ML20148N994

Regulatory and Technical Reports (Abstract Index Journal). Annual Compilation for 1987

ML20148N994
Person / Time
Issue date:	03/31/1988
From:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
To:
References
NUREG-0304, NUREG-0304-V12-N04, NUREG-304, NUREG-304-V12-N4, NUDOCS 8804080179
Download: ML20148N994 (171)

Text

{{#Wiki_filter:__ . . __

                              ~

NUREG-0304 Vol.12, No. 4 1 1 Regulatory and Technical Reports  !

  ' Abstract Index Journal?                                                 :

i Annual Compilation for 1987 l l l t ! U.S. Nuclear Regulatory  ! Commission I Office of Administration and Resources Management l f

• 9 h 4 ,

D.,, , l I l

                                                                          ^

l j  !!?4 ,98Ag *mai 03C- R PDR l

l Available from l Superintendent of Documents U.S. Government Print:ng Office Post Office Box 37082 Washington, D.C. 20013-7082 A year's subscription concists of 4 issues for this publicat i on. Single copies of this publicat;on are availab!e from Nations! Technica! Information Service, Springfield VA 22161

NUREG-0304 Vol.12, No. 4 Regulatory and Technical Reports  : (Abstract Index Journal? Annual Compilation for 1987 Date Published: March 1988 Policy and Publications Management Branch Division of Publications Services Office of Administration and Resources Management U.S. Nuclear Regulatory Commission Washington, DC 20555 1 p i * * ** 'w, e

       -~...../

l I

CONTENTS Pref ace . . . . . . . . . .. .......... .......... ... . ... . .. . . .. . . .. v index Tab Main Citations and Abstracts . . . . .. ...... ... . ... .... . 1

• Staff Reports
• Conference Proceedings
• Contractor Reports
• International Agreement Reports Secondary Report Number index . . . . . ....... . .. ........ .. . . 2 Personal Author index . . . . . . ......... . ... . . . . .. . . 3 Subject Index ... .. ... ................ .... .. . . . .4 NRC Originating Organization index (Staff Reports) . . .... .. . . ... ... . 5 NRC Originating Organizat'on Index (International Agreements) . . . 6 NRC Contract Sponsor index (Contractor Reports) . .. . . . . . 7 Contractor index . . . ...... . .. .. .. ....... .. . .. .. . . . 8 International Organization index . . .. . . .... . 9 Ucensed Facility Index . . . .. .. .. .. . . 'O l

l i;i

PREFACE This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued t,y the U.S. Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC's intention to publish this compilation quarterly and to cumulate it annually. Your comments will be ap-preciated. Please send them to: Division of Publications Services Policy and Publications Management Branch Publishing and Translations Section Woodmont 537 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 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 rsrecedes each index. The bibliographic elements of the main citations are the following: Staff Report NUREG-0808: MARK 11 CONTAINMENT PROGRAM EVALUATION AND ACCEPTANCE CRITERIA. ANDERSON, C.J. Division of Safety Technology. August 1981. 90 pp. 8109140048 09570:200. Where the entries a: 3 (1) report number, (2) acort title, (3) .eport author, (4) organizational unit of author, (5) date report was published, (6) nurwur 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 ENGINEERING IN NUCLEAR REGULATION. JANERP, J.S. Argonne National Laboratory. May 1981.141 pp. 8105280299. ANL 81-3. 08632:070. Where the entries are (1) report number, (2) report title, (3) report author, (4) organization that compiled the proceedings, (5) date report was published, (6) number of pages in the report, (7) the NRC Docu-ment Control System 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 Laboratorios. May 1981.100 pp. 8107010449. SAND 80-0929. 08912:242. Where the entries are (1) report number, (2) report title, (3) report authors, (4) organizational unit of ' authors or publisher, (5) date report was published, (6) number of pages in the report, (7) the NRC Document Control System accession number, (8) the report number of the originating organization (if given), and (9) the microfiche address (for NRC internal use). v

{ l l 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 - volume Availability of NRC Publications Copies of NRC staff and contractor reports may be purchased either from the Government Printing Office (GPO) or from the National Technical Information Service, Springfield, Virginia 22161. To purchase documents from the GPO, send a check or money order, payable to the Superintendent of Documents, to the inflowing 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 advanco either by international Postal Money Order, payable to the Superintendent of Documents, or by draft on a United States or Canadian bank, payable to the Superintendent of Documents. NRC Report Codes The NUREG designation, NUREG-XXXX, indicates that the document is a formal NRC staff generated report. Contractor prepared formal NRC reports carry the report code NUREG/CR XXXX. lhis type of identification replaces contractor-established codes such as ORNL/NUREG/TM XXX and TREE-NUREG XXXX, as well as various other numbers that could not be correlated with NRC sponsorship of the work being reported. In addition to the NUREG and NUREG/CR codes, NUREG/CP is used for NRC-sponsored conference proceedings and NUREG/lA is used for international agreement reports. All these report codes are controlled and assigned by the staff of the Publishing and Translations Section of the NRC Division of Publications Services. vi

Main Citations and Abstracts The report listings in this compilation are arranged by report number, where NUREG-XXXX is 3 an NRC staff originated report, NUREG/CP XXXX is an NRC-sponsored conference report, NUREG/CR-XXXX is an NRC contractor-prepared report, and NUREG/lA XXXX is an inter-national agreement report. The bibliographic information (see Preface for details) is followed by a brief abstract of this report, NUREG-0020 V10 N09: LICENSED OPERATING REACTORS NUREG-0020 VII NO3: LICENSED OPERATING REACTORS STATUS

SUMMARY

REPORT. Data As Of August STATUS

SUMMARY

REPORT Data As Of February 31,1986(Gray Book 1) ROSS.P.A.; BEEBE,M R. Drvison of 28,1987.(Gray Book 1) SCHWARTZ,1. Drvison of Computer & Computer & Telecommuncabons Semces (Pre 870413). March Telecommunicatons Seryces (Post 870413). October 1987. 1987. 463pp. 8703170242. 40032:208. 465pp. 8710210040. 43123.291. The OPERATING UNITS STATUS REPORT - LICENSED OP- See NUREG-0020,V10,N09 abstract. ERATING REACTORS provides data on the operaton of nuc!e-at units as timely and accuratery as possible. This informabon is NUREG-0020 V11 N04: LICENSED OPERATING REACTORS collected by the Offce of Resource Management from the STATUS

SUMMARY

REPORT. Data As Of March 31,1987.(Gray Headquarters staff of NRC's Office of Inspecton and Enforce. Book 1) SCHWARTZ 1 Dmson of Computer & Telecommunica-ment, from NRC's Regonal Offices, and from utates. The three tons Servces (Post 870413). October 1987. 502pp. sectons of the report are monthly highlights and statistics for 8710230043. 43140.253. commercial operating units, and errata from prevously reported See NUREG-0020,V10,N09 abstract. data, a compilation of detaded informaton on each unit, provid-ed by NRC's Regonat Offices,IE Headquarters and the utilities; NUREG-0020 V11 N05: LICENSED OPERATING REACTORS STATUS

SUMMARY

REPORT. Data As Of Apol 30,1987.(Gray and an appendar for mescellaneous informaton such as spent Bock 1) SCHWARTZ 1 Omsson of Computer & Telecommunica. fuel storage capability, reactor years of expenence and non. power reactors in the U.S It is hoped the report is helpful to all tior's Servces (Post 870413). October 1987. 495pp. agencies and indmduals enterested in maintairung an awareness 8711030219 43244 047. See NUREG-0020,V10.N09 abstract. of the U.S. energy situaton as a whole. NUREG-0020 V10 N10: LICENSED OPERATING REACTORS NUREG-0020 VII N06: LICENSED OPERATING REACTORS STATUS SUVMARY REPORT. Data As Of September STATUS

SUMMARY

REPORT Data As Of May 31,1987.(Gray 30,1986(Gray Book 1) ROSS,P.A.; BEEBE.M R Dmson of Book 1) SCHWARTZ,l. Dmson of Computer & Telecommunca. Computer & Telecommurucatons Servces (Pre 870413) March tons Services (Post 870413). October 1987. 48 4 ; 1987. 450pp. 8704090032. 40468 027. 8711030080. 43242.164. See NUREG.0020,V10.N09 abstract See NUREG-0020,V10,N09 abstract. NUREG 0020 V10 N11: LICENSED OPERATING REACTORS NUREv-0020 VII N07: LICENSED OPERATING REACTORS STATUS

SUMMARY

REPORT Data As Of June 30,1987.(Gray STATUS

SUMMARY

REPORT. Data As Of October 31,198t (Gray Book 1) ROSS,P.A.; BEEBE M R. Dmson of Book 1) SCHWARTZJ Dmson of Computer & Telecommunca-Computer & Telecommunicatons Services (oost 870413) Apol tons Services (Post 870413). October 1987. 508pp. 1987. 471pp. 8705120010 40901.348 8710270253. 43185 327. See NUREG 0020,V10,N09 abstract. See NUREG-0020,V10.N09 abstract. NUREG-0020 V10 N12: LICENSED CPERATING REACTORS NUREG-0020 Vit N08: LICENSED OPERATING REACTORS STATUS

SUMMARY

REPORT Data As Of July 31,1987.(Gray STATUS

SUMMARY

REPORT Data As Of November 30,1986 (Gray Book l} ROSS,P. A. Omson of Computer & Tele. Book 1) SCHWARTZ,f. O,vison of Computer & Telecommunica-communicators Services (Post 870413) June 1987. 460pp. tons Services (Post 870413) October 1987. 514pp. 8707060427.41582:185 8710280145. 43207.001. See NUREG-0020,V10.N09 abstract See NUREG.0020,V10,N39 abstract. NUREG-0020 VII N01: LICENSED OPERATING REACTORS NUREG 002C VII N09: LICENSED OPERATING REACTORS STATUS

SUMMARY

REPORT Data As Of December STATUS

SUMMARY

REPORT Data As Of August 31,1986 (Gray Book 1) ROSS,P A Dmson of Computer & Tele. 31,1987.(Gray Book 1) SCHWARTZ 1 Deson of Computer & communicatons Services IPost 870413). September 1987. Telecommunicatons Services (Post 870413) December 1987. 473pp. 8710080382. 42994.112 496pp. 8712280075. 43822105. See NUREG 0020,V10 N09 abstract See NUREG-0020.V10.N09 abstract-NUREG-0020 V11 NO2: LICENSED OPERATING REACTORS NUREG-0020 V11 NIO: LICENSED OPERATING REACTORS STATUS

SUMMARY

REPORT Data As Of January STATUS SUVMARY RE PORT. Data As Of September 31,1987,(Gray Book 1) SCHWARTZ,1 Dmson of Computer a 30,1987 (Gray Book 0 SCHWARTZ 1 Dmson of Computer & Telecommun,catons Sereces (Post 870413) October 1987. Telecommunecatons Semces (Post 870413) December 1987. 456pp. 8710200566 43100 329 489pp 8712300202. 43847 021. See NUREG 0020,V10 N09 abstract See NUREG-0020,v10.N09 abstract. 1

2 Main Citations and Abstracts NUREG-0020 V11 N11: LICENSED OPERATING REACTORS abnormal occurrences reported by Agreement States. One in. STATUS

SUMMARY

REPORT. Data As Of October voNed an uncontrolled release of Arypton-85 to an unrestncted 31,1987.(Gray Book 1) SCHWARTZ,l. Divison of Computer & area: the other invoNed a contaminated radiopharmaceutcal Telecommuncatons Sensees (Post 870413). December 1987. used in diagnoste admnstrabons. The report also contains in. 425pp. 8801110233. 43970167 formation updatng some previously reported abnormal occur. See NUREG-0020,V10,NO$ abstract. rences. NUREG-0040 V10 N04: LICENSEE CONTRACTOR AND NUREG 0090 V09 NO3: REPORT TO CONGRESS ON ABNOR-VENDOR INSPECTION STATUS REPORT, Quarterty MAL OCCURRENCES. July-September 1986.

• Offce for Anaty-Report, October December 1986 (WNte Book)
• Div of sis & Evaluabon of Operatonal Data, Drector, Aprd 1987.60pp.

CAVendor & Technical Training Center Programs,tE (850212- 8705290301. 41115:296. 870413). February 1987. 274pp. 8703170192. 40047:139. Sechon 208 of the Energy Reorgaruzabon Act of 1974 identi-TNs penodcal covers the results of inspectons performed by the NRC's Vendor Program Branch that have been dsinbuted fes an abnormal occurrence as an unscheduled incident or event which the Nuclear Regulatory Commisson determines to to the inspected orgaruzatons dunng the penod from October be segrufcant from the standpoint of pubhc health and safety 1986 thru December 1986. Also, included in tNs issue are the and requees a quarterfy report of such events to be made to results of certain inspecbons performed poor to October 1986 Congress. TNs report covers the penori July 1 to September that were not included in prevous issues of NUREG-0040- 30, 1986. Dunng the report penod, the/e were four abnormal NUREG-0040 V11 N01: LICENSEE CONTRACTOR AND occurrences at the nuclear power plants bcensed to operate. VENDOR INSPECTION STATUS REPORT. Quarterfy The events were (') a differenbal pressure switch problem in Report, January-March 1987.(WNte Book)

• Drvison cf Reactor safety systems at LaSalle facihty, (2) abnormal cooldown and Inspecten & Safeguards (Post 870411). May 1987. 235pp. depressunzaton transient at Catawba Unit 2, (3) signifcant 8706160106. 41311:032. safeguards defeiences at Wolf Creek and Fort St. Vrain, and TNs penodcal covers the results of inspectons performed by (4) s'gnifcant defciences in access controls at River Bend Sta-the NRC's Vendor inspect on Branch that have been distobuted ton. There was one abnormal occurrence at the other NRC h-to the inspected organizatons dunng the penod from January censees; it invoNed a therapeute medcal rnisadmirustraton.

1987 through March 1987. Also, included in tNs issue e c the There was one abnormal occurrence reported by an Agreement l results of certain inspectons performed pnor to January 1987 State; it involved a therapeuts medcal misadmirustraton. The that were not included in prevous issues of NUREG-0040. report also contains informaton updabng some previously re-NUREG-0040 V11 N02: LICENS'EE CONTRACTOR AND VENDOR INSPECTION STATUS REPORT. Quarterty NUREG-0090 V09 N04: REPORT TO CONGRESS ON ABNOR. Report Aprd-June 1987.(WNte Book)

• Division of Reactor In- MAL OCCURRENCES. October December 1986.
• Office for specten & Safeguards (Post 870411). August 1987, 150pp. Analysis & Evaluabon of Operatonal Data. Director. July 1987, 8708270427. 42391:011. 150pp. 8708170105. 42171:217, TNs penodcal covers the results of inspectons performed by Secton 208 of the Energy Reorganizaton Act of 1974 edenb-the NRC's Vendor Inspecten Branch that have been distnbuted fies an abnormal occurrence as an unscheduled incident or .

to the inspected orgaruzatons dunng the pered from Aprd 1987 event whch the Nuclear Regulatory Commissaon determines to I through June 1987. Also, included in this issue are the results be signifcant from the standpoint of pubic health and safety I of certain inspectons performed pnor to Aprd 1987 that were and requires a quarterly report of such events to be made to not included in prevous issues of NUREG-0040. Congress. TNs report covers the penod October i to December NUREG-0040 V11 NO3: LICENSEE CONTRACTOR AND 31,1986. Denng the report period, there were three abnormal VENDOR INSPECTION STATUS REPORT. Quarterly occurrences at the nuclear power plants bcensed to operate. Report, July September 1987.(WNte Book)

• Divisson of Reactor The events were (1) the loss of low pre ~sure servce water sys-Inspecbon & Safeguards (Post 870411). October 1987,166pp. tems at Oconee, (2) degraded safety systems due to incorrect 8711090267. 43316-029. twoue switch settings on Rotork motor operators at Cata*ba This periodcal covers the results of inspecbons performed by and McGute Nuclear Statens, and (3) a secondary system pipe the NRC's Vendor inspecton Branch that have been distnbuted break resulting in the death of four persons at Surry Unit 2.

to the inspected organizatons dunng the penod from Jufy 1987 There were six abnormal occurrerces at the other NRC heens-through September 1987. Also included in (Ns issue are the re- ees. One ded reease of amencium 241 mside a waste stw-suits of certarn inspecbons performed pror to July 1987 that age budding at Wnght-Patterson At Force Base; three invoNed were not included in reevous issues of NUREG-0040. medical misadmirustratons, one therapeute and two diagnostc; one invoNed a suspenson of hcense for servong teletherapy NUREG-0090 V09 N02: REPORT TO CONGRESS ON ABNOR- and radography units; and one involved an immediate effectrve MAL OCCURRENCES.Apnl-June 1986.

• Office for Analysis & order mooifying hcense and order to show cause issued to an Evaluabon of Operatonal Data, Director. January 1987. 71pp. industnal radography company. There were no abnormal occur-8703030835. 39866:152. rences reported by the Agreement States. The report also con-Secton 208 of the Energy Reorganizaton Act of 1974 idenb- tains informaton updating some prevously reported abnormal  !

fies an abnormal occurrence as an unscheduled incident or occurrences. I event whsch the Nuclear Regulatory Commisson determines to be significant from the standpoint of pubic health and safety NUREG-0090 V10 N01: REPORT TO CONGRESS ON ABNOR-and requwes a quarterfy report of such events to be made to MAL OCCURRENCES. January March 1987.

• Offee for Analy.

Congress. This report covers the penod Aprd 1 through June sas & Evaluabon of Operatonal Data. Drector. October 198-30,1986. Dunng the report penod, there were two abnormal oc. 58pp. 8711230326. 43426 226. currences at the nuclear power plants hcensed to operate. One Secten 208 of the Energy Reorganizaton Act of 1974 idenb-involved an out of sequence control rod withdrawal and the f:es an abnormal occurrence as an unscheduled incident or other involved a boihng water reactor emergency core coohng event which the Nuclear Regulatory Commesson determines to system design defoency. There were frve abnormal occur- be sigrufcant from the standpoint of pubhc hearth and safety rences at the other NRC bcensees Twa invoNed wdifuf failure and requires a quarterty report of such events to be made to to report diagnostaC medcal trasadministrabons to the NRC; one Congress. This report covers the perod January 1 to March 31, envoNed a therapavbc medical misadtrurnstraton; and two in- 1987. Dunng the report penod, there was one abnormal occur-voNed diagnosbc medical misadmirustratons. There were two rence at the nuclear power plants hcensed to operate The item l l

M;ln Cititlans cnd Abstr:cte 3 involved the NRC suspenson of power operations of the Peach NUREG-0327 R04: OWNERS OF NUCLEAR POWER Bottom Facihty due to inattentiveness of the control room staff. PLANTS. Percentage Ownership Of Commercial Nuclear Power There were seven abnormal occurrences at the other NRC li- Plants By Utility Companies. WOOD R S. Office of Nuclear Re-censees. Four involved diagnoste medical m.sadministrations; actor Regulaton, Derector (Post 870411). August 1987. 38pp. the other three involved breakdowns in management controls at 8708240084.42316.072. three separate industnal radography hcensees. There were two The report indicates percentage ownership of commercial nu-abnormal occurrences reported by the Agreement States. Both clear pcwer plants by utaty companies. The report includes all involved breakdowns in management controls at industnal radi- plants operating, under constructon, docketed for NRC safety ography hcensees. The report also contains informaton updat- and environmental reviews, or undct NRC antatrust review, but ing some prevously reported abnormal occurrences. does not include those plant announced but not yet under review or those plants formally cancelled Part I of the report NUREG-0090 V10 NO2: REPORT TO CONGRESS ON ABNOR- hsts plants alphabetically with their associated applicants or li-MAL OCCURRENCES.Apni-June 1987.

• Orface for Analysis & censees and percentage ownership. Part 11 hst apphcants or h-Evaluation of Operational Data, Director. November 1987.53pp. censees alphabetically w,th the r associated plants and percent-8801070275. 43945.079. age ownership. Par 1 l also indicates which plants have recerved Secton 208 of the Energy Reorganizaton Act of 1974 idente operat2ng hcenses (OLs).

fees an abnormal occurrence as an unscheduled incident or event which the Nuclear Regulatory Commisson determines to NUREG-0332: POTENTIAL HEALTH AND ENVIRONMENTAL IM-be significant from the standpo nt of pubhc health and safety PACTS ATTRIBUTABLE TO THE NUCLEAR AND COAL FUEL and requires a quarterly report of such everts to be made to CYCLES Final Report GOTCHY,R L. Office of Nuclear Reactor Congress. This report covers the perod April 1 to June 30, Regulation, Dvector (Post 870411). June 1987. 73pp. 1987. Dunng the report perod, there were no abnormal occur. 87070705M. 41600:001. rences at the nuclear power plants licensed to operate. There Estimates of mortahty and morbety are presented based on were five abnormal occurrences at the other NRC hcensees present-day knowledge of health effects resulting from current Three involved medical misadministratons (two diagnostic and component designs and operatons of the nuclear and coal fuel one therapeutic); one involved the issuance of an NRC Order to escles, and antcipated emisson rates and occupatonal expo-remove a hospitars radiation safety officer due to falsificaton of sure for the varcus fuel cycle facihties expected to go into oper-certain records; and one involved a signif cant breakdown in aton dunng the next decade. The author concluded that, al-management and procedural controls at an industnal radogra- though there are large uncertainties in the estimates of potential phy bcensee. There was one abnormal occurrence reported by hea'th effects, the coal fuel cycle attemative has a greater an Agreement State (Idsho). The item involved radographer health impact on man than the uranium fuel cycle. HoAever, the overexposures The report also contains informaton updat;ng increased nsk of hea?th effects for either fuel cycle represents a some prevously repor1ed abnorraal occurrences very small incremental nsk to the average individual in the pubhc for the balance of this century. The potential for large im-NUREG-0304 VII N04: REGULATORY AND TECHNICAL RE- pacts exists in both fuel cycles, but the potential impacts asso-PORTS (ABSTRACT INDEX JOURNAL). Annual Compilaton ciated with a runaway Greenhouse Effect from combuston of For 1986.

• Office of Administraton (Pre 870413) March 1987. fossil fuels, such as coal, cannot yet be reasonably quantif ed 212pp. 8704010175. 40324 254. Some of the potential environmental impacts of the coal fuel This journal includes all formal reports in the NUREG senes cycle cannot currently be reahstically estimated, but those that prepared by the NRC staff and contractors; proceedings of con- can appear greater than those from the nuclear fuel cycle.

ferences and workshops; as well as internatonal agreement re- NUREG-0383 V01 R10; DIRECTORY OF CERTIFICATES OF ports The entnes in this compdaten are indexed for access by title and abstract, secondary report number, personal author, COMPLIANCE FOR RADIOACTIVE MATERIALS PACKAGES Summary Report Of NRC Approved Packages.

• subject, NRC organization for staff and internatonal agree- Dmson of Safeguards & Transportaton (Post 870413). Novem.

ments, contractor, internatonal organizaton, and hcensed f acih-ber 1987. 603pp. 8712020110. 43524 244. ty. This directory contains a Summary Report of NRC Approved NUREG-0304 V12 N01: REGULATORY AND TECHNICAL RE. Packages (Volume 1), Certif cates of Comphance (Volume 2), PORTS (ABSTRACT INDEX JOURNAL). Compdaten For Fast and a Summary Report of NRC Approved Ouahty Assurance Ouarte' 1987, January March.

• Dmson of Pubhcaton Servees Programs for Radcactive Matenal Packages (Volume 3) The (Post 870413) May 1937. 62pp. 8706030076. 41166:112. purpose of this directory is to make available a convenient See NUREG-0304,V11,N04 abstract source of informaton on packagings which have been approved by the U S. Nuclear Regulatory Commesson. To assist in idente NUREG-0304 V12 N02: REGULATORY AND TECHNICAL RE. tying packaging, an index by Model Number and corresponding PORTS (ABSTRACT INDEX JOURNAL) Compdation For Certif cate of Comphance Number is included at the back of Second Quarter 1987,Apnl-June.
• Dmson of Pubhcaton Serv. each volume of the directory. The Summary Report includes a aces (Post 870413) August 1987. 60pp. 870 % 40390. hsting of all users of each package design pror to the pubhca-42522 207. tion date of the directory. Shipments of redcactrve matenal ute See NUREG-0304,V11,N04 abstract hzing these packagings must be in accordance w th the provn sons of 49 CFR 173 471 and 10 CFR Part 71, as apphcable. In NUREG-0304 V12 NO3: REGULATORY AND TECHNICAL RE. satisfying the requirements of Secticn 71.12, it is the response-PORTS (ABSTRACT INDEX JOURNAL) Compdation For Third bihty of the hcensees to ensure them that they have a Copy of Ouarter 1987,Jufy September.
• Dmson of Pubhcaton Services the current approval and conduct ther transportaton actmties (Post 870413). November 1987, 60pp. 8711250102. 43460 306. in accordance mth an NRC approved quabty assurance pro-See NUREG-0304,V11,N04 abstract. gram. Copies of the current approval rnay be obtained from the U S. Nuclear Regulatory Commisson Pubhc Document Room NUREG-0325 RIO: U S NUCLEAR REGULATORY COMMISSION foes (see Docket No ksted on each certifcate) at 1717 H FUNCTIONAL ORGANIZATION CHARTS.
• Office of Adminas- Street, Wash.ngton, DC 20555 Note that the general bcense of traton (Pre 870413). February 1987. 57pp. 8702240496 10 CFR 71.12 does not authonze the recerpt, possession, use 39725.023. or transfer of byproduct source, or special nuclear matenal, Functonal ceganizaton charts for the NRC wmmisson Of- such authonzaton must be obtained pursuant to 10 CFR Parts fices, Diviscos, and Branches are presented. 30 to 36,40, 50, or 70.

4 Main Citations and Abstracts NUREG-0383 V02 RIO: DIRECTORY OF CERTIFICATES OF NUREG-0525 R12: SAFEGUARDS

SUMMARY

EVENT LIST COMPLIANCE FOR RADIOACTIVE MATERIALS (SSEL). GRAMANN.R.H. Dvison of Safeguards (Pre 870413). PACKAGES.Certifcates Of Co npliance.

• Dmsion of Safe- February 1987. 47pp. 8703130205. 40005:289.

guards & Transportation (Post 870413). November 1987.654pp. The Safeguards Summary Event List provides bnef summa-8712020034.43526:127.. nes of hundreds of safeguards-retated events involving nuclear See NUREG 0383,V01,R10 abstract. matenal of facdities regulated by the U.S. Nuclear Regulatory

  - NUREG-0343 V03 R07: DIRECTORY OF CERTIFICATES OF                        Commission. Events are described under the categones: bomb-COMPLIANCE               FOR      RADIOACTIVE         MATERIALS       related, intrusion, m ssing/ allegedly stolen, transportaton-relat-PACKAGES. Summary Report Of NRC Approved Quality Assur-               ed, tampenng/ vandalism, arson, f. rearms-related, radological ance Programs For Radioactue Matenal Packages.

• Dwision of sabotage, nonradiological sabotage, and miscellaneous. Infor-Safeguards & Transportaton (Post 870413). November 1987. maton in the event desenptons was obtained from official NRC 141pp. 8712020037. 43521:246. reports.

See NUREG-0383301,R10 abstract' NUREG-0525 R13: SAFEGUARDS

SUMMARY

EVENT LIST NUREG-0386 D04 R04: UNITED STATES NUCLEAR REGULA- (SSEL). Dwision of Safeguards & Transportaton (Post TORY COMMISSION STAFF PRACTICE AND PROCEDURE 870413). July 1987. 85pp. 8708240212. 42316:282. OlGEST. July 1972 - June 1986.

• Office of the General Coun- See NUREG-0525.R12 abstract.

sel February 1987. 661pp. 8703170245. 40050.267. TNs Rewsion 4 of the fourth edabon of the NRC Staff Pracbce NUREG 0540 V08 N10: TITLE LIST OF DOCUMENTS MADE and Procedure Dgest contains a digest of a number of Com- PUBUCLY AVAILABLE. October 1 31,1986.

• Drvision of Tech-messon, Atomic Safety and Licensing Appeal Board, and Atomic necal informaton & Document Controf (Pre 870120). December Safety and Licensing Board decisions issued dunng the pered 1ec6. 479pp. 870i200424. 3935310e.

Ju'y 1,1972 to June 30,1986, interpret;ng the NRC Rules of TNs document :s a monthly publication containing desenp-Practice in 10 CFR Part 2. TNs Rewson 4 replaces in part eark- bons of informabon recewed and generated by the U.S. NRC. er editions and supplements and includes appropnate changes TNs informaton includes (1) docketed matenal associated with reflecting the amendment to the Rules of Practice effectue ciwhan nuclear power plants and other uses of radcactue ma-June 30,1986. tenals, and (2) nondocketed matenal recerved and generated by NUREG-0386 D04 ROS: UNITED STATES NUCLEAR REGULA- NRC perbnent to its role as a regulatory agency. The folicwing TORY COMMISSION STAFF PRACTICE AND PROCEDURE indexes are included. Personal Author index, Corporate Source OtGEST. July 1972 September 1986.

• Offee of the General Index, Report Number inder, and Cross Reference to Pnnerpal Counsel. June 1987, 628pp. 8707130184. 41682:228. Documents index.

This Rewsion 5 of the fourth edibon of the NRC Staff Practice and Procedure Dgest contains a dgest of a number of Com- NUREG-0540 V08 N11: TITLE UST OF DOCUMENTS MADE misson, Atomic Safety and Lcensing Appeal Board, and Atome PUBLICLY AVAILABLE. November 1 30.1986

• Office of Ad-ministraton (Pre 870413). January 1987. 377pp. 8701200372.

Safety and Licensing Board decisons issued dunng the perod 39319 208 July 1,1972 to September 30,1986, interpreting the NRC Rules See NUREG-0540,V08,N10 abstract. of Practice in 10 CFR Part 2. TNs Rews>on 5 replaces in part earlier editions and supplements and includes appropnate NUREG-0540 V08 N12: TITLE UST OF DOCUMENTS MADE changes reflecting the amendments to the Rules of Practice ef- PUBUCLY AVAILABLE. December 1 31,1986

• Ottice of Ad.

fectue September 30,1986. ministrat on (Pre 870413). February 1987. 439pp. 8703120259 NUREG 0386 D04 R06: UNITED STATES NUCLEAR REGULA. 39984.032. TORY COMMISSION STAFF PRACTICE AND PROCEDURE See NUREG-0540,V08,N10 abstract. r1987 597 871 2 6 43 1 001 NUREG-0540 V09 N01: TITLE LIST OF DOCUMENTS MADE TNs rewson 6 of the fourth editon of the NRC Staff Practce PUBUCLY AVAILABLE. January 1 31,1987.

• Office of Admines-and Procedure Dgest contains a digest of a number of Com- traton (Pre 870413). March 1987, 342pp. 8704060097.

mission, Atomic Safety and Ucensing Appeal Board, and Atomec 40 Safety and bcensing Board decis>ons issued dunng the penod e REG-0540'V08.N10 abstract' i July 1,1972, to December 31,1986, interprebng the NRC Rules

,     of Practice in 10 CFR Part 2. TNs rewsion 6 replaces in part        NUREG-0540 V09 N02: TITLE UST OF DOCUMENTS MADr PUBUCLY AVAILABLE. February 1-28,1987.

• Dwsion of Pubh-earlier edit ons and supplements and includes appropnate caton Serwces (Post 870413). Apol 1987. 411pp 8706240149.

changes reflecbng the amendments to the Rules of Practce ef-fectue December 31,1986' 41440:175 See NUREG-0540.V08.N10 ab*, tract NUREG-0430 V07 N01: LICENSED FUEL FACILITY STATUS REPORT. inventory Difference Data January June 1986 (Gray NUREG-0540 V09 NO3: TITLE UST OF DOCUMENTS MADE Book II)

• Ofc of Inspecton & Enforcement, Deector (820201 PUBLICLY AVAILABLE. March 1 31,1987.
• Dwson of Pubhca- ,

870413). February 1987.15pp. 8703120210. 39984 016. ton Services (Post 870413) May 1987. 469pp. 8706160119 NRC is comrrwtted to the penodc pubhcaton of licensed fuei 41315 256. facilibes inventory difference data, following agency rewew of See NUREG 0540.V08 N10 abstract l the informaton and completon of any related NRC investga-NUREG-0540 V09 N04: TITLE UST OF DOCUMENTS MADE af c ue fa to a t s e n PUBUCLY AVAILABLE Apnl 1 30.1987.

• Dmsion of Pubhca-one effectue kilogram of Ngh ennched uranium, low ennched ton Services (Post 870413) June 1987. 482pp. 8706230495 uranium, plutonium, or uranium 233. 41 fu EG-0540,V08.N10 abstract.

NUREG-0430 V07 N02: UCENSED FUEL FACluTY STATUS REPORT. inventory Dfference Data July-December 1986 (Gray NUREG-0540 V09 N05: TITLE UST OF DOCUMENTS MADE Book 41)

• Office of Nuclear Matenal Safety & PUBLICLY AVAILABLE. May 1 31.1987.
• Dmson of Pubhca.

Safeguards.Drector. August 1987. 14pp 8709090409 ton Services (Post 870413) July 1987. 346pp. 8707210755 42566 252. 41833 276. See NUREG-0430.V07 N01 sbstract. See NUREG-0540.V08.N10 abstract

Main Citations and Abstracts 5 NUREG-0540 V09 N06: TITLE LIST OF DOCUMENTS MADE incidence of cancer fatalities and genetc disorders. The most PUBLICLY AVAILABLE. June 1 30,1987. ' Dvison of Pubica- signifcant potential impact associated with any d sposal afterna-ton Servces (Post 870413). August 1987 505pp 8709030196 tue is the nsk of physical injury associated with transportabon 42471:111. accidents. Addit >onally, no significant impacts to aquatic or ter-See NUREG-0540,V08,N10 abstract. restrial botic from any disposal alternative are expected. NUREG 0540 V09 N07: TITLE LIST OF DOCUMENTS MADE NUREG-0728 R02: NRC INCIDENT RESPONSE PLAN.

• Office PUBLICLY AVAILABLE. July 1 31,1987.* Dvision of Publicaten for Analysis & Evaluaton of Operational Data. Drector. June Services (Post 870413). September 1987. 566pp. 8710220425. 1987. 29pp. 8706240202. 41448.219.

ar abry Commsson W $ams cmhan e U EG-0540,V08'N10 abstract ~ nuclear actmtes to protect the pubic health and safety and to NUREG-0540 V09 N04: TITLE LIST OF DOCUMENTS MADE preserve envronmental quabty. An Incident Response Plan had PUBLICLY AVAILABLE. August 1 31,1987.

• Dvison of Pubhca- been developed and has now been revised for the second time ton Servces (Post 870413). October 1987, 403pp. to reflect current Commission polcy. NUREG-0728, Rev 2 as-8711030215. 43241:019. signs responsibihties for responding to any potentially threaten.

See NUREG-0540,V08,N10 abstract- ing incident involving NRC lcensed actmtes and for assunng that the NRC will fulfdl its statutory misson. Revision 2 was nec-NUREG-0540 V09 N09: TITLE LIST OF DOCUMENTS MADE essary to reflect organizatonal changes. PUBLICLY AVAILABLE. September 1-30,1987.

• Dvision of Pubhcaton Senoces (Post 870413). November 1987. 514pp. NUREG-0750 V24 f01: INDEXES TO NUCLEAR REGULATORY 8711230343.43426.283. COMMISSION ISSUANCES. July September 1986.
• Drvison of ,

see NUREG 0540,V08,N10 abstract

• Pubhcaton Services (Fost 870413). June 1987. 61pp.

NUREG-0540 V09 N10: TITLE LIST OF DOCUMENTS MADE 8707020110. 41569.166. PUBLICLY AVAILABLE. October 1 31,1987.

• Dvison of Pubh- Digests and indexes for issuances of the Commission, the caton Sennces (Post 870413). December 1987. 434pp. Atomic Safety and Licensing Appeal Panel, the Atome Safety .

8801110224.43975:315. and Lcensing Board Panel, the Administratue Law Judge,. the [ See NUREG-0540,V08.N10 bstract. Drector's Decisions, and the Denials of Petitons for Rulemak-ing are presenM f NUREG-0654 S01 R01: CRITE A FOR PREPARATION AND EVA'.UATION OF RADtOLOGKAL EMERGENCY RESPONSE NUREG-0750 V24102: INDEXES TO NUCLEAR REGULATORY [ PL/,NS AND PREPAREDNESL IN SUPPORT OF NUCLEAR COMMISSION ISSUANCES. July-December 1986.

• Dvison of POWER PLANTS.Cntena for Ublity Offsite Planning And Pubhcaton Servces (Post 870413). July 1987. 100pp.

Preparedness Draft Report. NRC No Detailed Af$liaton 8708270324. 42389.007. Guen.

• Federal Emergency Management Agency. November See NUREG-0750.V24.101 abstract.

1987. 35pp. 8712080435. FEMA REP 1. 43591.2%. This document has been developed for mtenm use in review. NUREG-0750 V24 NOI: NUCLEAR REGULATORY COMMISSION ing and evaluating uthty-prepared offsate emergency plans and ISSUANCES FOR JULY 1986.Pages 1195.

• Office of Adrrunis-preparedness. This intenm-use document is intended to be used tratom (Pre 870413) January 1987. 204pp. 8702170032 with Secton I and Appendices 15 of the existing NUREG- 39659 214.

0654/ FEMA-REP 1, Rev.1. A notice has been provided in the Legalissuances of the Commisson, the Atomsc Safety and Li-

    "Federal Register" to announce the availabihty of this document                censing Appeal Panet. the Atomic Safety and Licensang Board and to mytte pubhc review and comment. Sthsequent to the re*                   Panel, the Administrative Law Judge, and NRC Program Offices ceipt of comments, this document wdl be issued in final. Except                are presented.

where specifically modified, the existing hcenAe-only evaluaton entena of the current Section 11 are not affected by this docu- NUREG-0750 V24 N02: NUCLEAR REGULATORY COMMISSION ment. For those situatons in which State and/or local govern- ISSUANCES FOR AUGUST 1986 Pages 197-396.

• Office of ments are participabng in the emergency planning process, the Administraton (Pre 870413). February 1987, 208pp.

existing NUREG-0654/ FEMA REP 1 Rev.1 evaluabon cntena 8703090229. 39930.021. will apply. See NUREG-0750,V24.N01 abstract. NUREG-0643 S02: PROGRAMMATIC ENVIRONMENTAL IMPACT NUREG-0750 V24 NO3: NUCLEAR REGULATORY COMMISS!ON 1 STATEMENT RELATED TO DECONTAMINATION AND DIS. ISSUANCES FOR SEPTEMBER 1986 Pages 397 488.

• Office i POSAL OF RADIOACTIVE WASTES RESULTING FROM O' m stra n Pre 870413). March 1987. 101pp.

MARCH 28,1979 ACCIDENT AT THREE MILE ISLAND NUCLE. O AR STATION. UNIT 2 Final Supplement Deakng With Disposal See NUREG 0750.V24,N01 abstract. Of_

• TMI 2 Cleanup Project Directorate. June 1987. 354pp.

8707080318.41616 213. NUREG-0750 V24 N04: NUCLEAR REGULATORY COMMISSION in accordance with the Natonal Enwonmental Pokey Act, the ISSUANCES FOR OCTOBER 1986 Pages 489-679

• Dmson Programmat>c Environmental impact Statement Related to De' of Pubbcaton Services (Post 870413). Apnl 1987. 202pp.

contaminaton and Dsposal of Radcactive Waste for the 1979 8705120123.40899 257. Accdent at Three Mile Island Nuclear Station. Unit 2 (PEIS) has See NUREG-0750,V24,N01 abstract. been supplemented. This supplement updates the enwonmen-tal evaluation of accdent-generated water disposal attematwes NUREG-0750 V24 N05: NUCLEAR REGULATORY COMMISSION pubhshed in the PElS. utikzing more complete and current infor- ISSUANCES FOR NOVEMBER 1986 Pages 681768.

