequency From in.

NURE G/CR 6116 V02: SYSTEMS ANALYSIS PROGRAMS FOR ternal Events For Plant Operatonal State 5 Dunng A Refueling HANDS-ON INTEGRATED RELIABillTY EVALUATIONS (SAPHIRE)

Outage Secton 1a VERSION 5 0 Integrated Rehabihty And Risk Analyses System (IRRAS)

NUREG/CR-6143 V02PIC: EVALUATION OF POTENTIAL SEVERE AC.

Reference Manua CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR4116 V03 SYSTEMS ANALYSIS PROGRAMS FOR GRAND GULF, UNIT 1 Anabyses Of Core Damage Frequency From In-HANDS-ON INTEGRATED RELIABILITY EVALUATIONS (SAPHIRE) temal Events For Plant Operational State 5 Dunng A Refueling VERSION 5 0 Integrated Rehability And Risk Analysis System (IRRAS)

Outage Main Heport.

Tutonal Manual.

NUREGICR-6143 V02PT2 EVALUATION OF POTENTIAL SEVERE AC-NUREG/CR-6116 V04. SYSTEMS ANALYSIS PROGRAMS FOR CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT HANDS-ON INTEGRATED RELIABILITY EVALUATIONS (SAPH)RE)

GRAND GULF UNIT 1. Analysis Of Core Damage Frequency From in.

VERSION 5 0 Systems Analysis And Risk Assessment (SARA) Refer.

ternal Events For Plant Operational State 5 Dunng Refueling ence Manual Outage internal...

NURE G/CR-6116 V05-SYSTE MS ANALYSIS PROGRAMS FOR NUREG/CR-6143 V02PT3 EVALUATION OF POTENTIAL SEVERE AC.

HANDS-ON INTEGRATED REL! ABILITY EVALUATIONS (SAPHIRE)

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT VERSION 5 0 Systems Analysis And Risk Assessment (SARA) Tutonal GRAND GULF. UNIT 1.Anatysis Of Core Damage Frequency From in-Manual ternal Events For Plant Operatonal State 5 Dunng A Refueling NUREG/CR 6116 % SYSTEMS ANALYSIS PROGRAMS FOR Outage internal..

t HANDS ON fNTEGRATED RELIABILITY EVALUATIONS (SAPHIRL)

NUREG/CR-6143 V02PT4 EVALUATION OF POTENTIAL SEVERE AC-VERSION 5 0 Fault Tree, Event Tree. And Piping & instrumentation CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT Diagram (F E P) Editors Reference Manuai GRAND GJLF, UNIT 1. Analysis Of Core Damage Frequency From In-

Subject index 39 ternal Events For Plant Operatonal State 5 Dunng A Refueling GRAND GULF, UNIT 1. Analysis Of Core Damage Frequency From In-Outsge lntemal...

NUREG/CR4143 V03. EVALUATION OF POTENTIAL SEVERE ACCI-ternal Events For Plant Operatonal State 5 Dunng A Refuehng Outage Mam Report.

DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT GRAND GULF, UNIT 1, Analysis Of Core Damage Frequency From In-NUREG/CR-6143 V02PT2: EVALUATION OF POTENTIAL SEVERE AC.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT terna Events For Plant Operat#onal State 5 Dunng A Refueling Outace i

l NUREG/CR4143 V04 EVALUATION OF POTENTIAL SEVERE ACCI.

GRAND GULF, UNIT 1 Analysis Of Core Da nage Frequency From In-i DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT temal Events For Plant Operatonal State 5 Dunng Refuehng GRAND GULF, UNIT 1. Analysis Of Core Dama e Frequency From In-Outage Internal i

ternally Induced Flood.ng Events For Plant Operational State 5 Danng NUREG/CR-6143 V02PT3: EVALUATION OF POTENilAL SEVERE AC.

CiDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT l

N RE C 1783 V05 EVALUATION OF POTENTIAL SEVERE ACCI.

a4 sis O be Damage Requeng Rmn in-l DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT temal Events For Piant Operatonal State 5 Dunng A Refueling Sec E ents r

dL p Opera ens Ma R NU G/CR 614 V02PT4: EVALUATION OF POTENTIAL SEVERE AC-NUREG/CH 6144 V0272: EVALUATION OF POTENTE SEVERE ACCl-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT GRAND GULF, UNIT 1. Analysis Of Core Damage Frequency From In-SURRY, UNIT 1. Analysis Of Core Damage Frequency From intemal ternal Events For Plant Operatonal State 5 Dunng A Refueling Evems Dunng Md-Loop Operations Appendices A-D.

Outage internal....

NUREG/CR 6144 V02P3A: EVALUATION OF POTENTIAL SEVERE AC.

NUREG/CR-6143 V03 EVALUATION OF POTENTIAL SEVERE ACCl-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SURRY. UNIT 1. Analysis Of Core Damage Frequency From intemal GRAND GULF, UNIT 1. Analysis Of Core Damage Frequency From In-Events Dunng Md-Loop Operatens Appendices E (Sectons E 1 E 8) temal EverWs For Plant Operatonal State 5 Dunng A Refuehng Outage.

NUREG/CR-6144 V02P38. EVALUATION OF POTENTIAL SEVERE AC.

NUREG/CR-6143 V04: EVALUATION OF POTENTIAL SEVERE ACCl-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SURRY. UNIT 1 Analysis Of Core Damage Frequency From Internal GRAND GULF. UNIT 1. Analysis Of Core Damage Frequency From In-Events Dunng M4 Loop Operatens Append.ces E (Sections E 9-E 16)

NUREG/CR-6144 V02P4: EVALUATION OF POTENTIAL SEVERE ACCl-ternally Induced Flooding Events For Plant Operational State 5 Dunng a Refusiing..

DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR-6143 VOS EVALUATION OF POTENTIAL SEVERE ACCI-SURRY. UNI'

1. Analysis Of Core Damage Frequency From Internal Events Dunng Mid-Loop Operatons. Append!ces F-H-DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR 6144 V02PS EVALUATION OF POTENTIAL SEVERE ACCl-GRAND GULF, UNIT 1 Analysis Of Core Damage Frequency From DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT Seismsc Events Dunng Md-Loop Operatons Main Report.

SURRY, UNIT 1. Analysis Of Core Damage Frequency From Internal NUREG/CR-6144 V02 PIA EVALUATION OF POTENTIAL SEVERE AC.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUI C

44 V03 A

I O

TENTIAL SEVERE AC-SURRY, UNIT 1. Analysis Of Core Damage Frequency From Intemal CIDENTS DURING LOW POWER AND SHUTDO VN OPERATIONS AT Events Dunng MdLoop Operatons Main Report (Chapters 16).

SURRY. UNIT 1 Analysis Of Core Damage Frequency From Internal G/

44 2MEWAM&WWM WW&

NUREG/CNrMeloop Operatons. Main Re CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT Fres Du 144 V03 P2: EVALUATION O POTENTIAL SEVERE AC.

SURRY, UNIT 1. Analysis Of Core Damage Frequency From intemal CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT Events Dunng Md-Loop Operations Main Report (Chapters 712).

SURRY. UNIT 1. Analyse Of Core Damage Frequency From intemal NUREG/CR-6144 V02P2: EVALUATION OF POTENTIAL SEVERE ACCI.

Fres Dunng Mid Loop Operations Appendices DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR 6144 V04 EVALUATION OF POTENTIAL SEVERE ACCI.

SURRY, UNIT 1. Analysis Of Core Damage Frequency From internal DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT Events Dunng MdLoop Operalens Appendices A-D.

SURRY. UNIT 1. Analysis Of Core Damage F requency From Intemal NUREG/CR4144 V02P3A-EVALUATION OF POTENTIAL SEVERE AC.

Floods Dunng M d Loop Operatons.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR-6144 V05. EVALUATION OF POTENTIAL SEVERE ACCI-SURRY, UNIT 1 Analysis Of Core Damage Frequency From internal DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT Events Dunng MdLoop Operations. Appendices E (Sectons E.1-E 8).

SURRY, UNIT 1. Analysis Of Core Damage Frequency From Seismic NUREG/CR 6144 V02P38 EVALUATION OF POTENTIAL SEVERE AC.

Events Dunng MdLoop Operatons Main Report CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR-6168 O! RECT CONTAINMENT HEATING INTEGRAL EF-FECTS TESTS AT 1/40 SCALE IN ZION NUCLEAR POWER PLANT SURRY, UNIT 1. Analysis Of Core Damage Frequency From intemal GEOMETRY.

Events Dunng M4 Loop Operations. Appendices E (Sections E 9-E.16).

NUREG/CR-6144 V02P4 EVALUATION OF POTENTIAL SEVERE ACCl-DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT N REG /C 61 PERIMENTS TO INVESTIGATE DIRECT CON-SURRY, UNIT 1. Analysis Of Cose Damage Frequency From Internal TAINMENT HEATING P NOMENA WITH SCALED MODELS OF THE NUR CR 144 02 E 10 F

TE l'AL SEVERE ACCI-NUREG/CR-6218 A REV:EW OF THE TECHNICAL ISSUES OF AIR IN.

DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT GRESSION DURING SEVERE REACTOR ACCIDENTS.

SURRY, UNIT 1. Analysis Of Core Damage Frequoney From Internal Events Dunng Mid-Loop Operatons Appendices L Shur Stress NUREG/CR-6144 V03 P1: EVALUATION OF POTENTIAL SEVERE AC-NUREG/CR-6178 LABORATORY CHARACTER 12ATION OF ROCK CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT JOINTS SURRY, UNIT 1. Analysis Of Core Damaga Frequency From internal j

f Shutdown Fres Dunng MdLoop Operatons Main Report.

NUREG/CR-6144 V03 P2. EVALUATION OF POTENTIAL SEVERE AC-NUREG/CR-6093 AN ANALYSIS OF OPERATIONAL EXPERIENCE DURING LOW POWER AND SHUTDOWN AND A PLAN FOR AD.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT DRESSING HUMAN RELIABILITY ASSESSMENT ISSUES.

SURRY, UNIT 1. Analysis Of Core Damage Frequency From Internal Fres Dunng Meloop Operatons. Appendices.

Shutdown Operation

""*d

1. N## @

"M" ""

• NUREG/CR 6143 V02P1 A-EVALUATION OF POTENTIAL SEVERE AC.

DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SURRY, UNIT 1. Analysis Of Core Damage Frequency From Internal GRAND GULF. UNIT 1 Analysis Of Core Damage Frequency From In-Floods Dunng MdLoop Operatons temat Events For Plant Operationa! State 5 Dunng A Refueling NUREG/CR-6144 VOS EVALUATION OF POTENTIAL SEVERE ACCl-Outa e Sectons 1-9 DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREd/CR4143 V02PtB. EVALUATION OF POTENTIAL SEVERE AC.