• Divison i maton, and covenng the hcensee's proposal to dispose of the of Pubhcaton Services (Post 870413) May 1987. 99pp- )

water by evaporation to the atmosphere. The staff concludes 8706040313. 41180 238-that the water can be disposed of without incurnng s>gnificant See NUREG.0750.V24.N01 abstract environmental impact The staff's evaluaton of a number of dis-posal arternatrves indicates that no alternatrve is clearty prefera- NUREG4750 V24 N06: NUCLEAR REGULATORY COMM!SSION ble to the others, and that the bcensee's proposal method es (SSUANCES FOR DECEMBER 1986 Pages 769-930.

• Dmson satisf actory, The nsks to the general public from exposure to ra- of Pubhcaton Servces (Post 870413) June 1987. 170pp ,

deoactive effluents from any attemative have been quantitatively 8707090378 41633 182. o eshmated and are very small fracbons of the estimated normal See NUREG4750.V24.N01 abstract. 4 2

                             - - - . - .         . -. ,--- ,--            - . -       ,-    , - . . , , , - - - , . , -          w---.- ...-,..-y  ,

6 Main Citations and Abstracts NUREG-0750 V25101: INDEXES TO NUCLEAR REGULATORY Safety Evaluaton Report and Supplement No.1. Th4s Supple-COMMISSION ISSUANCES. January. March 1987.

• Dnnsson of ment No 3 also addresses and resolves some of the outstand-Pubhcaton Serwces (Post 870413). September 1987. 41pp. ing issues remanng after issuance of the SER and Supple-8710290301. 43217:257. ments 1 and 2.

NUREG-0781 SO4: SAFETY EVALUATION REPORT RELATED NUREG-0750 V25 N01: NUCLEAR REGULATORY COMMISSION TO THE OPERATION OF SOUTH TEXAS PROJECT,0 NITS 1 ISSUANCES FOR JANUARY 1987.Pages 162.

• Dmson of AND 2. Docket Nos. 50-498 And 50-499. (Houston Lighting And Publication Sennces (Post 870413). June 1987. 71pp. Power Company)
• Dmson of Peactor Projects til,lV V & Spe.

8707210720. 41833:198. cial Projects (Post 870411). July 1987.162pp. 8708240094. See NUREG-0750,V24 N01 abstract. 42323 002. NUREG-0750 V25 N02: NUCLEAR REGULATORY COMMISSION The Safety Evalutton Report issued in April 1986 provided ISSUANCES FOR FEBRUARY 1987.Pages 63128.

• Dmson of the results of the NRC staffs review of the Houston Lighting Pubhcation Senoces (Post 870413). July 1987. 74pp. and Power Company's appicaton for Icenses to operate the 8708060402. 42072-330. South Texas Project The facihty consists of two pressunzed See NUREG-0750,V24,N01 abstract water reactors located in Matagorda County, Texas. Supple-ment Ne 1, issued in September 1986 updated the informaton NUREG-0750 V25 NO3: NUCLEAR REGULATORY COMMISSION contained in the Safety Evaluaton Repert and addressed the ISSUANCES FOR MARCH 1987.Pages 129 266.
• Dmson of ACRS Report issued on June 10, 1986. Supplement No. 2, Pubhcaton Sennces (Post 870413). August 1987. 148pp. issued in January 1987 addressed and resolved some of the 8709110219.42626 269. outstanding issues remanng after issuance of the Safety Eva!-

See NUREG 0750,V24.N01 abstract uaton Report and Supplement No.1. Supplement No. 3, rssued NUREG-0750 V25 N04: NUCLEAR REGULATORY COVMISSION in May 1987 addressed and resolved some of the outstanding ISSUANCES FOR APRll 1987.Pages 267-416.

• Dmsaon of 'ssues remanng after issuance of the Safety Evaluaton Report Publicaton Services (Post 870413). September 1987. 160pp. and Supplement Nos.1 and 2. Supplement No. 4 also address-8710080359. 42990 081. es and resolves some of the outstanding rssues remanng after See NUREG-0750,V24,N01 abstract issuance c) the Safety Eva!uaton Report and Supplement Nos.

1, 2, and 3. NUREG4762 RI DRF FC: STANDARD FORMAT AND CONTENT FOR EMERGENCY PLANS FOR FUEL CYCLE AND MATERI. NUREG-0800 06.5.2 R2: STANDARD REVIEW PLAN FOR THE ALS FACILITIES Draft Report For Comment.

• Dmson of Indus. REVIEW OF SAFETY ANALYSIS REPORTS FOR NUCLEAR tnal & Medical Nuclear Safety (Post 870729). November 1987. POWER PLANTS LWR Ed, ton Proposed Revison 2 To Secton 35pp. 8711250119. 43450:155. 6 5 2, "Containment Spray As A Fisson Product Cleanup This report is issued as guidance to those fuel-cycle and System " For Comment.
• Office of Nuclear Reactor Regulaton, major matenals licensees who are reovired by the NRC to pre. Director (Post 870411). Apnl 1987. 80pp. 8704270036.

pare and subm t an emergency plan. This Standard Format has 40682.016. been prepared to help ensure uniformity and completeness en Proposed revison 2 to SRP Secton 6.5 2 would incorporate the preparation of those plans. changes in the reovirements for containment spray chemical additive systems, and euphertty states computatonal models NUREG-0781 S02: SAFETY EVALUATION REPORT RELATED whch had only appeared in references in prevous revisons. TO THE OPERATION OF SOUTH TEXAS PROJECT, UNITS 1 The requaement for immediate ntiaton of caustic add 2 ton to AND 2. Docket Nos. 50-498 And 50-499. (Houston Lighting And the spray would be deleted, and the mamum pH to be Power Company)

• Dmson of Pressunzed Water Reactor Li* achieved would be reduced from 8 5 to 7. If adopted, this revw censing . A (851125-870411). January 1987. 76pp. pon would be required to be used for future plants, and would 8702190398. 3 % 90 058. be optional for present hcensees The proposed revision is ac.

The Safety Evaluation Report issued in Apnl 1986 provided companied by a regulatory analysis and two supporting techrw-the results of the NRC staff's review of the Houston Lightn9 cal documents. and Power Company's apphcaton for hcenses to operate the South Texas Protect The facihty consists of two pressun2ed NUREG-0800 06.5.5 R0- STANDARD REVIEW PLAN FOR THE water nuclear reactors located in Matagorda County, Texas. REVIEW OF SAFETY ANALYSIS REPORTS FOR NUCLEAR Supplement No.1, issued in September 1986 updated the infor. POWER PLANTS LWR Editon Proposed Revison 0 To New maton contaned in the Safety Evaluation Report and ad- SRP Secton 6.5 5. "Pressure Suppression Pools As Fission dressed the ACRS Report issued on June 10, 1986. Supple. Product Clean-Up Systems " For Comment.

• Office of Nuckar ment No. 2 addresses and resoNes some of the outstanding Reactor Regulaton, Director (Post 870411). Apol 1987. Sipp.

issues remanng after issuance of the Safety Evaluation Report 8704280166. 40716.350. and Supplement No.1. Proposed new SRP Secton 6.5 5 would provide acceptance

                                                                 #"   " * " " *** #           **       "**d * ******"9       '

NUREG 0781 S03: SAFETY EVALUATION REPORT RELATED f pressure suppresson p is as fisson pr duct cleanup sys-TO THE OPERATION OF SOUTH TEXAS PROJECT, UNITS 1 AND 2 Docket Nos. 50-498 And 50-499. (Houston Lightng And 8' * *~^** Power Company)

• Dmson of Reactor Profects - Ill.IV,V & Spe-

                                                                 ' ###            W**         ****9"*            **        ***"

product decontaminaton factors are ksted for use in instances cial Protects (Post 870411). May 1987.171pp. 8706240260. in whch no detarted calculatons of pool scrubbing have been T ety Evaluaton Report issued in Apol 1986 provided is accompaw by a regua-

                                                                      ""*          **                  8' the results of the NRC staff's review of the Houston Lightng and Power Company's app 4caton for hcenses to operate the     NUREG-0825         S01:     INTEGRATED        PLANT      SAFETY South Texas Protect. The faaty consists of two pressunzed       ASSESSMENT. SYSTEMATIC                            EVALUATION    ;

wat,.c nuclear reactors locatea in Matagorda County, Texas PROGRAM, YANKEE NUCLEAR POWER STATION Docket No. ' Supplement No.1 issued in September 1986 updated the infor- 50 029 (Yankee Atome Electnc Company)

• Dmson of Reae. 1 maton contaned an the Safety Evaluaton Report and ad. tor Projects 1/11 (Post 870411). October 1987. 34 pp. J dressed the ACRS Report issued on June 10, 1988. Supple- 8710220292.43130.143 -

ment No. 2 issued in January 1987 addressed and resolved The U S Nuclear Regulatory Commssion (NRC) has pre. j some of the outstanding rssues remanng after issuance of the pared Supplement I to the f nal Integrated Plant Safety Assess. l

Mein Citations and Abstracts 7 ment Report (IPSAR) (NUREG 0825), under the scope of the Design Approval for the Combust.on Engineering Standard Systemate Evaluation Program (SEP), for Yankee Atomic Elec- Safety Analysis Report (CESSAR) (Docket No. STN 50-470) has tre Company's Yankee Nuclear Power Staten located in Rowe, been prepared by the Office of Nuclear Reactor Regulaton of Massachusetts. The SEP was initiated by the NRC to review the the Nuclear Regulatory Commissen. The purpose of tNs sup-desyn of older operating nuclear power plants to reconfirm and piement is to update the Safety Eva uaten by providing (1) the document their safety. This report documents the review com- evaluat>on of ad6 tonal informaton subtntted by the applicant pleted under the SEP for those issues that requaed refined en- since Supplement No. 2 to the Safety Evaluaton Report was gineenng evaluations or the continuaton of ongoing evaluatons issued and (2) the evaluaton of the matters that staff had under after the Final IPSAR for the Yankee plant was issued. The review when Supplement No. 2 to the Safety Evaluation Report review has provided for (1) an assessment of the significance of was issued. 6fferences between current techrucal positons on selected safety issues and those that existed when Yankee was 16 NUREG-0453 SO8: SAFETY EVALUATION REPORT RELATED censed, (2) a bases for deci6ng how these differences should TO THE OPERATION OF CLINTON POWER STATION, UNIT be resolved in an integrated plant review, and (3) a documented 1. Docket No. 50-461.(Ilknois Power Company,et a0

• Division of evaluaton of plant safety. Boihng Water Reactor (BWR) Licensing (851125-870411).

March 1987, 47pp. 8704090033. 40466:158. NUREG-0837 V06 N03: NRC TLD DIRECT RADIATION MONI- Supplement No. 8 to the Safety Evaluation Report on the ap-TORING NETWORK. Progress Report, July September 1986 phcaten filed by lihnois Power Company, Soyland Power Coop-JANG.J.; RABATIN.K.; COHEN.L Regon 1, Ofc of the Director. erative, Inc., and Western lihnois Power Cooperative, Inc., as February 1987. 224pp. 8703120254. 39985:111. apphcants and owners, for a keense to operate the Chnton This report provides the status and results of the NRC Ther- Power Station, Unit No.1, has been prepared by the Offee of moluminescent Dosimeter (TLD) Drect Ra6ation Monitonng Nuclear Reactor Regulaten of the U.S. Nuclear Regulatory Network. It presents the radiaton levels measured in the venty Comtnssion. The facihty is located in Harp Township DeWitt of NRC hcensed facihty sites throughout the country for the thed County, liknois. TNs supplement reports the status of items that quarter of 1986. have been resolved by the staff since Supplement No. 7 was NUREG-0837 V06 N04: NRC TLD DIRECT RADIATION MONI. issued. TORING NETWORK Progress Report. October December 1986. NUREG-0857 S11: SAFETY EVALUATION REPORT RELATED JANG.J.; COHEN L Region 1. Ofc of the Drector. Apnl 1987. TO THE OPERATION OF PALO VERDE NUCLEAR GENERAT. ING STATION, UNITS 1,2 AND 3. Docket Nos. 50 528,50-529 Thsre es t us and results of the NRC Ther- And 50-530.(Anzona Pubic Service Company et a9

• Division of moluminescent Dosimeter (TLD) Drect Radaten Monitonng Network. It presents the radiation levels measured in the venty essunzed Water Reacw WensN 8 (85H258%).

a 9 8 8 NRC heensed ihty Stes throughout the country for the ae au tion Report for the apphcation filed by Anzona Pubic Sennce Company, et al, for NUREG-0837 V07 N01: NRC TLD DIRECT RADIATION MONI- Iconses to operate the Palo Vorde Nuclear Generating Staton, TORING NETWORK. Progress Report, January. March 1987. Units 1,2 and 3 (Docket Nos. STN 50-528/529/530) located in JANG.J; MCNAMANA N.; COHEN L Regon 1, Ofc of the Di- Marcopa County, Anzona, has been prepared by the Office of rector. July 1987. 226pp. 8708100398. 42095:325. Nuclear Reactor Regulation of the U.S, Nuclear Regulatory Th s report provides the status and results of the NRC Ther. Commission. The purpose of tNs supplement is to update the moluminescent Dosimeter (TLD) Drect Ra6aton Monctonng Safety Evaluaton Report by providing an evaluaton of (1) add-Network it presents the ra6aton levels measured in the vienty tional information submitted by the apphcant since Supplement of NRC heensed facility sates throughout the country for the fast No.10 was issued and (2) Other matters requring statt review quarter of 1987. Since Supplement No.10 was issued, specifcally those $ sues that requred resoluton before Unit 3 low power hcens4ng. NUREG-0437 V07 N02: NRC TLD DIRECT RADIATION MONI. TORING NETWORK Progress Report. Apni-June 1987. NUREG-0857 S12: SAFETY EVALUATION REPORT RELATED JANG,J.; MCNAMARA,N.; COHEN,L Regon 1. Ofc of the D'- TO THE OPERATION OF PALO VERDE NUCLEAR GENERAT. rector. October 1987. 226pp 8710260458. 43176.145. ING STATION, UNITS 1,2 AND 3 Docket Nos 50-528,50-529 TNs report provides the status and results of the NRC Ther- And 50-530.(Anzona Pubic Servce Company,et aQ

• Drvision of moluminescent (TLD) Drect Ra6aton Monitonng Network it Reactor Protects - lit.IV,V & Special Protects (Post 870411). No-presents the ra$aton levels measured in the vicnty of NRC li- vember 1987, 98pp. 8712150439. 43723:320.

censed facihty stes throughout the country for the second quar. Supplement No.12 to the Safety Evaluation Repor1 for the ter of 1987. apphcaton fded by Ardona Pubbc Service Company, et al, for NUREG-0437 V07 NO3: NRC TLD DMECT RADIATION MONI. hcenses to operate the Palo Verde Nuclear Generating Stations, TORING NETWORK. Progress Report, July September 1987. Units 1,2, and 3 ( Docket Nos. STN 50 528/529/530), located STRUCKMEYER.R.; MCNAMARA,N.; COHEN.L Regon 1. Ofc in Mancopa County, Anzona. has been prepared by the Office of the Drector. December 1987. 229pp. 8801110268 of Nuclear Reactor Regulaton of the Nuclear Regulatory Com-43977.343. mission. The purpose of tNs supplement is to update the Safety This report govides the status and results of the NRC Ther. Evaluaton Report by providng an evaluaton of (1) ad6 tonal in-r9oluminescent Dossmetry (TLD) Drect Radation Morwtonng formaton submitted by the (censee since Supplement No.11 Network. It presents the radation levels measured in the vienty was issued and (2) other matters requinng staff review sarce of NRC kcensed facihty s tes throughout the country for the thed Supplement No.11 was issued, specifica!!y those issues that re-quarter of 1987. Qated resoluton before Unit 3 full power hcensing NUREG 0852 S03: SAFETY EVALUATION REPORT RELATED NUREG-0876 S08: SAFETY EVALUATION REPORT RELATED i TO THE FINAL DESIGN OF THE STANDARD NUCLEAR TO THE OPERATION OF BYRON STATION. UNITS 1 AND STEAM SUPPLY REFERENCE SYSTEM CESSAR System 2. Docket Nos. 50-454 And 50-455. (Commonwealth Edison 80 Docket No. 50 470 (Combustson Engineerrg. incorporated)

• Company)
• Drvison of Pressunzed Water Reactor Licensing -

Dmson of Reactor Protects lit.fV,V & Special Projects (Post A (851125-870411). March 1987. 24pp. 8704010157. 870411) December 1987, 78pp. 8801060284. 43940 294. 40321:134. Supplement No. 3 to the Safety Evaluaton Report for the ap- Supplement No. 8 to the Safety Evaluaton Report related to phcaton filed by Combuston Engineenng. Inc., for a Final Commonwealth Edson Company's apphcaton for teenses to i.y-r"--t--"'~--- - " ^ - - - " -- W*+P-~ T - '- -"Ww - - - ' - ' ' - - -' - -----'w .---------'=T-twy---WP -.--'-'-'T-7--"--'r' 3--'wv^ w w w" -' ' ' ' --r - " -

I 8 Main Citations and Abstracts operate the Byron Staton, Units 1 and 2, located in Rockvale The NRC Regulatory Agenda $ a compilabon of all rufes on Township, Igle County, Ilhnois, has been prepared by the Office which the NRC has proposed or is considenng action and all of Nuclear Reactor Regulabon of the U.S. Nuclear Regulatory peitens for ruiemaking which have been recerved by the Com-Comm!ssion. This supplement provides recent informaton re- mission and are pend.ng disposition by the Commission. The garding resoluton of the hcense conditions identified in the Regulatory Age ida is updated and issued each quarter. The SER. Because of the favorable resolution of the items dis- Agendas for Apnl and October are pubhshed in their entirety in cussed in this report, the staff concludes that Byron Station, the Federal Register while a notice of availabihty is pubhshed in Unit 2 can be operated by the licensee at power levels greater the Federal Register for the January and July /gendas. than 5% without endangering the health and safety of the public. NUREG-0936 V05 N04: NRC REGULATORY AGENDA.Ouarterly Report, October December 1986.

• Drvision of Rules & Records NUREG-0885106: U.S. NUCLEAR REGULATORY COMMISSION (Post 870413). May 1987.160pp. 8706150112. 41300:247.

POLICY AND PLANNING GUIDANCE 1987.

• Commissoners. See NUREG-0936,V05 NO3 abstract.

September 1987. 58pp. 8710010440. 42883.183. The purposes of the Polcy and Planning Guidance document NUREG-0936 V06 N01: NRC REGULATORY AGENDA.Ouarterfy are: to set forth the regulatory approach of the Nuclear Regula- Report. January-March 1987.

• Divison of Rules & Records tory Commisson and provide supporting pnnciples to the ap- (Post 870413). June 1987.139pp. 8706300230. 41491:320.

proach; to state the major pohcies and planrung objectives of See NUREG4936,V05.NO3 abstract. the Commisson; and to provde a common basis for the devel-opment of programs, the estabhshment of pronbes, and the al- NUREG 0936 V06 N02: NRC REGULATORY AGENDA.Ouarterfy locaton of resources. Report.Apni-June 1987.

• Omsson of Rules & Records (Post 870413). July 1987.128pp. 8708260001. 42333:062.

NUREG-0896 S07: SAFETY EVALUATION REPORT RELATED See NUREG-0936,V05,NO3 abstract. TO THE OPERATION OF SEABROOK STATION. UNITS 1 AND 2 Docket Nos. 50-443 And 50-444 (Pubhc Service Company Of NUREG-0936 V06 NO3: NRC REGULATORY AGENDA.Ouarterfy New Hampshire.et al)

• Dmson of Reactor Projects .1/ll (Post Report July. September 1987.
• Dmsson of Rules & Records 870411). October 1987, 76pp. 8711100384. 43341:178. (Post 870413). November 1987. 117pp. 8712150231.

Supplement No. 7 to the Safety Evaluaton Report related to 43724:153. operaton of the Seabrook Staten, Unit 1 addresses items relat- See NUREG-0936,V05,NO3 abstract. ing to the issuance of a 5% low power heense. The report re-lates to the apphcaton filed by the Pubic Service Company of NUREG-0940 V05 N04: ENFORCEMENT ACTIONS SIGNIFICANT New Hampshire for a heense to operate the Seabrook Stabon, ACTIONS RESOLVED Quarterly Progress Report. October-De. Unit I located in Rockingham County, New Hampshire. cember 1986.

• Ofc o' Inspecton & Enforcement, Director 20 870413). February 1987. 579pp. 8703120167.

NUREG-0904 S01: DRAFT SUPPLEMENT TO THE FINAL ENVI. h8 RONMENTAL STATEMENT RELATED TO THE DECOMMIS. SiON NG OF THE RARE EARTHS FACillTY, WEST This compilation summanzes significant enforcement actions CHICAGO,lLUNOIS Docket No. 40-2061.(Kerr-McGee)

• Dm- that have been resolved dunng one quarterly pered (October-sion of Fuel Cycle, Medcal. Academic & Commercial Use December 1986) and includes copies of letters, Notces, and Orders sent by the Nuclear Regulatory Commission to hcensees Safety 870413-870728. June 1987, 492pp. 8707060327. mth respect to these enforcement actons and the hcensee's T s att Supplement to the Final Environmental Statement **# '' " """### " "* # '" ' **'

tion will be mdefy disseminated to managers and employees is issued by the U S. Nuclear Regulatory Commis9on in re- engaged in activities kcensed by the NRC, in the interest of pro-sponse to the Atomc Safety and Lcensing Board's ruhng that rnobng pubhc health and safety as well as common defense the staff must supplement the Final Environmental Statement in and secunty. oroer to evaluate the impact of permanent disposal of the Kerr-McGee Rare Earths Facihty wastes located at West Chicago, ll- NUREG-0940 V06 N01: ENFORCEMENT ACTIONS.SlGNIFICANT hnois. The statement consders the Kerr McGee preferred plan ACTIONS RESOLVED Ouarterly Progress Report. January March and vanous a'tctnatues to the pisn. The acton proposed by the 1987.

• Ofc of Enforcement (Post 870413). June 1987. 337pp.

Commisson is the renewal of the Kerr McGee hcense to anow 8706240320. 41450 266 disposal of wastes on9te and for possesson of the wastes This compilaton sumrnanzes significant enforcement actons under bcense for an indeterminate time The hcense could be that have been resolved dunng one quarterly penod (January . terminated at a later date if certain specif ed requirements were March 1987) and includes copies of letters, Notices, and Orders met sent by the Nuclear Regulatory Commisson to heensees eth NUREG-0933 S06: A PRIORITIZATION OF GENERIC SAFETY respect to these enforcement actons. It is anticipated that the ISSUES. EMRIT.R; VANDERMOLEN.H.; PITTMAN,J.; et al. Di- informaton in this pubhcaton mil be mde!y disseminated to vison of Safety Review & Oversight (851125-870411). March managers and employees engaged in actmties hcensed by the 1987. 314pp. 8704090020. 40467.073 NRC, so that actons can be taken to improve safety by avoid-The report presents the pnonty rankings for genenc safety ing future volatons smilar to those desenbed in this pubica-assues related to nuclear power plants The purpose of these tion. rankings is to ass st in the t mely and efficent anocaton of NRC resources for the resoluton of those safety issues that have a NUREG-0940 V06 M2: ENFORCEMENT ACTIONS SIGNIFICANT sgnificant potental for reducing nsk The safety pronty rankings ACTIONS RESOLVED Ouarterly Progress Report.Apnl-June are HIGH, MEDIUM, LOW, and DROP and have been assigned 1987. Ofc of Enforcement (Pott 870413). August 1987, 399pp. 8709090464 42564 282. on the bavs of nsk significance estimates, the ratio of nsk to costs and other impacts esbmated to result if resolutions of the This compilaton summanzes significant enforcement actions safety issues were implemented, and the consderaton of un- that have been resolved dunng one quartefty penod (Apnl certainties and ot%r quantitatrve or qualitative factors. To the June 1987) and includes copies of letters. Notices, and Orders erient practical, estimates are quant 2tative. sent by the Nuclear Regulatory Commesson to hcensees mth respect to these enforcement actons. It is anbeipated that the NUREG-0936 V05 N03: NRC REGULATORY AGENDA Ouarterty information in this pubhcaton will be mdely disseminated to Report. July September 1986

• Dmson of Rules & Records managers and employees engaged in actmties hcensed by the (Pre 870413) January 1987.160pp. 8702060261. 39527 089. NRC, so that actons can be taken to improve safety by avoid-

Main Citatinns and Abstracts 9 ing future violatons similar to those desenbed in this pubica- garding the application filed by the Commonwealth Edison Com-ton. pany, as appicant and owner, for a license to operate Braid-wood Station, Units 1 and 2 (Docket Nos. 50-456 and 50-457). NUMO-n940 V06 NO3: ENFORCEMENT ACTIONS:SIGNIFICANT The first supplement to NUREG-1002 was issued in September ACTIONS RESOLVED.Ouarterfy Progress ReportJuly Septem- 1986; the second supplement to NUREG 1002 was issued in ber 1987.

• Ofc of Enforcement (Post 870413). December October 1986; the third supplement to NUREG 1002 was issued 1987, 218pp. 8801110274. 43972:308. in May 1987. This fourth supplement to NUREG-1002 reports This compilaton summanzes significant enforcement actons the status of cMain items that remained unresolved at the time that have been resolved dunng one quarterfy perod (July - Sep- Supplement 3 was published. The facility is located in Reed tember 1987) and includes copies of letters, Notees, and Township, Will County, lilinois.

Orders sent by the Nuclear Regulatory Comrnisson to icensees with respect to these enforcement actions. It is antcipated that NUREG-1002 S05: SAFETY EVALUATION REPORT RELATED the informaton in this pubhcaton wdl be widely disseminated to TO THE OPERATION OF BRAIDWOOD STATION,'JNITS 1 managers and employees engaged in activities licensed by the AND 2. Docket Nos. 50-456 And 50-457.(Commonwesith Edison NRC, so that actons can be taken to improve safaty by avoid

• Compny)
• Drmon of Reactor Projects . lil,lV,V & Special ing future violations similar to those desenbed in this pt.olca. Projects (Post 870411). December 1987, 21pp. 8801110217, ton. 43975:207.

NUREG-0975 V05: COMPILATION OF CONTRACT RESEARCH In November 1983, the staff of the Nuclear Regulatory Com-FOR THE MATERIALS BRANCH, OlVISION OF ENGINEERING mission issued its Safety Evaluation Report (NUREG-1002) re-SAFETY. Annual Rept For FY 1986.

• Divison of Engineenng garding the apphcaten Ned by the Commonwea!th Edison Com-Safety (860720 870413). March 1987. 409pp. 8704030183. pany, as apphcant and owner, for a license to operate Braid-40377.267. wood Staten, Uruts 1 and 2 (Docket Nos. 50-456 and 50-457).

This report presents summanes of the research work per. The first supplement to NUREG-1002 was issued in September formed dunng Fiscal Year 1986 by laboratones and organiza. 1986; the second supplement was issued in October 1986; the tons under contracts admitustered by the NRC's Matenals third supplement was issued in May 1987; the fourth supple. Branch, Office of Nuclear Regulatory Research. Each contractor ment was issued in July 1987. This fifth supp;ement to NUREG-has wntien a more complete and detaded annual report of their 1002 is in support of the low. pawer license for Unit 2 and pro-work which can be obtained by wnting to NRC; however, we be- vides the status of certain items that remained unresolved at beve it is useful to have a summary of each contractor's efforts the time Supplement 4 was pubhshed. The facdity is located in for the year combined into one volume. Reed Townsh p, Wdi County, Ilknois. NUREG-0980 R03: NUCLEAR REGULATORY LEGISLATION. NL; REG-1021 R04: OPERATOR LICENSING EXAMINER STAND-HOSPODOR,S. Offce of the General Counsel. Aprd 1987. ARDS.

• Operator Licensing Branch. May 1987. 200pp.

115pp. 8705290061. 41116.266. 8706030301, 41165:001. NUREG-0980 is a compdaton of nuclear regulatory legislaton The Operator Licensing Examiners Standards provide pokcy and other relevant matenal through the 99th Congress, 2nd and guidance to NRC examiners and establishes the proce-Sesson. Ths compdaton has been prepared for use as a re* dures and practces for examarung and hcensing of apphcants source document, which the NRC intends to update at the end for NRC operator Icenses pursuant to Part 55 of Title 10 of the of every Congress. Contents of NUREG 0980 include: The Code of Federal Regulations (10 CFR 55). It is intended to Atome Energy Act of 1954, as amended, Energy Reorgarwza- assist NRC examiners and facdity hcensees to understand the ten Act of 1974, as amended, Uranium Mal Taihngs Radiaton examination process better and to provde for equitable and Control Act of 1978; Low Level Radcactive Waste Polcy Act; consistent administraton of examinatons to alt appicants by Nuclear Waste Pohcy Act of 1982; and NRC Authonzaton and NRC examiners. This standard is not a substitute for the Opera. Appropnatons Acts. Other matenals included are statutes and for Licensing Regulations. As appropnate, this standard will be treaties on export hcensing, nuclear non-prohferation, and envi- penodcany revised to accommodate comments and reflect new ronmental protecton. informaton or expenence. NUREG 1002 S03: SAFETY EVALUATION REPORT RELATED NUREG 1030: SEISMIC QUAllFICATION OF EQUIPMENT IN OP-TO THE OPERATION OF BRAIDWOOD STATION. UNITS 1 ERATING NUCLEAR POWER PLANTS. Unresolved Safety issue . AND 2 Docket Nos. 50-456 And 50-457.(Commonwealth Edison A 46. CHANG,T.Y. Divison of Safety Review & Oversight Company) Division of Reactor Projects - lit,lV,Y & Special (851125-870411). February 1987. 183pp. 8703130028. Protects (Post 870411). May 1987, 35pp. D 6150208. 40007d 96 4 N212' The margin of safety provded in existing nuclear power plant in November 1983, the staff of the Nuclear Regulatcsv Com- equipment to resist seismically induced loads and perform their masson issued its safety Evaluaton Report (NUREG 1 A 2) re- intended safety functons may vary corsderably, because of garding the appication hied by the Commonwearth Edison Com' signifcant changes in design cnteria and methods for the seis-pany, as ap"+ cant and owner, for a hcense to operate Brad- mic quakficaton of equipment over the years. Therefore, the wood Statori. Units 1 and 2 (Docket No. 50-456 and 50 457). seisme quahfcation of equiptr snt in operating plants must be The hrst supplement to NUREG 1002 was issued in September reassessed to determine whether requalificaton is necessary. 1986; the second supplement to NUREG 1002 was issued m The oblective of USI A-46 is to estabksh an expbcit set of October 1986. This third supplement to NUREG 1002 reports gudehnes and acceptance entena to judge the seisme adequa-the status of certain items that remained unresolved at the time cy of equipment at all operating plants m heu of requenng quah-Supplement 2 was pubbshed. The facility is located in Reed fcaton to the current entena that t r apphed to new plants Township, Wdi County, uhnois. This report summanzes the work so o phsned on USl A-46 by NUREG 1002 SO4: SAFETY EVALUATION REPORT RELATED the Nuclear Regulatory Commisson Waff and its contractors. In TO THE OPERATION OF BRAIDWOOD STATION. UNITS 1 additon, the collecton and review of seismic expstience data AND 2 Docket Nos. 50-456 And 50-457.(Commonwealth Edison and existmg setsme test data by the SOUG and EPRI respec-Company)

• Division of Reactor Projects . Ill,IV,V & Special trvely, and the review and recommendatons of the SSRAP are Protects (Post 870411). July 1987. 22pp. 8708040187. presented The pnncipal technical finding o' USl A-46 is that 42039 049. seismec expenence data, supplemented by exishng seismic test in November 1983, the staff of the Nuclear Regulatory Com- data, apphed o accordance with the guidehnes developed. pro-misson issued its Safety Evaluaton Report (NUREG 1002) re- vdes the most reasonable a:ternative to current quakficaton en-

         .                     _                   _     _         _      _                     .m     __                       _ _

6 10 Miln Citati:ns End Abstr: cts tena to venfy the seismic adequacy of equipment in operating TNs report contains the fiscal year budget justafcations to nuclear plants. Exphcit seismic quakhcaton should be required Congress. The budget provides estimates for salanes and ex-onty sf seismic expenence data or existing test data on similar penses for fiscal years 1988 1989. components cannot be shown to apply. NUREG 1100 V03 ADD: BUDGET ESTIMATES. Fiscal Years NUREG-1047 S06: SAFETY EVALUATION REPORT RELATED 1988 1989.

• Divison of Budget & Analysis (Post 870413). May TO THE OPERATION OF NINE MILE POINT NUCLEAR 1987. 44pp. 8706300181. 41491:060.

STAT:ON. UNIT 2. Docket No. 50-410.(Niagara Mohawk Power This report contains the fiscal year budget justificatons to Corporaton,et al)

• Orvision of Reactor Projects - 1/11 (Post Congress. The budget provides estimates for salaries and ex.

870411). July 1987. 65pp. 8707230283. 41879:171. peses for fiscal years 1988 1989. This addendum is required Thes report supplements the Safety Evaluaton Report due to the NRC reorgancaton of Apol 12,1987. (NUREG 1047. February 1985) for the apphcaten fded by Niag-ara Mohawk Power Corporation, as appleant and co-owner, for NUREG 1101 V02: ONSITE DISPOSAL OF RADIOACTIVE WASTE. Methodology For The Radological Assessment Of Dis-the hcense to operate Nine Mile Point Ntclear Station, Unit 2 posal By Subsurface Bunal. NEUDER S M.; KENNEDY,W.E. Di-(Docket No. 50-410). It has been preparet by the Office of Nu-vision of Waste Management (Pre 870413). February 1987. clear Reactor Regulaton of the U.S. Nuc. ear Regulatory Com' 50pp. 8704010173. 40340:309. misson. The facihty is located near Oswego, New York. This Volume 1 of tNs NUREG provides guidance for academic, report supports the issuance of the full-power heense for Noe medical, and edustrial heensees seeking authorgaton to dis-Mile Point Nuclear Staten, Unit No. 2. pose of small quantities of radcactive matenal by onsite subsur-face disposal. Licensee requests for such authorizatons are NUREG 1057 SO4: SAFETY EVALUATION REPORT RELATED made pursuant to Section 20.302 of 10 CFR Part 20 "Standaids TO THE OPERATION OF BEAVER VALLEY POWER for Protecton Against Radiation." TNs volume (Volume 2) de-STATION. UNIT 2. Docket No. 50-412 (Duquesne Ught Company et al)

• Dmson of Pressurced Water Reactor Licens- scnbes the entena ar'd technical methodology used by NRC ing A (851125-870411) March 1987. 92pp. 8704010184. staff to evaluate requests by bcensees for approval of ons:te 40324:162. disposal by bunal in sod. The techrucal methodology includes Supplement No. 4 to the Safety Evaluaton Report for the ap- the ONSITE/MAXII code for calculating ra$ological exposure picaton filed by Duquesne Ught Company, et al., for hcense to from varous pathways, the MOMOD84 code, and analytcal methods for calculating contaminant transport and concentra.

            - operate the Beaver Valley Power Staten Unit 2 (Docket No.

. 50-412), located in Beaver County, Pennsytvania, has been pre. ton of radionuchdes in flowmg groundwater. Radiological expo. pared by the Offce of Nuclear Reactor Regulaton of the Nucle' sure analyses eclude the following pathways: (1) exposure to } direct gamma from any surface contamsiaton or buned waste, '

+            at Regulatory Commissort The purpose of tNs supplement is to update the Safety Evaluation of (1) addit >cnal informaton sub-   (2) dnnking water from a well contaminated by mgraton of ra-       [

donuchdes, (3) ingesting agrcultural products denved from radi-mtted by the applcants since Supplement No. 3 was issued-and (2) matters that the staff had under review when Supple- onuchde- contaminated soil, and (4) inhaling radonuchdes resu-spended at the bunal s4te. Ucensee-proposed disposal actmtes ment No. 3 was issued' are evaluated in terms of radological npact on pubhc heatth NUREG 1057 SOS: SAFETY EVALUATION AEPORT RELATED and sa% and N enwonment W eshmaW come 6 TO THE OPERATION OF BEAVER VALLEY POWER fectue dose equwatent resunog korn N tecMeal evabaton STATION UNIT 2 Docket No, 50-412.(Duquesne Ught mil usually be the determining factor in the authonzaton of the  : Company.et al)

• Dmson of Reactor Protects - l/ll (Post propsed ds@ sal 870411). May 1987,176pp. 8706120079. 41186:104. NUREG 1122 S01: KNOWLEDGES AND ABILITIES CATALOG Supplement No. 5 to the Safety Evaluaton Report for the ap- FOR NUCLEAR POWER PLANT OPERATORS Pressunzed phcatson filed by Duquesne Ught Company, et al, for hCense to Water Reactors.
• Office of Nuclear Reactor Regulaton, Direc.

operate the Beaver Valley Power Staten, Unit 2 (Docket No. tor (Post 870411) Apol 1987. 240pp. 8705290304. 41116.001. ' 50-412), located in Beaver County, Pennsylvania, has been pre- TNs document catalogs roughly 5300 knowledges and abih-pared by the Offce of Nuclear Reactor Regulaton of the Nucle- t es of reactor operators and senior reactor operators. It results at Regulatory Commission. The purpose of tNs supplement is to from a reanalysis of a much targer job-task analysis data base update the Safety Evaluaton of (1) additonal informaton sub- compiled by the institute of Nuclear Power Operatons (INPO). mtted by the apphcants sece Supplement No. 4 was issued, Knowledges and abilities are cataloged for 45 major power ar,d (2) matters that the staff had under revew when Supple- plant systems and 38 emergency evolutions, grouped according ment No. 4 was issued. to 11 fundamental safety functons (e g, reactmty control and reactor coolant system eventory control). Supplemental pages - NUREG-1057 S06: SAFETY EVALUATION REPORT RELATED have been added to conform to NUREG 1123, "Knowledges TO THE OPERATION OF BEAVER VALLEY POWER and Abshties Catalog for Nuclear Power Plant Operatois: Boehng STATION. UNIT 2 Docket No. 50-412 (Duquesne Light Water Reactors," September,1986. A structured samphng pro-Company.et a!)

• Dmson of Reactor Projects - t/Il (Post cedure for both catalogs is under development by the Nuclear 870411). August 1987. 83pp. 8709090412. 42566 356 Regulatory Commission (NRC) and will be pubhshed as a com.

Supplement No. 6 to 'he Safety Evaluaton Report for the ap- panon document, "Examners' Handbook for Developing Oper-phcation ided by Duquesne Light Company, et al., for hcense to ator Ucensing Examnations" (NUREG 1121). With appropnate operate the Beaver Valley Power Staten, Urst 2 (Docket No. samphng from these catalogs, operator heensing examinatons 50-412), located in Beaver Ccunty, Pennsylvarva, has been pre- haveg content vahdity can be developed. The examinatons de-pared by the Offee of Nuclear Reactor Regulaton of the Nucle- veloped by using the catalogs and handbook mil cover those , at Regulatory Commisson. The purpose of tNs supplement is to ' l topics listed under Title 10,

• Code of Federal Regulatons," Part update the Safety Evaluaton of (1) additional informaton sub- 55.

mitted by the kcensees sece Supplement No. 5 was issued, I i and (2) matters that the staff had under review when Supple. NUREG 1125 V08: A COMPILATION OF REPORTS OF THE AD-ment No. 5 was issued. VISORY COMMITTEE ON REACTOR SAFEGUARDS,1986.

• ACRS Advisory Commttee on Reactor Safeguards. Apna 1987. r' NUREG 1100 V03: BUDGET ESTIMATES Fiscal Years 1988- 217pp. 8705200003. 40987.013.

4 1989.

• Dmson of Budget & Anatysis (Pre 870413). January TNs compilaton conf 9ns 58 ACRS reports submitted to the 1987, 72pp. 8702060081 39526.087. Commssion or to the Executive Director for Operations dunng i

MCin CitCtisns end Abstracts 11 the calendar year 1986. All reports have been made available to and morutonng, or of evaluating residual life of equipment, sys-the pubhc through the NRC Public Document Room and the tems, and mapr components, which will ensure timely detecten U S. Lrbrary of Congress. The reports are divded into two of wgnificant ag'ng effects pnot to loss of safety functon, and groups. Part 1: ACRS Reports on Project Reviews, and Part 2: (3) to evaluate the effectiveness of storage, maintenance, ACRS Reports on Genenc Subjects. Part 1 contains ACRS re- repair, and replacement practices in mitigating the rate and ports alphabetized by project name and within project name by extent of degradalcn Caused by aging and service wear. chronologeal order. Part 2 categonzes the reports by the most NUREG 1145 V03: U S. NUCLEAR REGULATORY COMMlSSION appropnate genene subject area and within sub;ect area by 1986 ANNUAL REPORT.

• Office of Administraton & Re-chronological oroer. Sovicm Management, Director (Post 870413). June 1987.

NUREG 1137 S05: SAFETY EVALUATION REPORT RELATED 258pp. 8707020359. 41567.001. TO THE OPERATION OF VOGTLE ELECTRIC GENERATING Th s report covers the major activities, events, decisions and PLANT, UNITS 1 AND 2 Docket Nos 50-424 And 50-425 (Geor- plannmg that took place 62nng fiscal year 1986 w th;n the NF,C gia Power Company.et al)

• Drasion of Pressunzed Water Reac- or involving the NRC.

tor Licensing A (851125-870411). January 1987. 121pp. 8702060100. 39526 288. NUREG 1147 Rtm SEISMIC SAFETY RESEARCH PROGRAM in June 1985, the staff of the Nuclear Regulat:ry Commisson PLAN.

• Dmson of Encineenng (Post 870413). May 1987.

 !ssued its Safety Eva'uaton Report (NUREG 1137) regarding               242pp. 8700240r;t. 41436.334.

the apphcaton of Georgia Power Company, Murecipal Electnc This document presents a plan for seismic research fa be Authonty of Georg:a, Ogetthorpe Power CorporaMn, and the perforrned by the Structural and Seismic Engineenng Branch in City of Dafton, Georgia. for licenses to operate the Vogt!e Elec- the Offic6 of Nuclear fiegulatory Research. The plan desenbes tre Generating Plant, Units 1 and 2 (Dockat Nos SG-424 and the regulatory needs and related issaarch necessary to address 50-425) Supplement 1 to NUREG 1137 was 6 sued by the staff the following issues uncertain'es e seism >c hazard, aarth-in October 1985, Supplement 2 was issued in May 1986. Suru avakes larger than the desge basis, seismtc vulnerabAtas, piement 3 was issued in August 1986, and Supp'ement 4 was shifts in building 4equecy, pip;ng design. and the adequacy of issued in December 1986 The facility is loca%d in Eurii s current critena and methods + ado' ten to presenting crrent County, Georg>a. approomately 26 rndes south.soutneast of Au- and propsed research w thin the NRC, the plan discusses re-Search sponsored by other domesbc and foreign sources. gusta. Georg'a. and on the Savannah Ruet TNs fift% supple-ment to NUREG 1137 provdes recent <dormaton regarding resoluton of some of the open and confirmatory items that re- g . ma:ned unresoNed at the tene the Safety Evaluaton Report MURPHY,J A.; CUNNINGHAM.M A ; et at Office of Nuclea"r was issued Regulatory Research, Director (Post 860720). February 1987. NUREG 1137 S06: SAFETY EVALUATION REPORT RELATED 364pp. 8703100040 39934 011. TO THE OPERATION OF VOGTLE ELECTRIC GENERATING This document discusses the nsks of severe acc dents in a PLANT. UNITS 1 AND 2 Docket Nos 50-424 And 50-425 (Geor- set of commercia; nuclear power plants. This risk is character-g+a Power Company.et af)

• Drvison of Pressunzed Water ReaC- tzed by the types and frequencies of accidents leadeng to tor Licensing A (851125-870411) March 1997. 126pp. severe core damage, the performance of containment struc-8704010183. 40341.294. tures under severe accident loadings. poss,ble rad oactive re-In June 1985, the sta'1 of the Nuclear Regulatory Commisson leases ento the environment if tne conta<nment were to fail, and issued its Sa'ety EvaluaSon Report (NUREG 1137) regarding the offsite consequences of such releases. Volume 1 of th s the apphcaton of Georg!a Power Company, Munic! pal Electnc document summanzes the pnncipal results of the r< s analyses.

Authonty of Georg a. Ogtethr>e Power Corporaton, and the and displays these results in the Context of specmc regulatory City of Da' ton. Georg a. for licenses to operate the Vogtie Elec- issues (e g , safety goats) tre Generating Plant. Units 1 and 2 (Docket Nos 50-424 and 50-425) Supptement 1 to NUREG 1137 was issued by the staff NUREG 1150 DRF V2 FC: REACTOR RISK REFERENCE DOCUMENT Appereces A-I Draft For Comment, in October 1985, Supplement 2 was issued in May 1986, Sup. DENNING.R S ; LEONARD.M ; WREATHALL.J. Office of Nucle-piement 3 was essued in August 1986 Suppiement 4 was issued in December 1986. and Supplement 5 was issued in Jan. ar Regulatory Research, Director (Post 860720) February 1987. 320pp 8703170207,40053 342 uary 1987. The f acihty is located in Burke County, Georg:a ap. proomately 26 miles south-southeast of Augusta, Georgia. and This document discusses the nsks of severe acedents in a set of commercial nuclear power plants This r sk is character-on the Savannah Rwer TNs sath supplement to NUREG 1137 provdes recent informaton regard.ng resoluton of some of the ized by the types and frequencies of accidents leading to cpen and confirmatory items that remained unresoNed at the severe core damage the performance of conta.nment struc-tures under severe acc dent load.ngs, possibte radioactrve re-time the Safety Evaluation Report was issued NUREG 1144 RO1: NUCLEAR PLANT AGING RESEARCH the offste consequences of such releases Volume 2 of tNs (NPAR) PROGRAM PLAN VOR A.) P. Divison of Eng neenng document provdes a discusson of the methods used to calcu-(Post 870413) September 1987. 135pp 8710090155 late nsk. and summanzes the pnncipal results of the ana'yses of 43010 082- the stud >ed plants The nuclear plant aging research desenbed in tNS plan is in-tended to resoNo issues re:ated to the ag ng and service wear NUREG 1150 DRF V3 FC: REACTOR RISK REFERENCE cf equipment and systems and mapr components at commer- DOCUMENT Appendices J-O Draft For Comment.

• Off<e of cial rea: tor f acat>es and the r poss:ble impact on plant safety Nuclear Regulatory Research, Director (Post 860720). February Emphasis has been placed on dentficaton and . iaractenza- 1987. 517pp 8703180080. 40072142.

ten of the mechanisms of matenal ard component degradaten Th s document d:Scusses the nsks of severe accdents in a during service and evatuaton of raethods of inspecten, surveil- set of commercial nuclear poner plants This risk is character-larie, cond, ten rnonitonog and mantenance as means of miti- ized by the types and frequencies of accdents leaing to gating such eMects Specif.cahy, the goa's of the program are severe core damage, the peformance of conta;nment struc-as fonows (1) to denth and charactenze ag ng and service tures under severe accdent loadings. possue rad oactrve re-wear effects e rf unchecked could cause degradatcn of leases into the env ronment if the conta'nment were to fa0 and equipment. Syst+cs. an1 mapf Components and thereby impair the offs.te consequences of such releases. Volume 3 of this l plant $3Mif , (2) to dent fy rrethods of insfoClon, surveilance. document provdes d,scussens c,f NRC staff anafyses of specif.

12 M;in Citatbns and Abstracts ic technical and regulatory issues, compares present risk results plant specific basis to evatuate all hcensing actons, licensee inn. with those of other studies, and desenbes computer codes used trated p! ant improvements and selected unresolved genenc/ in the nsk analyses safety issues to estabksh implementation schedules for each NUREG 1163: COORDINATION OF SAFETY RESEARCH FOR item in add; ton, procedures will be established to allow for a THE BABCOCK AND WILCOX INTEGRAL SYSTEM TEST puede updabng of the schedules to account for hcensing PROGRAM. YOUNG M W.; SURSOCK,J.P. Division o' Reactor issues that arise in the future. This report documents the review System Safety (860720-870413). March 1987. 233pp. of Haddam Neck Plant, operated by Connecticut Yankee Atomic 8704010410. 40328.068. Power Company, which is one of two plants being reviewed This report desenbes the MIST facihty and all the integral under the pdot program for ISAP. This report indicates how 82 System Test (IST) support protects sponsored by the USNRC 10P'cs selected for review were addressed and presents the and by EPRI. These support projects have been deemed to play staff's recommendatons regarding the corrective actons to re-an essential role in helping resolve issues raised by MIST scal- solve the 82 top *cs and other actons to enhance plant safety. ing compromises. Each support project is desenbed in detail The report is being issued in drait form to obtain comments and application of the expected data to resoluton of issues is from the licensee. nuclear safety experts, and the Advisory discussed The combined effort of MIST and seven other sup. Committee for Reactor Safeguards. Once those comments have port projects will resolve virtually all questions addressed by the been resolved the staff wal present its positons. along w th a IST program. long-term implementaten schedule from the hcensee, in the final version of this report HUREG-1166: RNAL ENVIRONVENTAL STATEMENT FOR DE-COMMISSIONING HUMBOLDT BAY POWER PLANT. UNIT NUREG 1185 V02 DRFT: INTEGRATED SAFETY ASSESSMENT

3. Docket No. 50133 (Pacific Gas And Electnc Company)

• Divi- REPORT. Integrated Safety Assessment Program Haddam Neck son of Reactor Projects Ill.IV,V & Special Protects (Post 870411) April 1987.164pp 8705190499. 40978 319. Plant Docket No 50-213 (Connecticut Yankee Atomec Power Company) ' Division of Reactor Projects ill.lv.V & Special The Final Envirormental Statement contains the assessment projects (Post 870411) July 1987. 715pp 8708260092.

of the environmental impact associated with decommissonan9 42386 128 the Humboldt Bay Power Plant Unit 3 pursua'i to the Natonal See NUREG 1185,V01.DRFT abstract Enwonmental Pohey Act of 1969 (NEPA) and Tit;e 10 of the Code of Federal Regu!atons, Part 51, as amended, of the Nu-NUREG 1194: CONSTRUCTION APPRAISAL TEAM INSPECTION clear Regulatory Commission regulatons The proposed decom- RESULTS ON WELDING AND NONDESTRUCTIVE EXAMINA. missoning would involve safe storage of the facihty for about 30 TION ACTIVITIES WU.P C ; SHAABAN,H.l Div: son of Reactor years. after which the residual radcactivity would be removed inspecton & Safeguards (Post 870411) September 1987.57pp. so that the facihty would be at levels of radioactivity acceptable 8710050558. 42905 227. for release of the facility to unrestr<ted access This report summantes cata and findings of deficiencies and NUREG 1184 DRFT: INTEGRATED SAFETY ASSESSMENT d,screpancies in *elding and nondestructrve examinaten (NDE) REPORT. INTEGRATED SAFETY ASSESSMENT PROGRAM actmt,es ident.f.ed by the U S Nuclear Regulatory Commisson MILLSTONE NUCLEAR POWER STATION. UNIT 1 Docket No_ Constructon Appra! sal Team (CAT) dunng its inspecton of 11 5 04245 (Northeast Nuclear Energy Co) Draft Report

• Office of plants The CAT reviewed selected welds and NDE packages in Nuclear Reactor Regulat>on. Director (Post 870411) Apol 1987. its inspecton cf the foho* ng plant areas piping and pipe sup-524p0 8704270155 40682 334 ports and/or restra nts, mod.f> cation and instauaton of reactor The Integrated Safety Assessment Program OSAP) was initiat. iNernals. Mncal insta9abons and electncal supports, instru-ed in November 1984. by the U S Nuclear Regulatory Commis- mentation tubing and supports. heating ventdaton, and aer con-son to conduct integrated assessments for operating nuclear d, toning (HVAC) systems and supports, fabocaton and erecton power reactors The integrated assessment is conducted on a of structural steel, fabocaton of refuehng canty and spent fuel plant-specific basis to evaruate all hcens<ng actions, hcensee inn pool I.ner. contarnment kner and conta nment penetratons. and tiated plant improvements and selected unresolved genenc/ fee prctecten systems The CAT inspected both structural safety issues to estabhsh impternentaton schedules for each *Ws at preswre-reta,n ng
• elds and reviewed
• cider quahfi-item in ad$ ton, procedures adi be estabbshed to a!Io* for a caten test records and *eid.ng procedJre documents for code penodic updat,ng of the schedules to account for licensing comphance The NDE act#bes that were evaivated included issues that anse in the future This report documen.s the review visual exam <nat on, magnet >c particle esamnahon. bqwd pene-of Md! stone Nuclear Power Stat on. Unit No 1, operated by tram esamenaton. ultrason,c examinaton, and rad.ographic ex-Northeast Nuclear Energy Company. *hich is one of t*o p! ants d *'"8 t*' 0' * * 'd 5 being revrewed under the pdot program for ISAP. This report en-d<ates how 85 topcs se ected for rev.e* *ere addressed and NUREG 1199: ST ANDARD FORVAT AND CONTENT OF A Lt.

presents the staff s recommendabons regard:ng the correctrve CENSE APPUCATiON FOR A LOW LEVEL RADICACTIVE actons to resolve the 85 topics and other a: tons to enhance WASTE DISPOSAL FACiUTY ' Dmson of Waste Management plant safety The report is be,ng issued in dra+t form to obtain (Pre 8 70413) January 1997.1Cepp 6702170341 39668 281. comments from the bcensee. nuclear safety esperts, and the The %nM Fcmat and Ccntert of a License Appkabon Absory Comm.ttee for Reactor Sa'eguards Once those com- br a Mend RN'".e Waste Disposal Facity, NUREG. ments have been resolved, the sta'f wuf present its pos:tions* 11R d scusses me informabon to be pronjed in the Safety a!ong w th a long-term irrplernentaten schedWe from the hcens' Ana$s:s Report and Estat%hes a un; form format for presert.ng ee. in the final verson of this report tre informaton repred to treet the Lcenseg regwrements for land disposa! cf ra j oactwe *aste as reawred by 10 CFR 61 NUREG 1185 V01 DRFT: INTEGRATED SAFETY ASSESSVENT The use of the Staadard Format wJI (1) betp ensure that the REPORT Integrated Safety Assessment Program Haddam Neck Safety Anajs;s Report (SAR) Contams the (formaton required P! ant Docket No 50-213 (Connec t<ut yankee Atom.c Power ty 10 CFR 61 (2) a d the appucant in ensunng that the informa-Company)

• Dvs on of Reactor Progets m IV,V & Special ton is co p,ete (3) he!p per>cns reatng the SAR to locate in-Protects (Post 870411) July 1997 141pp 8708260003 forrrabon. and (4) contr bute to shortening the t me required for 42333 190 the recc
• prca ss The Standard F ormat and Content The Integrated Safety Assessment Program USAP) was in bat. (NUREG tire; ensures that tre informaton reqwred to periorm ed in November 1984. by the U S Nuclear Regdatory Commis- the recen is proode-1 and c a usabie format *hne the Stand-son to conduct irtegrated assessments for operahng nuciear ard Rece* Man N'#EG 1200 def n(s tre technol recca pc*er reactors The in'egrated assessment is conducted on a pron ss These dxa ments praede assu rance that N AC Can 4

l Main Citations and Abstracts 13 review and process a license application within 15 months and NUREG-1210 V05: PILOT PROGRAM.NRC SEVERE REACTOR meet the requirements of Section 9(1) and (2) of P.L 99 240, ACCIDENT INCIDENT RESPONSE TRAINING MANUAL.U.S. the low Level Radcactive Weste Pobey Amendments Act Nuclear Regulatory Commisson Response. SAKENAS.C.A.; , MCKENNA,T.J.; PERKINS.K.; et al. Div of Emergency Prepared- t (LLRWPAA) of 1985. ness & Engineenng Response,tE(850212-870413). February NUREG-1200: STANDARD REVIEW PLAN FOR THE REVIEW OF 1987.105pp. 8703090067. 39921:258. A LICENSE APPLICATION FOR A LOW-LEVEL RADIOACTIVE See NUREG 1210,v01 abstract ' WASTE DISPOSAL FACILITY.

• Dmson of Waste Management (Pre 870413). January 1987, 473pp. 8702170380. 39669.243. NUREG 1211: REGULATORY ANALYSIS FOR RESOLUTION OF The Standard Review Plan (SRP) is prepared for the gud- UNRESOLVED SAFETY ISSUE A-46. SEISMIC OUAllFICATION ance of staff revewers in the Office of Nuclear Material Safety OF EQUIPMENT IN OPERATING PLANTS. CHANG,T.Y.;

and Safeguards in performing safety revews of apphcations to ANDERSON.N R. Dmsson of Safety Review & Oversight 73pp. 8703120330. 4 construct and operate a low 4evel waste disposal facaty. The (851125-870411). February 1987. pnncipal purpose of the SRP is to assure the quahty and uni- 39981:321. forrruty of staff revews and to present a well-defined base from The margin of safety provided in ernsting nuclear power plant which to evaluate proposed changes in the scope and require- equipment to resist seismically induced loads and perform re-ments of reviews. It is also a purpose of the SRP to make infor- quired safety functons may vary consderably, because of sig-  ; maton about regulatory matters wdely availatte and to improve nrficant changes in design critena and methods for the seismic communicaton and understanding of the staff's review process qualification of equ*pment over the years. Therefore, the seismic by anterested members of the pubbc and the nuclear industry. quahficaton of equipment in operating plants must be reas-NUREG-1200 consists of 11 Chaoters containing approximately sessed to determine whether requalifwaton is necessary. The 60 indsydual SRP sectons. Each secton dentifes who per- objective of USl A-46 ts to estabhsh an exphcst set of gudelines forms the review, the matters that are revewed, the basis for and acceptance cntena to judge the seismic adequacy of equip-review, how the review as performed, and the conclusons that ment at all operating plants, in heu of requinng these plants to  ; meet the entena that are apphed to new plants. This report pre. , are sought. sents the regulatory analysis for Unresolved Safety issue (USI) NUREG 1210 V01: PILOT PROGRAM.NRC SEVERE REACTOR A 46. It includes (1) Statement of the Probtem, (2) the Objective I ACCIDENT INCIDENT RESPONSE T RAINING of USl A-46, (3) a Summary of A-46 Tasks. (4) a Proposed im-MANUAL.Overvew And Summary O' Maror Po;nts. piementaten Procedure. (5) a Value Impact Analysis. (6) Imple- , MCKENNA T.J.; MARTIN,J.A.; MILLER C.Wa et al. Div or Emer- mentaton, (7) a Summary of A-46 Risk Analyses and (8) Oper- - gency Preparedness & Engineenng Response.tE(850212- ating Plants To Be Reviewed to USl A 46 Requvements. . 870413). February 1917.111pp. 8703090078. 39931:107. - This is one in a Sr les of volumes that collectrvely prowde for NUREG 1213 R01: PLANS AND SCHEDULES FOR IMPLEMEN-the U.S. Nuclear Regulatory Commission (NRC) emergency re- TATION OF U S. NUCLEAR REGULATORY COMMISSION RE-sponse personnel the necessary background informaton for an SPONS!BILITIES UNDER THE LOW LEVEL RADIOACTIVE WASTE POLICY AMENDMENTS ACT OF 1985 (P.L. 99-2@). j adequate response to severe reactor accdents The volumes in the senes are: Volume 1. "Overview and Summary of Maior DUNKELMAN.M M. Division of Low Level Waste Management  ; Points," Volume 2, "Severe Reactor Overvew " Volume 3 "Re- 8 Decommissoning (Post 870413). August 1987, 100pp. ' sponse of Licensee and State and Local Officials." Volume 4, 8709090253. 42564.182.

                    "Pubbc Protective Actons - Predetermined Crttena and initial                                                                                 The purpose of th s document is to make available to the Actons," and Volume 5. "U S. Nuclear Regulatory Commisson                                                                              States and other interested part es, the plans and schedules for Response." Each volume serves, respectively, as the test for a                                                                         the U.S Nuclear Regulatnry Commisson's (NRC's) implementa-course of instructon in a senes of courses for NRC response                                                                            ton of its responsibilites under the low-Level Radcactrve personnel These materials do not prende gudance or license                                                                            Waste Pohcy Amendments Acf of 1985 (P.L. 99 240) requirements for NRC licensees or state or local response org&                                                                        (LLRWPAA). This document dentites the provisons of the

) I ruations Each volume es accomparked by an appendir of LLRWPAA which affect the programs of the NRC, dentifes sides that can be used to present this materisi The shdes are what the NRC must do to fulfill each of its requaements under the LLRWPAA, and estabbshes schedules for c&rying out these called out in the text. requirements Revison 1 of tNs document includes the accom-NUMEG 1210 V02: PILOT PROGRAM.NRC SEVERE REACTOR phshments and schedule revisons made by NRC sance Juty 1, ACCIDENT INCIDENT RESPONSE TRAIN!NG MANUAL Severe 1986 Reactor Acceent Overvew. MCKENNA.T J., MARTIN.J A; MILLER,C.W; et al. Dev of Energency Preparedness & Engi. NUREG-1214 Ro1: HISTORICAL DATA

SUMMARY

OF THE SYS-neenng Response.lE(850212-870413) February 1997. 132pp TEMATtC ASSESSMENT OF LICENSEE PERFORMANCE. JOHNSON.M R : WAT E RM AN.DX Div of Inspecton 8703090131.39931 218 Aptd 4, 1987. 69pp. See NUREG 1210,V01 abstract crograms.lE (850212 870413) 8704270378 40704.218 NUREG 1210 V03: PILOT PROGRAM NRC SEVERE REACTOR TNs report presents a Nstory of Systemat.c Assessment of INCIDENT RESPONSE TRAINING Licensee Performance (SALP) ratings for nuclear power plant ACCIDENT MANUAL. Response Of Licensee And State And Local Offca!s facAtres in operaton and under constructon. The SALP results SAKENAS,C A; MCKENNA T.J ; M!LLER.C W ; et al Div cf are ksted by NRC region in three sectons the most recent Emergency Preparedness & Engineenng Response.lE(850212- report. operatng facetes, and facetes under constructon The 870413). February 1987 101pp. 8703090090 39931006 histoncal data summary report has been prepared by the NRC See NUREG 1210N01 abstract Offee of inspecton and Enforccment (IE) Informaton con- , ta,ned in trvs report has been updated to enclude those pub-  ; NUMEG 1210 V04: PILOT PROGRAM NRC SEVERE REACTOR I,shed SALP rr> ports recerved before March 19.1987. ACCIDENT INCIDENT RESPONSE TRAINING MANUAL Pubhc Protective Actons - Predetermined Critena And initial Actons NUREG 1214 R02: HISTORICAL DAT A SUMV ARY OF THE SYS- ,

                                                                                                                                                                                                                                          ^

MARTIN.J A.; MCKENNA.T J ; M!LLER.C W ; et al Dv of Erter. TEMATIC ASSESSMENT OF LICENSEE PERFORMANCE. R AVEY-SMIT H. A Dyson of Licensee Performance & Quakty gency Preparedness & Engineemg Response.lE(8A212-870413) February 1987.117pp 8703090147 39922 001 Evaluaton (Post H70411) October 1997 70pp 8711030070 , i Tsee NUREG-1210,V01 abstract 43243 337 i l 1 4

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

1 l l

14 . Main Citations and Abstracts '

The Historcal Data Summary of the Systematic Assessment erat >ons (EDO) informed tne Chairman of the B&W Owners of Ucensee Performance (SALP) rs produced penodically by the Group (BWOG) that a number of recent events at B&W de-U.S. Nuclear Regulatory Commisson. This summary provides s ped reactors have led the NRC staff to conclude that the the resutts of the assessment for each facihty by NRC region base requwements of B&W reactors need to be reexamined. In and is further donded into the follomng three sections: Section 1 sts February 13,1986 response to the EDO's letter, the BWOG presents the most recent SALP report ratings for fac* ties under committed to lead an effort to define concems relative to reduc-constructon and ln operabon. Section 2 presents a chronologi. ing the frequency of reactor tnps and the complexity of post tnp cal listing of all SALP report ratings for each operating facihty. response in B&W plants. The BWOG submitted a descripton of Secton 3 presents a chronological hsting of all SALP report rat. the B&W program entitled "Safety and Performance improve. ings for each facaty under constructon. For histoncal purposes, ment Program" (BAW 1919) on May 15,1986. Five revisens to ' past constructen SALP ratings for facilities that recently have BAW 1919 have also been submitted. The NRC staff has re-been hcensed also are listed in Secton 3. viewed BAW- 1919 and its five revisions and presents its eval-NUREG 1224: SAFETY EVALUATION REPORT RELATED TO uaton n ws report. THE RENEWAL OF THE OPERATING LICENSE FOR THE NUREG 1232 V01: SAFETY EVALUATION REPORT ON TEN-UNIVERSITY OF NEW MEXICO RESEARCH REACTOR Docket NESSEE VALLEY AUTHORITY. Revised Corporate Nuclear No. 50 252. (Urvversrty Of New Mexico)

• Dnnsion of Pressur-Performance Plan.
• Ofc of Special Projects, July 1987. 64pp.

ized Water Reactor Licensing B (851125-870411). March 8710080392.42995:225.

• 1987. 48pp. 8704090018. 40466:110.

Ttus Safety Evaluation Report on the informabon submitted by This Safety Evaluaben Report for the appleaton fded by the the Tennessee Valley Authonty (TVA) in rts revised Corporate Unrversity of New Meco for renewal of operating Icense Nuclear Performance Plan, through Revison 4, has been pre-number R.102 to conhnue to operate a research reactor has pared by the U.S. Nuclear Regulatory Commisson staff. The been prepared by the Orface of Nuclear Reactor Regulabon of TVA Corporate Nuclear Performance Plan addresses those cor-the U.S. Nuclear Regulatory Cornm.sson. The facility is owned porate concerns dentified by the staff in its letter to TVA dated and operated by the Unrversity of New Mexco and is located on September 17,1985. On the basis of its review, the staff finds the Unrvers4ty's campus in Albuquerr.,ue, New Mexico. The staff TVNs revised Corporate Nuclear Performance Plan (Revison 4) concludes tirai the AGN 201M type reactor facdity can conbnue acceptable. to be operated by the Unrversity of New Mexco without Jndan-genng the health and safety of the pubic. NUREG 1235: TECHNICAL SPECIFICATIONS FOR CLINTON NUREG-1230 DRFT FC: COMPENDIUM OF ECCS RESEARCH POWER STATION. UNIT 1. Docket No. 50-461.(filinois Power ' FOR REAUSTIC LOCA ANALYSIS. Draft Report For Comment- Company)

• Office of Nuclear Reactor Regulaton, Drector
• Dnnsion of Reactor & Plant Systems (Post 870413). Apnl (Post 870411) Apnl 1997. 562pp. 8705120069. 40897;147.

1987.1.348pp. 8705290033. 41101:238. The Chnton Power Stabon, Unit No.1 Techncal Specsfica-Emergency Core Coohng Systems (ECCS) are requwed on all tions were prepared by the U.S. Nuclear Regulatory Commis-light water reactors (LWRs) in the United States to provide cool- son to set forth hmits. operating conditons, and other require-ing of the reactor core in the event of a break in the reactor ments appleable to a nuclear reactor facdity as set forth in Sec-pipeng These accidents are called loss-of-coolant acesdents tion 50.36 of 10 CFR 50 for the protecten of the hea!th and (LOCA), and they range from small leaks to a postulated full safety of the pchk break of the largest pepe in the reactor coohng system. Federal NUREG-1237: TewNICAL SPECIFICATIONS FOR VOGTLE government regulatons reqvwe that calculatons of the LOCA ELECTR'C GENERATING PLANT, UNIT 1. Docket No. 50-be performed to show that the ECCS will maintain fuel rod clad- 424 (Georgia Power Company)

• Dvis4on of Pressunzed Water i

ding temperatures, claddr.g oxidabon, and hydrogen production Reactor Lcensing A (851125-870411). January 1997. 460pp.

,                                                      within certain kmits. The Nuclear Regulatory Commsson (NRC)                                                8702060231. 39538-194.
 )

and others have completed an extensive invesbgaton of fuel The Vogtle Electnc Generatng Plant, Urvt No.1, Techncal rod behavior and ECCS periormance The technology has been Specificatons were prepared by the U S. Nuclear Regulatory . advanced to the point that is now possible to make a realiste Commsson to set forth the hmits, operabng condibons, and  ! estimate of ECCS performance dunng a LOCA and to quantify other requirements applicable to a nuclear facdity as set forth in the uncertainty of this calculaton. Tnts report seSes as a gen- Secton 50.36 of 10 CFR 50 for the protecton of the heafth and eral reference for ECCS research. The report (1) summanzes safety of the pubic.

'                                                     the understanding of LOCA phenomena in 1974, (2) reviews ex.

penmental and analytscal programs developed to address the NUREG 1239: ENVIRONMENTAL ASSESSMENT FOR RENEW. phenomena, (3) desenbes best-estimate computer codes devel- AL OF SOURCE MATERIAL LICENSE NO. STB-401. Docket No. oped by the NRC, (4) d scusses the sahent techrucal aspects of 40-6563 (Columbium Tantalum Omsaon,Malhnckrodt.inc )

• Dnn-LOCA phenomma and our current understanding of them, (5) sion of Fuel Cycle, Medical, Academe & Commeretal Use discusses probabahste nsk stud >es, and (6) examines the impact Safety 870413-870728 Apnl 1987. 69pp. 8705190502.

of research on the ECCS regulatons. 40980-267. I' , in response to an apphcabon for renewal of Matenals Ucense NUREG-1231: SAFETY EVALUATION REPORT RELATED TO No. STB 401 for the Columbium-Tantalum Dvision of Maffinck-i THE BABCOCK AND WILCOX OWNERS GROUP PLANT RE- rodt. Inc., St. Louis, Missoun, the NRC statt prepared this Erm-ASSESSMENT PROGRAM. SIEGEL B. Offee of Nuc! ear Reac* tor Regulation, Director (Post 870411). November 1987.232pp. ronmental Assessment- The Environmental Assessment in-  ! ciudes discussions of the need for the proposed renewal, arter-8711250145.43449 095 natives to the acton, and the envronmental impacts of pro-  ! After the accident at Three Mile Island, Unrt 2, nuclear power posed acton. plant owners made a number of rnprovements to tner nuclear f aciht es. Despite these rnprovements, the U S. Nuclear Regula. NUREG-1240: TECHNICAL SPECIFICATIONS FOR SHEARON tory Commsson (NRC) staff rs concerned that the number and HARRIS NUCLEAR POWER PLANT, UNIT 1 Docket No. 50-

• complexity of events at Babcock & Wilcox (B&W) nuclear plants 400 (Carolina Power & Light Company)
• Drvison of Pressunzed have not decreased as exputed. This concern was reinforced Water Reactor Ucensang A (851125-870411). January 1987.

by the June 9,1985 total loss- of feedwater event at Daws- 473pp. 8702040174. 39508:110 Besse Nuclear Power Station and the December 26,1985 over- The Shearon Hams Nuclear Power Plant, Unit 1 Techrucal coohna transient at Rancho Seco Nuclear Generatng Staten. Specfications we prepared by the U S Nuclear Regulatory By letter dated January 24,1986. the Executive Drector of Op- Comrrnssion to set fceth the hmts, operating conditons, and I . i e

    -,-.-.,--.--..-,,,--.-,,,--,-,vi-.,.or.,----.,,,.,,4-,,
                                                                                          . - ,,-.-, . , , - ----,, ,,,.m,,-,y.,,     , . , - ,e,,.,,,,,-,,,-.            , , - , . , - - - , - - . + - .       -,-----,,m-,, . , , - - - - - - - , , , . - . . - , - - - , - wy. - . - , -..

Main Citations and Abstracts 15 other requirements apphcable to a nuclear f acihty as set fora in NUREG-1248: TECHNICAL SPECIFICATIONS FOR PALO VERDE Secten 50.36 of 10 CFR 50 for the protecten of the health and NUCLEAR GENERATING STATION, UNIT 3 Docket No. 50-safety of the public. 530(Anzona Pubhc Senoce Company) ' Dmson of Pressurized Water Reactor Licensing - 8 (851125-870411). March 1987. NUREG-1243: GROUND-WATER PROTECTION ACTIVITIES OF 490pp. 8704090024. 40462:114 THE U S. NUCLEAR REGULATORY COMMISSION.

• Dmson The Palo Verde, Unit 3 Technical Specificatons wero pre-of Waste Management (Pre 870413). February 1987. %pp. pared by the U.S. Nuclear Regulatory Commisson to set forth 8703130105. 40007:134. the limits, operating cond. tons, and other requirements upphca-The U S. Nuclear Regulatory Comrnission (NRC) provid:s for ble to a nuclear reactor facihty as set forth in Secton 50.36 of ground water protecton through regulatons and bcensing con- 10 CFR Part 50 for the protecton of the health and safety of ditions that require preventon, detecton, and correcton of the pobhc.

ground water contaminaten. Prepared by the inte office Ground Water Protecton Group tNs report evaluates the inter. NUREG 1250- REPORT ON THE ACCIDENT AT THE CHERNO-nal consistency of NRC's ground- water protection proyams. BYL NUCLEAR POWER STATION.

• NRC No Detailed Affils.

These programs have evolved cons 4stently with grow ng pubhc aton Grven.

• Energy, Dept. of *; et al. Envvonmental Protec-concerns about the s>gnificance of ground-water contarr naton ton Agency. January 1987. 214pp. 8702170005. 39657:142, and environmental impacts. Earty NRC programs provred for This report presents the compilaton of informaton obtained the protecton of pubhc healtn and safety by minemtzing rdeases by vanous organizatons regardeg the accident (and the conse-of radonuchdes. More recent programs have includer! provi- quences of the accident) that occurred at Unit 4 of the nuclear sons for minimizing releases of non radclogical cons ,tuents, power staton at Chernobyl in the USSR on Apnl 26,1986. Each mat > gating environmental impacts, and correcting grourewater organizaton has independently accepted responsibthty for one contam,naton. NRC's ground-water protecten progre ms are or more chapters. The varcus authors are identfed in a foot-categonzed according to program areas, including nucle tr mate- note to each chapter. Chapter 1 provdes an ovennew of the nals and waste management (NMSS), nuclear react < oper- report. Very bnefly the other chapters cover: Chapter 2, the atons (NRR), confrrmatory research and standards develop- desen of the Chernobyl nuclear staten Urat 4; Chapter 3, ment (RES), inspecton and enforcement (IE), and agreement safety analyses for Urut 4; Chapter 4, the accdent scenarc; state programs (SP). Chapter 5, the role of the operator; Chapter 6, an assessment of the radcactive release, disperson, and transport; Chapter 7, NUREG 1244: PLAN FOR INTEGRATING TECHNICAL ACTIVI- the actmties associated with emergency actons; and Chapter 8.

TIES WITHiN THE U S. NRC AND ITS CONTRACTOR'iIN THE informaton on the hea!th and environmental consequences AREA OF THERMAL HYDRAULICS.

• Office of Nuchar Regu- from the acodent. These subjects cover the mator aspects of latory Research, Director (Post 860720). Apol 19s7. 42pp the accdent that have the potential to present new informaton 8705120074.40896 152. and lessons for the nuclear industry in general. The task of The Executrve D<ector for Operatons (EDO) da acted the evaluating the informaton obtained in these vanous areas and NRC staff to prepare a coordinated plan for the inte graton of the assessment of the potential impbcatons has been left to techrucal actmties witNn the agency and specif,ed a number of each organ #2aton to pursue accord 4ng to the relevance of the issues to be addressed TNs report summanzes 10 status of subject to ther organizatons. Those findings will be issued sep-agency programs involved in thermal hydraubc re! earch ant., aratety by the cognizant orgaruzatons. The basic purpose of proposes management methods to accomphsh the E XTs direc- tNs report is to provde the informaton upon wNch such as-tives. sessments can be made.

NUREG-1245 V01: RADIOACTIVE WASTE MANAGl MENT RE- NUREG 1250 R01: REPORT ON THE ACCIDENT AT THE CHER-SEARCH PROGRAM PLAN FOR HIGH. LEVEL WA iTE - 1987. NOBYL NUCLEAR POWER STATION.

• NRC - No Detailed Af-Dmscn of Engineenng (Post 870413) May 987. 62pp. fihaton Given.
• Energy, Dept. of. *; et al Electnc Power Re-8706120346. 41280.026. search Institute. December 1987. 400pp. 8801110242.

The program of research desenbed in tNs plan r intended to 43977:121. odentify and resolve technecal and scentific issues invofved in See NUREG 1250 abstract. the NRC's hcens.ng and regulation of disposat sy tems intend-ed to isolate high-level hazardous radioactrve v astes (HLW) NUREG 1251 DRFT FC: IMPLICATIONS OF THE ACCIDENT AT from the human envvonment. The Plan descnbe! the program CHERNOBYL FOR SAFETY REGULATION OF COMMERCIAL goals, discusses the research approach to be ued, lays out NUCLEAR POWER PLANTS IN THE UNITED STATES Draft peer revew procedures, discusses the Nstory and development For Comment.

• NRC No Detaded Affthaton Grven. August of the Ngh-level radcactrve waste problem anc the research 1987. 98pp 8709040049. 42507:277.

effort to date and descnbes study obtectives anc research pro- TNs draft report issued for comment was prepared by the Nu-grams in the areas of; (a) matenals and engineer og. (b) hydrob clear Regulatory Commisson (NRC) staff to assess the emphca-ogy and geochemistry, and (c) comphance w, i internatonal tons of tne acceent at the Chernobyl nuclear power plant as waste management research programs. In additr in, a proposed they relate to reactor safeh regulaton for commercial nuclear Earth Scenca Seismotectoruc Research Prog *ar plan for rad >o- power plants in the Uruted States. The facts used in this as-acttve waste facihtes is appended sessment have been drawn from the U S. fact. finding report (NUREG-1250) and its sources NUREG-1247: TECHNICAL SPECIFICATIONS FOR VOGTLE ELECTRIC GENERATING PLANT, UNIT 1 Cocket No. 50- NUREG 1253: TECHNICAL SPECIFICATIONS FOR NINE MILE 424 (Georgta Power Company) ' Divison of P essunzed Water POLNT NUCLEAR STATION. UNIT 2 Docket No. 50-410(Nagara Reactor Licensing A (851125 870411) Var .h 1987 458pp. Mohawk Power Corporaton et af)

• Drvison of Reactor Projects 8704020068. 40344 250 - I/II (Post 870411) Ju'y 1987. 526pp 8707210703. 41832 032.

The Vogtle Electnc Generating Plant Unit No.1, Techrucal The N:ne M le Poant Nuclear Staton. Un.t 2 Techrucal Specif>- Specificatons were prepared by the U S. N clear Regulatory cations were prepared by the U S Nuclear Regulatory Commis-Commisscn to set forth the hmits, operatin i cond: tons, and son to set forth tho irm,ts. operating cond, ton % ard other re-other requeements appbcable to a nucicar fac lity as set forth in Quirements appbcat4e to a nuclear reactor facihty as set forth in Secton 50 36 of 10 CFR 50 for the protector of the heaith and Secton 50 36 of 10 CF R Part 50 for the protacton of the health safety of the pubic and sa'cty of the pubhc.

16 Main Citations and Abstracts NUREG 1255: TECHNICAL SPECIFICATIONS FOR SOUTH updating. mod,fication and testing Inspectons will be performed TEXAS PROJECT, UNIT 1. Docket No. 50-498 (Houston Lighting by NRC staff with interdisciphnary skills including hcense exam-and Power Company)

• Dmsson of Reactor Projects Ill,lV,V & iner, operations speciahst and human factors expert. Inspec-Special Protects (Post 870411), August 1987. 445pp. tons may conset of off site and/or on-site phases The off-s,te 8709090260. 42577:044. phase consrsts of an examinaton of simulaton facihty docu.