SURRY, UNIT 1. Analysis Of Core Damage Frequency F om Seismic l

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT Events Dunng M4 Loop Operatons Main Report GRAND GULF, UNIT 1 Analysis Of Core Damage Frequency From In-temal Events For Ptint Operational State 5 Dunng A Retueling Shnulated Emergenc es Outage Secton 10 NUREG/CR 6208. AN EMPIRICAL INVESTIGATION OF OPERATOR NUHEGICR-6143 V02P1C EVAL UATION OF POTENTIAL SEVERE AC.

PERFORMANCE IN COGNiTIVELY DEMANDING SIMULATED EMER.

CIDENTS DURING TOW POWER AND SHUTDOWN OPERATIONS AT GENCIES

40 Subject index Southern Appalachlan Seismic Zone Transport NUREG/CR 6254 SOUTHERN APPALACHIAN REGIONAL SEISMIC NUREG/CR E203 VALIDATION STUDIES FOR ASSESSING UNSATU-NETWORK RATED FLOW AND TRANSPORT THROUGH FRACTURED ROCK.

Sta6n&e Cune Transport Calculation FA I UE SMAIN41FE NUREG/CR-6206 TRANSPORT CALCULATIONS OF RADIATION Ex-D TAF CARE N LOW ALLOY T ELS POSURE TO VESSEL SUPPORT STRUCTURES IN THE TROJAN RE-Stainless Steel ACTOR NUREG/CR 4513 ROI. ESTIMATION OF FRACTURE TOUGHNESS OF CAST STAINLESS STEELS DURING THERMAL AGING IN LWR SYS-Trqan Reactor TEMS NUREG/CR-6206 TRANSPORT CALCULATIONS OF RADIATION Ex-NUREG/CR-6233 V01 STABILITY OF CRACKED PIPE UNDER INER.

POSURE TO VESSEL SUPPORT STRUCTURES IN THE TROJAN RE.

TIAL STRESSES Subtash 11 Final Report ACTOR Standard Review Plan Unsaturated Flow NUREG/CR 5973 ROI CODES AND STANDARDS AND OTHER GUID-NUREG/CR-5965 MODELING FIELD SCALE UNSATURATED FLOW ANCE CITED IN REGULATORY DOCUMENTS AND TRANSPORT PROCESSES.

NUREG/CR-6203 VALIDATION STUDIES FOR / SSE ""NG UNSATU-NU EG/CR 6127 THE EFFECTS OF STRESS ON NUCLEAR POWER PLANT OPERATIONAL DECISION MAKING AND TRAINING AP-Utility Requ6rements Document PROACHES TO REDUCE STRESS EFFECTS NUREG-1242 V03 PT01: NRC REVIEW OF ELEC1. POWER RE.

SEARCH INSTITUTE'S ADVANCED LIGHT WATER - F. ACTOR UTILI.

Surtsey Test Facility TY REOUIREMENTS DOCUMENTS. Passive Plant Designs Chapter NUREG/CR-6152. EXPERIMENTS TO INVESTIGATE DIRECT CON.

P TAINMENT HEATING P E O A WITH SCALED MODELS OF THE AE 1 2V3 T02: NRC REVIEW OF ELECTRIC POWER RE-SEARCH INSTITUTE'S ADVANCED LIGHT WATER REACTOR UTILl-System 80 + Design TY REOUIREMENTS DOCUMENT Passive Plant Designs Chapters 2-NUREG-1462 V01 FINAL SAFETY EVALUATION REPORT RELATED 13 Protect Number 669.

TO THE CERTIFICATION OF THE SYSTEM 804 DESIGN Chapters 1 14 Docket No 52-002 (Asea Brown Boven-Combustion Engineenng)

Vadose Zone Transport NUREG-1462 V02 FINAL SAFETY EVALUATION REPORT RELATED NUREG/CR-6120 CONTROLLED FIELD STUDY FOR VALIDATION OF TO THE CERTIFICATION OF THE SYSTEM 804 DESIGN Chapters VADOSE ZONE TRANSPORT MODELS 15 22 And Appendices Docket No 52 002( Ases Brown Boven-Com-ETLD bustion Engineenng)

Valve And Pump Testing NUREG/CP-0137 VOI PROCEEDINGS OF THE THIRD NRC/ASME SYMPOSIUM ON VALVE AND PUMP TESTING Held At The Hyatt Re-NUREG-0837 V14 NOI NRC TLD DIRECT RADIAT!ON MONITORING gency Hotel, Washington.DC, July 18 21, 1994 Session 1 A - Sesseon NETWORK Progress Report January March 1994 2C.

NUREG 0837 V14 NO2. NRC TLD DIRECT RADIATION MONITORING NETWORK Progress Report Apnt-June 1994 Valve Testing NUREG/CP-0137 V02: PROCEEDINGS OF THE THIRD NRC/ASME SYMPOSIUM ON VALVE AND PUMP TESTING Held At The Hyatt Re-N REG /CR-6193 PEER REVIEW OF THE TMI-2 VESSEL INVESTIGA-9'"'Y "0 "9'0"

"'E ' ~

• • • 'U"

^

TlON PROJECT METALLURGICAL EXAMINATIONS 4B Thermal Aging NUREG/CR-4513 ROI ESTIMATION OF FRACTURE TOUGHNESS OF Vapor Transport i

CAST STAINLESS STEELS DURING THERMAL AGING IN LWR SYS.

NUREG/CR 5965 MODELING FIELD SCALE UNSATURATED FLOW TEMS AND TRANSPORT PROCESSES Thermoluminescent Dosimeter Vehicle Barrier System NUREG 0837 V14 N01: NRC TLD DIRECT RADIAT80N MONITORING NUREGICR.6190 V01: PROTECTION AGAINST MALEVOLENT USE OF NETWORK Progress Report January-March 1994 VEHICLES AT NUCLEAR POWER PLANTS. Vehicle Barner System NUREG-0837 V14 NO2. NRC TLD DIRECT RADIATION MONITORING Siting Guidance For Blast Protection.

NETWORK Progress Report Apni-Jura 1994 NUREG/CR-6190 V02 PROTECTION AGAINST MALEVOLENT USE OF VEHICLES AT NUCLEAR POWER PLANTS Vehicle Barner System ng ance 6 BaM %cw UR / 6252 LESSONS LEARNED FROM THE THREE MILE ISLAND-UNIT 2 ADVISORY PANEL Vessel Support Structure NUREG/CR 6206. TRANSPORT CALCUl.ATIONS OF RADIATION Ex-1 Title W POSURE TO VESSEL SUPPORT STRUCTURES IN THE TROJAN RE-NUREG-0540 V16 NOS TITLE LIST OF DOCUMENTS MADE PUBLICLf ACTOR AVAILABLE May 1 31,1994 Tram 6ng Vibration Emperiment NURLG/CR 6121 THE EFFECTS OF STRESS ON NUCLEAR POWER NUREG/CR-6236 SEISMIC INVESTIGATIONS OF THE HOR SAFETY PLANT OPE RATIONAL DECISION MARING AND TRAINING Ap.

PROGRAM Summary Report PROACHES TO REDUCE STRESS EFFECTS Weste Burial Transient Analysis NUREG 1307 Rod REPORT ON WASTE BURIAL CHARGES Escatation NUREG 1502 ASSESSMENT OF DATABASES AND MODELING CAPA.

Of Decommasioning Waste Disposa? Costs At Low-Level Waste Bunal BillilES FOR THE CANDU 3 CESIGN Facilitiec.

NRC Originating Organization Index (Staff Reports)

This index lists those NRC organizations that have published staff reports. The index is ar-ranged alphabetically by major NRC organizations (e.g., program offices) and then by sub-s@ctions of these (e.g., divisions, branches) where appropriate. Each entry is followed by a l

NUREG number and title of the report (s). If further information is needed, refer to the main citation by NUREG number.

1 OFFICE OF EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)

EDO - OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL REGION 1 (POST 820201)

DATA NUREG-0837 V14 NO1:NRC TLD DIRECT RADIATION MONITORING OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA, Di-NETWORK. Progress Report. January-March 1994.

RECTOR NUREG-0837 V14 NO2 NRC TLD DIRECT RADIATION MONITORING NUREG-0090 V17 N01: REPORT TO CONGRESS ON ABNORMAL NETWORK Progress Report. Apnl-June 1994.

OCCURRENCES. January-March 1994 OFC OF ENFORCEMENT (POST 870413)

TRENDS & PATTERNS ANALYSIS BRANCH NUREG-0940 V13N01P01: ENFORCEMENT ACTIONS SIGNIFICANT NUREG/CR-6116 VOI: SYSTEMS ANALYSIS PROGRAMS FOR ACTIONS RESOLVED REACTOR LICENSEES Quarterly Progress HANDSON INTEGRATED RELIABILITY EVALUATIONS (SAPHIRE)

Report. January-March 1994.

VERSION 5 0 Technical Reference Manual.

NUREG 0940 V13N01P02-ENFORCEMENT ACTIONS: SIGNIFICANT NUREG/CR-6116 V02: SYSTEMS ANALYSIS PROGRAMS FOR ACTIONS RESOLVED MEDICAL LICENSEES Quarterly Progress HANDS-ON INTEGRATED RELIABILITY EVALUATIONS (SAPHIRE)

Report. January March 1994 VERSION 5 0 lntegrated Rehability And Risk Analysis System NUREG 0940 V13N01P03: ENFORCEMENT ACTIONS SIGNIFICANT (IRRAS) Reference Manual.

ACTIONS RESOLVED INDUSTRIAL LICENSEES Quarterly Progress Report. January-March 1994_

EDO - OFFICE OF INFORMATION RESOURCES MANAGEMENT & ARM NUREG 0940 V13N02P01: ENFORCEMENT ACTIONS SIGNIFICANT (POST 861109)

ACTIONS RESOLVED REACTOR LICENSEESOuarterly Progress OFFICE OF INFORMATION RESOURCES MANAGEMENT (POST Report. April June 1994.

890205)

J NUREG 0940 V13N02P02 ENFORCEMENT ACTIONS. SIGNIFICANT NUREG-1460 R01: GUIDE TO NRC REPORTir G AND RECORD-l KEEPING REQUIREMENTS Compiled From Requirements in Title ACTIONS RESOLVED MEDICAL LICENSEES Ouarterly Progress Report.Apni-June 1994.

10 Of The U S. Code Of Federal Regulations As Codified On Decem-NUREG-0940 V13N02P03. ENFORCEMENT ACTIONS. SIGNIFICANT ber 31,1993.

AC NS RESOLVED INDUSTRIAL LICENSEESQuarterly Progress f

EDO - OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS DIVISION OF FUEL CYCLE SAFETY & SAFEGUARDS (POST 930207)

NUREG 1504. REVIEW CRITERIA FOR THE PHYSICAL FITNESS EDO OFFICE OF ADMINISTRATION (PRE 870413 & POST 890205)

TRAIN!NG REQUIREMENTS IN 10 CFR PART 73.

DIVISION OF FREEDOM OF INFORMATION & PUBLICATIONS SERV-OPERATIONS BRANCH ICES (890206-9407 NUREG 0525 V02 R02: SAFEGUARDS

SUMMARY

EVENT LIST NUREG-0304 V19 N01. REGULATORY AND TECHNICAL REPORTS anuay 1. M Wough NcemW M,1993 (ADSTRACT INDEX JOURNAL). Compriation For First Quarter 1994. January-March' U.S. NUCLEAR REGULATORY MMMidSION NUREG-0750 V37: NUCLEAR REGULATORY COMMISSION OFFICE OF THE INSPECTOR 'lENERAL (POST 890417)

ISSUANCES Opinions And Decisions Of The Nuclear Regulatory NUREG-1415 V06 NO2: OFFICE OF THE INSPECTOR Commission With Selected Orders. January-June 1993 GENERAL.Semtannual Report, October 1,1993 March 31,1994.

NUREG 0750 V38.

NUCLEAR REGULATORY COMMISSION ISSUANCESOpinions And Decisons Of The Nuclear Reguistory EDO - OFFICE OF NUCLEAR REGULATORY RESEARCH (POST 820405)

Commession With Selected Orders July-December 1993 DIVISION OF ENGINEERING (POST 870413)

NUREG 0936 V13 N01: NRC REGULATORY AGENDA Ouarterly NUREG 1426 V02. COMPILATION OF REPORTS FROM RESEARCH Report. January-March 1994.

SUPPORTED BY THE MATERIALS ENGINEERING OFFICE OF ADMINISTRATION, DIRECTOR (POST 940714)

BRANCH, DIVISION OF ENGINEERING.19911993 NUREG 1145 V10. U S. NUCLEAR REGULATORY COMMISSION DIVISION OF REGULATORY APPLICATIONS (POST 870413) 1993 ANNUAL REPORT.

NUREG 1307 R04 REPORT ON WASTE BURIAL DIVISION OF FREEDOM OF INFORMATION & PUBLICATIONS SERV.

CHARGES Escalation Of Decommissioneng Waste Disposal Costs At ICES (POST 940714 Low-Level Waste Bunal Facilities.

NUREG-0304 V19 NO2: REGULATORY AND TECHNICAL REPORTS NUREG-1496 V1 DRF FC: GENERIC ENVIRONMENTAL IMPACT (ABSTRACT INDEX JOURNAL) Compilation For Second Quarte, STATEMENT IN SUPPORT OF RULEMAKING ON RADIOLOGICAL 1994,Apr61. June.

CRITERIA FOR DECOMMISSIONING OF NRC-LICENSED NUCLE-NUREG 0540 V16 N05 TITLE LIST OF DOCUMENTS MADE PUBLIC.

AR FACILITIES Ma:n Report. Draft Report For Comment LY AVAILADLE May 1 31,1994 NUREG 1496 V2 DRF FC: GENERIC ENVIRONMENTAL IMPACT NUREG 0750 V39101: INDEXES TO NUCLEAR REGULATORY COM-STATEMENT IN SUPPORT OF RULEMAKING ON RADIOLOGICAL MISSION ISSUANCES. January -March 1994 CRITERIA FOR DECOMMtSSIONING OF NRC-LIUENSED NUCLE-NUREG 0750 V39102: INDEXES TO NUCLEAR REGULATORY COM-AR FACILITIES. Appendices Draft Report For Comment.

MISSION ISSUANCES. January June 1994 NUREG 1500: WORKING DRAFT REGULATORY GUIDE ON RE.

NUREG 0750 V39 N05: NUCLEAR REGULATORY COMMISSION IS.

LE ASE CRITERIA FOR DECOMMtSSIONING. NRC ST AFF'S DRAFT SUANCES FOR MAY 1994 Pages 249 284.

FOR COMMENT.

NUREG-0750 V39 N06: NUCLEAR REGULATORY COMMISSION IS-NUREG-1501 DRFT. BACKGROUND AS A RESIDUAL RADIOACTIV-SUANCES FOR JUNE 1994 Pages 285-390.

ITY CRITERlON FOR DECOMMISSIONING Appendix A To The Draft NUREG-0750 V40 N01: NUCLEAR REGULATORY COMMISSION IS-Genenc Environmental Impact Statement in Support Of Rulemaking SUANCES FOR JULY 1994 Pages 141.

On Radiological Critena For Decommissioning Of NRC...

NUREG 0936 V13 N32: NRC REGULATORY AGENDA Ouarterly DIVISION OF SYSTEMS RESEARCH (POST 880717)

Report. April-June 1994.

NUREG 1502. ASSESSMENT OF DATABASES AND MODELING CA-PABILITIES FOR THE CANDU 3 DESIGN EDO OFFICE OF THE CONTROLLER (PRE 820418 & POST 890205)

HUMAN FAC'. ORS BRANCH OFFICE OF THE CONTROLLER (POST 890205)

NUREG/CR 6208 AN EMPIRICAL INVESTIGATION OF OPERATOR NUREG-1470 V03. FINANCIAL STATEMENT FOR FISCAL YEAR PERFORMANCE IN COGNITIVELY DEMANDING SIMULATED 1993.

EMERGENCIES 41

42 NRC Originating Organization index (Staff Reports)

EDO - OFFICE OF NUCLEAR REACTOR REGULATION (POST 800428)

NUREG-1503 V01: FINAL SAFETY EVALUATION REPORT RELATED ASSOCIATE DIRECTOR FOR ADVANCED REACTORS & LICENSE RE-TO THE CERTIFICATION OF THE ADVANCED BOILING WATER NEWAL (POST 910918 REACTOR DESIGN Docket No. 52 001 (General Electre Nuclear NUREG-1242 V03 PT01: NRC REVIEW OF ELECTRIC POWER RE-Energy)

SEARCH INSTITUTE'S ADVANCED LIGHT WATER REACTOR NUREG 1503 V02. FINAL SAFETY EVALUATION REPORT RELATED UTILITY REOUIREMENTS DOCUMENTS Passwe Plant TO THE CERTIFICATION OF THE ADVANCED BOILING WATER Designs Chapter 1 Protect Number 669 REACTOR DESIGN Append #ces Docket No. 52 001.(General Elec-NUREG-1242 V03 PT02. NRC REVIEW OF ELECTRIC POWER RE-trc Nuclear Energp SEARCH INSTITUTE'S ADVANCED LIGHT WATER REACTOR DIVISION OF REAUTOR CONTROLS & HUMAN FACTORS (POST NU

-0711: HUMAN FACTORS ENGINEERING PROGRAM D ns Chapte s 2 3Po Numbe 9 NUREG-1462 V01. FINAL SAFET / EVALUATION REPORT RELATED NURE 78 dN-POWER REACTOR OPERATOR LICENSING Ex.

TO THE CERTIFICATION OF THE SYSTEM 80 + DESIGN Chapters NER ANDA S 114 Docket No 52 002. (Asea Brown BoverFCombuston Engeneer' PRO A9)

NUREG/CR-6093: AN ANALYSIS OF OPERATIONAL EXPERIENCE NUREG 1462 V02: FINAL SAFETY EVALUATION REPORT RELATED DURING LOW POWER AND SHUTDOWN AND A PLAN FOR AD-TO THE CERTIFICATION OF THE SYSTEM 80 + DESIGN Chapters DRESSING HUMAN RELIABILITY ASSESSMENT ISSUES.

15-22 And Appendees. Docket No. 52 002(Asea Brown Boverk REACTOR SYSTEMS BRANCH Combuston Engineenng)

NUREG/CR-3950 V09. FUEL PERFORMANCE REPORT FOR 1991.

)

i

NRC Originating Organization Index (International Agreements)

This index lists those NRC organizations that have published international agreement re-ports. The index is arranged alphabetically by major NRC organizations (e.g., program of-fices) and then by subsections of these (e.g., divisions, branches) where appropriate. Each 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 pubHshed during this quarter i

e i

1 43

m u 3

am..

.s-----.

f

NRC Contract Sponsor Index (Contractor Reports)

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

l l

500. OFFICE OF NUCLEAR REGULATORY RESEARCH (POST 820405)

NUREG/CR-6116 V02: SYSTEMS ANALYSIS PROGRAMS FOR DIVISION OF ENGINEERING (POST 870413)

HANDS ON INTEGRATED RELIABILITY EVALUATIONS (SAPHIRE)

NUREG/CR 4219 V10 N1: HEAVY SECTION STEEL TECHNOLOGY VERSION 5 0 integiated Reltatnhty And Risk Analyses System PROGRAM Semiannual Progress Report For October 1992 - March (IRRAS) Reference Manual T993 NUREG/CR-6116 V03-SYSTEMS ANALYSIS PROGRAMS FOR NUREG/CR 4513 R01: ESTIMATON OF FRACTURE TOUGHNESS HANDS-ON INTEGRATED REUABluTY EVALUATONS (SAPHIRE)

OF AST STAINLESS STEELS DURING THERMAL AGING IN LWR VERSION 5 0 integrated Rehatnhty And Risk Analysis System

" ^8 T

'M NURE /CR 28 01 EVA UATION AND REFINEMENT OF LEAK-AEG/fR V

SYSTEMS ANALYSIS PROGRAMS FOR HANDS-ON INTEGRATED RELIABILITY EVALUATONS (SAPHIRE)

NUREGICR 5591 V02 N1: HEAVY SECTION STEEL IRRADIATON PROGRAM Semiannual Progress Report For October 1990 March VERSION 5 0 Systems Analysis And Risk Assessment (SARA) Refer.

1991.

ence Manual.

NUREG/CR 5861: CRACK-SPEED RELATIONS INFERRED FROM NUREG/CR-6116 V05. SYSTEMS ANALYSIS PROGRAMS FOR LARGE SINGLE EDGE-NOTCHED SPECIMENS OF A 533 B STEEL-HANDS-ON INTEGRATED REUABluTY EVALUATONS (SAPHIRE)

NUREG/CR4121. COMPONENT EVALUATION FOR INTERSYSTEM VERSION 5.0 Systems Analysis And Risk Assessment (SARA) Tuto-LOSS-OF. COOLANT ACCIDENTS IN ADVANCED UGHT WATER nal Manual.