The South Texas Project, Unit No.1, Techn, cal Specificatons mentaten, and the dentiteaten of those operatons that may were prepared by the U.S. Nuclear Regulatory Comtnession to be considered for use in on site performance test.ng in the on-set forth the limits, operating conditons, and other requirements s:te phase, the staff wdl work wth the facaty licensee to con-apphcable to a nuclear reactor facihty as set forth in Section duct a review of the four technical areas, and to evaluate the 50.36 of 10 CFR 50 for the protecton of the heafth and safety re uits of tests that are conductea Findings will be based upon of the public. ttk . 3ff's judgment of the degree of comphance of the simula. NUREG 1256 VO1: INCENTIVE REGULATION OF NUCLEAR ten facMty with 10CFR55 rn terms of its suitabihty for the con-POWER PLANTS BY STATE PUBLIC UTIUTY COMMISSIONS. duct of operating examinatons. PETERSEN.J C. Program Management, Policy Development & NUREG 1259; TECHNICAL SPECIFICATIONS FOR BEAVER Anatysis Staff (Post 870411) December 1987. 59pp. VALLEY POWER STATION. UNIT 2 Dochet No 50-412 (Du-8712240211. 43793:245. Quesne Light Company)

• Division of Reactor Protects 1 / 11 This is a report on incentrve regulation of nuclear power (Post 870411) May 1987. 429pp. 8706120083 41282.007.

plants by State pubhc utSty commissons (PUCs) Economic The Beaver Valtey Power Staton, Unit 2 Technical Specifica-performance incentives estabhshed by State PUCs are apphca- tons were prepared by the U S. Nuclear Regutatory Commes. ble to the constructon or operaton of about 45 nuclear power sion to set forth the kmits, operat;ng cond tons, and other re-reactors owned by 30 utAtes in 17 States. The NRC staff mont- quirements appbcable to a nuclear reactor facAty as set forth in tors development of the incentr<es and perodica9y provides an Sect;on 50.36 of 10 CFR 50 for the protecton of the hea!th and updated report on a!l nuclear plan incentives to its Regonal Of- safety of the pubhc. fices. The staff ma<ntains contact with the PUCs and the utsties responsible for emplementing the incentrves in order to obta:n NUREG 1260 V01: A REPORT TO CONGRESS ON NUCLEAR the updated informaton and to consder potential safety effects REGULATORY RESEARCH Pro r ect Descnptcns For FY87. ' of the incentrves This report presents the NRC staff's concerns Office of Nuclear Regulatory Research. Director (Post 860720) on potential safety effects of economic performance incentives February 1987. 574pp. 8703260021. 40244 001. It also includes a plant-by-plant survey that desenbes the me. The report presents project desenptions cf NRC research chanics of each incentive and discusses the financial effects of prorcts funded in Fiscal Year 1987 The indtvdut project de-the incentrve on the utsty-owner (s) of the plant. scnptons presented in this report are dvded into six major groups of related projects These groups, caHed issues. are as NUREG 1258: EVALUATION PROCEDURE FOR SIMULATION foitows Severe Accdent. R sk and Rehabety, Thermal Hydraul'c FAC1UTIES CERTIFIED UNDER 10 CFR 55 Final Report- Transients. Piant Ag'ng and Life Extensen. Seismic Research. WACHTELJa PLOTT,C.; LAUGHERY,K R ; et al Dmson of Lb and Waste Management. Within each issue, the project desCnp-censee Performance & Ouakty Evaluaton (Post 870411) De- teos are further dmded ento subgroups, ca!!ed subissues An cember 1987.141pp. 8801060431. 43929.093 overv.ew is provded pror to each issue and subissue grving a This document desenbes the procedure to be followed by statement of the problem being acessed and the research ob-NRC for the inspecten of simulaton facetes certif ed under 10 lectives CFR 55 Inspectons are Omded into four areas based on types of evaluatons conducted 1) performance testing. 2) physical fi- NUREG 1261: TECHNICAL SPECIFICATIONS FOR BRA lDWOOD dehty/ human factors, 3) control capabiht,es, and 4) desig% up. STATION UNITS 1 AND 2 Docket Nos 50-4 L6 And 50-dating. mod:fication, and testing NRC staff representog several 457 (Commonwea'th Ed1 son Company) ' Dmson of Reactor d.scipknes including bcense examiners operatens speciahsts. Projects IlUV.V & Special Projects (Post 870411) May 1987. and human factors experts. under directen of a team leader. 490pp 8707140211. 41692120 w,Il perform these inspectons A simulation fachty inspection The Bradwood Staton, Unit Nos 1 and 2. Techntcal Specifr may include on-site and off-site pases The off-site phase will catons were prepared by the U S Nuclear Reguiatory Commis-consist of an examinaton of simulaton f acaty documentaten son to set forth the hmits. operating cond tiors. and other re-and an identificaton of those operations and procedures which quirements appbcable to a nuclear reactor facity as set forth in may be considered for use in periormance testing dunng the Secton 50 36 of 10 CFR Part 50 fcr the protecten of the hea:th on site phase. In the on site rewe* the staff *:11 work closely and sa'ety of the pubhc

• th the facihty bcensee to conduct a sound and fair inspecten and to evaluate the results of those tests that are conducted NUREG 1262: ANSWERS TO OUESTIONS AT PUBLIC MEET.

Inspecten findings mil be based on staff Judgment of the simu' INGS REGARDiNG IMPLEMENTATION OF TITLE 10. CODE (.7 laton facAty's comphance w/10 CFR 55 45 Find ngs may FEDERAL REGULATIONS PART 55 ON OPERATC'RS' U. range from "no adverse impact on the conduct of operat.ng CENSES

• Dms on of Ucensee Performance & Oval ty Evalua-tests" through degrees of ' adverse impact requinng correction tion (Post 870411). N ovember 1987 17Epp 8712230304 43800 3N to "adverse impacts so sercus that the s:mu'aton facility may This document presents quest ons and answers based on not be used in the conduct of operaSng tests untd the d+screp-transcrpts of four pubhc meet:ngs (and from wntten questons ancies ar the NR*, e corrected and the simulaton faobt f is recert: fed to subm;tted a'ter rntetings) conducted from Apol 9 to Apnl 20, 1987 by the staff of the U S Naciear Regu'atory Commrsson NUREG-1258 DRFT: EVALUATION PROCEDURE FOR SNJLA- The meet,rgs d scussed irrpfementat en of the Commiss.on's TION FACILITIES CERTIFIED UNDER 10 CFR 55 Draft Report f,nal rute go vern.ng Ocerator s Ucenses ard Conforming LAUGHERY,K R ; PLOTT.C ; WACHTEL) Dmson of Human Amendments (10 CFR Pam 55 and 50) The ru'e became ef-Factors Technology (651125-870411). March 1987 14tep fectrve May 26 1987 and is intended to clar+y the regu'ations 8704270073. 4 % 82 096 for iss#ng bcenses to operators and senor cperators, reose This document describes the process to be fono*ed by the the req #rements and scope cf *ntien enaminatons and operat-NRC for the inspecton of s,mutaton facat>cs cen f:ed by faca.ty ing tests for operators and sence cperators includ ng a regere-hcensees rn accordance with 10CFR55 Such inspectons are ment for a simulaton f ac.1:ty clanff procedures for adm nistenng deded into four major technical areas performance tesbng requabficat.on examinatons. and descr'be the form and conteni phys, cal fdetty/hurnan factors. controt capabAftes and design. for operator Icense appbcatons

Main Citati:ns and Abstricts 17 NUREG 1264: CONTAINMENT INTEGRITY RESEARCH PRO- pressunzed to approximately 710 psig The NRC AIT members GRAM PLAN.

• Divison of Engineenng (Post 870413). August concluded that the Dtablo Canyon, Unit 2 plant was, the time of 1987. 38pp. 8709160104. 42693:130. the event, in a cond. tion not prevously analyzed by the NRC This report presents a plan for research on the queston of staff. The AIT findings from this event appear significant and ge-conta:nment performance in postulated severe accident scenar- nenc to other pressurized water reactor fachties hcensed by the ios. It focuses on the research being performed by the Structur- NRC.

al and Seismic Engineenng Branch, Dmscn of Engineenng. NUREG 1270 VOI: INTERNATIONAL CODE ASSESSMENT AND Office of Nuclear Regulatory Research. Summanes of the plans Annual Report. TING,P.; APPLICATIONS PROGRAM. for this work have prevously been published in the Nuclear HANSON.R ; JENKS,R. Offce of Nuclear Regulatory Research. Power Plant Severe Accdent Research Plan" (NUREG-0900). Director (Post 860720). March 1987, 298pp. 8704270543. This report provdes an update to reflect current status. This 40713.223 plan provides a summary of results to date as well as an outline The first ICAP Annual Report is devoted to coverage of pro-of planned actmties and milestones to the contemplated com-gram actmties and accomphshments dunng the pered between pietion of the program in FY 1989 Apnl 1985 and March 1987. The ICAP was organized by the NUREG-1265: UNCERTAINTY PAPERS ON SEVERE ACCIDENT Office of Nuclear Regulatory Research, United States Nuclear SOURCE TERMS.

• Office of Nuclear Regulatory Research, Di- Regulatory Commisson in 1985. The ICAP is an international rector (Post 660720) May 1987. 194pp. 8707140200. cooperative reactor safety research program planned to provide 41691 216. independent assessment of the NRC computer codes devel-An assessment of the severe accdent source term technolo- oped for analysis of reactor transients and loss cf-coolant acci-gy was recently pubhshed by the NRC in NUREG-0956. State- dents.

of.the art methods descr, bed in NUREG-0956 are now being used in risk assessments and as the basis for implementing the NUREG 1271: GUIDELINES AND PROCEDURES FOR THE NRC's Severe Acc; dent Policy Statement and its Safety Goal. INTERNATIONAL CODE ASSESSMENT AND APPLICATIONS PROGRAM, TtNG,P.; BESSETTE,0.; HANSON.R. Dmson of Notwithstand:ng major advances in source term technology re. Reactor & Plant Systems (Post 870413). Apnl 1987. 80pp. suiting from recent severe accident research programs, NUREG 0956 dentified eight technical areas where uncertain. 8705120086. 40896 073 This document presents the guidehnes and procedures by ties remain large and where our near term research efforts which the Internatonal Code Assessment and Apphcations Pro-should be focused. Indvidual programs ethin the severe acco dent research program are being adjusted to address these gram (ICAP) will be conducted The document summanzes the management structure of the program and the relatonships be-eight areas of uncerta.nty eth a concentrated effort. To plan for tween and responsibihties of the United States Nuclear Regula-these program changes. NRC research program managers have reviewed the nature of the uncertainties in their respectfve sutp tory Commisson (USNRC) and the internatonal participants The procedures tor code maintenance and necessary documen-feet areas and prepared background papers. These background taten are desenbed Gudehnes for the performance and docu-papers (or uncertarnty papers) are presented in this report. mentaten of code assessment stud.es are presented An over-NUREG-1266 VO1: NRC SAFETY RESEARCH IN SUPPORT OF view of an effort to quantity code uncertainty, which the ICAP REGULATION 1986

• Office of Nuclear Regulatory Research, supports, is included.

Director (Post 860720) Septerr.ber 1987. 66pp. 8710080407. 42991.067. NUREG 1272: REPORT TO THE U S NUCLEAR REGULATORY This report ts the second in a series of annual reports re. COMMISSION ON ANALYSIS AND EVALUATION OF OPER. sponding to congressonal inquines as to the utihraton of nucle. ATIONAL DATA 1986.

• Othce for Analysis & Evaluaton of ar regulatory research. NUREG 1175, "NAC Safety Research in Operat,onal Data. D, rector. May 1987. 249pp. 8706160095 Support of Regulaton," pubbshed in May 1986. reported major 41315 007.

research accomphshments between about FY 1980 & FY 1985. This annual report of the U S Nuclear Regulatory Commis-This rvort narrates the accompushments of FY 1986 and does son's Othce for Analysts and Evaluaton of Operatonal Data not restate earter accomphshrrwnts Earter research results are (AEOD) is devoted to the aClivities performed dunng the Calen-mentened in the context of current resutts in the interest of dar year 1986. Comments and observations are provided on op. continuity Both the direct contnbutons to scientific and techru. erating expenence at nuclear power plants and other NRC le-cal knowledge and their regulatory apphcatons, when there has censees, including results from selected AEOD studies. summa. Leen a def<n:te regulatory outcome dunng FY 1986, have been tres of abnormal occurrences involving U S nuclear plants; re-vie *$ of bcensee event reports and theer quahty, reactor scram desenbed nce om eng e a ams aN NUREG 1269, LOSS OF RESIDUAL HEAT REMOVAL " " *

• 9'8 * *'

SYSTEM Diablo Caryon Unit 2, Apnl 10,1987. CREWS.J L - mmM d ems W Md mNem ww TRAMMELL.C M , LYON,W C ; et al. Regen 5. Ofc of the Direc- n additon, the report provdes the year-end status of all recom-tor. June 1987.107pp. 8707060049 41584 040 " 9 U' This report presents the find:ngs of an NRC Augmented in-specton Team (AIT) invcstgation into the circumstances asso-c)ated with the loss of residual heat removal (RHR) system ca- NUREG-1274: REVIEW PROCESS FOR LOW LEVEL RADIOAC-pabaty for a pered of approomately one and one-half hours at TIVE WASTE DISPOSAL LICENSE APPLICATION UNDER the Diablo Canyon. Unit 2 reactor facd4 on Apol 10,1987. This LOW LEVEL RADIOACTIVE WASTE POLICY AMENCMENTS event occurred whde the Diablo Canyon. Unit 2, a pressunzed ACT PITTIGLIO,C L Droson of Lo* Level Waste Management nater reactor. was shutdown w:th the reactor Coolant system & Decommissoneng (post 870413) August 1987. 22pp (RCS) water levet dra ned to approximately md level of the hot 8708240196. 42319 186 leg p prng The reactor conta:nment build:ng ogspment hatch This document dentsf.es and desenbes the U S Nuclear Reg-was removed at the t,me of the event, and plant personnel were ufatory Commisson's (NRC's) process for bcens:ng a low-level in the process of removing the pomary sede manways to gain radcactrve waste d4sposal facuy uthin the time required by the access into the steam generator channel head areas. Thus, two Low level Radioactive Waste Pohey Amendments Act of 1985 fisson product bamers were breached throughout the event. This document also estimates the level of effort and erpert.se The RCS temperature increased from approximately 87 degrees that is needed to review a bcense appbcaton *, thin the required F to bum boang conditions ethout RCS temperature irdicaton time it is intended to be used by the NRC staff as well as avadable to the plant operators The RCS was subsequentty States and interested part>es to provide a better understanding

18 Miln Citations End AbstrCcts of what the NRC envisions wdl be involved in hcensing a low- NUREG-1279: TECHNICAL SPECIFICATIONS FOR BEAVER level radcactr<e waste facility. VALLEY POWER STATION, UNIT 2. Docket No. 50 412.(Du-quesne Light Company.et af)

• Desen of Reactor Projects 1/11 NUREG 1275V1: OPERATING EXPERIENCE FEEDBACK REPORT- (Post 870411) August 1987. 424pp 8709090526. 42575:340.

NEW PLANTS Commercial Power Reactors. DENNIG,R.L.; The Beaver Valley Power Staten. Unit 2. Technical Specifica-O'AEILLY.P D. C+fice for Analysis & Eva!uation of Operatonal tion were prepared by the U.S Nuclear Regulatory Commissen Data. Director. July 1987. 285pp. 8709040358. 42522 267. to set forth the hmits, operating conditions, and other require-This report documents a deta. led review of the cause of un. ments appkcable to a nuclear reactor facility as set forth in Sec-planned events dunng tne early months of licensed operation tion 50.36 of 10 CFR 50 for the protecten of the health and for plants licensed be+ ween March 1983 and Apnl 1986. The safety of the public. major lessons and corrective actons that appear to have the greatest potential for improving the effectiveness of plant star. NUREG 1280: STANDARD FORMAT AND CONTENT ACCEPT-tups are provded for consderation through the operating expe. ANCE CRITERIA FOR THE MATERIAL CONTROL AND AC. ronce feedback prog *ams and a:tivitres of the industry and the COUNTING (MC&A) REFORM AMENDMENT.10 CFR Part 74 NRC staN Subpart E. EMElGH.C.W. Dmson of Safeguards (Pre 870413) March 1987.102pp 8704060097. AA50-2 032. 40446.284. NUREG-1275 V02: CPERATING EXPERIENCE FEEDBACK This report documents a standard format suggested by the REPORT AIR SYSTEMS PROBLEMS. Commercial Power Re- N C for use in Nepanng fedawntal Nclear matenal comrol actors ORNSTEIN.H L Office for Analys s & Evaluation of plans as required by the Material Control and Account 2ng Operatonal Data. Director. December 1987. 129pp. Reform Amendment (port;ons of 10 CFR Part 74) The report 8801070064 43943 154 also desenbes the necessary contents of a comprehensive plan This report hghbghts segrtficant operating events involving and provdes example acceptance entena which are intended to observed or potent.a fadures of safety 4 elated systems in U S- communicate acceptable means of acNeving the performance piants tNit resulted from degraded or ma!functoning non-safety capabdites of the Reform Amendment. By using the suggested grade air systems Based upon the eva!uation of these events. format, the hcense appbcant will minsmae admin.stratve prob-the Oftce for Ana'ysis and Evaluaton of Operatcnal Data lems associated with the submittal review and approval of the (AEOD) concluces that the issue of air systems problems is an FNMC plan. Preparaten of the plan in accordance with this format will assist the NRC in evaluat;ng the plan and in stand-important one wNch requwes addtonal NRC and industry atten- ard2 zing the review and hcens ng process However. conform-ton. TNs report atso provdes AEOD's recommendatons for ance wth this gudance is not required by the NRC. A heense corrective actons to deal wrth the issue. appbcant who employs a format that provdes an equivalent NUREG 1276: TECHN! CAL SPECIFICATIONS FOR BRAIDWOOD STATION. UNITS 1 AND 2 Docket Nos. 50 456 And 50- NUREG 1281: EVALUATION OF THE QUALIFICATION OF 457 (Common

• earth Edison Company)
• Dmson of Reactor SPERT FUEL FOR USE IN NON-POWER REACTORS ' Dm-Projects - m.IV.V & Special Projects (Post 8704f1). July 1987. son of Reactor Protects lil.fV.V & Special Projects (Post 493pp 8707290233. 41952 082. 870411). August 1987. 89pp 9708240112 42319 001.

The Braidwood Staton. Un,ts 1 and 2. Technical Specifica. TNs report summanzes the U S. Nuclear Regulatory Commis. tons nere prepared by the U S Nuclear Regulatory Commis- son staff's evaluation of the quanficaton of the stainless-stech saen to set forth the bmits, operating cond. tons and other re. clad uranium /onde (UO2) fuel pins for use in non-power reac-quirements appkcab!e to a nuclear reactor facery as set forth in tors. The fuel pns were or9nally procured in the 1960's as part Secten 50 36 of 10 CFR Part 50 for the protecton of the health of the Special Power Excurson Reactor Test (SPERT) program. and safety of the pubhc. Argonne Natonal Laboratory (ANL) examined 600 SPERT fuel pins to venty that the pins were produced according to specif>- NUREG 1278: VOGTLE UNIT 1 READINESS caton and to assess then present cond't.on The pins were vis-REV!EW Assessment Of Georg'a Power Company Readtness vally inspected under 6X magnAcat on and by X-radograpNc, Rev,ew Pdot Program LEWIS.G. Dms>on of Lv.ensee Perform. destructive, and metattograpNc examinatons Spectrographic ance & Quahty Evaluaton (Post 870411). September 1987, and chemical anaiv ses were per4ormed on the UO2 fuel The 29pp 8710080317 42990 320 results of the Qualificaton esaminatrons indicated that the Geo'gia Power Company (GPC) performed a readiness review SPERT fuel pins meet the requirements of PNikps Specacaton at vogte Un:t 1 as a pdct program. The pilot program was a No. F 1 SPT and have suffered no phys 4 cal damage since fabn. new and innovative approach for the systemateC and discipkned caton Therefore. the quahficaton results give reasonable as-reve*, with senor rnanagement invoNement. of GPC's imple- surance that the SPERT fuel rods are suitable for use in non-montaten of des'gn, constructon, and operatonal readiness power reactors provded that the effects of tNn wa:I defects in processes The prograres puncipal othectrve was to increase the regon of the upper end cap and low-density fuel peuets are the level of assurance tha Quahty programs at Vogtle Unit I wabaW W N Wended operaW co*cos have been accomphshed in accordance with regulatory requee-rnents This report assesses the effectueness cf the GPC's NUREG 1282: SAFETY EVALUATION REPORT ON HlGH-URA-read. ness reven plot program (RRPP) at Vogtre Unit 1 it in. NtVV CONTENT LOW-ENRICHED UR AN!UV. ZIRCON:UM HY. ciudes (1) an overce* cf what was expenenced dunng the pro- DRIDE FUELS FOR TRlGA REACTORS Docket No 50163 (GA Technolog>es.It'corporated)

• Dmsen of Reactor Projects -

gram's implementaSon. (2) an assessment of how well program m.IV.V & Spectat Protects (Post 870411) August 1987 17pp obgectives were tret, and (3) lessons learned on the future use 8708240190 42319 207. of the readress recew concept. Overall. GPC and the NRC The properbes and performance of the TRIGA higher weight sta'i beheve that the RRPP at Vogtie Un11 was a success and percent (*%). Iow-ennched uranium fue's are compared **th that the program provided sig% cant added assurance that those of the currentry hcensed 8 5 wN fuels Neutron physics Vogtie Un1t 1 hcens;ng commitments and NRC regulatons have consideratons. matenals properties. eratat.on performance, f:s-been adequatePy implemented Although a'tering the NRC h- son product release. pulse heating. aM hmit:ng design bases censing reoca process for the few plants stal in the construc- were eva'uated Tne performance of uranium-zirconium hydnde ton p4pehne may not be approonate, bcensees rnay benef.199- fuel is substanha9y independent of uranium content up to 45-nificantly by performing read: ness reviews on their own initiative w% uranium The behanor of the proposed 20- and 30-*% ura-as GPC d d for Vogt:e nium fuels is irnstinguishabh, from tnat of tne urent!y ap.

Main Citations and Abstracts 19 proved 8.5 w% uranium fuel. Both the 20 20 and 30-20 urant- de power was restored 26 minutes after its loss. This report pre-um rirconium hydode fuels are acceptable for use in the GA sents the staff's evaluaton of me corrective actons taken by Mark F TRIGA reactor, and these two types of fuel are genen- the hcensee to prevent recurrence and to improve overall pe;. cally acceptable for use in other hcensed TRIGA reactors, with formance of Rancho Seco with respect to safety. the provison that case-by case analyses discuss indiv dual re-actor operating conditons in applications for authonzation to NUREG-1287: TECHNICAL SPECIFICATIONS FCR PALO VERDE NUCLEAR GENERATING STATION. UNIT 3 Docket No. 50-use them. 530.(Anzona Nuclear Power Project)

• Drvison of Reactor NUREG 1284: PROGRAM PLAN FOR CORRECTION OF U.S. IN- Projects - IlUV,V & Special Projects (Dcst 870411). November STRUMENT DEGRADATION OR FAILURE IN THE UPPER 1987. 489pp. 8711180065. 43386.112 PLENUM TEST FACIUTY (UPTF)IN THE FEDERAL REPUBUC The Palo Verde. Unit 3 Technical Specifications were pre.

OF GERMANY. RHEE.G S; CHEN,Y.S; SHOTKIN.L.M. Dmsion pared by the U S Nuclear Regulatory Commisson to set forth of Reactor & Plant Systems (Post 870413), July 1987. 254pp- the hmits, operating conditions, and other requirements apphca-8708040274 42060:142- ble to a nuclear reactor facility as set forth in Se: tion 50 36 of This report documents the investigaton of the fadure or dag. 10 CFR Part 50 for the protecton of the health and safety of radaten of some of the advanced two-phase flow instruments the pubhc. supplied by the USNRC to the Upper Pienum Test Facility (UPTF), including Tie-Plate Drag Bod >es. Breakthrough Detec. NUPEG 1290: DIFFER lNG PROFESSIONAL OPINIONS 1987 tors, Loop Drag Disc paddles, Fluid Distobuton Gnd sensors. Special Review Panel

• NRC - No Deta+1ed Aff.haton Grven.

and Liquid Level Detector sensors. The exact causes for these November 1987.166pp. 8712180023. 43756 025. instrument degradatens or failures are not known, but several In mid 1987, the Executive Director for Operatons of the U S potential causes have been dent.fted For DBs and BTDs, the Nuclear Regulatory Commisson appointed a Special Review pnmary mechanism for the degradaten seems to be a leakage Panel to review the exist:ng NRC pokcy for express.ng d.ffenng in the inconel 600 strain gage encapsulaton and the subse. professonal views and to recommend possible improvements to quent burnout of the stra.n gage elements. For DDs the degra- the pokcy, if warranted. Through its own efforts and those of daten of fa< lure cause seems to be excessive loads The degra. three subpanets and three consultants, the Panel developed daten cause for most of the FDGs and LLDs seems to be recommendatons for changes and improvernents in frve major either steam / water eroson or mechanical abrason of sensor areas. This report presents those recommendations. along with tps, which are made of sapphire. However, some of the FDG a detailed explanaton of the Paners findings, copies of the re-tips were found to be cracked also. The corrective actons are ports of the subpanels and consuttants. and the resutts of a being directed toward finding out what are the pnmary causes survey of NRC ncn ciencal employees on the issue for the instrument degradaten or fadure and what should be NUREG 1291: BWR AND PWR OFF NORMAL EVENT DESCRIP-done to prevent these degradatons or failures from continumg TIONS.

• Dmson of Ucensee Performance & Quakty Evafuaten OCU'""9 (Post 870411) November 1987. 297pp 8712230297.

NUREG 1285: NRC STAFF EVALUATION OF THE GENERAL 43796 354. ELECTRIC COMPANY NUCLEAR REACTOR STUDY ("REED This document chrortcles a total of 87 reactcr event descnp-REPORT") VIRGIL #ON Ja BEVAN.R Office of Nuclear Reactor tons for use by operator hcensing examiners in the constructon Regulaton, Director (Post 870411). Juty 1987. 63pp of simulator scenanos Events are organized into four catego-8708060378. 42071'199. nes (1) boiling-water reactor abnormal events, (2) tohng-water in 1975, the General Electoc Company (GE) pubhshed a Nu- reactor emergency events; (3) pressunzed-water reactor abnor-clear Reactor Study, also referred to as "the Reed Report," an mal events; and (4) pressunzed-water reactor emergency internal product-improvement study. GE consdered the docu- events. Each event described indudes a cover sheet and a pro-ment "propnetary" and thus, under the regu!atons of the Nucle- gress.on of operator actons flow chart The cover sheet con-ar Regulatory Commisson (NRC), enempt from mandatory tains the followsng general parameters: initial plant state, se-oubhc disclosure. Nonethetess. members of the NRC stet re- quence init+ator, important plant parameters, major plant sys-viewed the documnnt in 1976 and determined that #1 did not tems affected, tolerance ranges, final plant state, and compe-ra se any sgnificant new safety issues The staff also reached tencies tested The progresson of operator actons flow chart the same concluson m subsequent rewews However, in re- depicts, in a flow chart manner, the representative sequencets) sponse to recent inquines about the report. the staff re-evaluat- of expected immed: ate and subsequent canddate actons, in-ed the Reed Report from a 1987 perspective TNs re-evalua- ciud<ng communicatons, that can be observed dunng the event. ton, documented in this stati *eport. Concluded that (1) there These desenptons are intended to provde examir ers w:th a re-are no issues ra sed in the Reed Report that support a need to habic, performance-based source of informaton frem whch to curtad the operaron of any GE boAng water reactor (BWR), (2) desegn simulator scenanos that will prov de a vahd test of the there are no new sa'ety issues raised in the Reed Report of candidates' abaty to safety and competently perform a9 h-which the staff was unaware and (3) although certain issues censed duties and responsbhties. addressed by the Reed Report are stall being stud ed by the NUREG 1293 DRFT FC: OUAUTY ASSURANCE GUIDANCE NRC and the inJustry, there is no basis for suspend:ng licensing aton of GE B AR plants wNe these issues are being FOR LOW LEVEL RADIOACTIVE WASTE DISPOSAL and FACIUTY. Draft For Comment. PITTIGUO.C L Dms.on of Low Level Waste Management & Decommesson;ng (Post 870413). NUREG 1286: SACETY EVALUATION REPORT RELATED TO November 1987.13pp 8712170240. 43753 037. THE RESTART OF RANCHO SECO NUCLEAR GENERATING This document provdes gu+ dance to an appbcant on deve:op-STATION. UNIT 1 FOLLOWING THE EVENT OF DECEMBER ment of a low-levet waste (LLW) disposal f acety in meeting the i 26.1985 Doc 41 No. 50 312 (Sacrarr. ento Municpal Utaty Dis- quahty control (OC) requirements of 10 CFR 6112 The CC re-tnct)

• Deson of Reactor Projects Ill.IV,V & Special Projects Quirements are the basis for develop ng of a quaktf assurance l

l (Post 870411). October 1987.199pp 8711030225 43256 001. (OA) program and for the gu dance provded here.n The cntena On December 26,1985, the Rancho Seco Nuclear Genertt- developed for this document are similar to the mtena deveh ing Staton e,penced a loss of dc power wrthin the integra% j oped for 10 CFR Part 50 Append!x B A!ttcugh Append;n 8 of control system whde the plant was at 76% power The ensuing 10 CFR Part 50 is not a regulatory requ>rement for an LLW d>s-reactor tr<p was foDowed by a raped overcoohng transent and posal f achtf , the cntena that were devebred for 10 CFR Part j automatic trut.aton of tne safety features actuaton system The 50 are basic to any OA program The document ucifcah es. I overcoohng transient continued unta integrated control system tabbshes OA gudance for the desgn constructon, and oper-l

20 Main Citations and Abstracts aton of those structures, systems, Components, as well as, for features and other plant systems; effects of extreme in plant en-site charactenzaton actmties necessary to moet the perdorm. vironments (such as high radiaton 6 elds and combustion ance objectwes of 10 CFR Part 61 and to limit exposure to or zones); and potentially d<sruptive phenomena (such as high-release of radioactivity. This documeit 's issued as a draft and pressure ejecton of the melt from the vessel). The proceedings comments are requested, Uter the cornnents are reviewed and represent the compilaton of a!! the papers presented at the analyzed, the document will oe revised. This draft was reviewed symposium. daho N onal E g ne ng la ra l NUREG/CP-0082 V01: PROCEEDINGS OF THE FOURTEENTH WATER REACTOR SAFETY INFORMATION MEETING. NUREG 1300: ENVIRONVENTAL STANDARD REV!EW PLAN WEISS.A J. Brookhaven Nabonal Laooratory.

• Office of Nucie.

FOR THE REVIEW OF A LICENSE APPLICATION FOR A ar Regulatory Research, Director (Post 860720). February 1987. LOW LEVEL RADIOACTIVE WASTE DISPOSAL FACILITY, 521pp. 8702270064. 39764.109. PANGBURN,G C. Office of Nuclear Matenal Safety & This six volume report contains 156 papers out of the 175 Safeguards.Dwector. Apnl 1987. 251pp. 8705120121. that were presented at the Fourteenth Water Reactor Safety in-40899.001. formaton Meeting held at the Natonal Bureau of Standards, The Environmental Standard Review Pfan (ESRP) (NUREG- Ga.thersburg, Mar >tand, dunng the week of October 27 31, 1300) provdes gu dance to staff reviewers in the Off ce of Nu- 1986. The papers are pnnted in the order of their presentaton clear Matenal Safety and Safeguards who perform envronmen- in each sesscn and descnbe progress and resutts of programs tal reviews of Apphcant's environmental reports prepared in in nuclear safety research conducted in this country and support of license appi;catons to construct and operate new abroad Foreign partic:pation in the meeting included thirty four low level rad oactrve waste disposal facilites The indiv dual different papers presented by researchers from Canada, ESRP's whech make up this document ident,ty the informaton Czechoslovakia, Finland, Germany, Italy. Japan, Mexico Spain, considered necessary to conduct the review, the purpose and Sweden, S*rtzerland and the United Kingdom The titles of the scope of the review, the analysis procedure and eva'uaton, the papers and the names of the authors have been updated and forrnal inputs made to the Environmenta! Statement and the ref- may d:ffer from those that appeared in the f.nal program of the erences considered appropnate for each review. By provding meetog this informaton to the staff, the ESRP is intended to assure quality and uniformity of approach in indivdual reviews as well NUREG/CP-0082 V02: PROCEEDINGS OF THE FOURTEENTH as comphance with the National Envronmental Pohey Act of WATER REACTOR SAFETY 6NFORMATION MEETING 1969. In add. ton, the ESRP will make informaton about the en. WEISS.A.J Brookhaven Natonal Laboratory.

• Office of Nucle-vvonmenta5 component of the lecensing process more readily ar Regulatory Research, Director (Post 860720) February 1987.

available and thereby improve the understandog of this process 444pp. 8703030039 39837.163 among the pubhc, States and Regonal Cor.1cacts and the regu. See NUREC/CP-0082,V01 abstract lated commumty NUREG/CP-0082 V03: PROCEEDINGS OF THE FOURTEENTH NUREG/CP-0054: PROCEEDtNGS OF THE WORKSHOP ON WATER REACTOR SAFETY INFORMATION MEETING SOIL STRUCTURE INTERACTION GRAVES.H L; PHILIPPA- WEISS.A.J. Brookhaven National Laboratory.

• Oftce of Nucle-COPOULO Brookhaven National Laboratory. December 1986. ar Regu!atory Research, Director (Post 660720). February 1987.

423pp 8703090227. BNL NUREG 52011. 39932 006 433pp. 87030308?0. 39867 011. The Workshop on Sod-Structure interaction provded an er. See NUREG/CP 0082,V01 abstract. change of informaton between regulators, practitioners and re-searchers for the purpose of examening SSI bcensing critena in NUREG/CP-0082 V04: PROCEEDINGS OF THE FOURTEENTH the hght of recent arrytcat and expenmental development. WATER REACTOR SAFETY INmR M ATION MEETING These proceed,ngs cor.tain the papers presented ty paneksts WEISS.A J. Brookhaven Natonal laboratory

• Office of Nucle.

and summanes of the sessons along with recommordatens of ar Regutatory Research. Director (Post 060720) February 1987. the panel members for each sessen Technical areas covered 528pp. 8702270057 39760 303 See NUREG/CP.0082,V01 abstract by the panels were (1) debton of free feld moton, (2) ground moton input needed for site specific SSI analysis, (3) SSI meth. NUREG/CP-0082 V05: PROCEEDINGS OF THE FOURTEENTH odology, and (4) esperence and expenmental observaton The WATER REACTOR SAFETY INFORMATION MEETlNG summanes were derrved to dentJy areas in the hcenseng enteria WEISS,A J Brookhaven Natonal Laboratory

• Off.ce of Nucle-wh*ch could be changed to improve the hcens.ng process ar Regulatory Research, Director (Post 860720) February 1987 NUREG/CP-0078: PROCEEDINGS OF THE SYMPOS!UM ON 594pp 8702270056 39765 270 CHEMICAL PHENOVENA ASSOCIATED WITH RAD;OACTiv. See NUREG/CP-0082,V01 abstract ITY RELEASES DURING SEVERE NUCLEAR PLANT ACCI-NUREG/CP-0082 V06: PROCEED!NGS OF THE FOURTEENTH DENTS NIEMCZYK S J American Chemical Society June WATER REACTOR SAFETY INFORMATION MEETING 1987. 710pp. 8706250118 41465 079 WEISS.A J Brookhaven Natonal Lateratory
• Off.ce of Nucle.

The Symposium on Chemmal Phenomena Associated *"th at Regu!atory Research D, rector (Post 660720) February 1987 Radcactroty Releases Dunng Severe Nuclear Plant Accdents 424pp 8703030035 39836 099 was held dunng the Amencan Chemical Soc >ety Natonal Meet- See NUREG/CP 0082,v01 abstract tog in Anaheim, Cakfornea, September 9-12. 1986 The ourpose of the sympossum was to provide a forum for d;scuss.on of NUREG/CP-0084: PROCEEDtNGS OF THE WORKSHOP ON A chem. cal processes and phenomena potant a!!y occurnng dunng CONTAINVENT PERFORMANCE DES GN OBJECTIVE MAY severe nuclear reactor accdents The symposium ocluded an 1213.1986, HARPERS FERRY, WEST VIRGINTA

• Brockhaven ovennew sessco desgned to he!p place chemical issues in Natonal Laboratory November 1986 77pp 8704080102 BNL-contert en a severe accdent perspect;ve, as well as su ses- NUREG-52044 40447 026 sons devoted to a vanety of severe accedert chemistry topics The "Conta-nment Performance Desgn Otsective Wor 6 shop" Those top <cs included releases of rad oactrue and nonradcac. was des,gned to obtain a broad range of kno*'edgeable views trve spec es from core matena's in the reactor vessel, transport concerning the issues in the developrnent and implementaten and behavor of those species in the reactof Coolant system, of a conta nment pericfmance desgn obt ective (CPDO) It was transport and behacor of released specios within the conta.n. a discusson workshop, involving invrted esperts representing a ment, releases dunng core concrete interactons as n' ell as broad rarge of cewpo.nts, and drawn from utat<s. reactor ven-other aspects of such interactons, effects of engineered safety dors, architect engrocers. unrversit'es, natonal laboratones. and

Main Citations and Abstracts 21 pubhc interest groups. The participants were requested to NUREG/CP-0088: TPANSACTIONS CF THE 9TH INTERNATION-review background informaSon concerning the safety goats and AL CONFERENCE ON STRUCTURAL MECHANICS IN REAC-their status. a desenpton of CPDO options selected for evalu+ TOR TECHNOLOGY. Panel Sesson JK: Structural And Mechans-ton, an outhne of an implementation approach and recognized cal Engineenng Research At The US Nuclear Regulatory Com-issues of CPDO structure and implementaton. The general ob- mission. BROWZINS S. Dvison of Eng'neenng (Post 870413) jective of tne workshop was to generate informaton that could July 1987. 265pp. 87072'0681. 41830 271. be used in the NRC's study and decision process concerning These transactions of the JK panel sestion include preponts the formulatx>n of a conta,nment performance design obtective of papers which are lated in the Second Announcement for the The participants' ve*s were obtained on spec fic CPDO optons 9th International Conference on Structural Mechanics in Reac-and issues that were presented to the Workshop and new ones tor Technology. These papers represent the body of the JK that emerged dunng the discusson An attempt was a!so made panel session. "Structural and Mechanical Engineenng Re-to dentdy areas of consensus emerg:ng from the discusson. search at the U S. Nuclear Regulatory Commisson." NUREG/CP-0085: MEET'NG WITH STATES ON THE LOW- NUREG/CP-0090: TR ANSACTIC NS OF THE FIFTEENTH LEVEL RADIOACTIVE WASTE POLICY AMENDMENTS ACT WATER REACTOR S/FETY INFORMATION MEETING. (LLRvvPAA) OF 1985 MAUPIN.C ; SCHNEIDER K. Assistant Di- WEISS A J. Office of Nucicar Regulatory Fw,earch, Director rector for State Agreemerts Programs February 1987.168pp (rost 860720). October 1987. 270pp 8710290263. 43215:350. 8703260292. 40238.111. This report contains summanes of papers on reactor safety The purpose of this meeting was to dtscuss w'th selected research to be presented at tM 15th Water Reactor Safety In-State officials NRC respons;bdities under the Low-Level Rado- formaton Meeting held at the Natonal Bureau of Standards in actue Waste Pohey Amendments Act, including the approach Gaithersburg, Marytond, October 26-29. 1987. The summares beog taken and progress being made in fulfung NRC responsi- briefly descnbe the programs and results of nuclear safety re-bittes The NRC staff objective was to obtain State veas on search sponsored by the Office of Nuclear Regulatory Re-technical and institutional issues assocaated with NRC and State search. USNRC. Summanes of invited papers concerning nucle-implementat2on of the Act and to determine any add tonal areas at safety issues are included from the Office of Nuclear Regula. m which NRC Chn be of assistance in the development of dis. tory Research, USNRC, in add. ton to summaros of invited posal fachties We beneve this objective was accomphshed papers that cover the highhghts of reactor safety research con-The transcr pt of the meeting is being pubbshed at this time to ducted by the Department of Energy (DOE), the electnc utilstres make avadable informaton d>scussed at the meeting to those through the Electnc Power Research Institute (EPRI), the nucle-endmders and groups that have responsibskties under the ar industry, and the research of government and industry in LLR APAA for developing disposal capacity and for regutating Europe and Japan. The summanes have been compiled in one low level waste d.spost sites report to provde a bas;s for mean,ngful d scussion and informa-tion exchange durirq the course of the meeting, and are given NUREG/CP-0086 VO1: PROCEEDINGS OF THE 19TH DCE/NRC in the order of their presentat on in each sessort NUCLEAR air CLEAN!NG CONFERENCE Held in Seattle. Washington. August 18 21,1986 FIRST.M W Harvard NUREG/CR 2000 V05N12: LICENSEE EVENT REPORT (LER) School of Pubhc Hea:th. Boston. MA May 1987. 644pp. CCVPILATION For Month Of December 1986

• Oak Rdge Na-8706250268 CONF-860820. 41463 073 tional Laboratory .'a nua3 1987,133pp. 8702170056 ORNL/

This document contains the papers and the assoc:at d dis. NSIC-200 39657.009 cussons of the 19th DOE /NRC Nuclear Air Cleaning Confer. This monthly report conta.ns Licensee Eveat Report (LER) ence Sessions were devoted to (1) tre, esploson and accdent operatonal informaton that was processed into the LER data ana'ysis. (2) adsorpton and odene retenton. (3) faters and f ater fde of the Nuclear Safety Information Center (NSIC) dureg the testing. (4) standards and regulaton, (5) treatment of radon, one month penod ident.f,ed on the cover cf the document The krypton, tntium and carbon 14. (6) ventdaton and a,r cleaning LERs. from which this informaton is derrved, are submitted to in reactor operahrns, (7) d.soNer off-gas cleantry (8) adsorber the Nuclear Regulatory Commisson thRC) by nuclear power f'res. (9) nuclear grade caw testing. (10) samphng and mone- plant ficensees in accordance w th federal regulatons Proce-toong. and (11) f,end test esperence dures for LER reporting for reosons to tnose events occurnng pror to '984 are descrted in NRC Regulatory Gude 116 and NUREG/CP-0086 V02: PROCEED.NGS OF THE 19TH DOE /NRC NUR EG-1061, "Instructions for Preparaton of Data Entry NUCLE AR A!R CLE AN!NG CONF ERENCE Held in Sheets for L>censee Event Reports " For those events occurnng Seattle, Washington, August 18-21,1986 FIRST.M W Ha'vard on and after January 1,1984. LERs are being submitted in ac-School of Pubhc Hea'th. Boston. VA May 1987 630pp cordance *,th the revised rule contained in Tit;e 10 Part 50 73 8706240014 CONF-860820 41442 037 ef the Code of Federal Regulations (10 CFR 50 73 Licensce See NUREG/CP-0086.V01 abstract Event Report System) which was pubtshed in the Federal Reg-rster (Voi 48. No.144) on Ju!y 26,1983 NUREG 1022. "Ls NUREG/CP-0087: SUVVARY REPORT OF THE SWPOSiUV censee Event Report System Descnpton of Systems and ON SE!$WC AND GEOLOGIC SITING CRITERIA FOR NUCLE- Guidebt'es for Report ng." provdes supportng gudance and in-AR PC'AER PLANTS CUVV.NGS.G E ; BERNREUTER D L-, formaton on the rev' sed LER rule The LER summanes in this MURR AY,R Ca et af Lawrence Lrvermore Natonal Laooratory repod are arranged a'pt'abetica9y by facMy name and ' hen June 1987. 490p 8706300026 UCiD-21039 41515 242 chronodg.cauy by event date for each facihty Component. This is a summary report of the Symposum on Se:smee and system, keywort and coreponent vendor indexes fonom the Geologic S t ng Cntena for Nuc! ear Power Plants held in Rock- summa'+$ Vendors are those dent. fed by the utd4 when the vme. Maryiand. on October 7 9. 1956 The purpcse of the sym- LER form is inet.aled the keywords for the compor,ent. system, postum nas to provde a forum to dehneate and enamne the and germral keyword indenes are assigned by the computer issues relating to a proposed renson to ApMnda A cf 10 CFR using correlaten tables from the Se%ence Cod.ng and Search Part 100 Apperda A to Pa1100 is the bas < U S Nucles, R"9- System u!atory Commisson regJaton concern,ng se,smic s,trng crrtena for nuclear power plaats Some of the issues d scussed at the NUREG/CR 2000 V06 N1: LfCENSEE EVENT REPORT (LER) symposaum puta ned to mcorporat ng cu"ent prctaba st>c con- CCVPtLATION For Vonth Of Ja%ary 1987

• Oak Roge Na-cepts into the rnu'at on. decoupi ng tre CBE and SSE and re- tonal Laboratory Vrch 1987 117pp 8703250557 ORNL /

v+ng tne def,ntton of basic concepts and parameters The NSIC 200 43234 330 entent of any rev+cn es yet to be dotermoed See NUREG/CR 200SV05 N12 abstract

8 22 M"in Cit:tions and Abstracts NUREG/CR 2000 V06 N2: UCENSEE EVENT REPORT (LER) Benchmarking, Source Term Code Package Venfcaton and COMPILATION For Month Of February 1987.

• Oak Ridge Na- Benchmarking. Uncertanty Analysis of the Source Term; Stress tonal Laboratory. March 1987.1230p. 8704270093. ORNL/ Corrosaon Craciung of PWR S:eam Generator Tubing, Sod-NSC200. 40678.297. Structure Interacbon Evaluatort and Structural Benchmarks, i See NUREG/CR 2000,V05,N12 abstract. Identheaton of Age Related Failure Modes; Apphcaton of H A Resuus to Suppod ResoMon of Genenc Safeh NUPiEG/CR 2000 V06 N3: UCENSEE EVENT REPORT (LER) Issues invotving Human Performance, Protectye Acton Deci-COMPILATION For Month Of March 1987.
• Oak R4ge Naton-al La')ocatory. Aprd 1987.107pp 8705190343. ORNL/NSIC. senmalung, Rebasehneng of Risk for Zon, Containment Per.

200.40975 324. 3

!               See NUREG/CR-2000,V05,N12 abstract.                                                      Re a ch.

NUREG/CR 2000 V06 N4: UCENSEE EVENT REPO3T (LER) NUREG/CR 2331 V06 N3: SAFETY RESEARCH PROGRAMS j i SPONSORED BY OFFICE OF NUCLEAR REGULATORY COMPILATION For Month Of Aprd 1987.

• Oak Ridge National l Laboratory. May 1987,145pp. 8706230059. ORNL/NSIC-200. RESEARCH.Ouarterly Progress Report, July-September 1986.

4142t297 WEISSAJ. Brookhaven Nabonal Laboratory. March 1987. See NUREG/CR-2000,V05,N12 abstract. 114pp.8706120037. BNL-NUREG-51454. 41187.087. See NUREG/CR 2331,V06,N02 abstract. NUREG/CR 2000 V06 N5: LICENSEE EVENT REPORT (LER) COMPILATION For Month Of May 1987.

• Oak R49e Natonal NUREG/CR 2331 V06 N4: SAFETY RESEARCH PROGRAMS Laboratory. June 1987.108pp. 8707090381. ORNL/NSC200. SPONSORED BY OFFICE OF NUCLEAR REGULATORY 4

41633 074. RESEARCH Ouarterty Progress Report. October December See NUREG/CR 2000,V05,N12 abstract 1986. WEISS.AJ. Brookhaven Nabonal Laboratory. May 1987. 75pp.8710080214. BNL-NUREG-51454. 42990.350. } NUREG/CR 2000 V06 N6: LICENSEE EVENT REPORT (LER) Ttws progress report wdl desenbe current activrbes and techru-  ! COMPILATION For Month Of June 1987.

• Oak Roge Nabonal cat progress m the programs at Brookhaven Natonal Laboratory I Ltboratory. July 1987,138pp. 8708120301. ORNLINSC200. sponsored by the Drvson of Acc4ent Evaluaton, Drosaon of 42128:253. Eng,neenng Technology, and Dmsson of Risk Analysis and Op-See NUREG/CR-2000,V05,N12 abstract. eratons of the U.S. Nuclear Regulatoy Commisson, Offee of NUREG/CR-2000 V06 N7: LICENSEE EVENT REPORT (LEP) Nuclear Regulatory Research. The projects reported are the foi-COMPILATON.For Month Of July 1987.
• Oak R4ga Natonal loweg: Advanced Reactor Review, Thermal-Hydrauhc Reactor Laboratory. August 1987.151pp. 8709150268. ORNL/NSC Safety Expenments. Therrnodynamic Core-Concrete interacton 200. 42679 007 Expenments and Analysis, Plant Anatyrer, Assessment and Ap-1' See NUREG/CR 2000,V05.N12 abstract. phcateon of TRAC-BF1 Code, Code Maintenance (RAMONA. ,

3S), MELCOR Venficaton and Benchmarking. Source Term ( NUREG/CR 2000 V06 N8: LICEN5EE EVENT REPORT (LER) Code Package Venfication and Benchmarking, Uncertainty Anal- ! COMPILATION For Month Of August 1987.

• Oak R49e Naton- ysis of the Source Term (OUASAR), Sod Structure interacton al Laboratory. September 1987. I20pp. 8710080189. ORNL/ l Evaluaton and Structural Benchmarks, Charactonraton and De- '

NSIC 200. 42987.075. tecten of Age-Related Fadures of Selected Components and , See NUREG/CR 2000.V05.N12 abstract Systems With Considerabon for Aging /Jessmic Interactons, NUMEG/CR 2000 V06 N9; LICENSEE EVENT REPORT (LER) Protectrve Achon Decisionmalung, Risk and Risk Reducten fnt  ! COMPILATON For Month Of September 1987.

• Oak R4ge Zon. and Operational Safety Rehability Research. -

Natonal Laboratory. October 1987. 81pp 8711250072. ORNL/ NUREG/CR 2331 V07 N1: SAFETY RESEARCH PROGRAMS l q NSC200. 43450 016-SPONSORED BY OFFICE OF NUCLEAR REGULATORY

See NUREG/CR 2000,V05.N12 abstract.

RESEARCH.Ouarterty Progress Report January-March 1987. WEISS.A.J. Brookhaven Natonal Laboratory. Jufy 1987. 75pp. ( ) NUREG/CR 2000 06N10; LICENSEE EVENT REPORT (LER) 4 COMPILATON For Month Of October 1987.

• Oak R49e Na. 8711100129. BNL.NUREG-51454. 43338 265. ,

j tenul Laboratory. November 1987. 74pp. 8712230196. ORNL/ See NUREG/CR 2331,V06,N04 abstract.

;     NSC200. 43796 28a d

See NUPEG/CR-2000,V05,N12 abstract. NUREG/CR 2452: RISK METHODOLOGY FOR GEOLOGIC DIS-POSAL OF RADIOACTIVE WASTE. Fmal Report. NUREG/CR 2000 V06N11: LICENSEE EVENT REPORT (LER) CRANWELLR M.; CAMPBELL,J E4 HELTON.J C.: et al. Sandia COMPILATON For Month Of November 1987.

• Oak R49e Na. Natonal Laboratones August 1987, 105pp. 8710010316.

bonal Laboratory. December 1987.66pp 8801110221 ORNL/ SAND 81-2573 42883.078. - j NSC200. 43975.230. TMs report contams the descnpbon of a nsk assessment ( See NUREG/CR 2000,V05.N12 abstract methodology developed for the US Nuclear Regulatory Commis- t i

 '                                                                                                     son for use in assessang the nsk from the disposal of radmac.

NUREG/CR 2331 V06 N2: SAFETY RESEARCH PROGRAMS trve wastes in deep geolog+c formatons. This methodology curk

;     SPONSORED BY OFFICE OF NUCLEAR REGULATORY                                                       sists of (1) techniques for selectog and screenang scenaros, (2)

RESEARCH Ouarterty Progress Report.Apol-June 1986- models for use m samutatog the physical processes and esb- I l WEISS.A J Brookhaven Nabonal Laboratory. November 1986- matog the consequences associated with the occurrence of 4 107pp. 87040e0236. BNL-NUREG 51454. 40445.157-these scenares, (3) probabehstic and statisbcal techniques for

This progress report wdl descr,be cunent actrebes and techr"-

use m risk estimates and sensitrvity and uncetanty analysis,

 ,   cal progress m the programs at Brookhaven National Laboratory                                    and (4) a procedure for uthng these rnodels and techniques to                                     i; sponsored by the Omson of Acc dent Evaluaton, Omson of assess comphance orth regulatory standards The use of this Engmeenng Technology, and Dmsson of RP.k Ana?yses & Oper*

methodology is demonstrated m thes report by appiyeg at m the 1 atons of the U S. Nuclear Regulatory Comtreon. Office of Nu-analysis of a hypothet> cal disposal s4te contairwng a bedded-satt , clear Regulatory Research. The protectt ter rted are the fol* format,on as the host medtum for the waste. ioeng: High Temperature Reactor Research, SSC Code im- i j provements Thermalmydrauhc Reactor Safety Expenments. NUREG/CR 2478 V03: A STUDY OF TRENCH COVERS TO min. i Therrnc4ynamic CoreConcrete Interaction Espenments and IMl2E INFILTRATON AT WASTE DISPOSAL SITES Feal Rept. Ana!ys<s, Piant Analyzer, Code Assessment and Apphcaton, CARTWRIGHT.K.; LARSON,T H ; HERIOG.D L.; et al. litmors. , Code Maintenance (RAMONA 35). MELCOR Venhcaton and State r>f February 1987.139pp 8703120215. 39987.171.  ! I i

    , . - . . .     -s  #   . -                                gs .e.,..g.rw
                                ,i.w__.g .-3-n w-- .i. v                 -. , - . -       -- e  y       ye.ga q wpgm aw. e ws 9 w 1.w- M -.-v--- - -
                                                                                                                                                         ---+-C   h- --V-T-         7uw-- w w'w.r.-

Maln Citations and Abstracts 23 We have oves %ated methods to hmst infiltration through formed with water atop the debns wNie the second had no trench covers by rev:ew,ng current practces, testing selected water added. The results show that lo*-temperature core debns geologic matenals, smutating selected cover designs, and de- wdl erode either basalt or kmestone-common sand concretes. sgning, constructing, and monitonng four field-scate expenmen. Downward eroson rates of 3 to 4 cm/hr were recorded for both tal covers. Of the many des >gns considered, we conclude that concrete types The hmestone concrete produced a crust layer multdayered soil covers are superor to sing'e-layered cove's. within the debris bed that was effectrve in prevent,ng the down. Laboratory and computer simuiations ind'cate that a wick effect ward intrusion of water. The basaft concrete crust was formed can be estabbshed by placing a f ne-grained layer over a above the debns and conssted of numerous, convoluted, tNn coarse-grained layer, thereby delayeg and possibly reducing layers Carbon doxde and water release from the decomposs-moisture mfdtraton through the entre cover. Field expenments ton of concrete were partia!iy reduced by the metalhc debns to edicate that the wick effect does occur under certain circum- yield carbon monoude and hydrogen, respectrvely. The overly-stances, but a potentially more important feature of the layered ing water pool did not effect the reducton reactons cover desgn is the ability of the coarse-grained layer to remove rrosture from the system thre.sgh drain tJes. NUREG/CR 3145 V05: GEOPHYSICAL INVESTIGATIONS OF THE WESTERN OHIO-INDIAN A REGION Final Report. October NUREG/CR 2850 V05: POPULATION DOSE COMMITMENTS 1981 - September 1986. CHRISTENSEN.0 ; POLLACK,H N ; DUE TO RADIOACTIVE RELEASES FROM NUCLEAR POWER LAY,T ; et al M>cNgan, Univ. of Ann Arbor, MI March 1987. PLANT SITES IN 19B3. BAKER.D A.; PELOQUIN.R A Battelle 333pp 870731004). 41997.018. Memonal lnst:tute. Pacibc Northwest Laboratones. Apnl 1987. Earthquake actrvity in the Western Ohio-Indiana reg on was 141pp. 8704280126. PNL 4221. 40713 082. monitored with a precison seismograph network cons st ng of Populaton radaton dose commetments have been estimated nine statens located in west-central ONo and four stations lo-from reported rad onuctde releases from commercial power re' cated in Indana Frve local and near-regonal earthquakes were actors operat ng dunng 1983 Fi'ty year dose comm tments from recorded dunng the fiscal 1985-86 report penod, ranging in a one-year esposure were calcu'ated from both hqu d and at- magnitude from 0 5 to 5 0m(b) The two largest events (January mosphenc releases for four populaton groups Onfant, cnid. 31,1986 near Cleveland, ONo. 5 Om(b). and July 12,1986 near teen ager and aduft; residing between 2 and 80 km from each St Marys. Ohio. 4 Sm(b)) were fett with minor damage reported of 52 sites TNs report tabutates the results of these calcula- in each case. Focal mechanisms and isoseismal maps for these tons, showing the dose commitments for both liqu.d and air- events are included in th s report. These events are the largest borne pathways for each age g*oup and organ. Also included to have occun- d in ONo since the events of March 2 and for each of the sates is a hstogram show,ng the fracton of the March 9.1937 (magnitude - 4 5 and 4 9. respectrvety). The re-total populaton witNn 2 to 80 km around each Ste receiving ma,nin( three earthqual as all occurred an Oho, north of the vanous average doss commitments from the arborne pathways. array. A total of 42 loca! and near-regonal events, eleven of The total dose commitments (from both liqud and airbome Nch were fem, have now been recorded by the ONo-Indiana pathways) for each site ranged from a h+gh of 45 person-rem to array since its initiation in 1976. Teleseismic P-wave amval and a low of 0 002 person-rem for the sites w,th plants operating resdual tables were updated to include newty acqvwed data throughout the year with an arithmetic mean of 3 person-rem- The results are similar to those in prevous years The local ve-The total populaton dose for all sites was estir9ated at 170 icoty structure was invest > gated using data acqueed dunng a re-person-rem for the 100 milhon people consdered at nsk. The fracton expenment in the summer of 1984, and travel times of site average indondual dose commitment from all pathways local anc near-regtonal earthquakes. ranged from a low of 1 x 10(-6) mrem to a h*gh of 0 06 mrem No attempt was made in tNs study to determine the maximum NUREG/CR 3228 V05: STRUCTURAL INTEGRITY OF WATER dose Commitment recerved by any one indrydual from the ra- REACTOR PRESSURE BOUNDARY COMPONENTS Annual d'onucides released at any of the s;tes Report For 1986 LOSS.F.J Matenals Engineenng Associates. NUREG/CR 2907 V05: RADIOACTIVE MATERIALS RELEASED inc. July 1987. 237pp 8708110406. MEA 2207. 42109.337. FROM NUCLEAR POWER PLANTS Annual Report 1984 TNs program is being conducted for the NRC to provde ana-TICHLER.J : NORDEN K ; CONGEMI.J Brookhaven Natonal  % cal and unpenmental methods and data that are necessary to Labc<ator[ August 1987. 256pp 8708260142 BNL NUREG. ensure the structurat safety and rehabd ty of pressure boundary 51581.42332 001. components in U S commercial. Ight water reactor power sys-Releases of radcactrve matena's in a rbome and hqud et. tems. Emphasis is placed on characten2aten of matenal prop-fluents from comme <cial hght water reactors dunng 1984 have ertes pedormance in a nuclear environment for the appicaton been compiled and reported Data on sohd *aste shipments as to plant 4fe entenson and mitgaton of the consequences of well as selected operating mformaton have been included Th s postulated accdent scenanos Current work is organized into repor't suppiements earher annual reports issued by the forme, three major tasks: (1) fracture mechanics invest.gatons. (2) en-Atome Energy Comm:ssaon and the Nuclear Regulatory Com. vironmentany ass.sted crack growth in Ngh temperature, pomary misson. The 1984 release data are summanzed in tabula' form reactor mater, and (3) radiaton senstrvity and post.rradiaton Data covenng spectic radonuc! des are summanzed propert es recovery Research progress in these three tasks for 1986 is summanzed in tNs report. NUREG/CR 3024: SUSTA NED CONCRETE ATTACK BY LOW. TEVPERATURE. FRAGMENTED CORE DEBRIS NUREG/CR 3231: PIPE TO-PIPE IMPACT PROGRAM, TARBELL,W W.; BRADLEY.D R.; BLOSE.R E ; et al Sand a Na- AL2HEIVER.) M ; B AMPTON.M C ; FR4 EY.J R , et al Battel le Donal Laboratores Ju!y 1987 247pp 8709090444. SAND 82- Memonal Inst, tate. Pacific Northwest Laboratores May 1987. 2476 42565 321. 100pp 8706240152 PNL 5779 41452 059 Four expenments were performed to study the interactons The obtective cf this research was to determine the extent of between low-temperature core debns and concretes typical of damage that occurs when two pipes esperence an impact reactor structures The tests addressed accident setuatons event due to one wNpping aga,nst the other The research was where the core debns is at elevated temperature. but not conducted through expenr'. ental and anatytical approaches. The molten. Concrete cruobles were formed in rght-ctcular cyhn- fc<mer requeed the devoopment of a spectahzed impact ma-ders *<th 45 kg of steel spheres (3-mm diameter) as the debris cNne that could acceierate a wNppeng per.e alth suffoent samulant. The debns was heated by an inductive power suppty energy to cause faVe of a target pipe that was heated and to nomenal temperatures of 1473 K to 1673 K Two tests were pressunzed to Pressunzed Water Reactor (PWR) conditions periorrred on each of two concrete types using either basatt or Damage was measured in terms of crusNng. tending and fa0 lemestone aggregate For each cracrete, one test was per- ute The results of the tests permitted the correlaton between

24 Main Citations and Abstracts pipes of a certain 'ize and the damage they could cause when The meta 3urgicat irradiaton expenment at the Oak Ridge Re-impactsng with a certain amount of known energy. These resutts search Reactor Pouwde Facihty (ORR PSF) is one of the senes were used to evaluate the pipe wh

neenng Development Labora. data tases that are used to predct the irradiaton embnttlement tory May 1987. 86pp 8706160066 HEDL TME 85-3. and fracture toughness of possure vessel and support structure 41310 233. stecis The p<edicton methodology includes procedures for neo-This NRC physscs-dos, metry compendeum (Sectons 10 tron phys,cs calculatons, dosemetry ard spectrum adpstment through 4 0) is a cof aton of informaton and data developed methods, metallurgical tests, and damage correlations. The from avadable research and commercial leght water reactor benchmark empenments serve to validate, improve, and stand-vessel survedlance program (RVSP) documents and related sur- ard4te tnese procedures The results of this program are imple, vemance capsule reports The Secton 4 0 data represents the mented in a set of ASTM Standards on pressure vessel surveil-results of the HEDL least-squares FERRET. SAND ll Code re. lance procedures These, in turn, may be used as guades for the evaluaton of exposure units and values for 47 PWR and B AR nuclear industry and for the Nuclear Regulatory Commess4on survedlance capsules Using a consastent set of audary data (NRC) To serve as a tenchmark, a very careful characteri2a-and dosimetry-adpsted reactor physacs results, the revised t.on of the OhR PSF esperiment is necessary, both in terms of fluence values for E greater than 1 MeV averaged 25% h.gher neutron flus fluence spectra and of metallurgical tests results. than the onginatty reported vabes The range of fluence values Stabstcah determired uncerta.nties must be grven in terms of (new/old) was from a low of 0 80 to a hgh of 2 38 These vanances and covanances to make compansons between pre. HEDL- denved FERRET SAND 11 exposure parameter va:ues d ctons and empenmental results meansngful. Detaded desenp-are being used for NRC-supported HEDL and other PAR and tons of the PSF metallurgy program and its results are report-BAR trend curve data development and testrng studes. which ed suppor1 Revison 2 of Regulatory Gsde 199. These trerd curves are used by the uttties and by the NRC to account fo, NUREG/CR44 i; V02: CONTAINMENT INTEGRITY neutron rataton damage in setting pressure /temwatura hmits. PROGRAM Proyess Report.Apnl 1983 -December 1964. in ana'yzing fractures. and in pred.cting neutronanduced BLEJWAS.T E . HOR $CHEL.D S Sandta Natonal Laboratores. changes in reactor PV steel fracture taughness and errte.tre. Deceder IE S9pp 8702060133 SAND 831482. 39527 249. ment durng the vessers service hfe The status of the develop. TNs report conta ns a descnpton of work performed ber*een ment and appbcation of new advancements in LAR reactor sur. Apol 1983 and December 1984 under the Containrnent integnty vedlance programs is discussed. such as canty physics dosrme. Prog am The program is one of three at Sandia Naticesi Lab-try for improving the rebatdty of current and end-of hfe (EOL) oratones in the general area of contamment integnty. The over. predictons on the metalurg cal condMons of pressure vesseis a'! otect:ye of the three programs as the quahfication of meth-and the.r support structures od3 for rehaUy predicting the capatety of contarnment struc-tur es far Lght water reactor nuclear power plants to function NUREG/CR 3320 V03: LWR PAESSURE VdSSEL SURVE ll- under load ngs caused by severe accidents and entreme envi. LANCE DOSMETRY IVPROVEVENT PROGRAM PSF Phys <s. ronrr.ent s in the s,4ect program, mode s of entire contain-Dosimetry Program MCELROY W N , GOLD.R HaMW f ot rrents are tested for loa %ngs beyond the design batss Erpen-rwenng De velopment L aboratFy October 1937. 323pp ments compie'ed during the repceting perod include a seres of 87*0230376 HEDL TME 87 3 43145 273 ins ernal pressure tests of 1/32 and 1/8 size models of hybnd Main Citations and Abstracts 25 steel conta1nments. Compansons with pretest ana!yses are de- or indirectly to occupational exposure reducton. This report scnbed contains 252 "*es - d both author and subject indices. NUREG/CR 3444 V04: THE IMPACT OF LWR DECONTAMINA- NUREG/CR 349 .0 ON OF FAILURE IMPORTANCE TIONS ON SOLIDIFICATION. WASTE DISPOSAL.AND ASSOCl- MEASURES F(.,

• ASI EVENTS AND PLANT SYSTEMS IN ATED OCCUPATIONAL EXPOSURE Annual Repor1, Fiscal Year NUCLEAR POWEh 7 ANTS. WHEELER,T.A ; SPULAK.R.G.

1986 PICIULO.P.L ; ADAMSlW. Brookhaven National Labora- Sand.a National ' xatones December 1987. 450pp. tory. October 1986. 48pp. 8704130283. BNL NUREG-51699 8801070265 SAND 83 0329. C)941:292. 40495 328. This is a report on the project "Determinaten of Event Se-Leach tests were intated in order to determine if organic rea- quences Contnbuting to Overall Frequer cy of Core Me:t." It is gents released from different size waste forms can be repre- an analysis of 13 eusting probabihstic nsk assessment (PRAs) sented by a d.ffusion controlled mechanism. Data for the re. covenng 15 power plants. The object of this project rs to ident.fy lease of EDTA from cement forms showed that the CFR from the plant systems and system components which Contribute the 5 cm diameter 10 cm long forms were smaller than that most to the overail core mett frequency and to some measure from the 15 cm diameter x 15 cm diameter forms This would of nsk The results of this anahsis are grouped into two major not be expected if the predominant mechanism of release was types of commercial reactors, bo.hng water reactors (BWRs), diffuson Specimens conta>ning Co-60 sp ked caton exchange and pressunzed water reactors (PWAS). Within each type of re-resins scicf<ed in cement were leached w,th deonized water actor, plants are grouped by manufacturer. The results are fest and leachants contanng e<ther formate or pecohnate Data from anatyred on a plant-by-plant basis Then, the results are dis-the first f;0 days of teaching in6cate that the releases of Co-60 cussed for all plants wrthen each plant manufacturer type to we% umar with deonized water and formate as leachants Pec- study any interrelatonships of common trends whsch might extSt ohnc ac.c present in the teachant caused an acceieraten of the amoN plants budt by the same manufacturer. The results are release of Co-60. then dtscussed among an PWRs and all BWRs NUREG/CR 3468: HYDROGEN AIR STEAM FLAMMABILITY NUREG/CR 3620 SO2: INTRUDER DOSE PATHWAY ANALYSIS LIMITS AND COMBUSTION CHARACTERISTICS IN THE FITS FOR THE ONSITE DISPOSAL OF RADIOACTIVE WASTES The VESSEL. MARSHALL.B W Sandia Natonal Laboratones De- ONSITE / M AXII Computer Program KENNEDY W Ea cember 1986 149pp 8704080363 SAND 84-0383 40445 008. PELOOUIN.R A ; NAPIER.B A ; et al Battene Memonal Institute. Espenmenta4y observed flamntabody hmits of Pacific N orthwest Laboratones. February 1987. 453pp hydrogen a+r steam matures in both turbulent and queescent en- 8703120220 PNL-4054 39986 078. veronments were measured and a correlaton developed that de- The document entitled "Intruder Dose Pathway Analys s of scnbes the three component fiammabihty hmrt The combuston the Ons:te Disposal of Radioactive Wastes The ONSITE/ pressure data measured fo* the hydrogen a:r steam tests indi. MAXII Computer Program" (1984) by Napier et al summanzes cate that the add: ton of steam reduces the normal zed peak our init:a! efforts to develop human intruson scenarcs and a combuston pressure (Pman/Po) as compved to equivalent mod f.ed verson of the MAXI computer program for potential hydrogen arr burns Turbulence *cs found to affect the extent use by the NRC in reviewing appbcatons for onsite rasoactive of combuston and other combuston charactenstics of the lean waste disposal Supplement 1 of NUREG/CR 3620 (1986) by hydrogen burns O e, less than or equal to 10% hydrogen by Kennedy et al summanzed mod.ficatons and improvements to volume) where buoyancy gove'ns flame propagaton The en- the ONSITE/ MAX 11 software package This document summa-penmentatty measured pressure decays were used to infer the nzes a mod f ed verson of the ONSITE/M Axit computer pro- "gtobel" heat transfer charactenstics dunng the postcombust.on gram This modAed verson of the computer program operates coohng phase Convecton was found to dominate the timeante- on a personal comgater and perm <ts the user to optonally grated heat transfer of the leaner Oess than or equal to 10%) se ect rad at on dose converson factors puthshed by the Inter-hydrogen air burns, account.ng for 50 to 70% of the postcom- natonai Commisson on Radolog cal Protecten (ICRP) in their buston heat transfer Rad atcn was shght!y more prevaient Pubhcat.on No. 30 (ICRP 1979 1982) in place of those pub-than Convecton for tr a hyd ogen a,r burns near st>chcmetry hshed by the ICRP in their Pubbcaton No 2 (ICRP 1959) (as When moderate quantrties of steam were added to the environ- implemented in the prevous versons of the ONSITE/ MAX 11 ment, ra$aton be:ame the dominant postcombuston cochng computer program) The pathway-to-human moders used in the mechanism due to the increase in bu'k gas emttance if richer computer program have not been changed from those de-steam concentratens we'e added to the env.ronment, rad aton scobed prevous*y (Naper et al 1984. Kennedy et al 1986) and convecton appear to be equauy important teat trans'er Computer hstings of the ONSITE/V AXII computer program and mechanisnis support ng data bases are included in the appereces of this document. NUREG/CR 3469 V03: OCCUPATIONAL DOSE REDUCTION AT NUCLE AR POWER PLANTS. Annotated B<bhography Of Se'ect. NUREG/CR 3861: STRESS-CORROSICN CR ACKING OF LOW-ed Reaangs in Rad 4aton Prctecton And ALARA B AUM.J W ; STRENGTH CARBON STEELS IN CANDtDATE HIGH-LEVEL KHAN.T A. Brockhaven Natenal Laboratory Nover-ber 1986 WASTE RE POSITORY ENV:RONVENTS BE AVERS.J A ; 124pp 8703100021 BNL NUAEG-517C8 33333 246 THCVPSON N G PARKINS R N BatteNe Vemonal Inst tute, This report is the third in a ser>es of btnograph es supoort ng Columbus Laboratones February 1987. 89pp 8703120328 the efforts at Brochhaven Nabona! Laboratory on dose reduc- EYb2147. 33381234 f.on at nuclear power plants Atstra:ts for th,s report *ere se- A survey of the I.terature was performed to dent,fy potent <al lected from papers presented at recent technical meet >ngs, lour- stress-ccerosion cra&ng agents for low strength ca' bon and na's and research reports revened at the BNL ALAA A Center. Ica ahoy stects in repository environments M *a* found that a and secches of the DOE /RECCN data base on energy-related number of potent craang agents a e present. bv. stress.corro-pubhcatons The references setected for inch. son in the bw son vaang is re'ativety unne'y in the bu a repos.tes y environ-ography re' ate not oNy to operatonal hea th pSs>cs top.cs but rnent because of their Ice concentraton On tne other hand, also to plant chernstry, stress corroson cra$ng and otner as- concentraton of these species may occur by a number of pects of plant ocerat on *Nch have .reportaet impacts on occu- mecharusms ard thus it is conceivatle that the waste package patonal esposur e Also tncluded a'e re'e'ences to iraprovt'd couM fa1 prematurely by stress Cortcson According!y rt is rec-desgn, pianning matena's sekton and other topics related tu ommended that the lower concentra!cn hm>ts for poter tial what m.grt be ca9ed ALAR A engumemq Thus. an at*empt has crachng agents be ident.f ed under typical repostory encrom teen made to cCver a troaj scectrum of tor.acs rNated direct!y Monts. in CorlunCt on w'th modehng stud es to a5%$5 the 14eli- r i b 26 Main Citations and Abstracts , 1

• tPht the cory.sntrating mechanisms will operate and to NUREG/CR-3966: METHODS FOR IMPACT ANALYSIS OF SHIP-N upper lents of concentrabon for each mechanism. PING CONTAINERS. NELSON,T.A : CHUN,R.C. - Lawrence Livermore Nabonal Laboratory. November 1987. 60pp.

i UREk .a3925 REV: SWIFT 11 SELF-TEACHING 8712010381 UCID-20639. 43487:123. CURRICULUM.llivstrative Proolems For The Sandia Waste-Iso- This report revews methods for performing impact stress abon Flow And Transport Model For Fractured Media. analyses of shspping contamers used to transport spent fuel 2 2 REEVES M.: WARD,D.S.: DAVIS P.A.: et al. Sanda National Three methods are discussed. Quass-static, dynannc lumped pa-  ! ' Laboratones. January 1987. 794pp. 8704300036. SAND 84- rameter and dyname f nite element. These methods are used t 1586.40749:199. by industry for performing irnpact analyses for Safety Analysis Several documents have been wntten desenbeng SWIFT 11, Reports. The approach for ea:h method ts desCnbed mcluding the most current varsson of the SWIFT (Sandia Waste Isolation assumptions and kmetatens and modehng cons.derabons. The i Flow and Transport) Model Reeves et al. [1986a), desenbes effects of uncertaintes in the modehng and anatyr ng of casks , the theory and implementabon, and Reeves et al. [1986b]. de- are identsed. Each of the methods usea t' ear elasbc structural t scnbes the requred input of data and parameters. Ward et al. analySs pnnciples. Methods for eterfacing impact stresses wth [1984a) and [1984b], desenbe the companson of the resufts the desyn and load combinations entena specified m R?gula-from the SWIFT code with field data and other exis5ng codes. tory Guides 7.6 and 7.8 are outisned. The quasb state methWf is

This document is devoted to assisteg the analyst who desres based on D'Alembert's pnnciple to subsbtute equivalent static j to use the SWIFT ll code. The analyst is referred to the User's forces for inerbal force = created by the impact. The lurr' ped pa- ,

j Manual for SWIFT II (Reeves et al. [1986b]) for detailed data rameter method is based on using a dscrete number of sb*f- ' input instructons Eght examples are presented to illustrate the ness elements and masses to represent the Cask dunng impact. { use of SWIFT 11. The implementabon of the numenesi simulaton The dynarmc fate element method uses fate element tech-of the physical problem is described for each example. For niques combined with bme etegraton to anatyze the casts . each problem, a hsting of the input data and a macrofiche hsbog impact. Each of these methods can provee an acceptable f of the output are provided. means, within certa n hmetatens, for analyrmg cask impact on unyeldtrig Suriaces. NUREG/CR 3950 V03: FUEL PERFORMANCE ANNUAL i

REPORT FOR 1985. BAILEY,W.J. Battelle Memonal Insbtute, NUREG/CR 3968

STUDY OF OPERATING PROCEDURES IN i l Pacific Northwest Laboratones WU.S. NRC No Detailed Affdi. NUCLEAR POWER PLANTS. Practices And Problems.  ;

i atson Grven. February 1987.103pp. 87031202a8, PNL 5210. MORGENSTERN,M ; BARNES.V E.: MCGUIRE,M V.; et al. Bat. 39985:335 telle Human Affairs Research Centers February 1987.156pp. t This annual report, the eighth m a senes, provdes a bnef de- ' ' ' [ 8 scripbon of fuel performance dunng 1985 m commercial nuclear * **#" 0##' # es, cdegs, aN e s power plants. Onef summanes of fuel design changes, fuel sur- ommendabons of a protect enbtled , Program Plan for Assess- r veillance programs, fuel operabng esperence and trends, fuel og and Upgra$ng Operating Procedures for Nuclear Power i d Plants." The protect was performed by the Pacific Nortnwest I problems, high-burnup fuel expenence, and stems of general sag' Laboratory and Battelle Human Affairs Research Centers for the rufcance are prov&d. References to additonal, more detailed i Divison of Human Factors Technology, Office of Nuclear Reac. mformation and related NRC evaluatons are included for Regulaton, U S. Nuclear Regulatory Commisson (NRC) The ( ) NUREG/CR 3954: !N SITU TESTING OF THE SHIPPINGPORT Foget team anaW aN paluaW samp4s of nonnal aN j d abnamal opwapg prochs from M cannecial nuc4ar ATOMIC POWER STATION ELECTRICAL CIRCUITS gww ants owabng m m W Stah N m team l 1 DINSEL M.R.: DONALDSON.M.Rr SOBERANO,F.T. EGAG j l a med w mar www sants m N W Staks to r Idaho, Inc. (subs. of EG&G, Inc ) Apnl 1987. a9pp~ " 8706120172. EGG 2443. 41261.001' etabng procedures A peer review g'roup' was convened to 4 l- This report discusses the results of electncal m satu tesbng of advise the protect team on the conduct of the protect and to 0 Selected cacu:ts and components at the Shippogport AtornC review and comment on the protect report. The report contains Power Stabon m Shppingport, Pennsylvania. Testag was per. findogs on the useabikty of operabng proceduras and on prac- ,! s formed by EG&G Idaho in support of the UrNted States Nuclear 14es concerning the development, use, arvi control of operabng r r Regulatory Comtns9on (USNRC) Nuclear Plant Aging Research procedures m nuclear power plants. The report encludes recom-(NPAR) Program. The goal was to determine tra ex1ent of agog mendatons to the NRC on the need to upgrGde the quakty of l or degradaton of vanous circuits from the orignal plant, and the operabng procedures. The report also discusses an approach to  ! , two major coreplant bpg<ades (represenbng three distect age a program plan to assess and upgrade operateg procedures. j groups), as well as to evaluate prevously dea, eloped surveil- j lance technology The electncal testeg was performed using NUREG/CR-4012 V02: REPLACEMENT ENERGY COSTS FOR l the Electncal Cacut Characteruabon and Diagnostc (ECCAD) NUCLEAR ELECTRICITY GENERATING UNITS IN THE system developed by EG&G for the U S. Department of Energy UNITED STATES 1987 1991. VANKUlKEN.JC; GUZiELK.A; I  ! to use at TMI 2. Testeg meluded measurements of voltage, ef. BUEHRING,WA: et al Argonce Natonal Laboratory. January fective senes eductance, impedance, effective seres reSst- 1987. 253pp. G o2190449 ANL AA 30. 39690 235. I ance, de resistance, msulaton re9 stance and time doma,n re- SeasorW replacement energy costs are estimated for poten-  ; ftectometry (TDR) parameters. The cacuts evaluated ecluded tial short term shutdowns M 116 nuclear electncity-generating i pressureer heaters, control rod poston ed>cator cables, and urvts. These esumates i 3 irveloped to he4p the U S Nuclear  ; safety intecton system motor operated vafves. It rs to be noted Regulatory Cominsson (NF,y estabbsh regulatory pohces, par- * , that the operabehty of these cacuts was tested after several bcularty those requirmg safety modificabons that rnght necessi-  ! a years had elapsed because plant operatons had concluded at tale temporary reactor shutdowns Cost estimates were denved I Sheppogport. There was no need followmg plant shutdown to from probabikstic producton-cost simulabons of pooled utAty-retarn the cacuits m wortung conditon, so no effort was expend- system operatons Fa"ors affectog replacement energy costs, ed for that purpose. Tre m situ measurements and aWyss of such as random urwt failures, maintenance and refueleg recure-l the data conftmer! the effectiveness of the ECCAD system for trents, and load vanabons are treated in the anatysis Seasonal  ; detectog degradaton of cacurt connectons and sphces be- costs are presented for the five-year pered begintwng with 1987 , 1 cause of high re9 stance paths, with most of the problems and ereng with 1991. This mformation updates cost estmates caused by corrovon. Results and>cate a correlaton between the that were developed previousty for the NRC and pubbshed m

chronologeal age of crcuts and cacuit degradatc,t NRC Report NUREG/CP-a012. Vol 1. The updates were under-l  !

i i I t h e Main Citations and Abstracts 27 1 taken to extend the time frame of cost estimates and to ac- mentary approach, namely the seismic frag:hty response of ac-Count for recent Changes in utihty system Condtsons, such as Celerated aged battenes. Of partcutar interest is the degree to i fiuctuatens in fuel pnces, changes in construction and rette- wNch such approaches accurately reproduce the actual failure ment schedules, and adjustments to system demand projec- modes and thresholds. In these tests the segruficant ogng ef-7 tions, lects observed, in terms of seismec survwabAty, were: embnttle-net of cd cases, positue bus matenal and postus plate NUREG/CM-4016 V02: APPLICATION OF SLIMMAUQA TEST OF AN INTERACTIVE COMPUTER-BASED METHOD FOR OR- actwo rnatenal causng hardenmg and expansion of postwe GANIZING EXPERT ASSESSMENT OF HUMAN PERFORM- plates. The IEEE Standard 535 accelerated ag<ng method suc-ANCE AND RELtABILITY Volume li. Appendices. cessfuffy reproduced seismicapy signifcant aging effects m new SPETTELL,C M.: ROSA.E.A.: HUMPHREYS P C.; et at Brookha- cens but accebated gnd embridement an eshmated fNe years i von Nabonal Laboratory. October 1986. 219pp. 8702060'28. beyW N ccm6 tonal age of other components. BNL-NUREG 51828. 39537.248. The U S. Nuclear Regulatory Commission (NRC) has been NUREG/CR-4134 R01: REPOSITORY ENYlRONMENTAL PA. conductog a muttryear research program to investigate 6ffer* RAMETERS AND MODELS RELEVANT TO ASSESSING THE ent methods for usmg expert Kdgments to esbmate human PERFORMANCE OF HIGH LEVEL WASTE PACKAGES error probabihties (HEPs) m nuclear power plants. One of the (BASALT, TUFF AND SALT). CLAIBORNE HC. CROFF.A G.: GRIESS.J C; et at. Oak Rdge Nabonal Laboratory. October methods invesbgated, derrved from mutti attnbute ubity themy, 1987. 247pp. 8711060223. ORNL/TM 9522. 43309.091. is the Success. Likelshood index Methodology implemented ' TNs document provdes specifcabons for models/methodolo-through Mulb-Attnbute Utsty Decompositon (SLIM.MAUD). This report desenbes a systematic test apphcaten of the SLIM' g,es that could be employed m determnng postclosure reposi- , MAUD methodology. The test appbcation is evaluated on the tory envvonmental parameters relevant to the performance of basis of three entena: practicality, acceptability, and usefulness- higMevel waste packages for the Basalt Waste isolabon Protect Volume i of tNs report presents an overview of SLIM MAUD, (BWIP) at Richland, Washington, the tuff at Yucca Mountain by i describes the procedures followed m the test apphcation, and the Nevada Test Site, and the bedded salt in Deaf Smith i provdes a summary of the resutts obtained. Volume 11 conssts County, Texas. Gudance is provded on (1) the denbty of the i relevant repository envronmental parameters (groundwater of technical appen6ces to support,in oetad the materials coa- charactensbcs, temperature, radation, and pressure), (2) the , tamed in Volume 1, and the users package of erplot proce- - i dures to be followed in ernplementing SLIM.MAUD. The results models/ methodologies employed to determine the parameters, obta ned in the test apphcation provde support for the appica- and (3) the input data base for the rnodels/ methodologies. Sup-portog studes included are (1) an anatysis of potental waste

. ton of SLIM.MAUD to a wde vanety of apphcatons requinng package failure modes leading to denbficaton of the relevant L estimates of human errors.

repostory envronmental parameters. (2) an evaluabon of the NUREG/CR 4082 V05: DEGRADED PIPING PROGRAM PHASE cre6ble range of the repository environmental parameters, and it.Semaannual Report. Apnt-September 1986. WILKOWSKl.G M.; (3) a summary of the review of enesting rnodets/methodologees AHMAD J.: BARNES.C.R.: et at Battelle Memonal insbtute. Co. currentty employed in determang repository environmental pa-lumbus Laboratores. Apol 1987. 238pp. 8704270130. BMI. rameters relevant to waste package performance. 2120, 40675:326. Presented herein is the Fifth Semiannual Report of the U S. NUREG/CR 4141 V02: CRITICAL PARAMETERS FOR A HIGH.