REACTORS.

NUREG/CR 6116 V07: SYSTEMS ANALYSIS PROGRAMS FOR NUREG/CR4151: FE 4SIBILITY OF DEVELOPING RISK-BASED HANDS-ON INTEGRATED RELIABluTY EVALUATIONS (SAPHIRE)

RANKINGS OF PRESSURE BOUNDARY SYSTEMS FOR INSERV-VERSION 5 0 Fault Tree. Event Tree, And Pipmg & Instrumentaten ICE INSPECTION Diagram (FEP) Editors Reference Manual.

NUREG/CR-6162. EFFECTS OF PRIOR DUCTILE TEARING ON NUREG/CR 6116 V08 SYSTEMS ANALYSIS PROGRAMS FOR CLEAVAGE FRACTURE TOUGHNESS IN THE TRANdlTION HANDS ON INTEGRATED REUABILITY EVALUATIONS (SAPHIRE)

REGION VERSION 5 0 Models And Results Database (MAR-D) Reference NUREG/CR-6181: A PILOT APPLICATION OF RISK-BASED METH-Manual.

ODS TO ESTABUSH INSERVICE INSPECTION PRIORITIES FOR NUREG/CR4143 V02PI A: EVALUATION OF POTENTIAL SEVERE NUCLEAR COMPONENTS AT SURRY UNIT 1 NUCLEAR POWER ACCIDENTS DURING LOW POWER AND SHUTDOWN OPER-STATION ATIONS AT GRAND GULF. UNIT 1 Analysis Of Core Damage Fre-NUREGICR4183. PEER REVIEW OF THE TMI-2 VESSEL INVESTI-quency From internal Events For Plant Operational State 5 Dunng A GATON PROJECT METALLURGICAL EXAMiNATONS Refueling Outage.Soctons 1-9 NUREG/CR-6206-TRANSPORT CALCULATIONS OF RADIATION EX-NUREG/CR4143 V02P18. EVALUATION OF POTENTIAL SEVERE POSURE TO VESSEL SUPPORT STRUCTURES IN THE TROJAN ACCIDENTS DURING LOW POWER AND SHUTDOWN OPER.

NU E /CR 6233 V01: STABluTY OF CRACKED PIPE UNDER INER-U"*"#Y E*'"*"*'

"""U ^

TIAL STRESSES Subtask 11 Final Report NUREG/CR4234 VALIDATION OF ANALYSIS METHODS FOR AS-NUR 43 VALUATION OF POTENTIAL SEVERE

^ "

ACCIDENTS DURING LOW POWER AND SHUTDOWN OPER.

NU E /

236 IS NV S I AT S

THE D SA ETY ATONS AT GRAND GULF, UNIT 1 Analysis Of Core Damage Fre.

PROGRAM Summary Report NUREG/CR 6254 SOUTHERN APPALACHIAN REGIONAL SEISMIC quency From Internal Events For Plant Operatonal State 5 Dunng A NETWORK Refueling Outage. Main Report.

i NUREG/CR-6255. DESIGN OF AN OPEN ARCHITECTURE SEISMIC NUREG/CR4143 V02PT2: EVALUATION OF POTENTIAL SEVERE MONITORING SYSTEM ACCIDENTS DURING LOW POWER AND SHUTDOWN OPER.

)

DIVISION OF REGULATORY APPUCATIONS (POST B70413)

ATIONS AT GRAND GULF. UNIT 1. Analysis Of Core Damage Fre-

?

NUREG/CR 5344 H01: REPLACEMENT ENERGY COST ANALYSIS quency From internal Events For Ptant Operational State 5 Dunng PACKAGE (RECAP) USER'S GUOE Refuehng Outage Internal.

NUREG/CR-5965: MODELING FIELD SCALE UNSATURATED FLOW NUREG/CR4143 V02PT3. EVALUATON OF POTENTIAL SEVERE ANs TRANSPORT PROCESSES.

ACCIDENTS DURING LOW POWER AND SHUTDOWN OPER-NUREG/CR-6120. CONTROLLED FIELD STUDY FOR VALIDATION ATIONS Al GRAND GULF. UNIT 1. Analysis Of Core Damage Fre-ncy ne nts a

no A NU EG 4178 LA O H RA TERIZATON OF ROCK JOINTS-NUREG 4143 V02PT4. EVALUATION OF POTENTIAL SEVERE NUREG/CR4203. VALIDATION STUDIES FOR ASSESSING UN-ACCIDENTS DURING LOW POWER AND SHUTDOWN OPER-SA URATED FLOW AND TRANSPORT THROUGH FRACTURED ATIONS AT GRAND GULF. UNIT 1 Analyses Of Core Damage Fre.

l NUREG/CR4212: VALUE OF PUBUC HEALTH AND SAFETY AC-quency From Internal Events For Plant Operational State 5 Dunng A Refuels Outage. Internal.

l TIONS ANO RADIATON DOSE AVOIDED.

NUREG/ 4143 V03: EVALUATION OF POTENTIAL SEVERE ACCI-NUREG/CR4250- SUMM AR f OF COMMENTS PECEIVED ON STAFF DENTS DURING LOW POWER AND SHUTDOWN OPERATONS AT DRAFT PROPOSED RULE ON RADIOLOGICAL CRITERIA FOR DE, COMMISSIONING.

GRAND GULF. UNIT 1. Analysis Of Core Damage Frequency From In-i l

DIVISON OF SAFETY ISSUE RESOLUTION (POST 880717) ternal Events For Plant Operatonal State 5 Dunng A Refuehng NUREG/CR-5726 REVIEW OF THE DiABLO CANYON PROBABlus.

Outage.

TIC RISK ASSESSMENT.

NUREG/CR4143 V04: EVALUATON OF POTENTIAL SEVERE ACCl-NUREG/CR4093: AN ANALYSIS OF OPERATIONAL EXPERIENCE DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT DURING LOW POWER AND SHUTDOWN AND A PLAN FOR AD-GRAND GULF. UNIT 1. Analyses Of Core Damage Frequency From in.

DRESSING HUMAN REUABILITY ASSESSMENT ISSUES.

ternally induced Floodin0 Events For Plant Operatonal State 5 NUREG/CR-6116 V01: SYSTEMS ANALYSIS PROGRAMS FOR Dunng a Refuehng.....

HANDS ON INTEGRATED REUABluTY EVALUATIONS (SAPHIRE)

NUREG/CR4143 VOS: EVALUATION OF POTENTIAL SEVERE ACCI-VERSION 5 0. Technical Reference Manual.

DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT I

45

I 46 NRC Contract Sponsor index GRAND GULF, UN'T t. Analysis Of Core Damage Frequency From DIVISION OF SYSTEMS RESEARCH (POST 880717)

Seismic Events Dunng Mid Loop Operatons Main Report NURE G/CR-4639 V5R4P2. NUCLEAR COMPUTERIZED LIBRARY NUREGICR-6144 V02P1 A. EVALUATION OF POTENTIAL SEVERE FOR ASSESS!NG REACTOR REllABILITY (NUCLARR) Volume 5 ACCIDENTS DURiNG LOW POWER AND SHUTDOWN OPER-Data Manual Part 2-Human Error Probatulity (HEP) Data ATONS AT SURF 3Y,0 NIT 1 Analysis Of Core Damage Frequency NUREG/CR 4639 V5R4P3 NUCLEAR COMPUTERIZED LIBRARY From intemal Events Dunng Mid Loop Operatons Main Report FOR ASSESSING REACTOR RELLABILITY (NUCLARR) Volume 5-(Chapters 14)

Data Manual Part 3 Hardware Component Failure Data NUREG/CR 6144 V02PIB EVALUATION OF POTENTIAL SEVERE NUREG/CR-5535 V07; RELAP5/ MOD 3 CODE MANUAL.Summanes ACCIDENTS DURING LOW POWER AND SHUTDOWN OFiR-And Revews Of Independent Code Assessment Reports ATIONS AT SURRY. UNIT 1. Analysis Of Core Damage Frequency NUREG/CR-5908 V01-ADVANCED HUMAN SYSTEM IN12RF ACE From inlemal Events Dunng Md Loop Operatons Main Report DESIGN REVIEW GUOELINE. General Evaluation Model Technical (Chapters 712)

Development. And Gudeline Descnpton NUREG/CR-6144 V02P2 EVALUATION OF POTENTIAL SEVERE AC.

NUREG/CR-5908 VON ADVANCED HUMAN-SYSTEM INTERFACE CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS DESIGN REVIEW GUIDELINE. Evaluaton Procedures And Gude.

AT SURRY, UNIT 1 Analysis Of Core Damage Frequency From Inter.

lines For Human Factors Engineenng Reviews nal Events Dunng MdLoop Operatons Appendees A D NUREG/CR-6127: THE EFFECTS OF STRESS ON NUCLEAR NUREG/CR-6144 V02P3A EVALUATION OF POTENTIAL SEVERE POWER PLANT OPERATIONAL DECISION MAKING AND TRAIN-ACCIDENTS DURING LOW POWER AND SHUTDOWN OPER.

ING APPROACHES TO REDUCE STRESS EFFECTS ATIONS AT SURRY, UNIT 1. Analysis Of Core Damage Frequency NUREG/CR 6152: EXPERIMENTS TO INVESTIGATE DIRECT CON-From Internal Events Dunng Meloop Operatons Appendees E TAINMENT HEATING PHENOMENA WITH SCALED MODELS OF (Sections E.1-E 8)

THE SURRY NUCLEAR POWER PLANT NUREG/CR 6144 V02P3B EVALUATION OF POTENTIAL SEVERE NUREG/CR 6168 DIRECT CONTAINMENT HEATING INTEGRAL EF.

ACCIDENTS DURING LOW POWER AND SHUTDOWN OPER.

FECTS TESTS AT 1/40 SCALE IN ZION NUCLEAR POWER PLANT ATIONS AT SURRY. UNIT 1 Analysis Of Core Damage Frequency GEOMETRY From Internal Events Dunng M4 Loop Operatens Appendees E NUREG/CR 6200: AN EMPIRfCAL INVESTIGATION OF OPERATOR (Sectons E 9-E.16)

PERFORMANCE IN COGNITIVELY DEMANDING SIMULATED NUREG/CR-6144 V02P4 EVALUATON OF POTENRAL SEVERE AC.

E MERGE NCIE S CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS NUREG/CR 6213. HIGH-TEMPE RATURE HYDROGE N-AIR-ST EAM AT SURRY. UNIT 1 Analysis Of Core Damage Frequency From Inter.

DETONATION EXPERIMENTS IN THE BNL SMALL SCALE DEVEL-nal Events Dunng Med-loop Operatons Appendces F H OPMENT APPARATUS.