• NRC's Degraded Pipeg Program Phase il The intent of this LEVEL WASTE REPOSITORY. Volume 2: Tuff. DIDWALLE.M.

program is to expenmentally vahdate and enhance available an. Lawrence Liverrnore Natonal Laboratory. BENSON.S.M.: alytical methods for evaluatog the mecharMal behavior of nu. BINNALLE P.: et af. Lawrence Berkeley Laboratory. May 1987. , clear power plant piping contanng cacumferentially-onented 106pp. 8706030120. UCID-20092. 41144 242. defects. Fifty-one pipe expenments have been conducted to TNs repod addresses enbcal parameters specife to a reposi-date. These and approximately 42 addtonal pipe expenments tory n tuff, using the Yucca Mountam tuffs of Nevada as the

• from other programs have been anatyred. In the anatytical precipal example. For the purposes of tNs report, a parameter l effort. a screening cnteron has been developed to show when is considered to be a physical property whose value helps de-the net secton-collapse analysis is vakd TNs shcas that even termine the Characten3bes or behavior of a reposttery system.

tough matenals such as stacless steel can fe* at less than net. Parameters which are defined as entical are those essent4! to , i secton-collapse loads if the pipe diameter is suffoentry targe. evaluate and/or morntor leakage of radonucides from the re-Numerous predict 1ve J-estmabon schemes have been evaluat. PCS' tory and to evatuate the need for retneval. The parameters ed and mo@f ed. A fate length surface cracked pipe estimaton are consdered with respect to the disciphnes of geomechancs. 4 scheme has also been developed Fate element analyses of geology, hydrology, and geochemestry and are rank ordered in 1 specemens with welds suggest that the see of the weld relative terms of importance. The specife role of each parameter, spe. to the specimen or structure see can affect the deformation J cife factors affect.ng the measurement of each parameter, and j values. Supporting research efforts involve investigating geome- the eterrelabonsNps between the parameters are consdered in

try effects on J-R curves, as well as charactenzing the matenal detail properties for each pipe tested' NUREG/CR 4161 V03

CRITICAL PARAMETERS FOR A HIGH.

NUREG/CR 4098: SEISMICJRAGILITY TESTS OF NEW AND LEVEL WASTE REPOSITORY. Volume 3.Satt. D!DWALLE M. ACCELERATED-AGED CLASS 1E BATTERY CELLS. Lawrence Lrvermore National Laboratory. WOt LENBERG.HA: ' i BONZON,LL Sanda National Laboratones JANIS.W.J ; BINNALL.E.p.; et al. La*Tence Berkeley Laboratory. July 1987. BLACK,0.A.: et at Ontn Hydro. January 1987. 135pp. 41pp. 8708120128 UCID-20092. 42128.057. , 8705200231. SAND 84 2631. 40984:326. TNs is the tNrd report of a three-volume senes addressing The seismc fragility response of naturalty aged nuclear s'a- entecal parameters for an underground NgMevel nuclear waste ton safety-related batteres rs of mterest for two reasons: (1) to repostory in basalt, tuff, or satt TNs report covers the identife-6 determee actual failure modes and thresholds and (2) to deter- cabon and pnonteaten of entcal parameters for a repostory m  ! mee the vahdty of usmg the electncal capacity of indtvdual bedded salt. For purposes of tNs work, a parameter is a physs- , cells as an mdicator of the potent 4) survivabihty of a battery cal property whose value helps determene the characterestscs or i grven a seismc event. Pnor reports e this senes escussed the behavior of a repostory system A pr.rameter is consdered to seismic.fragthty tests and results for three specihc naturally- be entical if a mistake m its mea ,urement, or in the nabikty to j aged cell types 12 year old NCX.2250,10. year old LCU-13. measse it, could lead to a wrong conclusion about the adequa.

and 10 year old FHC 19 This report focuses on the comple- cy of a repostory Consideraton was grven to the relative im-1' 4

w 28 Miln Cit:ti:ns Cnd At>stracts portance of critical parameters in four specific disc'phne areas- The investigaton focuses on the behaver and structural integri-geomechancs. geology, hydrology, and geochemistry. Relative ty of steel pressure vessels containing crackleke na*s. Current importance of the parameters was independentty considered for work is organized into t*etve tasks- (1) program management, each of the four major phases of repottory 8Clivity: site charac- (2) fracture-methodology and analysis, (3) matenal charactefi2a-tonzaton, site constructon 5:te operaton. and site closure and ton and properties. (4) enysonmentalty assisted crack-growth decommassoning important actmties that cover ait phases are stud.es, (5) crack arrest technology. (6) irrad,aton effects stud-determinaton of hydroogic charactenst.cs and satt dissoluton ies, (7) cladding evahcatens. (8) intermed; ate vessel tests and rates, and their long term mervtonng anatysis (9) thermal-shock technology. (10) pressunzed ther. NUREG/CR 4165: SEVERE ACCIDENT SEQUENCE ANALYSIS mal shock technology. (11) Pressure Vessel Research Users' PROGRAM - ANTICIPATED TRANS!ENT WITHOUT SCRAM Facdity, and (12) shipping-cask matenal evaluatons. SIMULATIONS FOR BROWNS FERRY NUCLEAR PLANT UNIT NUREG/CR 4300 V03 N2: ACOUSTIC EMISSION / FLAW RELA-

1. DALLMAN,R J ; GOTTULA.R C ; HOLCOMB E Ea et al.

TiONSHIP FOR INSERVICE MONITORING OF NUCLEAR EG&G Idaho. Inc. (subs. of EG&G, Inc ). May 1967. 92pp PRESSURE VESSELS Progress Rept.Apnt Sectember 1986. 8707060336 EGG-2379 41584147. HUTTON,P H BatteHe Memonal Institute, Pacifn Northwest An anatys4s of five anticipated transients without scram Laboratories January 1987. 16pp. 8702260636. PNL 5511' (ATWS) was conducted at the Idaho Nat onal Engineenng Labo- 39759 217. ratory (INEL) The fee deta>!ed deterministic simulatons of pos- This report discusses technical progress for the penod Apol tufated ATWS sequences v,ere irutiated from a main steam l$ne 1986 Septen ber 1966 for the NRC sponsored research pro. isolaten vatve (MSIV) closure. The subi ect of the anatysis was grarn concerned with "Acoustic Emission /F!aw Relatonships for the Browns Ferry Nuclear Plant Unit 1, a boding water reacto' Inservce Monitonng of Nuclear Reactor Pressure Bour danes ' (BWR) of the BWR/4 product line with a Mark I containment included in the d:scussion are the topics of AE rnonitonng of pn-The s,mutatons yelded insights to the poss:ble consequences mary piping dunng reactor operaton, sutstantiation of the AE resulting from a MSlV closure ATWS An evaluation of the ef- signal identif.cabon method, development of AEllGSCC rela-fects of plant safely systems and operator actons on accident tonships, and progress in estabbshing an ASTM AE standard progress.on and regaton is presented and an ASME appenda for on line AE monitonng NUREG/CR-4216: EXPER MENTAL RESULTS FOR A 18-SCALE STEEL MODEL NUCLEAR POWER PLANT CONTAINVENT NUREG/CR 4300 V04 N1: ACOUSTIC EM SSION/ FLAW RELA PRESSURt2ED TO FAILURE. KOENIG.L N Sands Natonal TIONSH:P FOR IN-SERVICE MONITORING OF NUCLEAR Laboratones December 1986 634pp 871001043 L SAND 85- PRESSURE VESSELS Progress Report, October 1986 March 1987. HUTTON P H ; FRlESEL.M A Battelle Memona! Inst;tute, 0790 42878 0a0. A 18 scale steel model of a Ight-water reactor containment Paofic Northwest Laboratones June 1987. 20pp. 8707100289. build'ng was tested as part of an NRC sponsored program PNL 5511. 41663 077. whose objective is to quahty methods for predicting the re. This report d>scusses technical progress for the perod Octo-sponse of contarnment buddings subiected to severe accidents ber 1986 to March 1987 for the NRG sponsord research pro-The model was pressunzed in steps to 195 ps>g and its re. gram concerned *,th "Acoustic Emisson/ Flaw Relatonships for sponse was recorded by strain and d;splacement transducers mservice Monitonng of Nuclear Reactor Pressure Boundanes " located throughout the model Perodic leak rate rneasurements Too.cs discussed included AE monitonog of pnmary piping were amo made An overview of the test is given, and the re. during reactor operaton, development of AEhGSCC relation-sponse cf the modet and specac features (such as equement ships. evaluaton of the effects of crack growth rate on detec-hatches, airlocks. and peng penetratens) are presented in this ton of the associated AE. vabdaten of the AE sgnal dentifica-report ton method. and progress in developing an ASME Section XI Code appendia for continuous AE monitoong of pressure NUREG/CR-4219 V03 N2: HEAVY-SECTION STEEL TECHNOL. boundary components OGY PROGR AM Semiannuat Progress Report For Apnt-Sr p-terr.ber 1986 PUGH C E. Oak Rdge Nat onal Laboratory Je- NUREG/CR 4301: STATUS REPORT ON EQUIPMENT QUALIFl-cember 1986 234pp 8706030097 ORNL/TM 9593 41151 228 CATION ISSUES RESEARCH AND RESOLUTION The HeavySecton Steel Technology (HSST) Program is an BONZCN L L. WYANT F J . BUSTARD.L D ; et al. Sand a Na-eng.neenng research actety conducted by the Oak Rdge Na. tional Laboiltones January 1987. 582pp 8703090128 tional Latoratory for the Nucicar Regulatory Commissen The SAND 851309 39922118 program corrpnses stud.es re!ated to alt areas of the technolo. Since its inceptcn in 1975. the Ouatdicaton Testing Evalua-gy of matenal fatocated into th>ck secten pnmary-coolant con- ton (OTE) Program has produced numerous results pert.nent to tainment systems of bght water-cooied nuclear power reactors equ pment quahfication issues Many ha<e been incorporated The invest gaton focuses on the teacor and structural integn. into Regu!atory Gudes. Ruies. and industry practices and stand-ty of steel pressu re vessels conta,ning cracklAe funs. Current ards This report summan2es the numerous reports and findings work is organized into ten tastis (1) program management, (2) to date Thirt/ separate issues are d:scussed encompassng fracture-methodolcgy and analysis. (3) ma'enal cnaractenzaton three genene areas accdent simutation methods, ag<ng simula-and propert es. (4) enc ronmentah ass >sted crack-growth stud. ton methods, and. special topics related to equipment quahf<a-ies, (5) crack-anest te;hnology. (6) irraj aton effects studies. t on Each issue-specdic section contains (1) a bnef desenpton (7) cladang eva!uators. (8) intumediate vessel tests and ana!. of the issue. (2) a summary of the apphcable research effort, y9s. (9) the ma% hock technology, and (10) pressunzed ther. and (3) a summary of the findings to date mal shock technoicgy NUREG/CR 4307 V03: LWR PRESSURE VESSEL SURVEIL-NUREG/CR-4219 V04 N1: HE AVY-SECTION STEEL TECHNOL- LANCE DOS METRY IMPROVEMENT PROGRAM 1986 Annual OGY PROGR AM Sern. annual Prog'ess Report For October Repor10ctoter 1985 September 1986 MCELROY W N Han-1986 Ma ch 1987 PUGH.C E Cak R.dge Na'- 'ai Laboratory ford Eng neenng Development L atcratory Apnl 1987 232pp August 1987 266pp 8710060244 ORNL / T P 1 42922 293 8705120103 HEDL TME 86-2.40896 256 The Heavy-Secton Steel Technoicgy (: jam is an The Lght Water Reactor Pressu re Vessel Surveillance Desim-engeeenng rocatch actyty cortted by t% Oak Rdge Na- etry improvement Program (LWR PV SDiP) has been estab-t.onat Laboratory for the Nuclear Regulatory Comm:ss on The lished by the U S Nuclear Rega:atory Commisson (NRC) to im- , Program compr'ses stAes related to all areas et the technolo- prove. test, venty. and standardtte the phy9cs-dosimetry metal-gy ct maletais fatocated into tNck secten pomacy coo' ant con- iur gy. damage corre!at.on, and associa'ed reactor ana!y9s ta.nrNint ystems of Ift water CcWed nuclear poner reactors rnethods. procedures and data used to pred>c1 ine integrated Main Citations and Abstracts 29 effect of 'eutfon exposure to LWR pressure vessels and their what insights might be ga ned (beyond those already document-support structures A vgorous research effort attacking the ed in the PRAs) by an andependent evaluaton. Th:s effort was same measurement and ana!ysts problems exists world*de, not intended to venfy the specMC details and results of each and strong Cooperatrve hnks between the U S. NRC supported PRA but rather, having accepted the results, to see what they actmtes at HEDL. ORNL, NBS. and MEA and those supported might mean on a plant-specific and/or genenc level The four by CEN/SCK (Mol. Be'gium). EPRI (Palo Atto, USA). KFA PR As evaluated were those for MJ! stone 3. Seabrook, Shore-(Jubch, Germany) and several United Kingdom Laboratones ham, and Oconee 3 Full detaded revews of each of these four have been entended to a number of Cther countnes and labora. PRAS have been Commissoned by the N'4C, but only two have tores These cooperatae hnks are strengthened by the actrve been completed and available as further input to this study: the membership of the scient.fic staff from many participating coun- review of Mdistone 3 by LLNL and the review of Shoreham by tres and laboratones in the ASTM E10 Committee on NucWar BNL The review reported here focused on dentifying the domi-Technology 'ind Appbcatons Several subcommittees of ASTM nant (lead;ng) initiators, faaure modes, plant systems, and spe-E10 are respons.ble for the preparaton of LWR survetitance cific components that affect the overall core mett probabel.ty standards. Results of FY-86 research by a number of LWR PV- and/or nsk to the pubhc In add tson, the varcus elements of SDlP part.crpants are reported in this progress report. the methodolog:es employed by the four PRAs are discussed NUREG/CR 4320: THE RELATIONSHIP AND INFLUENCES OF and ranked (per NUREG/CR 3852). PRA specific insaghts arc FUEL AND COOLANT SYSTEM PROCESSES DURING LWR presented within the report secton addressing that PRA. and SEVERE ACCIDENTS RIVARD.J B. Sanga Natonal Laborato- osau insigMs are presented in the Summary res December 1966 59pp 8704080124. SAND 851449 40446 182 NUREG/CR 4407: PlPE BREAK FREQUENCY ESTIMATION FOR NUCLEAR POWER PLANTS WRIGHT.R E ; STEVERSON.J A ; This report places the processes of fuel and core damage, re' actor coolant system (RCS) flow and heat transfer, and pres' ZUROFF.W F. EG&G Idaho. Inc. (subs of EG&G. Inc ) May 1987. 2S5pp. 8708040304. EGG-2421. 42037.260. sure vessei breach and their respectrve fisson product consad-This study empincally develops treauencies of sa'ety signife-erat >ons in the context of typical r sk-dominant accdent se-cant p,pe fai!ures in commercial nu"lear power plants (NPPs) quences. Thus the enhanced pecepton of tne relationsh.p (and its pnmary purpose is to update the p4pe break frequencies ro-thus importance) of these processes to the potential conse-ported in the Reactor Safety Study, W ASH-1400, which are Quences of a severe accident is provided Thrs is accomphshed using both generic and plant specific relatonal methods It is used in many nsk anahses The study envolved reviewing van-ous data sources for actual p ping fa: lure events of sign.ficant found that the vessel and RCS procesres pervaswely influence magnitude. When entant in the documentaten reviewed. infor-consequences The expenment piograms designed to provde maton was entracted concerning cond tional factors such as the in vessel and RCS fuel damage data base are esamined :n the system in which the failure occurred cperatonal mode of hght of this concluson, and some suggest>ons are offered the plant. and size of the p.pe involved to estimate conotional NUREG/CR 4330 V03: REVIEW OF LIGHT WATER REACTOR pipe break fiequencies useful to risk analysts Because of the REGULATORY REQU!RtiVENTS Assessment Of Selected high Quakty piping used in NPPs. there have been few signa-Regulatory Requirements That May Have Varginal importance cant p pe falu res An attempt was made to augment the analy-To Risk Postaccident Sampt.ng System. Turbine sis with synthetic data from a Delphi approach. but the *de un-Missdes. Combust:ble Gas Control Charcoaf Filters SCOTT.W B ; certarnty bounds on the resulting est; mates rendered the results JAMiSON J D ; STOET2EL.G A ; et al. Battelle Memona: Inst,- unsuitable for combining data tute. Pacific Northwest Laboratones May 1987 134pp 8706150009 PNL 5809 41301193 NUREG/CR-4409 V02: DATA BASE ON NUCLEAR POWER in a study commissioned by the Nuclear Regulatory Commis- PLANT DOSE REDUCTION RESEARCH PROJ ECT S. s>on (NRC). Pacific Northnest Laborato'y LPNL) evaluated the KHAN.T A ; BAUM.J W Brookhaven Natonal Laboratory. No-costs and benet:ts of streamhning regutatory requirements in the vember 1986 234pp 8704080217. BNL-NUREG-51934 areas of rosta0cdent sampling systems, turbine missdes. com- 40444 134 bustible gas control. and impregnated charcoat fdters The basic This report descnbes 142 nternat>onal protects on dose re-framework of the analyses was that presented in the Regutatory ducton research it is the second report on a data base main. Analysis Gudehnes (NUREG/BR-0058) and in the Handbock ta+ned by Brookhaven Natonal Laboratory as part of an NRC for Value-impr,ct Assessment (NUREG/CR 3568) The effects sponsored protect on occupat.onal dose reduct.on The first of streamhned regutatons were eva'uated in terms of such fac. report dcscnbed 180 simdar projects A *de area cf research is tors as populaton dose and costs to industry and NRC The re. coered, incluang plant chernistry. stress corrosen cracking, sutts ind cate that streamwng regulatory requirements in three steam generator repa*r and replacement, robotics. and decon. of the four areas, ie . postaccident samphng systems. turtune taminaten Analysts ind cates that dose reducten research is missdes. and combustible gas control. would have httle impact beg nning to a'fect occupational ra$aton esposure There is a on pubhc nsk Streamhned regulatory reawremerts in the fourth generaf diminuton in esposures in countnes *:th dose reduction area. impregnated charcoal faters. might increase pubhc nsg research programs, such as Japan The Federal Repubbe of Cost evaluatons ind,cate substant.al saengs by lengthening the Germany. Canada, Sneden. Frave, and the Un ted States inspection interval for low pressure turbine rotors Smatl.to. Most of the present research, honever, is d,rected towards en-moderate sanng may be reahzed through postulated mod.feca. gmenng approaches to dose reducten More attention in the tons to the postaccdent samphng system requiremerts and to nonegmenng areas is ca%d for the conbust.bie gas control requirernents for hydrogen recom. biners en enerted B AR Varm I and 11 conta,nments The results NUREG/CR 4418: DOSE CALCULATION FOR CONTAM.N ATION in6cate that the use of impregnated cha coal fdters is tre most OF THE SKIN US!NG THE COYPUTER CODE VARSKIN cost-effective method of radcod ne removal from buslang vent" TRAUB.R J . REECE W D. SCHERPE L2.R I . et al BatteFe Me-laton systems mortal Inst,tute. Pacific Northwest Latcratones August 1987 101pp 8708280132 PNL SE.10 42333 289 NUREG/CR 4405: PROB AB;LISTIC R'SK ASSESSMENT (PRA) This report describes a rnethod for computing the raiat,on INSIGHis FITZPATRICK,R , ARRtET A L . TEICHMANN.T , et dose to the skin from rascactive contammaton on the sbn al Brookhaven Natonal L aboratory December 1987 142pp The calculatcnal method is based on tne tables of absorbed 8801070031 DNL-NUREG 51931 43344 018 ener gt d1stnoutens around port source s in water that have Four dfferent prot,atastic nsk assessments (PRAs) have been developed by M J Berger and puttst,ed rn 1971 en Pam-been bnetty reviewed w to the broad object.ve of ascerta,ning phtet No 7 of the ' Journal cf Nuc: ear Ve@ cine ' The method i - 30 Main Citations and Abstracts I has been implemented n a computer code, VARSKIN, that wdl transient etemal initiating events, and seisme, fire, entreme compute the rad abon dose at a specifed depth in the skm from wtnd, internal and external flood, and lightning entemal events.  ; a raeaton source ranging in size from a point to a disc having a A fullscale systems analysis was performed with detailed fault ' 100-cm(2) area. This report conta' e s a source code lisbng of trees and event trees mcludng support system dependencies. the computer code and tables of dose factors that have been The system analysis results were emirapolated into release cate- i derNed from the code, as well as sample runs and user instruc. gones usmg apphcable past PRA phenomenologcal results and ticas. This report also escusses the contamination level that unproved containment fadure mode probabiktes. Puble conse-corresponds to the recording level desenbed by the intomabon- quences were estimated using site specifc CRAC2 calculatons.

al Commisson on Radclogcal Protection. The Value impact (VI) analys4s of possible attematives consid- 5 NUREG/CR 4444; SHUTDOWN DECAY HEAT REMOVAL ANAL- ered both onsite and offs 4te impacts arrnnng at several nsk YSIS OF A GENERAL ELECTRIC BWR3/ MARK l. Case Study, measures such as averted populaton dose out to a 50-m.le ,

HATCH,S.W.; ERICSON.D M : SANDERS,G.A. Sanda Natonal radus and dottars per person tem averted. Oncertaintes m the . Laboratones. March 1987. 781pp. 8704060465. SAND 85 2373. VI anab s are escussed and the issues of feod and bleed and l 40405.123. secoMary Nowdown are analyrd A General Electnc Boihng Water Reactor (BWR3) with a Mark > l contamment has been evaluated as part of Task Acton Plan NUREG/CR-4469 YO4: NONDESTRUCTIVE EXAMINATION A 45, ' Decay Heat Removal Requrements." Probabihstc nsk (NDE) RELtABILITY FOR INSERVICE INSPECTION OF LIGHT I WATER REACTORS.Semannual Report. October 1985 March r , assessment models were constructed to determine the doms- 1986. DOCTOR,S.R.; BATES.DJ.: DEFFENBAUGH,J.; et al. i nant internal, randomly ntiated accident sequences and special Battelle Memonal Institute, Pacife Northwest Laboratories. ' emergency sequences (e g., earthquakes). The domnant se- March 1987. 90pp. 8704060414. PNL-5711. 40410:169. . quences were reviewed to deternne what rnodifcatens mght The Evaluaton and improvement of NDE ReliaMty for in- ,

be made to enhance the plant's aMty to remove decay heat. meryce inspecten of Light Water Reactors (NDE Rehabshty) 4 Modficatons wNch held promse went through a preigninary Program at the Pacific Northwest Laboratory was estabhshed by i'

cost and des gn anatysis. Additonally, the impact on the proba*

the Nuclear Regulatory Commissaon to determme the rehaMty

Mty of core mett accidents was estmated grven implementa- of current insemco mspecton (ISI) techniques and to develop ton of modifcabons. In the final step, these results were com-recommendabons that will ensure a suitably high inspecton teh-bened en a valueampact format accor$ng to NRC guidehnes. aMty. The objectives of this progrw ~1ude determong the The results andcate that feasible modifcatons to enhance rehaMty of ISI performed on the prrnary a ystems of comrner-a decay heat removal do exist at the subject plant. The central cial ight. water reactors (LWRs); usmg prob Mste fracture me-estimates of the value-empact results tended, however, to show chancs anafysts to determee the vnpact # NDE unrehaMty on  !

marginal cost effectiveness under current guidehnes for most of system safety; and evaluatmg rehaMty mprovements that can the modfcatons. Attemate assumptons evolving source term be acNeved with improved and advanctd technology. A foal magrvtude and interd>cton critena were found to segnificantfy objectrve is to formulate recommended re visons to ASME Code affect the results The msights gained from tNs study will and Regulatory regurements, based on matenal properties, become part of an mformaton base whch mil be used to deveb service condtons, and NDE uncedaintes. The program scope op genenc recommendatons regarang the adequacy of decay is hated to ISI of the pnmary systems inclu$ng the piping. ' heat removal systems m hght water reactors- vessel, and other espected components. This is a progress NUREG/CR 4457: AGING OF CLASS 1E BATTERIES IN report covenng the programmate work from October 1985 i SAFETY SYSTEMS OF NUCLEAR POWER PLANTS. through March 1986. . EDSON,J L; HARDtN.J E. EG&G Idaho. Inc. (subs. of EG&G, f inc ). July 198L 43pp. 8709040461. EGG 2488. 42522.019. NUREG/CR-4469 V05: NONDESTRUCTIVE EXAMINATION i TNs report presents the resutts of a study of aging effects on (NDE) REllABillTY FOR INSERVICE INSPECTION OF LIGHT safety-related battenes 6n nuclear power plants. The purpose is WATER REACTORS Semiannual Report. Apnt September 1986. to evaluate the agmg effects caused by operaton mtNn a nu. DOCTOR,S R.; BATES,D.J.; DEFFENBAUGH.J ; et al. Battelle i clear facihty and to evaluate maintenance, testing, and morvtor- Memonal Institute, Pacife Northwest Laboratores. Apnl 1987. og practices with respect to their effectiveness m detectog and 39pp. 8705280412. PNL 5711. 41097.183. ' mitigabng the effects of aging The study fonows the U S. No. Evaluabon and Imtwovement of NDE RehaMty for Inse4vce clear Regulatory Commisson's (NRC's) Nuclear Plant-Aging Re. Inspecbon of Lght Water Reactors (NDE RehaMty) Program at . d search approach and ovestgates the matenals used in battery the Pacifc Northwest laboratory was estabbshed by the Nucle- ] construebon, identies stressors and aging mechanisms, pre, ar Regulatory Commesson to determee the rehapty of current ' sents operabng and testing expenence with aging effects, ana, mservice inspecton (ISI) techniques and to develop recommen-i fyres battery fadure events reported e varous data bases, and datons that will ensure a suitably high inspecton rekaMty. The I evaluates recommended maintenance practces. Data bases obf ectives of this program include determining the rehabihty of ) that were anabrted meluded the NRC's Lcensee Event Report ISI performed on the pnmary systems of commercel bght water i system, the inst 4tute for Nuclear Power Operatons' Nuclear reactors (LWRs), using probaMsbc fracture mechanses anatysis ~ Plant Rehapty Data System, the Oak Ridge Nabonal Laborato- to determene the impact of NDE unrehaMty on system safety; ry's In Plant Rehapty Data System, and The S M Stoner Cor- and evaluatmg rehabbty wnprovements that can be actweved oorabon's Nuclear Power Experence data base. *'th enproved and advanced technology. A foal obt ective is to i formulate recommended revisons to ASME Code and regula- l l NUREG/CR-4456: SHUTDOWN DECAY HEAT REMOVAL ANAL- tory requrements, based on matenal propertes, service con 6-4 YSIS OF A WESTINGHOUSE 2 LOOP PRESSURIZED WATER tons, and NDE uncertainbes. The program scope is hrruted to i REACTOR. Case Study. CRAMOND,W R.: ERICSON D M.; ISI of the pnmary systems mclading pipeng vessel, and other wk i SANDERS,G A. Sandia Natonal Laboratores. March 1987- spected components. This is a progress report covenng the 994pp. 8704060155. SAND 85-2496. 40395 017. programmabc work from Apnl 1986 through September 1986, This is one of ser case studes for USI A-45 Decay Heat Re. *  ; moval (DHR) Requrements. The purpose of ttws study is to NUREG/CR-4449 V06: NONDESTRUCTIVE EXAMINATION , identify any potenbal vulnerabshtes in tt s DHR systems of a (NDE) RELIABILITY FOR INSERVICE INSPECTION OF LIGHT  ! , typcal Westqhouse 2-loop PWR, to suggest possible modifica- WATER REACTORS Semannual Report, October 1986 - March I tons to wnprove the DHR cepabshty, and to assess the va;ue & 1987. DOCTOR,S R ; DEFFENBAUGH.J.; GOOD.M S et al , anpact of the most prom:smg attematrves to the earsting DHR Battene Memonal Institute, Pacifc Northwest Laboratones June  : stems The systems anatysis cons 4ered small LOCA' and 1987. 63pp. 8707080329 PNL 5711. 41621:250 l r i i .n - . - , n - , - - . - . - , _ . - ~ , .. , , , , . , .- . , . ~ . ~ , . Main Citations and Abstracts 31 The Evaluaton and improvement of NDE Rehabaty for in- dCTOD* FLOW. The inte ewment modet is used to simulate a service inspecton of Light Water Reactors (NDE Reliability) load-unload-cool fracture (LUCF) type of WPS cycle for which Program at the Pacific Northwest Laboratory was established by expenmental results are avalable The varous models and cn-the Nuclear Regu!atory Commisson to determine the reliatul'ty tena are evaluated in terms of their agreement with the firste. Of current mservice inspecton (ISI) technques and to develop e!ement results such as crack opening displacements, stresses recommendatons that wdl ensure a suitably hgh inspecton reb and plastic-zone wes, and in terms of their abihty to pre 6C1 abary. The objectives of this program include determirwng the fracture load. The nonfinite-e!ement based models of Chell and rehabaty of ISI performed on the pomary systems of commer. Curry are used to samulate 32 ad$ tonal WPS expenments to Ctal teght water reactors (LWRs), using probabastic fracture me* as to further assess the relative ments of the models and the CharhCs analys4s to determine the ampact of NCE unretelty on J(e) entical stress, and dCTOD* FLOW fracture entena Whae system safety; and evaluating rehabety improvements that can K(Ic) scatter band behavior allows significant latitude for manip-be achieved with improved and advanced technology. A final ufaton of model predictons, which impedes ent<a! evabaton objective is to formutate recommended revisons to ASME Code of the models and entena, both nodels and all three fracture and Regulatory requirements, based on matenal properties- critena are found to predict WPS behavior which is quahtatively swce conatons, and NCE uncerta nties. The program scope consistent oth expenmental data is lirruted to ISI of the pnmary systems including the piping. vessel, and other inspected components This is a progress NUREG/CRwS24: CLOSEOUT OF lE BULLETIN 80-24 PREVEN-report covenng the programmatic work from October 1986 TION OF DAMAGE DUE TO WATER LEAKAGE INSIDE CON-through March 1987. TAINVENT (OCTOBER 17,1980 INDIAN POINT 2 EVENT) NUREG/CR-4485 V02: THE IMPACT OF FUEL CLADDING FAIL. FOLEY,W J.; DEAN.R S ; HENNICK A. Parameter, Inc March URE EVENTS ON OCCUPATIONAL RADIATION EXPOSURES 1987. 51pp. 8704090025 IEB-80-24 40464.058. AT NUCLEAR POWER PLANTS Case Study PWR Dunng An On October 24,1980, IE Informaton Notice 80-37 was issued Outage. MOELLER.M P ; MARTIN.G F.; KENOYER.J L Batteile by the NRC to descnbe reactor vessel pit flooding which had Memonal Institute, Pacific Northwest Laboratores August 1987. been Oscovered a week earher at Indian Po nt 2. The newer 145pp. 8710080227. PNL 5606 42993 327. nine feet of the reactor vessel had been wetted whde at operat-This repo"t is the second in a series of C4se stud es desgned ing i Imperature, and a thermal stress cond, ton of potential to evaluate the magnitude of ocrease in occupatonal rada$on safety s gruficance had been caused IE Bunetin 80-24 was exposures at commercial U S nuclear power plants resulting issued by the NRC on November 21,1980 because of concern from sma'l incidents or abnormal events. The event ovatuated is about this event. Licensees of operatog power reactors were fuel claddng fadure, which can result in elevated pr mary cool- regg, red to take short term actons to ensure continued intenm ant activ<ty and increased ra$aton exposure rates within a operaton without contarnment floodng The long term purpose plant For this case study, redaten measuremer.ts were made of the buhetm was to obtain operatog data on which to base at a pressurized-nater reactor (PWR) dunng a ma<ntenance and future NRC requirements for genenc corrective actons The bul-refueling outage The PWR had t+en operating for 22 months letin was issued to holders of constructon permits for informa. with fuel claddog failure charactenzed as 105 ptn-hole leakers. tion, inspection requirements for reviewing licensee actons the equivalent of 0 212 percent failed fuel Gamma spcetrosco- were etang,ed by issung Temporary Instruction 2515/47 on De-py measurements, raf aton esposure rate determinat on, ther- cember 18.1980, and a special memorandum on February 19, moluminescent dosameter (TLD) assessments, and air sample 1981. Evaluaton of utihty responses bcensee event reports. an anafyses were made in the plant s rad *aste, pipe penetraton, NRC/IE memorandum, NRC/IE inspecton reports and an NRC/ and containment bud @ngs Based on the data coUected, evalua-lE letter shows that the bulletin can be closed per specific cnte-tons indicate that the retatrve contnbutons of actuaton procl- na for all of the 69 facil. ties to which it was issued for acton, ucts and fisson products to the total exposure rates were con-stant over the duraton of the outage This constancy is due to and that no further acton is necessary the significant contnbuton from the longer trved isotopes of NUREG/CR 4527 V01: AN EXPERNENTAL INVESTIGATION OF cesium (a fisson product) and coba!t (an activaton product) INTERNALLY !GNITIED FIRES IN NUCLEAR POWER PLANT For this reason, fuel clad 4ng faduce events remain as sgruf" CONTROL CABINETS Part 1 Cabinet Effects Tests cant to occupatonal rataten exposure during an outage as CHAVEZ) M Sanoa Natonal Laboratores Aprd 1987.115pp dunng routine operatons As documented m the previous case 8707060099 SAND 86-0336. 4 t 563 285 study (NUREGICR-4485 Vol 1), fuel clad 6ng fadure events in-creased ra$aton exporire rates an estimated 540 percent in A series of full scale cabinet fire tests was conducted by some areas of the plant dunng routine operat ons Consequent- Sand.a Natonal Laboratones for the U.S Naciear Regulatory fy, such events can resurt in sgnificantry greater radaten espc Commisson. The cabinet fire tests were prompted by the po-sure rates in rnany areas of the plant dur ng the maintenance tential threat to the safety of a nuclear power plant by a cabinet fire in either the control room or o a switchgear type room The and refueong outages than wou6d have been present under purpose of these cabinet fire tests was to charactente the de-normal fuel corvtitions velopment and eMects of internany ignated cabinet fires as a NUREG/CR 4491: DEVELOPMEN1 OF MODELS FOR WARM functon of several parameters believed to most influence the PRESTRESSING

• Matenals Engineering Associates, Inc burning process A pnmary goal of this test program nas to test RYBICKl,E F. PROSIG, Inc STONESIFER.R B Computatonal representatrve and credde confquratons and matenals. This Mechanics January 1987. 78pp 8702060276 ME A 2122 senes of 22 cabinet fire tests demonstratad that fires in eeer 39538 107. benchboard or vertical cabinets *:th ether IEEE-383 quaufted The obi ective cf this protect is to evaluate avadable mathe- cable or unquahted cable can be gruted and propagate How-matical models and associated fracture cntena for predcting ever, fires n,th IEEE 383 ouakfied cabte do not propagate as warm prestress (WPS) ettects A venf+d model of the WPS rapdly not to the er1ent that unquahf.ed cable does Futher.

phenomenon is required before creet for improved low temper- more, the results sho*ed that the thermal environment in the ature toughness can be taken in analyss of postulated accident test enclosure and ad i acent cabenets is not severe enough to scenares such as pressuni-d thermal shock The pnmary basis resutt in autogneton of other combust 4bles. a'though in some of of evaluaton is finite- element andyvs us.ng a highly refined the larger f.res mettog of pastic matenats may occur Smoke mesh and work hardening. modeled by a peece wise knear fit of accumulaton in the room appeared to be the rrest sign f, cant stress-strain data The entena beng evaluated are Ae), (Chell, provem. as smoke obscured the e .w in the enclosure within et al), entical stress (Curry).1 *(p) (Attun) and a cntenon intro- minutes after gniton Essent.any, a cabinet fire can propagate duced %run wheth is related to d.fferent.al CTOD and reneted *, thin a seg e cabinet, hnnever, for the condtor's tested it l [ i 32 Main Citations and Abstracts f does not appear that the fire poses a threat outside the burnog granrte cubes containing saw cuts, three 23-cm Gameter ande- i cabinet en,ept the resultog smoke. site cores containing induced tension cracks, and one 15-cm 6- 3 4 NUREG/CR 4530 V02: U.SJFRENCH JOtNT RESEARCH PRO-amter ma@e cue contamog a naval fracue, Pror to grout-mg, the hydrauhc conductivity of the fractures is determined GRAM REGARDING THE BEHAVtOR OF POLYMER BASE  ; under a range of normal stresses, apphed m the loadog and un- e MATERIALS SUBJECTED TO BETA RADIATION. Volume 2: Phase-2a Screening Tests. BUCKALEW,W H.; WY ANT,F.J.; loadog cycks, kom 0 to 14 Wa (2000 pst Gout is Wd j CHENION.J.: et al. Sande National Laboratones. September through an axial borehole, at a pressure of 1.2 to 8.3 MPa (180 i 1987, 59pp. 8712280236. SAND 86-0366. 43815 242. to 1200 ps), pressure selected to provide a hkely groutable ,; As part of the ongoing joint NRC/CEA cooperabve test pro- fracture aperture, whsle the fracture is stressed at a constant l

gram to mvestgate the relauve effectiveness of beta and normal stress. The fracue permeam is measured ah gw-

[ gamma arradation to produce damage in polymer base maten- ng. Flow tests on the ungrouted samples confirrn the mverse sis, ethylene propylene rubber (EPR) specimens, in slab geome- relaton between normal stress and tracturo permeability. The ,! try, were exposed to Cobalt-oO gamma rays and accelerator equivaient aperture determned by these tests is a rehable ino- , produced electron beams Specimens were irradated and eval, cator of groutabihty. Post-groutmg permeabihty measurements  ;

uated at research facihties m the U.S. (Sanda Nabonal Labora. as performed here, and frequently n practice, can be enslead- p tores) and France (Compagnie OR15 industre). These tests m. mg, sece ecomplete groutog of fractures can result m maior  ;

' cluued several etectron beam energies, sample tNcknesses, ex. apparent reductions m permeabihty. The apparent permeabihty posure doses, and dose rates. Based on changes o the tensde reductco is caused by grouting of a small area of a Nghly pref-propertes of the test specimens, iesults of these stud es sug. erential flowpath directly ad}acent to the hole used for grouting , gest that matenal damage resultng from electron and gamma and for permeabihty testing Expenmental results confirm claims ' irrasatons can be correlated on the basis of absort.ed ra$aton in the hterature that ordinary portland cement madequately pen. eates foe fractures. Jose for several EPR formulations m stab geometry. ( NUREG/CR-4531: AN INVESTIGATION OF INTEGRAL FACILITY N,' REG /CR 4550 V01: ANALYSIS OF CORE DAMAGE FRE-SCALING AND DATA RELATION METHODS (INTEGRAL OUENCY FROM INTERNAL EVENTS. METHODOLOGY

• SYSTEM TEST PROGRAM). LARSON,T.K. EG&G idaho, Inc. GUIDELINES HARPER.F.T.; CAMP,A L. Sandia Natonal Lab-(subs. of EG&G, Inc.). February 1987,129pp. 8704080137. oratones. DROUIN M.T. Science Apphcations internatonal Corp.  !

EGG-2440 40440:178 (formerty Scence Apphcatons, Inc.). September 1987. 292pp. The intopal Systems Test Program was irwtiated #n 1982 by 8711250143. SAND 66-2084. 43450:190. i 4 government and mdustry in response to the Three M,le Island NUREG 1150 examines the nsk to the pubhc from a selected I accident Three 6fferent etegral test facihtes, each scated to a group of nuclear power plants TNs report desenbes the meth-Babcock and Wdcon desgn nuclear s:aam suppty system, wdl odology used to estimate the eternal event core damage fro-  : ultimately contnbute data to the program. Eaci of the facdities quencies of four plants m support of NUREG 1150. In ponctple, l i was de9gned using afferent scalog methodoiogies, and each tNs methodology is smlar to methods used m past probabihstic , i has different operateg capabikties The overall scaling of each nsk assessments; however, based on past stuees and using a facility is examined m tNs report, and local scalog is anatyred analysts that are expenenced m these techniques, the analyses , to demonstrate potential smlantes and dissmtantes m facdity can be focused m certain areas. In tNs approach, only the most [ response relative to expected plant responses. The scahng rela- important systems and f ailure modes are modeled m detail. Fur- -

tonsNps are used to show how local thermal-hydrauhc phenom- ther, the data and human rehabikty ana'yses are simphfied, with i 1 ena m each facahty can be compared to each other or to ex- emphasis on the most important components and human ac- E j pected plant behavor, The concept of an equ%num plot is tons. Utng these methods, an analyss can be completed n $m I j used to Show how the global response of each facihty can be to nine months useg two to three full-hme systems anatysts [

related for a specafic small break loss-of cootant transaent. Po- and part-time personnel m other areas, such an data anatySs j j tential comphcatons that may anse as a consequence of the fa- and human rehabdity anaySs s TNs is sgnificantry faster and 5

cthty scahng or facihty hintatons are enumerated The potental less costty than previous ana%es and proedes most of the m- i i use of dimensionless groupings for relating and specifyeg en- s,ghts that arv obtained by the more costly studes.

penments is d%ussed Finally, some specific expenments and conetone ,,e proposed for the purpose of vmphtyeg mterfac6- NUREG/CR-4550 V03: ANALYSIS OF CORE DAMAGE FRE-hty companson of test results. QUENCY FROM INTERNAL EVENTS SURRY UNIT 1. 1 NUREG/CR 4534: ANALYSIS OF DIFFUSION FLAME TESTS I at Laboratores. November 1986. 466pp. 8704130170 SAND 86-SHEPHARD.J E. Sanaa Natonal Laboratones. August 1987. 2084.40512:157 i 89pp. 8710010109. SANO86-0419 42881:333 This document contains the accident sequence for Surry, Urvt TNs report escusses the results and anatysis of hydrogen d.f. 1: one of the reference plants being examened as part of the  ! 1 fuson flame tests conducted at the Nevada Test Sde by EPRI NUREG 1150 effort by the Nuclear Regulatory Commcssion and the USNRC. Those tests were dessned to simulate the ef' (NRC). NUREG 1150 will document the nsk of a selected group r fects of hydrogen combuston m9de a nuclear power plant con- of nuclear power plants As part of that work, tNs report con- {i taenment following a degraded core accident Test irttial cond" tains the overall core damage frequency estimate for Surry, Urvt ~ teons and sample data plots are grven for 16 tests. Mmng and , 1, and the accompany ng plant damage state frequences. Sen. i ignaton phenomena are escussed m terms of the source pa' Stnrity and uncertainty anatyses provide adetsonal msghts re. , rameters and igniter locatort A samp4e model is developed fo' gars.ng the dominant contnbutors to the Surry core damage fre-

simulating the heat transfer and computirg convective heat quency estimate. The mean core damage frequency at Surry 1 transfer coettic>ents for expenmental pressure measurements was calculated to be 2 EE 5 per year. Station blackout type ac-l Convective heat transfer coefficients are reported for four tests cadents (loss of all AC power) were the largest contnbutors to t The effect of stagnaten point beat transfer is estimated core earnage frequency accounting for approsimatery 38% of

] NUREG/CR 4541: EXPERIMENTAL ASSESSMENT OF THE the total The next type of dominant contnbutors were transient i l SEAltNG EFFECTIVENESS OF ROCK FRACTURE GROUT. induced LOCAs caused by loss of eetncal bus init,ators ( ING SCHAFFER.A : DAEMEN.J J Argona, Unrv of. Tucson, These sequences account for 19% of core damage frequency ' . A2. March 1987.191pp 8704010149. 40340 0$0 No other type of sequence accounts for more than 10% of core i The obfective of thrs investgaton rs to deternine the effec- damage frequency The numencal results are drrven to some trveness of cement grouts as sealants of fractures e rock Lab- degree by modehng assumptons and data selecton for issues oratory expenments have been conducted on seven 15-cm such as reactor coolant pump seal LOCAs. common cause fani-i l - - . - = - . -_ -- . - , . _. Main Citations anC, Abstracts 33 Ure probab&tes. and plant response to staton blackout and as part of the NUREG 1150 effort by the Nuclear Regulatory loss of electncal bus otators The sens1tmty stud es explore Commiss.on. NUREG- 1150 *,11 document the risk of a selected the irnpact of afternate theories and data on these issues The group of nuclear power p! ants. As part of that work this report resu'ts of the uncerta.nty and sens2tivrty analyses should be conta rs the overall core damage frequency estimate for Grand considered before any future actons are taken based on this Gu!f Unit 1 and the accompanyng plant damage state frequen-analy sis. c.es Sensitety and uncertainty anahses provide addetonal in-NUREG/CR 4550 V04: ANALYSIS OF CORE DAMAGE FRE- sights regard:ng the dominant contnbutors to the Grand Gulf OUENCY FROM INTERNAL EVENTS PEACH BOTTOM UNIT cae damage hquency esbmaw he mean core damage ke-

2. KOLAC2KOWSKI.A.; LAVBRIGHT,J A ; FERRELLW L ; et al. quency at Grand Gutt was calculated to be 2.9E 5. Stat on Sandia Natonal Laboratones October 1986 663pp. blackout type accidents Ooss of aft AC po*er acc4ents) were to dommaw the owau resWs AnWpated transent *o 8703090175 SAND 86 2084. 39319 315 This document conta ns trvs internal event ntiated accdent out scram accdents were also found to be Contnbutors. The nu-sequence ana!yses for Peach Bottom. Unit 2, one of the refer. mencal results are largely dnven by common mode f ailure prob-ence plants be;ng enamined as part of the NUREG 1150 effort abaty est. mates and, to some extent. human error. Because of by the Nuclear Regulatory Commisson. NUREG 1150 *,il docu-seficant data uncertainties in these two areas, it is recom-ment the risk of a selected group of nuclear power plants. As mended that the resutts of the uncerta:nty and sensetmty anaty-part of that work. this report contars the overall core damage ses be consdered before any future actons are taken based on frequency estimate for Peach Bottorn. Unrt 2. and the accompa- this anahsis in particular, the single most dominant scenarc nyng ptant damage state frequencies Sens:tmty and uncerta.n- may rMuse a more deta: led data search and analysis before actons are implemented on the bases of this sCenarc.

ty anahses provde add t onal msghts regarding the dominant contnbutors to the Peach Bottom core damage frequency este-NUREG/CR 4550 V06PT2: ANALYSIS OF CORE DAMAGE FRE-mate The mean core damage frequency at Peach Bo' tom was calculated to be 8 2E 6 Staton Blackout type accidents (loss of OUENCY FRCM INTERNAL EVENTS GR AND GULF. UNIT 1 Appendices DROUiN M T.; LACHANCE.J L; SHAPiRO.B J ; all AC power) were found to dominate the overall results Antic" et at Sanaa National Labcratones. Apnt 1987. 653pp pated Trans ents Ethout Scram accidents were a'so found to 8707080295 SAND 86 2084 41619 317 be non neghg=bre contrbutors The numencal resufts are targefy See NUREG/CR-4550.V06,PT01 abstract. drrven by common mode faaure probabWty est> mates and to some eatent. human error Because of sign:f cant data and anal- NUREG/CR 4551 V1 DRF: EVALUATION OF SEVERE ACCl-ysis uncerta.ntees in these two areas bmportant, for instance to CENT RISKS AND THE POTENTIAL FOR RISK the rnost dominant scenarc in this study), it is recommended REDUCTION SURRY POWER STATION. UNIT 1 Draft For Com-that the results of the uncerta:nty and sensrtroty ana'yses be ment BENJAMIN.A S ; BOYD.G J ; KUNSM AN.D M ; et a!. considered before any actions are taken based on this ana'rs's Sand.a Natonal Laboratones February 1987. 720pp NUREG/CR 4550 V05: ANALYS:S OF CORE DAMAGE FRE, 8703170262 SAND 861309 43044 071 QUENCY FROM INTERNAL EVENTS SECUOYAH. UNIT 1 The Severe Accident Risk Reducton Program (SAR AP) has BERTUCIO.R C ; VOORE.D La HE LD.J T.. et at Sand a Naton. completed a rebasebrung of the risks to the pubhc from a par-al Laboratones Fcbruary 1987. 424pp 8705200221 SAND 66- t cular pressunied nater reactor mth a subatmosphenc contain-2084 40985 101. ment (Surry, Unit 1) Empnasis was placed on determening the This document contains the accident sequence anaNsc5 for magnitude and character of the uncerta4nt es, rather than focus-Sequoyah. Un,t 1, one of the reference plants be,ng eaamined mg on a point estimate. Tne nsk-reducten potential of a set of as part of the NUREG-1150 effort by the Nxlear Regulatory proposed safety opton backt.ts was also stud led, and their Commesson (NRC) NUREG 1150 *at document the r:sk of a costs and benefits were a'so evaluated it was found that the seiected group of nuclear power plants As part of that work, risks from interna! events are genera 0y lov.er than prevous:y this report conta,ns the overa!i core damage frequency esumate nabaN in the Reactor Safety Study (RSS) However, certain for Sequoyah. Unit 1. and the accompanying ptant damage unresoNed issues (such as direct contaenment heatng) caused state frequencies Sens:troty and uncerta.nty analyses provide the top cf the uncertaenty band to appear at a level that is com-add tonal insights regarang the dominant contnbutors to the P8'at'e *:th the RSS po,nt estimate None of the postulated Sequoyah core damage frequency ertimate The mean core satery optons appears to be cost effectrve for the Surry pc*er damage frequency St Sequoyah was calculated to be 1 OE 4 per piant Thas work supports the Nxiear Rega!atory Comtrusson's year Small LOCAs

• th falure of emergency cootant recereuta, assessment of severe accidents in NUREG-1150 ten account for over ha't of core damap frequency Lcss of compocent cochng water, lea 1ng to a mactor coolant pump NUREG/CR 4551 V2 DAF: EV ALUATION OF SEVERE ACCl-seal LOCA is the next largest contr:bumt accounting for nearty CENT RISKS AND THE POTE NTIAL FOR RISK one third of core damage fragsency Staton blackout se- REDUCTION SEQUOYAH POWER STATION UNIT 1 Draft For Comment BENJ AVN A S , kUNSVAN.D M ; LEWIS.S R , ct af quences accou n t for 5% of core vage frequency No other sequence types account for more t*.an 5,. of core damage fre- Sand a Natorial Laboratones Fet<uary 1987. 516pp quency The numencal resu"s a'e infhienced ty modeng as' 87M120125 SANDe6-1309 41283 076 sumptons and data selecton for issues such as coolant pump The Severe Accident R;sk Reducton Program (SARAP) has

, g g , seal LOCA. common cause f a lur e probabet<es. and operator re-sponse to emergency cond. tons such as sman LOCA and sta-r ert e e e m e w m m ton blackout The sens,tury stud <es emptore the impact of a'ter- ment (Sequoyah. Un.t 1) Emphas s was placed on determirvng mantude and character o' the uncer13.nt.es, rather than to-nate theones and data on these issues The results of the un- cusing on a pcynt estima e The nsk-reducton potential of a set certainty and sensat>cty ana'yses should te considered t(tore g g g g any futur e actcns are taken basfd or1 this anaNs:s NUREG/CR-4550 V06PT1: ANALYSIS OF CORE DAY AGE FRE- ns6 s frorn internal events are generacy compa able to those OUENCY FROV INTERNAL EVENTS GR AND GULF. UNIT evaVated in the Reactor Safety Study for a d:tterent pressunied 1 Main Report DROU;N.V T . LACHANCE.J L , SH AP;RO B J , mater reactor. a'though the calcula'ed uncerta:nty bats inda et al SanO4 Natonal Laboratones Apol 1987 51 app cate that the nsk could be Ngher or lower by as much as an 8707080284 SAND 86 2084 41618163 order of magnitude Pr.ncpe sources of uncertainty eclude the The$ document conta.ns the accioent sequence anabses for mn hng of common-cause f aau re in the component cootng Grand Gulf Unit 1. ord of the reference plants be ng esamined mater system, the character st>Cs Cf hydrogen generaton and 34 Maln Citations and Abstracts burning. and the poss-baty of frs9on product releases that events are genera 0y low relat$e to prey,ous studies; for enam-bypass the ice condtnser. Most of the postulated safety optons ple, most of the uncettamty range is lower than the pont este do not appear to be cost efiectrve for the Sequoyah plant; how- mate of nsk for the Peach Bottom plant in the Reactor Safety ever, ce<1ain relat<vely inexpensive hard*are and procedural Study (RSS) However, certain unresolved issues cause the top changes to prevent core damage appear to be marg'naPy cost of the uncertainty band to appear at a level that is comparable effectae it should be noted that th,s work is based on a draft eth the RSS pont estimate These issues include the desel report of the ASEP study of core-dama2e frequency for Se- generator failure rate, od.ne and cesium reevoluton after vessel quoyah The f>nal ASEP resutts have lower frequencies for sta- breach, and the possbkty of reactor vessel pedestal fadure ten-blackout sequences These final ASEP resuits will be incor- caused by core debns attack. Some of the postulated safety op-potated in the final version of this study The d.tferences are not tons appear to be potentialty cost effectrve for the Grand Gulf espected to cause significant changes in the conclusons of the power plant, partcuiarty when onste accident costs are includ-report because risk is influenced by a vanety of accdent 50- ed in the evaluaton of benefits. Pnncipa ly these include proce-quences, not just staton brackout This work supports the Nu- dural mod <ficatons and relatively inespensrve hardware addi-Clear Regu;atory Comm<ss,on's assessment of severe accdents tions to insure core coohng in the event of a staton blackout. in NUREG 1150 This work supports the Nuclear Regulatory Commisson's as-NUREG/CR 4551 V3 PT1: EVALUATION OF SEVERE ACCI- Sessment of severe accdents in NUREG 1150. DENT RISKS AND THE POTENTIAL FOR RISK NUREG/CR 4552: A REVIEW OF THE SEABROOK STATION REDUCTION PEACH BOTTOM. UNIT 2 Main Report Drar t For PROBABILISTIC SAFETY ASSESSMENT Containment Falute Comment AMOS.C N ; BENJAMIN.A S ; BOYD.G J.; et al Modes And Ra$olog<al Source Terms. KHATIB-R AHSAR, Sand a Natonal Labora". irs Aoni 1987. 244pp 8707060116 AGRAWALA K.; LUDEWlG.H : et al. Brockhaven Natonal Labo-SAND 86-1303 41593 078 ratory. March 1987. 75pp 8704090039. BNL NUREG 51961 The Severe Accident Risk Reducton Program (SARRPJ has 40463 244 completed a rebasehning of the nsks to the pubhc from a boihn9 A techtscal review and evabaton of the Seabrook Staton water reactor eth a Mark l conta.nment (Peach Bottom. Unit 2) Probabibstic Safety Assessment has been performed it is deter-Emphasis was placed on determining the magn,tude and char- mined that (1) contatnment response to severe core rnelt acci-acter of the uncertacties, r%ner than focusng on a point esti- dents is fudged to be an important factor in mitgatsng the con-mate. The nsk reduct on potential of a set of proposed safety sequences. (2) fatture dunng the f rst few hours after core mett opton backf:ts was also stud.ed, and their costs and benefits is a!so unhkely and the timing of overpressure failure is very were a!so evaluated it was found that the nsks from internal long Compared to WASH 1400. (3) the point-est' mate radologr events are generany low relative to prevous stud es, for exam- cal releases are comparable in magnitude to those used in pie, most of the uncertainty range is ic*er than the poent este WASH.1400, and (4) the envrgy of release is somewhat higher mate of nsk for the Peach Bottom plant in the Reactor Safety than for the prevousty reve*ed stu4es Study (RSS) However, certain unresoNed issues cause the top of the uncertainty band to appear at a level that is comparable NUREG/CR-4577: AUTOMATED LONG TERM SURVEILLANCE mth the RSS pont est. mate. These issues include the modehng OF A COMMERCIAL NUCLEAR PCWER PLANT. SMITH.C M ; of the common-mode fadures for the dc pc*er system, the 1.ke. GONZALEZ,R C Oak Ridge Natonal Laboratory August 1987. hhood of offs:te po*er recovery versus time dunng a station 66pp 8710080198 ORNL/TM-10015. 42995 290 blackout, the probability of drywell failure resulting from meltth. This report presents and descnbes a pattern recognition rough of the drywell shell, the magnitude of the fisson product system W monitorrng nucleai reactor segnals The system is releases dunng core-concrete interactons, and the decontami. based on detect.ng deoatons from basehne s,gnatures idente naton effectiveness of the reactor enciesure building Most of fed dunng normal plant operaton. The capabiht es and hmaa-the postulated safety optons do not appear to be cost effective, tons of this pat'ern recogmton approach were investigated a!though some based on changes to procedures or inexpen9ve dunng a 21/2 year sere's of c'.ntinuous onhne expenments at hard*are add: tons rney be marg,naHy Cost efioctive This dra't the Sequoyah 1 nuclear r >*er p! ant. for comment of the SARRP report for Peach Bottom does not NUREG/CR-4583 V02: DEVELODVENT AND VAllDATION OF A include detailed technical appendeces, whch are still in prepara. ton. The appendices wdl be issued under separate cover when REAL TIVE SAFT-UT SYSTEM FOR THE INSPECT 60N OF LIGHT WATER RtEACTOR COMPONENTS Annual completed This work supports the Nuclear Regu!atory Commis- Report. October 1984 Septemter 1985 DOCTOR,5 R , son's assessment of severe accidents in NUREG 1150 HALL T E.; REID L D; et al Battel;e Memonal Institute, Pacac NUREG/CR 4551 V3 PT2: EVALUATION OF SEVERE ACCl- Northwest Laboratones June 1997. 85pp 8707080345 PNL-DENT RISKS AND THE POTENTIAL FOR RISK 5822 4 t621314 REDUCTION PEACH BOTTOM. UNIT 2 Appendces Dra't For The Pacific Northwest Laboratory is working to de9gn fabn-Comment AMOS.C N ; BENJAMIN A S; BOYD.G J ; et al cate. and evafuate a real t me flaw detection and charactenza-Sanda Natonal Laboratones May 1997. 531pp 8707060135 ton system based on the synthetic aperture focu9ng technique SAND 86-1309 41591267. for ultrasoriec testing (SAFT-UT) The system is deogned to per. See NUREG/CR-4551,V03 PT01 abstract form inservice especton of hght-water reactor components in-cluded oWyes f this program for the Nuclear Regulatory NUREG/CR-4551 V4 DAF: EVALUATION OF SEVERE ACCI- men am t p pr res system caWawn DENT RISKS AND THE POTE NTIAL FOR RISK aM W paton, to va4date the system through laboratory REDUCTION GR AND GULF. UNIT 1 Drah For Comment a ns, aN to generate an engenng data base AVOSf N ; BENJAM N.A S.; BOYD G J ; et al Sandia Natonal Laboratones Apnl 1987. 761pp 8707060161 SAND 86-1309 to support ASME Code acceptance of the technology T his p $gg gg progress report covers the programmatic *M from Octoter The Severe Accident R,5k Reducton Program (SARRP) has N completed a rebasskning of the risks to the pubhc from a tohng NUREG/CR-4583 V03: DEVELOPVENT AND VALIDATION OF A water reactor n,th a Mark Ill containment (Grand Gu rf, Unit 1) REAL TIVE SAFT UT SYSTEM FOR THE INSPECTION OF Emphases was placed on determang the magstude and char- LIGHT WATER REACTOR COVPONENTS Annual acter of the uncertacties, rather than focus >ng on a point este Report.0ctoter 1985 Septemter 1966 DOCTOR.S R ; mate The nsk-reducton potential of a set of proposed safety HALL.T E , RETD.L D , et al Battene Memonar inst,tute, Paafic opton backfits was a'so studed, and their costs and benet,ts Northwest Laborator es JJy 1997. 73pp 8709210489 PNL-were a so eva6ua'ed it was found that the nsks from entemal 5822 42738 004 1 l l l l Maln Citations and Abstracts 35 The Pac f.c Northwest Laboratory is working to desgn, fabre drynell floor between the pedestal and the containment shell. cate, and evaluate a real-time fla* detecton and charactenza. This report assesses the impact on calculated containment re-t.on system based on the synthet*C aperture focu0ng technique sponse and the producton and release of fisson product-laden for ultrasonic test;ng (SAFT UT). The system is deugned to per- aerosols for two offerent cases of debns cstntoton: Uniform form inservice inspecton of hght *ater reactor components In- dstnbuton and the latera!Py separated case of 95% oudes 5N cluded objectives of this program for the Nuclear Regulatory metals ens 4e the pedestal and 5% ondes 95N metats outude Commisson are to develop procedures for system calibraton the pedestal The computer codes used in this assessment are and feld operaton, to vatdate the system through taboratory CORCON MOD 2, MARCON 2.18, and VANESA. and field mspectons, and to generate an eng neenng data base to support ASVE Code acceptance of the technology. This NUREG/CR 4613: EVALUATION OF NUCLEAR POWER PLANT progress report covers the programmatic work from October OPERATING PROCEDURES CLA%IFICATIONS AND 1985 through September 1986. INTERFACES Problems And Techruques For improvement. BARNES.V E.; RADFORD.L R Battelle Human Affaas Research NUREG/CR 4590 V01: AGING OF NUCLEAR STATION DIESEL Centers

• Battelle Memonal Institute, Pacific Northwest Labora.

GENERATORS EvaWaton Of Operat.ng And Empert tores February 1987. 120pp. 8703120284. PNL 5852. Experence Phase I Study HOOPINGARNER,K ; VAUSE.J W ; 39983 256 DINGEE,0.A ; et al. Battede Memonal Institute. Pacific North- This report presents actmt:es and fin 4ngs of a project de-west Laboratones August 1987, 300pp 8709150302. PNL- $>gned to evaluate current practices and probtems related to 5832.42679 158- procedure clastfcaton schemes and procedure inMrfaces in PacAc Northwest Laboratory evaluated operatonal and commercial nuciear power plants. The phrase "procedure c!as-espert esperence pertaining to the aging degradaton of d,esel S.ficaton scheme" refers to how plant operating procedures are generators in nuclear service. The research, sponsored by the categorged and indexed (e g , normat, abnormal, emergency U S. Nuclear Regulatory Commisson, dentified and character- operat,ng procedures) The term "procedure interface" refers to ced the contnbuten of aging to emergency @esel generato' ho* reactor operators are mstructed to trans t on w' thin and be-failures Volums ' rewews d esel generator experence to ident" tween procedures The protect consisted of four key tsus, m-fy the systems rd components most subrect to aging degrada- clueng (1) a survey of literature regarding problems associated ton and isolates the major causes of f ailure that may affect eth procedure classAcatons and interfaces ethin and between future operatonal rea$ ness Eva'vatons show that as plants procedures, as well as techruques for overcoming them, (2) age, the percent of aging-related latlures increases and f ailure interv ews mth experts in the nuclear industry to d<scuss the ap-modes change A compdaton is presented of recommended proprate scope of d tferent classes of operating procedures and correctae actions for the failures dentifed A review of cu' rent techniques for managing interfaces between them; (3) a reanal-relevant industry programs, research, and standards is included ys:s of data gathered about nuclear power plant normal operat-Volume 2 reports results of an mdustry ede workshop ing and c?f normal operahng procedures in a related protect. NUREG/CR 4590 V02: AG;NG OF NUCLEAR STATION DIESEL "Program Plan for Assessing ano Upgrasng Operating Proce-GENER ATORS Ev aluaton Of Operating And Espert dures for Nuclear Power Plants"; and (4) schettaton of the com. E spenence Workshop HOOPINGARNER.K.; VAUSE.J W. Bat- ments and empert openons of a peer review group on the draft telle Memonal Institute, Pacific Northwest Laboratones August pro;ect report and on proposed techneques for resolving classif>- 1987. 69pp 8709150331. PNL 5832. 42678 301 cat.on and intedace issues. In adoton to desenbing these ac-Pauf c Northwest letnratory evaluated operational and tyttes and their resu!!s, recommendations for the NRC and utile expert expenence pertainmg to the aging degradatcn of Gesel ty actons to address procedure clastfacaton and entedace generators in nuclear service. The research, sponsored ty the problems are offered U S Nuclear Regutatory Commis9on, dent;f.ed and character-ized the contnbution of agtng to emergency d.esel generator faavres This report, Volume 2, reports the resutts cf an indus. PORT IN THE UNS ATUR ATED ZONE. Workshop Proceedings SPRINGER.E Pa FUENTES,H R. Los Alamos Natond Laborato-try-wee workshop held on May 28 and 29.1966 to d scuss the technical issues associated mth ag ng of nuclear seroce emer- ry Aprd 19e7 250pp 8705190513 LA 10730-MS 40976191 gerx.y aesel generators The techrucal issues escussed most These proceed >ngs mclude the technecal papers, a panel extensvety were man / mach.ne mterfaces, component inter, summary report. and escussions held at the workshop on Mod-faces, thermal gra$ents of startup and cooldown and the need ebog of Solute Transport in the Unsaturated Zone held June 19 for an accurate industry database for trend anatys,s of the 20,1986, at Los Alamos, New Mexico The central focus of the desel generator system Volume 1 reports the resutts of the *0'kshop was the anahsis of data collected by Los Alanios Phase i research under agreement w'th the U S Nuclear Regulatory Commesson on intermedate-sca'e ca sson empe iments. Frye d.fferent mod-NUREG/CR 4610: EFFECTS OF LATERAL SEPARATION OF ehng approaches were used The purpose was to evaluate OX1DiC AND METALUC CORE DEBR:S ON THE BWR MK I models for near surface waste d sposal of low level radcactive CONTAINMENT DRYWELL FLOOR HyMAN,C R . WEBER.C F wastes The workshop was part of a larger study being Conduct. Oak Rdge Natonal Laboratory January 1987. 118pp ed by Los Alamos on transport in the unsaturated zone under 8704080065 ORNL/TM 10057 40444 007 agreement mth the U S Nuclear Regulatory Commession in evaluating core debris / concrete for a BWR MK I contain-ment de9gn. it has been common practice to assume that at NUREG/CR-4616: ROOT CAUSES OF COMPONENT FAILURES reactor vessel breach, the core debris is homogeneous and of PROGRAM Methods And Apphcatons SATTERWHITE.D ; low vacosty so that it is unoormly estnbuted raf ally on the CADWAlt ADER.L. ME ALE.B M , et at EGAG idaho. inc (subs drywell f'oor. In a recent study periormed by the NRC-spon- of EGaG. inc ) December 19r36 60pp 8702060177. EGG-2455 sored BWR Severe Accdcnt Technology tBWRSAT) program at 39526 227. Oak Roge Natonal Laboratory. calculatons and< ate that at re- This repor1 contains informaton pertairung to det.netons. actor vessel bottom head fadure, the debns is such that tne me- methodolog.es. and apphcat.ons of root cause analysis Of spe-tanic components (Zr, Fe, Nu Cr) are completely molten wh,le cdic interest, and hig%ghted throughout the discusson, are ap-the orec components (UO2. ZrO2, FeO) are completely frozen pacatons perta ning to curreni and future Nuclear Regu'atory Thus, the frozen ondes are espected to rema:n withen the reac- Commisson (NRC) hgh; water safety programs These appbca-tot pedestal whde the rnotten rnetalkc speces rad a4y separate tons are 65 cussed in ven of addressing spec fic program from the frozen onec species, t'ow through the opening m the rssues under NRC consoeraton and reflect cunent root cause reactor peestal, and spread over the annutar regon of the anahsis capabstes 36 Main Citations and Abstracts NUREG/CR 4617: ONSITE ASSESSMENTS OF THE EFFEC- Pacific Northwest Laboratory is conduct.ng a research project TiVENESS AND IMPACTS OF UPGRADED EMERGENCY OP- to recommend good engineenng practices in the apphcaton of ERATING PROCEDURES MEYER.O R.; B LACKM AN,H S : 10 CFR 50, Appendix B requirements to assure quahty in the FORD.R E.; et at EG&G Idaho. Inc (subs of EG&G. Inc ) development and use of computer scitware for the design and March 1987.167pp. 8706220014. EGG-2456 41415 226. operation of nuclear power plants for NRC and industry. This The implementaton of upgraded emergency operating proce- handbook defines the ;ontent of a software qualty assurance dures (EOPs) by the nuclear utileties supports Three M.le Island program by enumerating the techniques apphcable. Definetons, (TMI) Acton Plan items LC.1 and LC 9. This is the final report of descriptens, and references where further informaton may be a research project c:rected at assessing the costs and benefits obtained are prowded for each topic. of the resuttant EOPs A dual methodology was used to assess effectrveness; expenmental and onsite data collecton. A simula- NUREG/CR 4645: TOUGH USER'S GUIDE. PRUESS,K. Sandia tor-based, laboratory expenment was conducted, wh.ch was de- Natonal Laboratones

• Lawrence Berkeley Laboratory. August signed to b5 Sens;tive to changes in operator effectiveness 1987. 348pp. 8710300024. SAND 86 7104. 43225 075 using functon onented EOPs versus event based EOPs The This document conta.ns a technica! descnot on of the onsste data collected were related to the effectiveness of up. TOUGH computer program, which was developed at Lawrence graded EOPs as implemented with a!I attnbutes (e g . functon Berketey Laboratory for simulating the Coupled transport of onented, human factored, etc ). The acceptance of the upgrad- water, vapor, air a'.d heat in porous and fractured med,a The ed EOPS by the control room operators was a!so measured. A physcal procasses tanen ento account in TOUGH are dis.