NUREG/CR 6144 v02P5 EVALUATION OF POTENTIAL SEVERE AC.

NUREG/CR-6216. A REVIEW OF THE TECHNICAL ISSUES OF AIR CIDENIS DURING LOW POWER AND SHUTDOWN OPERATIONS INGRESSION DURING SEVERE REACTOR ACCIDENTS.

na ns d

EDO - OFFICE OF NUCLEAR REACTOR REGULATION (POST 800428)

NUREG/CR 6144 03 P1: EVALUATION F POTENTIAL SEVERE PROGRAM MANAGEMENT, POLICY DEVELOPMENT & ANALYSIS ACCIDENTS DURING LOW POWER AND SHUTDOWN OPER.

NURE 5 73 Rot, CODES AND STANDARDS AND OTHER ATIONS AT SURRY. UNIT 1. Analysis Of Core Damage Frequency From Intemal Fires Dunng Md Loop Operatons Main Report GUIDANCE CITED IN REGULATORY DOCUMENTS NUREG/CR-6144 V03 P2. EVALUATION OF POTENTIAL SEVERE OlVISION OF OPERATING REACTOR SUPPORT (POST 921004)

NUREG/CR-6252: LESSONS LEARNED FROM THE THREE MILE ACCIDENTS DURING LOW POWER AND SHUTDOWN OPER-ISLAND-UNIT 2 ADVISORY PANEL ATIONS AT SURRY UNIT 1 Analysis Of Core Damage Frequency DIVISION OF SYSTEMS SAFETY & ANALYSIS (POST 021004)

From Intemal Fires Dunng Med Loop Oparations Appendices NUREG/CR 3950 V09 FUEL PERFORMANCE REPORT FOR 1991 NUREG/CR 6144 V04 EVALUATION OF POTENTIAL SEVERE ACCl-DIVISION OF RADIATION SAFETY & SAFEGUARDS (POST 921004)

DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR-5758 V04 FITNESS FOR DUTY IN THE NUCLEAR SURRY, UNIT 1. Analysis Of Core Damage Frequency From Intemal POWER INDUSTRY Annual Summary Of Program Performance Re-Floods Dunng MeLoop Operatens ports CY 1993 NUREG/CR 6144 V05. EVALUATION OF POIENTIAL SEVERE ACCl-NUREG/CR 6190 VOI: PROTECTION AGAINST MALEVOLENT USE DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT OF VEHICLES AT NUCLEAR POWER PLANTSVehicle Barrer SURRY, UNIT 1 Analysis Of Core Damage Frequency From Seismc System Sitsng Gudance For Blant Protection E vents Dunng Mai-Loop Operatens Main Report.

NUHEG/CR 6190 V02 PROTECTION AGAINST MALEVOLE NT USE NUREG/CR 6224 DRF FC PARAMETRIC STUDY OF THE POTEN-OF VEHICL ES AT NUCLE AR POWER PLANTS Vehele Barrer TIAL FOR BWR ECCS STRAINER BLOCKAGE DUE TO LOCA GE N-System Siting Guedance For Blast Protecton.

E RATED DEBRIS Draft For Comment DIVISION OF ENGINEERING (POST 921004)

NURE G / CR-6237 STATISTICAL ANALYSIS OF FATIGUE STRAIN-NURE G/CR-6128 PIPING BENCHMARK PROBLEMS FOR THE ABB/

LIF E DATA FOR CARBON AND LOW-ALLOY STEELS CE SYSTEM 804 ST ANDARDilED PLANT-

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

ADVANCED SYSTEMS TECHNOLOGY, INC.

NUREG/CR4233 V01: STABILITY OF CRACKED PIPE UNDER INER-NUREG/CR4250.

SUMMARY

OF COMMENTS RECEIVED ON STAFF TIAL STRESSES Subtasit 1.1 F nal Report DRAFT PROPOSED RULE ON RADIOLOGICAL CRITERIA FOR DE.

NUREG/CR4234: VALIDATION OF ANALYSIS METHODS FOR AS.

COMMISSIONING.

SESSING FLAWED PIPING SUBJECTED TO DYNAMIC LOADING.

AEA TECHNOLOGY BATTELLE MEMORIAL INSTITUTE, PAClFIC NORTHWEST NUREG/CR4144 V02P1A: EVALUATION OF POTENTIAL SEVERE AG-LABORATORY CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CA-3950 V09: FUEL PERFORMANCE REPORT FOR 1991.

SURRY. UNIT 1.Analyss Of Core Damage Frequency From internal NUREG/CR 5758 V04: FITNESS FOR DUTY IN THE NUCLEAR POWER NLf CR 44 b2 B ON F T T7A S RE AC*

93 COENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR-5973 RO1: CL 3 AND STANDARDS AND OTHER GUID-SURRY UNIT 1. Analysis Of Core Damage Frequency From Internal ANCE CITED IN REGULATORY DOCUMENTS.

Events Dunng M4 Loop Operations Main Report (Chapters 712)

NUREG/CR-6151: FEASIBILITY OF DEVELOPING RISK BASED RANK-NUREG/CR-6144 V02P2: EVALUATION Or POTENTIAL SEVERE ACCl-INGS OF PRESSURE BOUNDARY SYSTEMS FOR INSERVICE IN.

DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SPECTION.

SURRY. UNIT 1. Analysis Of Core Damage Frequency From Internal NUREG/CR4181: A PILOT APPLICATON OF RISK-BASED METHODS Events Dunng M4 Loop Operations A es A D-TO ESTABLISH INSERVICE INSPECTION PRIORITIES FOR NUCLE-NUREG/CR4144 V02P3A: EVALUAT OF POTENTIAL SEVERE AC.

AR COMPONENTS AT SURRY UNIT 1 NUCLEAR POWER STATION.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR4252: LESSONS LEARNED FROM THE THREE MILE SURRY. UNIT 1. Analysis Of Core Damage Frequency From Internal ISLAND UNIT 2 ADVISORY PANEL Events Dunng M4 Loop Operations Appendices E Sectons E.1-E 8).

NUREG/CR4144 V02P3B: EVALUATION OF POTE(NTIAL SEVERE AC-BATTELLE SEATTLE RESEARCH CENTER CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/OR4252: LESSONS LEARNED FROM THE THREE MILE SURRY. UNIT 1. Analysis Of Core Damage Frequency From Internal ISLANJ-UNIT 2 ADVISORY PANEL Events Dunng M4 Loop Operatons Appendices E Sections E 9-E 16 NUREG/CR4144 V02P4. EVALUATION OF POTENT (IAL SEVERE ACC[-

BROOKHAVEN NATIONAL LABORATORY DENTS DURING LOW POWER AND SHUTDOWN OPIRATIONS AT NUREG-0711: HUMAN FACTORS ENGINEERING PROGRAM REVIEW SURRY. UNIT 1. Analysis Of Core Damage Frequency From Intemal MODEL.

Events Dunng M4 Loop Operations Appendices F H NUREG/CR 5726; REVIEW OF THE DIABLO CANYON PROBABILISTIC NUREG/CR4144 V02PS: EVALUATION OF POTENTIAL SEVERE ACCI-RISK ASSESSMENT.

DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR-5908 VOI: ADVANCED HUMAN-SYSTEM INTERFACE SURRY. UNIT 1. Analysis Of Core Damage Frequency From internal DESIGN REVIEW GUIDELINE. General Evaluaton Model, Technical Events Dunng M4 Loop Orrvatons. Appendices 1.

Development, And Gudeline Desenpton.

NUREG/CR-5908 V02: ADVANCED HUMAN SYSTEM INTERFACE DESIGN REVIEW GUIDELINE. Evaluaton Procedures And Guidehnes NU EG/CR-4 3 RO1 EST M TION OF FRACTURE TOUGHNESS OF CAST STAINLESS STEELS DURING THERMAL AGING IN LWR SYS-NU E N NA Y IS OPERATIONAL EXPERIENCE D RING LOW POWER AND SHUTDOWN AND A PLAN FOR AD-NUI EG/CR 5344 RO1: REPLACEMENT ENERGY COST ANALYSIS DRESSING HUMAN RELIABILITY ASSESSMENT ISSUES NU E /

I C

AENT HEATING INTEGRAL EF-NUREG/CR4128: PIPING BENCHMARK PROBLEMS FOR THE ABB/

FECTS STS AT 1/40 SCALE IN FlON NUCLEAR POWER PLANT NL EG/ 414 0

VA A 10 POTENTIAL SEVERE AC-NUREG/CR4183. PEER REVIEW OF THE TMI-2 VESSEL INVESTIGA.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT TION PROJECT METALLURGICAL EXAMINATIONS SURRY. UNIT 1. Analysis Of Core Damage Frequency From Intemal NUREG/CR4234' VALIDATON OF ANALYSIS METHODS FOR AS-Events Dunng M4 Loop Operatons Main Report (Chapters 1-6).

SESSING FLAWED PIPING SUBJECTED TO DYNAMIC LOADING NUREG/CR4144 V02P18: EVALUATION OF POTENTIAL SEVERE AC-NUREG/CR4236: SEISMIC INVESTIGATIONS OF THE HDR SAFETY CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT PROGRAM Summary Report.

SURRY, UNIT 1. Analysis Of Core Damage Frequency From internal NUREG/CR 6237 STATISTICAL ANALYSIS OF FATIGUE STRAIN-LIFE Events Dunng M4 Loop Operatons Main Report (Chapters 712).

DATA FOR CARBON AND LOW-ALLOY STEELS NUREG/CR4144 V02P2: EVALUATION OF POTENTIAL SEVERE ACCI-DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT ARIZONA, UNIV. OF, TUCSON, AZ SURRY. UNIT 1. Analysis Of Core Damage Frequency From intemal NUREG/CR-6120: CONTROLLED FIELD STUDY FOR VALIDATON OF Events Dunng M4 Loop Operatons. Appendices A-D.

VADOSE ZONE TRANSPORT MODELS NUREG/CR4144 V02P3A: EVALUATON OF POTENTIAL SEVERE AC-NUREG/CR-6203 VALIDATON STUDIES FOR ASSESSING UNSATU" I

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATONS AT RATED FLOW AND TRANSPORT THROUGH FRACTURED ROCK.

SURRY, UNIT 1. Analysis Of Core Damage Frequency From Intemal ARMY, DEPT. OF, CORPS OF ENGINEERS Events Dunng M4 Loop Operations. Appendices E (Sectons E.1-E.8).

NUREGICR4190 VO1: PROTECTION AGAINST MALEVOLENT USE OF NUREG/CR4144 V02P3B: EVALUATION OF POTENTIAL SEVERE AC-VEHICLES AT NUCLEAR POWER PLANTSVetucle Bamer System CIDENTS OURING LOW POWER AND SHUTDOWN OPERATIONS AT Siting Guidance For Blast Protection.

SURRY, UNIT 1. Analysis Of Core Damage Frequency From intemal l

NUREu/CR-6190 V02; PROTECTION AGAINST MALEVOLENT USE OF Events Dunng M4 Loop Operatons.Apperdces E (Sectons ESE 16).

VEHICLES AT NUCLEAR POWER PLANTS Vehscle Bamer System NUREG/CR4144 V02P4 EVALUATON OF POTENTIAL SEVERE ACCI-Siting GuidaTe For Blast Protecten DENTS DURING LOW POWER AND SHUTDOWN OPERATONS AT SURRY. UNIT 1. Analysis Of Core Damage Frequency From Intemal EATTELLE MEMORIAL INSTITUTE, COLUMBUS LABORATORIES Events Dunng M4 Loop Operations Apperwisces F-H.

NUREG/CR-5128 R0t: EVALUATION AND REFINEMENT OF LEAK-NUREG/CR4144 V02P5. EVALUATION OF POTENTIAL SEVERE ACCl-RATE ESilMATION MODELS.

DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT i

47

48 Contractor Index SURRY. UNIT 1. Analysis Of Core Damage Frequency From Internal nerc Environmental Impact Statement in Support Of Rulemaking On Events Dunng M d Loop Operations Appendices 1.

Radiologeal Cntena For Decommissioning Of NRC...

NUREG/CR 6144 V03 P1: EVALUATION OF POTENTIAL SEVERE AC-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATONS AT ENSCO, INC.

SURRY, UNIT 1. Analysis Of Core Damage Frequency From internal NUREG/CR4255: DESIGN OF AN OPEN ARCHITECTURE SEISMIC Fires Dunng M4 Loop Operations Main Report.

MONITORING SYSTEM NUREG/CR-6144 V03 P2. EVALUATON OF POTENTIAL SE' VERE AC-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATONS AT EOE ENGINEERING CONSULTANTS (FORMERLY EOE ENGINEERING, SURRY.Ul41T 1. Analysis Of Core Damage Frequency From Intemal INC.)

Fires Dunng MdLoop Operations Appendices NUREG/CR-5726: REVIEW OF THE DIABLO CANYON PROBABILISTIC NUREGICR-6144 V04 EVALUATION OF POTENTIAL SEVERE ACCI.

RISK ASSESSMENT.

DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SURRY. UNIT 1 Anatysis Of Core Damage Frequency From intemal EOE, INC.

Floods Dunng M4 Loop Operations NUREG/CR-6143 V05 EVALUATION OF POTENTIAL SEVERE ACCl-NUREG/CR-6212. VALUE OF PUBLIC HEALTH AND SAFETY ACTIONS DENTS DURING LOW POWt:R AND SHUTDOWN OPERATIONS AT AND RADIATON DOSE AVOIDED GRAND GULF, UNIT 1. Analysis Of Core Damage Frequency From NUREG/CH4213 HIGH TEMPERATURE HYDROGEN-AIR-STEAM Seisme Events Dunng M4 Loop Opetations Main Report.

DETONATION EXPERIMENTS IN THE BNL SMALL-SCALE DEVELOP.

NUREG/CR 6144 V05: EVALUATION OF POTENTIAL SEVERE ACCI-MENT APPARATUS.

DENTS DURING LOW POWER AND SHUTDOWN OPERATONS AT SURRY, UNIT 1. Analysis Of Core Damage Frequency From Seisnuc CARLOW INTERN ATIONAL, INC.

Events Dunng M4 Loop Operations Main Report.

NUREG/CR 5908 V02: ADVANCED HUMAN-SYSTEM INTERFACE DESIGN REVIEW GUIDELINE. Evaluation Procedures And Guidehnes FUTURE RESOURCES ASSOCIATES,INC.

For Human Factors Engineenng Reviews.

NUREG/CR-6143 V05: EVALUATION OF POTENTIAL SEVERE ACCI-DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES GRAND GULF, UNIT 1 Analysis Of Core Damage Frequency From 1

NUREG/CR-6178. LABORATORY CHARACTERl2ATION OF ROCK Seisme Events Dunng M4 Loop Operations Main Report JOINTS NUREG/CR-6144 V05: EVALUATON OF POTENTIAL SEVERE ACCl-DENTS DURING LOW POWER AND SHUTDOWN OPERATONS AT fy, UR G/ 0 37' V01: PROCEEDINGS OF THE THIRD NRC/ASME y,d Opera ns a R SYMPOSIUM ON VALVE AND PUMP TESTING Held At The Hyatt Re.

gency Hotel, Wastungton.DC, July 18-21,1994 Session 1 A Session GERMANY, FEDERAL REPUBLIC OF 2C NUREG/CR-6236: SEISMIC INVESTIGATONS OF THE NOR SAFETY NUREG/CP-0137 V02: PROCEEDINGS OF THE THIRD NRC/ASME PROGRAM. Summary Report.

l I

SYMPOSIUM ON VALVE AND PUMP TESTING. Held At The Hyatt Re.

gency Hotel, Washington.DC. July 18-21, 1994 Session 3A Session ILLINOIS, UNIV. OF, URSANA, IL dB NUREG/CR 6162: EFFECTS OF PRIOR DUCTILE TEARING ON CLEAV-NUREG/CR 4639 V5R4P2: NUCLEAR COMPUTERIZED LIBRARY FOR AGE FRACTURE TOUGHNESS IN THE TRANSITION REGION.

ASSESSING REACTOR RELIABILITY (NUCLARR) Volume 5: Data Manual Part 2. Human Error Probability (HEP) Data.

IOWA STATE UNIV., AMES,IA NUREG/CR-4639 V5R4P3 NUCLEAR CDMPUTERIZED UBRARY FOR NUREG/GR-0013: APPUCATIONS OF A NEW MAGNETIC MONITOH-ASSESSING REACTOR REUABlUTY (NUCLARR) Volume 5. Data ING TECHNIOUE TO IN SITU EVALUATION OF FATOUE DAMAGE Manual Part 3. Hardware Component Fa: lure Data.

IN FERROUS COMPONENTS.

NUREG/CR-5535 V07: RELAP5/ MOD 3 CODE MANUAL Summanes And Reviews O' independent Code Assessment Reports KTECH CORP.

NUREG/CF 4116 V01: SYSTEMS ANALYSIS PROGRAMS FOR NUREG/CR4152: EXPERIMENTS TO INVESTIGATE DIRECT CON-HANDSON INTEGRATED RELIABILITY EVALUATIONS (SAPHIRE)

TAINMENT HEATING PHENOMENA WITH SCALED MODELS OF THE VERSON 5 0 Techrwcal Reference Manaal.

SURRY NUCLEAR POWER PLANT.

NUREG/CR-6116 V02: SYSTEMS ANALYSIS PROGRAMS FOR HANDS-ON INTEGRA1ED REUABluTY EVALUATONS (SAPHIRE)

LOUISIANA STATE UNIV., BATON ROUGE, LA VERSION 5 0. Integrated Rehabehty And Risk Analysis System (IRRAS)

NUREG/CR-6206 TRANSPORT CALCULATONS OF RADIATION EX-Reference Manual.

POSURE TO VESSEL SUPPORT STRUCTURES IN THE TROJAN RE.

NUREG/CR4116 V03. SYSTEMS ANALYSIS PROGRAMS FOR ACTOR.

HANDS-ON INTEGRATED RELIABILITY EVALUATIONS (SAPHIRE)

VERSON 5 0. Integrated Rehatulity And Risk Analysis System (IRRAS)

MASSACHUSETTS INSTITUTE OF TECHNOLOGY, CAMSRIDGE, MA Tutonal Manual.

NUREG/CR-5965. MODELING FIELD SCALE UNSATURATED FLOW NUREG/CR-6116 V04: SYSTEMS ANALYSIS PROGRAMS FOR AND TRANSPORT PROCESSES.

HANDSON INTEGRATED RELIABILITY EVALUATIONS (SAPHIRE)

NUREG/CR 6144 V02PI A. EVALUATION OF POTENTIAL SEVERE AC.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT VERSION 5.0 Systems Analysis And Risk Assessment (SARA) Refer.

ence Manual.

SURRY. UNIT 1. Analysis Of Core Damage Frequency From Intemal NUREG/CR-6116 V05 SYSTEMS ANALYSIS PROGRAMS FOR Events Dunng Mid-Loop Operations Main Report (Chapters 1-6).

HANDSON INTEGRATEO RELIABluTY EVALUATIONS (SAPHIRE)

NUREG/CR 6144 V02P18 EVALUATION OF POTENTIAL SEVERE AC-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS f T VERSION 5.0. Systems Analysis And Risk Assessment (SARA) Tutonal Manual.

SURRY. UNIT 1. Analysis Of Core Damage Frequency From Internal NUREG/CR-6118 V07: SYSTEMS ANALYSIS PROGRAMS FOR Events Durnig M4 Loop Operations Main Report (Chapters 712)

HANDSON INTEGRATED RELIABluTY EVALUATIONS (SAPHIRE)

NUREG/CR 6144 V02P2: EVALUATION OF POTENTIAL SEVERE ACCI-VERSON 5 0 Fault Tree. Event Tree. Ana Piping & Instrumentation DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT Diagram (FEP) Editors Reference Manual.

SURRY UNIT 1. Analysis Of Core Damage Frequency From intemal NURLG/CR4116 V08 SYSTEMS ANALYSIS PROGRAMS FOR Events Dunng M4 Loop Operations.Appendees A 0 HANDSON INTEGRATED REUABluTY EVALUATIONS (SAPHIRE)

NUREG/CR4144 V02P3A. EVALUATION OF POTENTIAL SEVERE AC.

VERSON 5 0 Models And Results Database (MAR-D) Reference CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT Manual.

SURRY. UNIT 1. Analysis Of Core Damage Frequency From intomal NUREG/CR4121. COMPONENT EVALUATION FOR INTERSYSTEM Events Dunno M4 Loop Operations. Appendices E (Sections E.1 E.8).

LOSSOF. COOLANT ACCIDENTS IN ADVANCED LIGHT WATER RE.

NUREGICR4144 V02P38: EVALUATION OF POTENTIAL SEVERE AO-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT

ACTORS, SURRY,0 NIT 1. Analysis Of Core Damage Frequency From Intemal EGYPT, GOVT. OF Events Dunng M4 Loop Operations. Appendices E (Sections E 9-E.16).

NUREG/CR 5726. REVIEW OF THE DLABLO CANYON PROBABlUSTIC NUREG/CR-6144 V02P4 EVALUATION OF POTENTIAL SEVERE ACCl-RISK ASSESSMENT.

DENTS DURING LOW POWER AND SHUTDOWN OPERATONS AT SURRY. UNIT 1. Analyses Of Core Damage Frequency From internal ENERGY, DEPT.0F, ENVIRONMENTAL MEASUREMENTS LABORATORY Events Dunng M4 Loop Operations Appendices F-H.

NUREG 1501 DRFT: BACKGROUND AS A RESIDUAL RADIOACTIVITY NUREGICR 6144 V02P5' EVALUATION OF POTENTIAL SEVERE ACCl-CRITERION FOR DECOMMISSIONING. Appendix A To The Draft Ge-DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT d

v r

Ti

Contractor Index 49 SURRY. UNIT 1. Analyses Of Core Damage Frequency From intemal GRAND GULF, UNIT 1. Analysis Of Core Damage Frequency From Events Durmg Md-Loop Operations Appendices 1.

Seistruc Events Dur;ng Md-Loop Operations.Mam Report.

NUREG/CR-6144 V03 PI: EVALUATION OF POTENTIAL SEVERE AC-NUREG/CR 6144 VOS: EVALUATION OF POTENTIAL SEVERE ACCI-COENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SURRY,0 NIT 1. Analysis Of Core Damage Frequency From Intamal SURRY, UNIT 1. Analysis Of Core Damage Frequency From Seismc Fres Dunna MdLoop Operations Main Report.

NUREG/CR4144 V03 P2: EVALUATON OF POTENTIAL SEVERE AC-Events Durmg Md-Loop Operations.Mam Report CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SANDIA NATIONAL LABORATORIES SURRY, UNIT 1. Analysis Of Core Damage Frequency From Intamal NUREG/CR-5726: REVIEW OF THE DIABLO CANYON PROBABILISTIC Free Dunng M4-Loop Operations.Apperdices RISK ASSESSMENT.

NUREG/CR-6093 AN ANALYSIS OF OPERATIONAL EXPERIENCE MEMPHIS STATE UNIV., MEMPHIS, TN r1URING LOW POWER AND SHUTDOWN AND A PLAN FOR AD.

NUREG/CR 6254. SOUTHERN APPALACHIAN REGIONAL SEISMIC DRESSING HUMAN RELIABILITY ASSESSMENT ISSUES.

NETWORK, NOIEG/CR4143 V02P1 A; EVALUATION OF POTENTIAL SEVERE AC-NATIONAL INSTITUTE OF STANDARDS & TECHNOLOGY (FORMERLY NATIONAL SUREAU OF GRAND GULF. UNIT 1. Analysis Of Core Damage Frequency From in.

NUREG/CR-6206 TRANSPORT CALCULATIONS OF RADIATION EX-nel we s ant Opsahonal State 5 Dunng A Wng POSURE TO VESSEL SUPPORT STRUCTURES IN THE TROJAN RE-NU EG C 41Y3 VO PIB. EVALUATION OF POTENTIAL SEVERE ACTOR CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NEW MEXICO STATE UNIV., LAS CRUCES, NM GRAND GULF, UNIT 1. Analysis Of Core Damage Frequency From Irk NUREG/CR4120: CONTROLLED FIELD STUDY FOR VALIDATION OF ternal Events For Plant Operational State 5 Durmg A Refueling VADOSE ZONE TRANSPORT MODELS.

1'0" 1 g

g g

NUCLEAR POWER ENGINEERING CORP.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR-6213.

HIGH-TEMPERATURE HYDROGEN-AIR-STEAM GRAND GULF, UNIT 1. Analysis Of Core Damage Frequency From trk DETONATION EXPERIMENTS IN THE BNL SMALL-SCALE DEVELOP.

temal Eventt For Plant Operational State 5 Dunng A Refuelmg MENT APPARATUS.

Outage Mam Report NUREG/CR-6143 V02PT2: EVALUATION OF POTENTIAL SEVERE AC-CAK RIDGE NATIONAL LABORATORY CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR-4219 V10 N1: HEAVY SECTION STEEL TECHNOLOGY GRAND GULF UNIT 1. Analysis Of Core Damage Frequency From tre PROGRAM Semeannual Progress Report For October 1992 March temal Events For Plant Opershonal State 5 Dunng Refueling 1993.

Outage infomal....

HUREG/CR-5591 V02 N1: HEAVY-SECTION STEEL IRRADIATION NUREG/CR-6143 V02PT3 EVALUATON OF POTENTIAL SEVERE AC-PROGRAM Semiannual Progress Report For October 1990 - March CIDENTS DURING LOW POWER AND SHUTDOWN GaERATONS AT 1991 GRAND GULF. UNIT 1. Analysis Of Core Damage Frequency From In-NUREG/CR-5861: CRACK-SPEED RELATIONS INFERRED FROM LARGE SINGLE-EDGE-NOTCHED SPECIMENS OF A 533 B STEEL-temal Events For Plant Operational State 5 Dunng A Refueling Outage.Intemal NUREG/CR-6206 TRANSPORT CALCULATIONS OF RADIATION EX-NUREG/CR 6143302PT4: EVALUATION Or POTENTIAL SEVERE AC-POSURE TO VESSEL SUPPORT STRUCTURES IN THE TROJAN RE.

ACTOR.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATONS AT GRAND GULF. UNIT 1. Analysis Of Core Damage Frequency From in-PLG, lNC. (FORMERLY PICKARD. LOWE & GARRICK,1NC.)

temal Events For Plant Operational State 5 Dunng A Reluoling NUREG/CR-6144 V02Pt A. EVALUATION OF POTENTIAL SEVERE AC.

Outage ir,temaL_

CIDENTS DURING I I >W POWER AND SHUTDOWN OPERATONS AT NUREG/CR-6143 V03. EVALUATON OF POTENTIAL SEVERE ACCI-SURRY, UNIT 1 Ano 1 sis Of Core Damage Frequency From Intemal

^

Events Dunng MeLoop Operations Main Report (Cha ters 14)

Ana ses O No Damage Requency Rm W NUREG/CR 6144 V02P1B. EVALUATION OF POTENT AL SEVERE AC-temal Events For Plant Operational State 5 Dunng A Refuelmg Outage.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATONS AT NUREG/CR-6143 V04 EVALUATION OF POTENTIAL SEVERE ACCI-SURRY, UNIT 1, Analysis Of Core Damage Frequency From intemal DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT Events Durmg Md-loop Operations Mam Report (Chapters 712)

GRAND GULF. UNIT 1. Analysis Of Core Damage Frequency From in.

NUREG/CR 6144 V02P2: EVALUATION OF POTENTIAL SEVERE ACCI.

temally induced Flooding Events For Plant Operat onal Stato 5 Durmg DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NURE C 652: EXPERIMENTS TO INVESTIGATE DIRECT CON.

von s d

a na s 0 TAINMENT HEATING PHENOMENA WITH SCALED MODELS OF THE NUREG/CR 6144 V02P3A ALUAT OF TENTIAL SEVERE AC.

SURRY NUCLEAR POWER PLANT.

COENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR-6218: A REVIEW OF THE TECHNICAL ISSUES OF AIR IN.

SURRY, UNIT 1. Analysis Of Core Damage Frequency From uternal GRESSION DURING SEVERE REACTOR ACCIDENTS.

NU bG C 6744 VO 8

A T

TEN [SEV SCIENCE & ENGINEERING ASSOCIATES,INC.

E C.

COENTS Dl4tlNG LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR-6143 V02P1 A. EVALUATION OF POTENTIAL SEVERE AC-SURRY,UN4

1. Analysis Of Core Damage Frequency From intomal CIDENTS DURING LOW POWER AND SHUTDOWN OPERATONS AT E ents Du mg Md-Loop Operations Appenrlices E (Sections E 9 E 16)

GRAND GULF, UNIT 1. Analysis Of Core Damage Frequency From In-NUhvH4144 V02P4: EVALUATON OF POTENTIAL SEVERE ACCI.

temal Events For Plant Operatonal State 5 Durmg A Refueling DENTS DURING LOW POWER AND SHUTDOWN OPERATONS AT Outage Sechons 09.

SURRY, UNIT 1. Analysis Of Core Demage Frequency From intemal NUREG/CR-6143 V02P1B. EVALUATON OF POTENTIAL SEVERE AC-Events Dunna M4-Lonp Operations Appendices F-H CIDENTS DURING LOW POWER AND SHUTDOWN OPERATONS AT NUREG/CR-6144 V02PS: EVALUATION UF POTENTIAL SEVERE ACCI.

GRAND GULF, UNIT 1. Analysis Of Cure Damage Frequency From in-DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT temal Events For Plant Operational State 5 Dunng A Refuelmg SURRY,0 NIT 1. Analysis Of Core Damage Frequency Frorn intemal Outage Section 10.

Events Dunng Md-loop ations Appendices i NUREG/CR-6143 V02PIC: EVALUATION OF POTENTIAL SEVERE AC-NUREG/CR4144 V03 P1 ALUATION OF POTENTIAL SEVERE AC.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATONS AT l

COENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT GRAND GULF, UNIT 1. Analysis Of Core Damage Frequency From in.

I SURRY. UNIT 1 Anatyses Of Core Damage Frequency From intemal temal Events For Plant Operational State 5 Dunng A Refueling l

Fws Dunng Md Loop Operations Ma n Report Outage Man Report.

l NUREG/CR-6144 V03 P2 EVALUATION OF POTENTIAL SEVERE AC.

NUREG/CR-6143 V02PT2: EVALUATION OF POTENTIAL SEVERE AC-CIDENTS DURiNG LOW POWER AND SHUTDOWN OPERATONS AT COENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT l

)

SURRY, UNIT 1. Analysis Of Core Damage Frequency From intomal GRAND GULF, UNIT 1. Analysis Of Core Damage Frequency From In-Fires Dunng Mid Loop Operations Appendices.

Iemal Events For Plant Operational State 5 Dunng Refuehng Outage internal.

PRD CONSULTING NUREG/CR-6143 V02PT3 EVALUATON OF POTENTIAL SEVERE AC-NUREG/CR-6143 V05-EVALUATION OF POTENTIAL SEVERE ACCI.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT GRAND GULF. UNIT 1 Analysis Of Core Damage frequency From In-

50 Contractor index torna: Events For Plant Operatonal State 5 Dunng A Refuehng NUREG/CR-6143 V03 EVALUATION OF POTENTIAL SEVERE ACCI-Outage lniemal -

DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREGICR 6143 V02PT4 EVALUATION OF POTENTIAL SEVERE AC-GRAND GULF UNIT 1.Anar s4s Of Core Damage Frequency From In-r CIDEteTS DURING LOW POWER AND SHUTDOWN OPERATIONS At tema! Events For Plant Operational State 5 Dunna A Rotvehng Outaje GPAND GULF UNIT 1. Analysis Of Core Damage Frequency From In-NUREG/CR 614J V04 EVALUATION OF POTENTIAL SEVERE AGGi-tomal Events For Plant Operatonal State 5 Dunng A Refuthng DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT Outage Intemal -

GRAND GULF. UNIT 1. Analysis Of Core Damage Frequency From in.

NUREu/CR-6143 V03 EVALUATION OF POTENTIAL SEVERE ACCI-ternally Induced Flooding Events For Plant Operatonal State 5 Dunng DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT a Refuehng..

GRAND GULF. UNIT 1 Analysis Of Core Damage Frequency From In-temal Events For Plant Operational State 5 Dunng A Refuehng Outage SOREQ NUCLEAR RESEARCH CENTER, VAVNE, ISRAEL NUREG/CR-6224 DRF FC: PARAMETRIC STUDY OF THE POTENTIAL NUREG/CR 8144 V02P1 A. EVALUATION OF POTENTIAL SEVERE AC-FOR BWR ECCS STRAINER BLOCKAGE DUE TO LOCA GENERAT-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT ED DEBRIS Draft For Comment SURRY, UNIT 1. Analysis Of Cove Damage Frequency From Intemal Events Dunng Md-Loop Operatons Main Report (Chapters 1-6) i SCIENCE APPLICATIONS INTERNATIONAL CORP. (FORMERLY NUREG/CR-6144 V02PIB t VALUATION OF POTENTIAL SEVERE AC.

SCIENCE APPLICATIONS, CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG 1484 V01: FINAL ENVIRONMENTAL IMPACT STATEMENT SURRY, UNIT 1. Analysis Of Core Damage Frequency From Intemal FOR THE CONSTRUCTION AND OPERATION OF CLAIBORNE EN.

Esents Dunng Md-Loop Operatons Main Report (Chapters 712)

RICHMENT CENTER, HOMER, LOUISIANA. Docket No. 70-3070 Louis,.

NUFiEG/CR 6144 V02P2. EVALUATION OF POTENTIAL SEVERE ACCI-ana Energy Services, L P. Environmental impact Statement DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NURE G-1484 V02: FINAL ENVIRONMENTAL IMPACT STATEMENT SURRY, UNIT

1. Analysis Of Core Damage Frequency From Intamal FOR THE CONSTRUCTION AND OPERAllON OF CLAIBORNE EN.

Events Dunno Md-loop Operations Appentlices A-D NUREG/CR 6144 V02P3A. EVALUATION OF POTENTIAL SEVERE AC-RICHMENT CENTER, HOMER, LOUISIANA. Docket No. 70 3070 Louis,.

ana Energy Services, L.P. Comments And Responses CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR-6143 V02PI A EVALUATION OF POTENTIAL SEVERE AC.

SURRY, UNIT 1. Analysis Of Core Damage Frequency From intemal CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT Events Dunng Md-Loop Operatons Appendices E (Sectons E 1 E 8)

NUREG/CR 6144 V02P3B EVALUATION OF POTENTIAL SEVERE AC-GRAND GULF. UNIT 1. Analyses Of Core Damage Frequency From In-CtDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT temal Events For Plant Operatonal State 5 Dunesg A Refueling Outage Sections 19 SURRY, UNIT 1. Analysis Of Core Damage Frequency From intemal NUREG/CR-6143 V02PIB EVALUATION OF POTENTIAL SEVERE AC.

Events Dunng Md-Loop Operatons Appendices E (Sectons E 9 E 16)

NUREG/CR-6144 V02P4 EVALUATION OF POTENTIAL SEVERE ACCl-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT GRAND GULF, UNIT 1 Analysis Of Core Damage Frequency From In-SURRY, UNIT 1. Analysis Of Core Damage Frequency From Intemal ternal Events For Plant Operatonal State 5 Dunng A Refuehng Outa Secton 10 Events Dunng Md Loop Operatens Appendices F H NUREG/CR-6144 V02P5 EVALUATION OF POTENTIAL SEVERE ACCl-NURE CR-6143 V02PIC. EVALUATION OF POTENTIAL SEVERE AC-DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SURRY, UNIT 1. Analysis Of Core Damage Frequency From Internal GRAND GULF, UNIT 1 Analysis Of Core Damage Frequency From in.

Events Dunng Mid Loop Operatons Appendices 1.

temal Events For Plant Operatonal State 5 Dunng A Refuehng Outage Main Report TEX AS A&M UNIV., COLLEGE STATION, TX NUREG/CR-6143 V02PT3 EVALUATION OF POTENTIAL SEVERE AC-NUREG/CR 6162. EFFECTS OF PRIOR DUCTILE TEARING ON CLE AV-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT AGE FRACTURE TOUGHNESS IN THE TRANSITION REGION GRAND GULF.UNil 1. Analysis Of Core Damage Frequerry From in.

ternal Events For Plant Operational State 5 Dunng A Refuehng WESTINGHOUSE ELECTRIC CORP.

Outage lntemal...

NUREG/CR 6127 THE EFFECTS OF STRESS ON NUCLEAR POWER NUREG/CR 6143 V02PT4. EVALUATION OF POTENTIAL SEVERE AC-PLANT OPERATIONAL DECISION MAKING AND TRAINING AP-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT PROACHES TO REDUCE STRESS EFFECTS GRAND GULF UNIT t Analysis Of Core Damage Frequency from In-NUREG/CR-6208 AN EMPIRICAL INVESTIGATION OF OPERATOR temal Events For Plant Operatonal State b Dunng A Refuehng PERFORMANCE IN COGNITIVELY DEMANDING SIMULATED EMER.

Outage Internal..

GE NCIE S.

9 l

l l

International Organization Index This index lists, in alphabetical order, the countries and performing organizations that pre-i pared the NUREG/lA reports listed in this compilation. Listed below each country and per-i 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 pubbshed during this quarter 1

51

I I

I i

i l

l

_0 l

l

1 Licensed Facility Index This index lists the facilities that were the subject of NRC staff or contractor reports. The i

facility names are arranged in alphabetical order. They are preceded by their Docket number l

Cnd followed by the report number. If further information is needed, refer to the main citation by the NUREG number.

E275 Demo Canyon Nutiser Power Plant. Und 1, NUREG/CR 5726 S 290 Surg Power Staten. Unn 1, Vrgne Eleckc & NUREG/CR4144 V0s Pacec Gas & Eiscar Co Power Co.

2 323 Demo Canyon Nucteer Power Plant, Und 2, NUREG/CR.5726 W200 Surg Power Staten, Und 1, Vepme Electrc & NUREG/CR4144 V05 Pecdc Gas & Elecer Co Power Co Propc1480 EPRI. ALWR NUREG1242 V03 PTD1 2 290 Surg Powe Staton, Und 1. Vrpo Electre & NUREG/CR4181 t

Pmisc1400 EPRI ALWR NUREG1242 V03 PT02 Powe Co.

52402 System 80+ Stander $ red Nuclear Power Pleni NUREG1462 V01 52401 GE Advanced BWR Desgn, General Elects Co., NUREG1503 V01 52401 GE Advanced BWil Demon, Generas Elecuc Co., NUREG15n3 V02 Des.. hton Enynee 52402 Systen 60+ Standere:od Nuclear Poww Plani NUREG1462 V02 E416 Grand Gull Nucteer Stalon Urst 1,IAssespp NUREG/CR4143 V03 2m2 60 m%M MEG /M28 E416 Grand Nuclear Staton, Und 1. Message evJREG/CR4143 V04 E416 Grand Gull Statog uret 1, Massspp NUREG/CR 6143 V05 p

70 3070 E

E Senaces. Wasmngton, DC, NUREG1464 V01 P

UWees 70 3070 Eoseena Energy Seraces, Wasmngton. DC.

NUREG 1484 V02 50 344 frolen Nuc6eer Plent. Pcrtland General Electnc NUREG/CR4206 E280 Suny Power Staten, Unn 1. Vrpna E>cInc & NUREGICR4144 V03 P1 S 295 Zon Nuclear Poww Staton. Und 1.

NUREG/CR4168 Power Co 01 _.. Z. Edson Co E280 Suny Power Slaton, Und 1. Vrips Elecinc & NUREG/CR4144 V03 P2 S 304 Zon Nuclear Poser Staten, Und 2.

NUREGICR4168 Power Co.

C.

J E4eonCo t

I i

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l 53

MIC FORM a36 U.S. NUCLEAR REGULATORY COMMCSION

1. REPORT NUMBE,4 (p.es)

(AI' signed by NRC, Add Vst.,

NRCM i #02, cupp., Rev., Cnd Addendum Num-anoi,amor 818UOGRAPHIC DATA SHEET

• * ' * - *ar-)

i case instrucuor s on the r. verse)

NUREG-0304 Vol.19, No. 3 i

a. m La AND sueTrTLe

a. DATE REPORT eUBussLD Regulatory and 'Ibchnical Reports (Abstract Index Journal)

MONTH YEAR l

Compilation for Third Quarter 1994 December 1994 July-September

4. FN OR GRANT NUMBER f

5. AUTHOR (5)

6. TYPE OF REPORT Reference 7 PERIOD COVERED (inclusive Dates) i July-September 1994 J

' 8. PERFORMING ORGANIZATION = NAME AND ADDRE68 (if NRC, previos Diviseon, Office or Region, U.S. Nuclear Regulatory Commission, and mallin0 address; if contractor, provide name and malling address.)

j Division of Freedom of Information and Publications Services Office of Administration U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

9. $PONSOHING ORGANIZATION = NAME AND ADDRESS (If NRC, type *6ame as above"; if contractor, provide NRC Div6s6cn, Oftsce or Region, U.S. Nuclear Regulatory Commission, and malling address.)

Same as 8, above.

)

l i

10. SUPPLEMENT ARY NOTES

11. AB8 TRACT (200 wuros or sees) l This joumal includes all formal reports in the NUREG series prepared by the NRC staff and contractors, proceed-L l

ings of conferences and workshops, grants, and international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal autbr, subject NRC organization for staff and international agreements, contractor, international organization, and licensed facility.

1 l

r r

12. KEY WORDS/DESCRIFTOR8 (List words or phrases that will assist researchers in locating the report.)

13. AVAILABILITY STATEMENT Unlimited i

14. SECURITY CLASSIFICATION

g,g abstract index Unclassified (This Report)

Unclassified

16. NUMBLR OF PAGL6

16. PRICE NRC FORM a36 (2-40) l

Printed on recycled paper Federal Recycling Program l

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