cost /benef.t ratio for upgraded EOPs was est, mated per reguta, cussed, and the governing equatons actually solved by the sim. tory anaNsis guidehnes Summary conclusons a'e disclosed as ulator are stated in full detail. A boef overview is given of the to the uttamate benefits of the upgraded EOP program for the mathematical and numencal methods, and the code architec-regulaton of the safety of commercial nuclear power plants ture. The report provides detaded instructons for prepanng input decks. Code applicatons are illustrated by means of six NUREG/CR 4623: IN-SITU STRESS MEASUREMENTS IN THE sample problems. EARTH S CRUST IN THE EASTERN UNITED STATES RUNDLE T.A.; SINGH,M M ; BAKER.C H. Eng neers intemat on. NUREG/CR-4651: DEVELOPMENT OF R!PRAP DESIGN CRITE-al, Inc. Apnl 1987. 609pp 8705120101. 40900 099 RIA BY RrPRAP TESTING IN FLUMriPhase I LEE.D W.; In-sttu stress measurements were made in three susmic HINKLE.N E. Oak Ridge Natonal Laboratory. ABT.S R.; et at areas en the Eastern United States, using the hydrauhc fractur. Colorado State Univ . Fort Colhns CO May 1987. 120pp ing technique. The areas covered were 0) Moodus. Connecticut, 8705280379 ORNL/TM-10100 41100 230. (le) the Ramapo fauft system, and tm) the Central Virginia seis- Flume stud 2es were wonducted in which nprap embankments mec zone. At each locaton, one borehole was dnded with:n the were subi cCted to overlopping : lows Embankment slopes of t, seismic zone and the second outside rt. so as to compare the 2,8.10 and 20% were protected with nprap layers with med,an results obtained No geolog.c interpretatinn of the data was stone sees of 1, 2. 4, 5 and/or 6 inches Riprap design entena made dunng this profect. for overtopping fions were developed in terms of unit drscharge NUREG/CR 4626 V02: IMPROVING THE RELIABlLITY 0F layer res'istance to flow over the norap surface, potent.ai m- i OPEN-CYCLE WATER SYSTEMS Apphcat on Of Biofoubn9 pacts of the fitter blanket on the nprap layer stab +ty, and the Survedlance And Control Techniques To Sedment And Corro-effects of flow concentraton on the r'prap stabaty The result-son Foukng At Nuclear Power Plants. JOHNSON.K l ; ing nprap desgn cntena were compared to the Stephenson, the NEITZELD A Battene Memonal Inst.tute, Pacific Northwest U S Army Corps of Eng=neers, the U S Bureau of Reclamaton. Laboratores March 1987. 55pp 8703300146. PNL 5876 and the Safety Fa: tors methods for nprap stone design, the 40200 22# Leps relaton for interst t,al velocities through nprap, and the An. Biotouhng Surveillance and control technrques are evaluated derson et at and Corps of Engineers relatonships for estimat-for theer apphcat>l4y to secment and corrosen fouhng and sug- ing Manning's n values for resistance to flow gestons are given to improve their effectiveness A!ternative techniques to better detect and control sedimentaton and Coc. NUREG/CR-4653: GASPAR 11 TECHNICAL REFERENCE AND rosen are also evaluated Environmental cond>t ons that a4cw USER GUIDE STRENGE.D L. BANDER.T J , SOLDAT.J K Bat-befouhng, se6mentaton, and corroson to occur are summa. telle Memonal Inst.tute. Pac.fic Northwest Laboratones March nzed A correlaton between sed. ment and corrosion is cent fied 1987 61f pp 8707090389 PNL 5907 41631:179 and the causes are desenbed Env6ronmental regu!atons, espe. The Nuclear Regulatory Commason's GASPAR ll computer ciaMy those in the Clean Water Act of 1977. are reviened to program performs ervironmental dose analyses from releases edentfy those that may hmit or prevent the use of surveillance of radcactve effluents from nuclear po*er plants into the at-and control technques desenbed in this report Flow velocity is mosphere The ana'yses estimate rad aton dose to indviduafs the mayor desgn factor that determ nes whether or not befoul- and popu!aton groups from inha'aton, engeston. and externa! ing, sedimentaten and corroson *di occur Monitonna flow esposure pathways The estimated doses provide informaton conatons can provce early warn.ng of cond tons that wal a!!ow for Natonal Environmental Pohcy Act evaluatons and for deter-fouhng to occur. Visual inspecton is the most common and mining comphan<.e with Append i i of 10 CFR 50 This report most eMectrve technique for identfring the cause and entent cf descnt.es the mathematical mode l% used in the G ASPAR 11 foubng in the ocen-cycle water system Most befouhng control computer program, instructs the user en prepanng input to the techniques in current use are not effective aga,nst se$ ment and program and supphes detaded informat.on on program structure corroson Frequent, high-velocdy fr ushing of coobng loeps may and parameters used to mod fy the program e*fectrvely remove sediment and reduce under sediment corro-son Ahernative boc de treatments such as tageted chlonna- NUREG/CR 4654: R AD ONUCLICE TRANSPORT AS VAPOR ton or the use of ozone or 2, 24 bromo-3-nitrdo proponam4e THROUGH UNSATUR ATED FR ACTURED ROCK GRE EN R T " l (DBNPA) may atso be eMectrve in reducing undeer-sed ment cor- EVANS D D Antona Unew of. Tucson, AZ July 198 7 19)pp  ! '05*" 870804C263 42036 028 l The ot;ect:ve of this study is to dentfy and examine potentia l NUREG/CR 4640: HANDBOOK Of SOFTWARE QUAliiY A S- mechanisms of radonuchde transport as vapor at a hegh-leve! l SURANCE TECHN CUES APPLICABLE TO THE NUCLE AR IN- rt:3cact<ve waste repos> tory located in unsaturated tractured ' DUSTRY, BRY ANT,J L. WILBURN.N P Battene Memonal Insk rock Transport mechanisms and processes have been investe tute, Pacific Northwest Laboratones August 1987 113pp gated n(.ar the reposatory and at larger 6 stances Transport Bf09090601 PNL 5784 42594 001 mechanisms potent any important at larger d stances include or- M:In Citations and Abstr: cts 37 dinary d,ffusion, vescous flow and free convecten. Ordenary dif- NUREG/ ;R 4664: CLOSEOUT OF IE BULLETIN 83 04. FAILURE fuson includes se:f and binary d.f4uson. Knudsen flow and sur- OF THE UNDERVOLTAGE TRIP FUNCTION OF REACTOR face diffuson. Pressure flow and shp flow compnse viscous TRIP BREAKERS. FOLEY,W J ; DEAN.R S ; HENNICK.A. Pa-flow Free conYeClive flow results from a gas density Contrast. rameter, Inc. May 1987. 31pp 8706240323. IEB 83-04. Transport mechanisms or processes dominant near the reposu 41439 216. tory include ordinary d.ffuson, viscous flow plus several mecha- Dunng shutdown of San Onofre units 2 and 3 on March 3 and rusms whose dnveg forces anse from the non isothermal, rado- 8,1933, four General Electnc (GE) Type AK 2 circuit breakers actue nature of high-level waste The add.tional mechanisms in- in the reactor protecten systems (RPSs) f aded to open on acte clude forced dMuson aerosol transport, thermal diffuson and vatcn of the undervoltage tnp coil dunng testing Since issu-thermophoresis Near a repository vapor transport mechanisms ance of IE Bulletin 79-09 Apol 17,1979 on fattures of GE Tyre and processes can provde a signifcant means of transport AK 2 breakers, add <teonal falures had been reported before the from a failed canister to the geologc medium from which other tests at San Onofre. Because of concern about continued fa>I-processes can transport radonucides to the accessbie envb ures of the subject breakers in RP$s, the NRC/IE issued IE ronment These issues are beheved to be important factors that Bulletin 83-04 on March 11, 1983 All licensees of operating must be addressed in the assessment of specific engineenng pressunzed water power reactors, except those with Westing-designs and site selecton of any proposed HLW reposrtory house Type DB breakers, were requeed to take five specific ac-tons The bulletin was issued for informaton to all other nuclear NUREG/CR-4655: UNSATURATED FLOW AND TRANSPORT power f acat es Evaluaton of utety responses and NRC/IE in-THROUGH FRACTURED ROCK RELATED TO HlGH-LEVEL specton reports indicates that the budetin can be closed out for WASTE REPOSITORIES Final Report Phase 11-all of the 50 facitatres to which it was issued for acten. Six RASMUSSEN.T C.; EVANS.O D Anzona Univ. of, Tucson. AZ- plants had breakers which failed to operate satisfactorily dunng May 1987. 499pp. 8706150101. 41298.131- tests for tunetin requirements. There are no remanng areas of in response to high-level rad.oactive waste repos4 tory bcens' concern for this butictin. ing needs of the U S Nuclear Regulatory Commisson, this report examines and provides insights into physical charactens- NUREG/CR 4667 V03: ENVIRONVENTALLY ASSISTED CRACK-tics and methodologies for performance assessment of candi- ING IN LIGHT WATER REACTORS Semiannual Report.Apni-date sites in unsaturated fractured rock The focus is on the September 1986. SHACK,W J ; KASSNEH.T F.; MAlYA.P S : et abaty of the geologic medium surround ng an underground re- al. Argonne Nat onal Laboratory October 1987. 89pp. pos< tory to isolate radonuchdes from the accessible env ron- 8601070270 ANL 87 37. 43944 351. ment Media of mterest are cor'soldated rocks w,th vanable This progress report summanzes work performed by Argonne fractunng, rock matnx permeabiht>es, contained water under Natonal Laboratory on environmenta4y assisted cracking in negatrve pressure. and air fmed vods Temperature gradients hght water reactors dunng the su months from Apni 1986 are a!so of interest. Studies present conceptual and theoretical through September 1986. cons deratens physical and geochemical charactenzaten, com-puier modehng techniques, and parameter estimaton proce- NUREG/CR-4672: ANALYSIS OF INSTRUMENT TUBE RUP-dures Radonucide transport pathways are as solutes in TURES IN WESTINGHOUSE 4 LOOP PRESSURIZED WATER groundwater and as vapor through air f,lled voeds The latter RE ACTORS. FLETCHER C D; BOLANDER.M A EG&G idaho, may be important near a heat source Water flow and solute Inc. (suts of EG&G. Inc ) December 1986 Sipp 8702060201. transport properties of a rock matnx may be quantifed using EGG 2461. 39527 310. rock core ana!yses Natural spatial vanation d,ctates many Sam- A recent safety concern for Westinghouse 4 loop pressunced pies Observed fractures can be charactenred and Combined to water reactors (PWRs) is that. because of a seismic event. in-form a fracture network for hydrauhc and transport assess. strument tubes may be broken at the fium mapping seal table. ments. Unresolved problems include the relatcn of network by- resutting in an .'ncovenng and heatup of the reactor core This d:auhc conductmty to ftud pressure and to scale Once charac- study's purpose was to determine the effects upon findings of a tenred, the matnx and fracture network can be coupled Reh. sam mar 1r 1 study if certain test vanables changed A 1980 able performance assessment requeres add; tonal studies U S Nuclear Regulatory Commisson (USNRC) analys,s Of PWR behavior used the RELAP4/ MOD 7 computer code to determine NUREG/CR 4663: CLOSEOUT OF IE BULLETIN 83-01 FAILURE the ettects of breanng mstrument tubes at the reactor vessel OF REACTOR TRIP BREAKERS (WESTINGHOUSE DB 50) TO low er senum wati The 1986 study discussed here was per. OPEN ON AUTOMATIC TRIP SIGNAL FOLEY,W J ; formed us.ng RELAPS/ MOD 2, an advanced best-estimate com. DEAN R S ; HENN!CK.A Parameter, Inc May 1987. 34pp puter code Seca< ate effects analyses investigated instrument 8706240093 IEB-83-01. 41450 074 tube pressu e loss. heat loss. and tube nodahzauon effects on Dunng startup of Satem Unit 1 on February 25.1983. the un- break flow Systems effects anatyses (a) investgated the ef-dervottage tnp attachments (UVTAs) of both Westinghouse DB- fects of chang ng the break locaton from the reactor vessel to 50 circuit breakers faded to open automatica4y upon receipt of the seal tat 4e, (t) corrpared RELAP4/ MOD 7 and RELAPS/ a vabd tno sgnal from the Reactor Protection System (RPS) on MOD 2 resur ts for an dent cal transient. (c) vent.ed a key f+nding low-low steam generator level The reactor was tnpped manuah from the 1930 ana'ysis, and (d) invesSgated instrument tube ty about 30 seconds later The manual tnp used shunt relays in- ruptures in th Zon-1 PWR us:ng best-estimate boundary and ini-Stalled n the DB-50 breakers Simdar fa lures of on'y one of a tial cond. tons 7he outcome cf these ana'yses permits adjust-pas of DB-50 breakers in senes had been reported ic the NRC/ ment of the 1980 anabs:s findings for mstrument tube ruptures IE and Westinghouse. Because of concern about the event at at seal tabte and ind& cates the best-estimate response of a Salem Unit 1 and prevous sangte fa:ivres, the NRC/IE iss ied Westinghouse PWR to the rupture of 25 small instrument tubes Bunetin 8341 on February 25, 1983. Licensees of operating at the seal table pressunzed water reactors with Westinghouse Type DB break-ers having UVTAs were required to take specAc actons The NUREG/CR-4674 V03: PAECURSORS TO POTENTIAL SEVERE bulletin was issued for nforrnaton to all other nuclear power fa- CORE DAMAGE ACCIDENTS 1994 A STATUS REPORT Main cAtees Evaluaton of utAty responses and NRC/IE inspecton Report And Appendaes A And 8 M:N ARICK,J W . reports shows that the bullet n can be closed out per specific HARRIS J D . AUSTIN P N . et al Oak R49e Nat.onal Laborato. cntena for all of the 50 facAtes to which it was issued for ry Ma, 1987 133pp 8706160050 ORNU NO AC-242 acton Ma!tunctons of the UVT As were reported for ong two 41309 296 sites other than Sa'em There are no remaeng areas of con- Forty e.ght operatonal events. reper1ed in Licensee Event cern for this bunctin Repor1s ItERs) and occumng at commercial hght water reac- 38 Main Citations and Abstracts lors dunng 1984, are conssdered to be precursors te potential along the Kentucky R,ver. Resutts from prehminary dntlang and severe core damage. These are described along with assoctat- electocaLres4stvity surveys indicate that a number of these ed sqMicance est mates. categortzaton, and subsequent analy. faults may have been active s.nce deposit,on of terrace maten-ses TNs study is a continuaton of the work presented in eart,er als Based on intbcations from the preliminary survey, four s4tes volumes in th s seres, whch evaluated the 1969-1981 and were se%cted and nine trenches were excavated Of these nine 1985 events. The report sequent.alty d scusses (1) the general trenches, four reveated faulted or fo!ded terrace sediments ratonafe for tNs study, (2) the program methods for review and Companson Of the (Ene trenches sugysts that the foldog and documentaton of operatonal events as precursors. (3) the use f aulting of the terrace depos;ts es tectorne r oogen and that the of the conobonal probabAty of subsequent severe core damage rentucky River Fault b3 tem has bean acove within the last $ estimates to rank precursor events, and (4) initial conclusons rMon years and probably when the Qst I millon years. frorn the assessment of 1984 events NUREG/CR 4674 V04: PRECURSORS TO POTENTlAL SEVERE NUREG/CR4689: THERh"t HYCRAUttC AND CHARACTERIS-CORE DAMAGE ACCIDENTS 1984.A STATUS TIC MODELS FM PAuED DEBR;S BEDS 1AUELLER,G E.; REPORT Appendues C.D And E. MINARICK J W.; HARRIS,,f Da SOZER.A. (M Roge i4 atonal Laboratory. JarNary 1987. AUSTIN.P N ; et al Oak Rdge Natonal Laboratory. May 1987. 108pp 870$1'6. 04NL/TM 1N17. 3M37:13f 534pp.8706160086 ORNL/NOAC 232_ 41312:196 APRIL cs a twchmsC : ore wde metidown and debns re'o-See NUREG/CR 4674 V03 abstract. caton corcWer tode for Bo&rg Waw DaaTer (BWR) severe acccent ar shses. The car,abmties of De code cont,nue to be NUREG/CR-4679: OUANTITATIVE DATA ON THE FIRE BEHAV- increased by the irr4 ovemnt of eMM ewdels.1Ns report IOR OF COMBUSTIBLE MATERIALS FOUND IN NUCLEAR contains infG son on tt pry and mools for degraded core POWER PLANTS A Literature Review NOWLEN.S P. Sanda packed debns beds. The models, when incorporsted into Natonal Laboratones. February 1987. 166pp. 8706120299 april, wdl prowse new arsd rnproved coabilt:es in ped <tirq SAND 66 0311. 41285 215. BWR debns be , coolabibty charactrostvl These modela wdl TNs report presents foe findings of a task in wNch currently gew for e,1we mecnan,stic treatment m. ga!culating tempera-ava,lable fire research ;.terature was reve*ed for quant.tative tu es r tne f9d anu sciid phaset in the debrrs bed, u t eter- i data on the burning charactenstics of combustible matena!$ that misnq deben Sed drgt. et3a Jed ipocNng from eether iop-are found in nuclear power plants The matenats considered for floodir'Q or bor'orn-ryr4 singte ar'd two-phase pressure whech quant.tatrve data were available include cable insulaton urocs 6ctr $t thI detms bed. %tes bed porosaty. and ri frddj rnatena's, f:ammable hounds, furnrture, trash and general refuse, tM miranum fivezate . tass wiocey The inclusion l' these and wood and wood products. A total of 90 fqures and tables, models in a Cebru bC computer trudule wdl permit a more sc. taken pnmanly from the referenced works, which summan2e the cul be predc%n J tFe coolatAty cha.a tenstic.S of the cWns avadable quant.tative fre charactenzaton oformaton for the?e bed end tMretcro% duce some of tt s o ncerta .bes en amess-matenals is presented r,g the severo ytdent charrctettes for BWR apphcarc. NUREG/CR-4681: ENCLOSURE ENVIRONVENT CHARACER. S 4 4 Of De n< sts bed tr'coretet models have been Ge3 M IZATION TESTING FOR THE BASE LINE VALIDATION AF devebp a FORTRAN 7/ sutenuunn remde called DEDR!S COMPUTER FIRE SIMULATION CODES NOWLEN.S P. barda DEBRIS e

• dover p?,ntam that rees xnw .oroutmes to arw-Natonal Laboratones March 1987. 82pp 87061b0*S1. b e the Lumat charac{q%:s of a packed 0,'bns bed. FOR-SANDB61296 41301047. TF l N 7 / !<st' { of eac} subroubne are prooded m the appen.

TNs report describes a senes of fee tests conductL1 under '** the Grecton of Sandia Nattonal Laboratones for the U S Nucie-at Regulatory Comrrusson. The prenary purpose of thet j tests NU. REG /C0469t; V01 N1: C*D&C COVOUNiCATIONS was to provide data agamst wtuch to valdate computer fee en. 7 rH F DWRS-vronment simulaton models to be used m the ana!ys<$ of nucie. STEINBRZHEFEC - HV (NW f arameter[Inc. Decemler at power plant enclosure fre situatons Examples of the data D2It019243974t?e gathered dunng three of the tests are presersted, though the pn-p g g mary ob,octrve of tNs report ts to provde a timely descnptscrt of gg ,, the test effort etself These tests were conducted in an encl > ' g sure measunng 60:40 20 feel All of the tests utshred forced (aw E A m>aton mes ;aw W4 ay cWars ventilaton corotons typical cf nuclear power plant instal:atons V** d'scontmed) The n pc.1 oweta an ues n a1 such A total of 22 tests usang s4mple gas burner, heptane pool, meth- comnmacations from 1971, wr'en such somentatm startet anoi pool, and PMMA sohd fres was conducted Four of these to 1986 The mden ,s the prmtout fron be stAputer database tests were conducted with a full-scale control room mockup in developed at the NRC for ea./ (%ess to iMormaton previousN place Parameters vaned dunng testing were fra entensity, en- published m these genenc CWr7unscecns TW record , row) closure ventilaton rate. and fre locaton Data gathered includ. entnes each consist of t*xn f.e'os webmr 4) of categonted ed as temperatures. a>r veiocites, radative and convectrve heat informaton about a paeutar occument. :nclud are felds for flun leveis. optcal smoke densmes. oner and outer enclosure N d cent dew 4M mh, W, and NRC tochrwei' surf ace temperatures, enclosure surface heat flux leveis, and contact, and fields for gcneal system c{lopec, spacf.c compo-gas concentratons w,than the enclosure m the exhaust stream nent or topic, cause or di k sct, sc*enta affect, reMrks, s.Nt vendors evolved The report al+o conta.ns ksts of commuruca. NUREG/CR 4685: POST.PUOCENE DISPLACEMENT ON tons sorted by each subrect catqory of ms General System o< FAULTS WITH!N THE KENTUCKY RIVER FAULT SYSTEM OF Top +c and the Spoofc Componeut x Top.c Uuds . A hst of the EAST-CENTRAL KENTUCKY. VANARSDALE R B4 category subjects used arv a a kst y vendx; involved in the SERGEANT,R E Kentucky, Unrv. of, Lenngton. KY. February communicat>ons are .nciuced, neo The NRC mtencM te penode ' 1987. 47pp 8703130193 40007.088 ca!!y update tNs report to = den lata tomrrvvcates 1 The Kentucky Arver Fault System forms the northern tounon-ry of the Rome Trough (a Paleoroec aulacogen) m east <entra! NUREG/CH 4690 V02- GE nF RIC COWU CC STu NS l Ventucky Pa'eozo.c recurrent movement along tNS fauft system INDEX User a Manel DEC LR S , PEINBRENER3. j has been documented by a number of prevous *-orhers; ho*ev. HENNICKA , et at br a.ater, *v rxember IW W er recogniton of Mesonne and early Tertary d:spiacement has 8712310211 43874 253 not been possible due to the absence of preserved post Paleo. Th s report es a manaal Dr ycveng chtou requered to Enc strata Numerous faJts of the Kentucky River Fault System use a speoal computer pngam hopod by the NRC *,r r4 are part#y overiaen by Ptocene. Pierstocene terrace deposits denng genenc communcabcas 'he pryg*am is antlen m a i l M:In Citati:ns cnd Abstr: cts 39 user frendly menu dnven form uung dBASE Ill programmog dent sequences current +y dent.f.ed as be.ng imoortant contnbu-language It faCAtates use of the requeed cBASE til search and tots to nsk The resa'ts ind< ate that contanment ventog can sort Capab,Ites to access records in a database caned Genene be effective in reducing fisk for several classes of severe accb Communicatcns inden This eden is made up of one record dents but. based on procedures in draft form ard equipment in each for all buitetos. circulars. and information notices, eclud- p' ace at the t2rrJ of the ana:yses, has limited potential for fu r-ing revisces and supplements, from 1971, when such docu- ther reducing the risk for severe accdents currenty dent fed as mentaton started, through 1986 (or to the latest update) The be ng important contreutors to the nsk for Peach Bottom. program m designed for use by anyone modestly acqua.nted with the general use of IBM-Compatible personal Computers NUREG/CR-4700 V1 DRF; CONTAINVENT EVENT ANALYSIS The manual conta;ns both a boef overview and a detaded de- FOR POSTULATED SEVERE ACCIDENTS SURRY POWER scnption of the program, as men as detaled estructons for get. STATION. UNIT 1 DraN For Comment BENJAMIN.A S ; ing started uscng the program on a personal computer *cth BEHR,V1; KUNSV AN.D M ; et al. Sanda Natonal Laborato-l i e,ther a two-fioppy disk or a hard d.sk system. Included at the nes February 1987. 195pp 8703170196. SAND 66-1135 i end are a bnet descnoton of how to hand!e prob! ems which 40054 302 l might occur, and notes on the makeup of the program and da- A study has teen performed as part of the Severe Accdent tabase fJes for heip en adding records of commuracatons for Risk Reducton Prcgram (SAR AP) to investigate the response future years of a particu'ar pressunzwd water reactor with a subatmosphenc NUREG/CR 4692: OPERATING EXPERIENCE REV:EW OF FAIL, conta<nment (Surry Urut 1) to postulated severe acciuents. A de-URES OF POWER OPERATED RELIEF VALVES AND BLOCK taded contaoment event tree for the Surry p' ant has been de-VALVES IN NUCLEAR POAER PLANTS MURPHY G A Oak vrsed to desenbe the wanous possible accdent patnways that Roge National Laboratory ULETCHER.J W Professonal Anary. can lead to raccact<ve releases from conta:nment. Data and s s, Inc. October 1987. 82pp 8712080440- ORNL/NOAC 233 analyses from a large number of NRC and industry-sponsored 43588 214 programs have been reve*ed and used as a basis for quantJy. Th s report contains a rev<e* of nuclear poner pl ant operating og the event tree, i e , determining the thehhood of each path-events involving fadures of power-operated rehef vanes way for a vane *y of accdent sequence irttiators. A generahted (PORys) and associated block vanes (BVs) Of the 230 events containment event tree code, ca"ed EVNTRE. has been deveL dentf.ed 101 invotved PORV mechanical fadure,91 were attreb. oped to fachtate the quantacaton. The uncertainty in the re-utable to PORV contro4 faaure,6 events invorved desqn or fab. suits has been examined by performing the quantAcation three ncat,on of PORVs. and 32 events ovoNed BV fa. lures The times, using a o f% rent set of input each time to represent the report contains a compdation of the PORV .and BV fa:1ure variat on of opinen in the reactor sa'ety community in the so-events, includ ng falure cause and sevehty the avents are called "centrar estimate, the 14el.hcod of early conta.nment dont.f ed as to plant and vane manufacturer An us.ssment of fadure (occumng before or at the time of reactor vessel breach) the need to upgrade PORVs and E ' to safety grade status was found to te very low for most accdent sequence irbtiators conc'udes that such acton would improve PORV and BV rein H3*ever, uncertainties surrourding the issues of direct conta.n-ab.Lty The greatest irnprovement in rehabaty would res/t from ment Dressure capacity could lead to much hgher earty f adure uung r's1 er, more rehab;e PORY designs and improvog testing. hkehhoods This work supports NRC's assessment of severe diagnostics and traantenance appbed to PORVs and Bys, par- accdent nsks to be pubbshed m NUREG 1150. ticularly the BV motor operator. A summary of interviens con-docted w'th four PORV manufacturers is afso inc uded m the NUREG/CR 4700 V2 DRF: CONTAINVENT EVENT ANALYSIS report. FOR POSTULATED SEVEAE ACCIDENTS SE QUOY AH POWER ST ATION UNIT 1 Draft Report For Comment NUREG/CR 4695: MATERIAL CONTROL AND ACCOUNTING BEHR V L ; BENJ AViN.A S ; hUNSM AN D M , et at Sand

• Na-(VC&A) LOSS DETECTION DURING TRANSITION PERIODS tonal Laboratores February 1987 200pp 8708200197.

AND FROCESS UPSET CONDIT60NS GRIFFIN.E A.; SAND 861135 40986165 YOUNG,J h SMITH B W , et al Battene Memonal Inst,tute, Pa-A study has been performed as part of the Severe Accdent c Nort west a atores March 1987. 62pp. 8704130187. Risk Reducton Program (SARRP) to mvestegate the response of a particuiar pressunted water reactor wth an ece<ondenser The Nuclear Regulatory Commisson has implemented regula-CMam $ w ya po aM swe ac AeNs tons that regste licensees to periorm tests to detect sgrtficant A detaW CMamnt eveN W W N Woyah pan has losses of strategic special nuclear matenal on a timery basis Me NoW b h@ N vaw WW axm pam-and to resoNe anomakes resJting from such tests Trese capa. ways at can kad b radcame C- e kom CWammem bat.es have been demonstrated for processes operating at equabnum, however, the cond: tons that exist donng transton ata W anaWs kom a y numW of E aN in&sh sponsomd gams had W m*M aN used as a bass perods. i e , at strtup and shutdown, and dunng process qua%mg eM Pet i e , dem q N Nmood d upsets edi impact a l*censee's ab&ty to achieve the speof ed ea3 pamay W a va% of accdent sequence initiators A levels of loss detecton and alarm resoluton This report d:s-generahred contamment event tree code. caued ENVTRE, has cusses the types of data ava.lable, potential!y useful loss tests, been deveW to f aMam Fe quaWcaton De uMI ty and technques that can be used in developing mcdets for the m N msaqs as Men esaW by Wmmg N quantfu abnormal corntons ton three times Lt.Ag a dMferent set of input each t>me to rip-NUREG/CR-4696: CC*7NMENT VENTING ANAL %ld FOR risent the vanatei of opinen in the reactor safety commun ty THE PCACH BOTtJV ATOVIC POWER S I '.T TON .n the so-canod "centrar est. mate, the Ikehhood of earfy corv Hi,N301 DJ BL/'.*M AN h D ; NELSON W R , et al Battelle tammera fNure toccurnng t efore or at the time of reactor N%cd tabtute Ocentes '.aooratones Fe bruary 1987 vehed breath) was found to be high for station blackout se-62Dr; MD507M PG M 24*> 40439 227 quences tn,:1 vby low for other acceent sequence int.ators Un-Teee bt4* t to &cn censnment venting es an effectrve cadabilty of gneters and a.r return f ar.s n as the pnnapal mean s of preve W O er r%tas%g the consequences of re, son fc/ the hgh fadur e probabitty for staton biachouts Tre ?verprmonN,tsun :bnng 1.evere accoents nas evaluated for analysis also showed that mNttng or t3 pass of tre ice twfore or ti e 4'eadh bo'tm Atynic Pwe Staton Unts 2 and 3 (boAng nith.n a short time after vessel breach can te eg+cted to m aier ructc,r5 wit Wa 1 co7tamets) Detaled anahses occur wth moderate to high hkehhocd duong staten blachouts '"we fondvCICC or, og W% petrmance eQuipanent perform- and durmg sequences inst.ated by very small LOCAs n,th fadure owe av Me phyCal phorenencegy or thrf n e sev9fe acCF Of emergency Cof e ccohng in the recirculaton phase a rter suc-N- 40 Main Citations and Abstracts cess in the injecton phase TNS work supports NRC's assess- damage induced in young hybrd mate mice Both radatons ment of severe accident risks to be pubbshed in NUREG 1150. were debwered at low dose levels over about one half the adutt NUREG/CR 4700 V4 DRF: CONTAINVENT EVENT ANALYSIS Metee as 60 once-weevy esposures Genetic damage as. FOR POSTULATED SEVERE ACCIDENTS: GRAND GULF NU- sessed induded both trans.ent and resdual injury. The latter is CLEAR STATION, UNIT 1. Draft For Comment. AMOS.C.N ; more entical, as resdual genetic injury can be transm tted to KOLAOZKOWSKI.A. Sanda National Labora.ones Apnl 1987, subwquent geratons long after the ra$aton esposures have 448pp 8706120033. SAND 661135 41287.115 ceased Assays wm Worm wcRany bog the Mweek A study has been performed as part of the Severe Accident esposure penod and at 10 or more weeks after the irra$atons R:sk Reducton Program (SARRP) to invest. gate the response Wea vah M few enceMons, raw k of a partcu!ar boang water reactor with a Mark lit contamment Me 5 aN 4 W vaw m W Wm M aN M W (Grand Gutf Unit 1) to postu!ated severe accdents. A detaileo ment Wes of ms&al genex % he m st imponaM conta:nment event tree for the Grand Gutt plant has been do- form of resdual genet.c damage in tNs study was the balanced veloped to describe the varous poss bfe accdent path *ays that rewocal cwmosome treaton. hew translocatons ce can lead to rad 4cactrve releases from containment Data and tinue to be transm.tted throughcut reprcductive hfe and can lead anatyses from a large number of NRC and industry sponsored to WM fed ty and increased prenatal mortahty The test programs have been reve*ed and used as a bas >s for quant #y- estimate of the RBE value for translocatons was 45 plus manus ing the event tree, s e , determining the likelehood of the path- 10. Imphcatons and recommendatons *:th regard to the neu-ways at each branch point for a vanety of accdent sequence W qua W fa s M N p se e e m W e m W gs ntrators A generalged contarnrsent event tree code, ca' led from the data obta.ned in tNs same protect on hfe shodening EVNTRE, has been developed to fac* tate the quant;fcaton and on the nsks of incidence or death from neoplastic disease The uncertarnty in the results has been esa%ned by performin9 NUREG/CR 4704 V02: RELATIVE BIOLOGICAL EFFECTIVE-the quant.f<aton tnree times, useg a different set of input each NESS (RBE) OF FISSION NEUTRONS AND GAMMA RAYS AT time to represent the variaton of opinon in the reactor safety OCCUPATIONAL EXPOSURE LEVELS Volume 11 Studies On community in the so- ca!!ed "central" estimate, the laelihood The Effects Of 60 Equal Once Week!y Esposures To Fasson of earty conta,nment fadure (occumng before or w:tNn a short Neutrons And Gamma Rays On Survrval Of Mece time a'ter reactor vessel breach) was found to be sig%ficant be- THOMSON.J F.; GRAHN.D Argonne National Laboratory Octo-Cause of the possibM!y of hydrogen def;agratons or detonatons ber 1987. 45pp 8712310077 ANL-86 33 43871252 that can trveaten contaoment integnty However, uncenainties A total of 6316 mice r$78L/6JAnl BALB/cJAnt F1 hybrds) surround ^g these issues could cause the earty f a lure 1:hehhood were esposed to 60 once-weeHy doses of 0 85 MeV fisson to be sgnibcantry tower than in the central esteate Further, ra- neutrons (0 033 to 0 67 cGy per weeHy fracton) or (60)Co ocactive releases following containment failure would most gamma rays (167 to 10 cGy per weekly fracton) and observed hkety be scrubbed by water, nNch would lower the overall until they d ed An aditional 1404 mice were entered into the source term Th s work supports NRC's assessment of severe empenment and fonowed for part of their kietsmes; a few of accdent nsks to be pubbshed in NUREG 1150- these mice were lost awdenta4y. but most were removed for NUREG/CR 4701 V02: SAFETY ASSESSMENT OF ALTERNA, genetic testing The mean aftersurvrval (MAS) tees showed TIVES TO SHALLOW LAND BURIAL OF LOW LEVEL RADIO. dose-re.ponse cur ves for both neutron and gamma-ray expo-ACTIVE WASTE Votume 2 Environmental Corctons Attecting sures to be linear over all doses escept the Nghest neutron Rehabary Of Engineered Bamers CERVEN F.; OTIS.M D dose The relat>ve bioic9 cal effectiveness (RBE) value for new. EG&G Idaho. Inc (subs of EG&G. Inc ) September 1987 45pp trons, calcutated as the rato of the knear slopes of the dose-8711090388 EGG 2465 43323 232 response curves for MAS times. mas about 20 for toth males The need for new dssposal capadty for low-level radcactive at females Essentiany the same value was obtained by other maste (LLW) has led to a re-exam,naton of disposal practices analyses of the data Th s RBE value of 20 is specific for A number of enhancements and a'ternatives to trattonal shal. deaths trom all causes after 60 once-weeWy esposures to 0 85 ka land bunal have been proposed to meet the need for new MeV f:sson neutrons. with once-*eeHy (60)Co gamma- ray es. capaoty and to adcress varous concerns about the perform, posures as the reference ra$aton The value for the RBE *,11 ance Nstory of er. sting commercial LLW $ tes Th.s document probably be d.Nerent for some, but not a!!, of the other end builds on the ressts of the Volume i e fort. r wNch cent;f,ed the P0'nts O e . specAc causes of death, especiany tumors). emportant LLW c sposal facery ergneered tamers of cover and structure F# teen potent.any important degradaton mechanisms NUREG/CR 4708 V01 N1: PROGRESS IN EVALUATION OF RA-for a LLW facety are dent't.ed. categonzed, and anatyzed t DIONUCLCE GEOCHEMICAL INFORMATION DEVELOPED BY determine theer importaxe to the proper functoning of the dts. DOE HIGH LEVEL NUCLEAR WASTE REPOSITORY SITE PROJECTS Semiannual Report For October 1985 March posal facAty over its 5001 ear Lfetime Wind storms bological 1986 VEYER.R E . ARNOLD.W D ; BLENCOE.J G ; et al Oak intruson, mechan. cal setthng. freeze /tha* cycling. chem. cal deg'adaton. *ind eroson, and mater eroson *ere consdered R4ge Natonal L aboratory January 1997 63pp 87021700$0 the most importa nt mechanisms Data support.ng concrete ORM/TM-1016 39655 245 d structse long term performance in suMate environments and Information Sat is beat developed by protects witNo the De-long term cover pedormance in erovve and tnolog<al it'truson mmeN C Enegy (DCL pertinent to the potent.al geocherni-enwonments were obta=ned Re<earch on the performance of cal behavor of radonocides at candaate sites for a hegn-level covers and concrete structures in the presence of the other radcactive waste repostory is being evaluated by Oak R49e ksted degradaton mechan <sms is recommended Natonat Laboratory (ORNL) for the Nuclear Regulatory Com-masson (NRC) Dunng th.s report peroj emphasis was placed NUREG/CR 4704 V01: RELATrvE BIOLOGICAL E F F E CTIVE. upon the Yucca Mountain Nevada. s te Seve<ai samples of tutt , NESS (RBE) OF FISStON NEUTRONS AND GAVMA RAYS AT were anagrec and charactenzed by Oray d.ffracton and petro- i OCCUPATIONAL EaPOSURE LEVELS volume 1 Stud.es On graphic anasts in.taf sorpton empenments w th ceoum and The Genet >c ENects in Mice Of 60 Equat Once Weeuy Espo. strontrum demonstrated the necess ty of preeouAt<aton and sures To Fisson Neutrons And Camma Rays GAAHN D ; control of the CO(2) pa%at pressur e over the expenment A CARNES.B A Agonne Natonal Laboratory Octcher 1987 small particle wie eNect was observed for sorpton of N(p) on 71pp 6712170245 ANL-86 33 43761209 varous 5 2e tractons of tuff DitScu! ties mere espenenced in The reiahve toogical eMectiveness (RBE) values for now prepanng standard solutons of europium Prehminary compan-doses of t,$sson rwtrons compared to (60) Co gamma rays son of our data for sorpt,on of cesium arv* strontium a th those were determ2ned wQnificance est# nates. Categon24 ton, and SUDsequent analy- faults rnAy have been actNe Wnce depositon of terf act materF ses Thrs study is a cont a's. E>ased on ordcatons from the prehmmary survey, four e tes volumes in this seres,'nuaton of the work wNch evatuated the presented 1969 1981 in earter and were selected and nine trenrAes were excavated. Of these rwne 1985 events The report sequenttany escusses (1) the genaraf trenches, 'our revealed fauttad or folded terrace se$ments.

ratonale for tn,s study, (2) the program methods for revew and Compeson of the rune trenctws suggests that the icong and documentaton of operatonal events as precursors. (3) the use fauttql o' the terra e derWs is tectorve in ongan and that the of the condatonal prooabaty of subsequent severe core damage Kentucky Rrver Fautt Sys'em has been active withm tw last $ estimates to rank PeCursor events, and (4) irutial Conclus*ons mMon )sars and probabFy within the last 1 PWlon year!6 from tne assessenent of 1984 events. NUREG/CR 4674 V04: PRECURSORS TO POTENTIAL SEVERE NURfG/CR 4689: THERMAL-HYDRAULIC AND CHARACTERIS-CORE DAMAGE ACCIDENTS 1984,A STATUS TIC HODELS FOR PACKED DEBRIS BEDS MUELLER.G E.; REPORT Appendues C,0 And E. M;NAR!CK.J W; HARRIS,J Da SOZE R. A. Oak Rdge Natonal Laboratory J.nuary 19d7. AUSTIN.P N ; et al. Oak Ridge Nat>onal Laboratory. May 1987. 108pp 8702060116 ORNL/TM 10117. D5211' APRll is a mechanistic cott'-*ide tr ltdown e and debns reto. N EG R 4674 V03 abs ac caton computer code for Boeg Water Reactor (BWR) severe accdent analyvs. The capabiht>es of the code conhnve to be NUREG/CR 4679: QUANTITATWE DATA ON THE FIRE BEHAV- increased by the improvemert Of exatng rnodets. This report . IOR OF CCMBUSTlBLE MATERIALS FOUND IN NUCCEAR contaas mformaton on theory and models for degraded core POWER PLAN?S A Uterature Review NOWLEN.S P. Sanda packed debns teds The mode!s. when eco porated into National Laboratones February 1987, 166pp 870(1202?9 APR:L, wat provce new and artptcved capabetes m p<eacSng SAND 86A311. 41285 215 BWR debos bed cootabMy charactenst<s. These rnodets was Th<s report presents the finangs of a task in which currentty arow for a rnore mechcnistsc treatment in calcust<ng tempera-avadable fire research hterature was reviewed for quantitatrve tures in the fluid and Sohd phases m the debns ted, in deter-data on the burning charactenstcs of combustbe matenats that rnining debns bed dryout, debns ted quencNng from e ther top-a'e found o nuclear power plants. The matena's cons 4cred for fioodog or bottom-flooding, ssngle and two-phase preswre which quant tative data were avadable eclude cable msulaton drops across the debns bed, debe4 bed rorosity, and in firving matenats. flammable tqeds, furruture, trash and general refuse, the minimum flurozator; mass velocity The incluson of it ese and wood and wood products A total of 90 fgures and tables, models in a debn3 bed computer module will porr=vt a rrore ac-taken pnmanty from the referenced works, wNch summar.re the cu'aie preccton of the coolab;hty charsetenst(s of the debns avadable Quant:tative fre chara:tenist;on informaton for these matenals is presented bed and therefore redJce some of the uncerta nbes in assess-ing the severe Mcdent charactenst:cs for BWR appicaton NUREG/CR-4601: ENCLOSURE ENviRONVENT CHARACTER. Some of the cebns bed theoretica! models hiive been used to 12ATION TESTING FOR THE BASE LINE VALIDATION OF develop a FORTRAN 77 subroutine module caned DEBRIS. COVPUTER FIRE SIMULATION CODES NOWLEN S P. Sanda DEBRIS is a drrver prcyram that cabs other subroutnes to ana. National Laboratores March 1987. 62pp 8706150161 h7e the thermal charactenstics of a pa3ed oebns bed FOR-SAND 86-1296 41301047. TRAN 77 listings of each subroutme are prceded m the appen. TNs report descobes a Senes of fire tests conducted under du the deecton of Sa%a Natonal Laboratones for the U S Nucle-ar Regulatory Commission. The pomary purpose of these tests NUREG/CR-46ec V01 N1; GE NERIC COMMUNICATIONS was to provce data against *Nch to vahdate computer fre en. g gg g . nronment 54mulaton rnodeis to be used m the anaty sa of nucle. STEINBRECHER.D , HENN!CX,A parameter, Inc. December ar power plant enclosure fre s<tuatons Enamples of the data 1987 3?OPD 8712310192. 43874 272-gathered dunng three of (5e tests are presented, though the pro As part of its program to feed back informat,on on operating mary objective of th,s report is to proode a bmely descnpton of emperence to ndush the U S Mear Wam Commisson the test erfort itsett. These tests were conduc*ed in an enclo- (NRC) issues certam genenc commurwca:ons cahed tullebns sure measunng 60:40x20 feet AII of the tests utdized forced (aW 10% inWton reteer (atout 100% and crculars ventilaton cond, tons typ<al of nuclear power plar;t estattations. (now escontinued) The report presents an inden of all such A total of 22 tests using $4mpte gas burner, heptane pool, meth- communicatons from 1971, mhen such documentaton started, anoi pool and PMMA solid fres was conducted Four of these to 1986. The mden is the pnntov trom the ecmputer database tests were conducted wth u full-scale control room mockup in develc4ed at the NRC for easy access to information previousty place. Parameters vaned dunng testing were fre mtensity, en- pubbshed in these gonenc commurwcatons The record (row) closure ventdation rate, and fre locaton Data gathered includ. erdres each cons:st of twenty fees (columns) of catMonzed  ; ed arr temperatures. at veiocites. rasative and convectrve heat mformaton aW a partcular rbcument Mcluded are feeds for I fluu levels optical smoke densst-es. inner and outer enclosure the document ident ficaton number, t,th, and NHC technecal i surface temperatures, enclosure surface teat flux levels. and contact and felds for general system at topic, specAc comr,o- I gas concentratons w:tNn the enclosure an the e haust stream nent or topic, cause or defect potent at effect, remarks and venjors mvotved The repor1 also conta:ns hsts of communico NUREG/CR 4645: POST PLIOCENE DISPLACEVENT ON tons sorted t'y each subject category of *he Gereral System or FAULTS WITHfN THE

• ENTUCKY river FAULT SYSTEM OF Topic and the Spec.fe component or Topc fieMs . A list of the E AST-CE NT RAL FENTUCKY VAN ARSDALE.R B . category subpcts used and a I:st of vendors evolved in the SERGEANT,R E. Kentucky, Univ of, Lesmgton. KY February communcatons are included. a'so The NRC intends to penod-1987,47pp 8703130t93 40007 088. ca9y update thm recort to ir*v later commun.catons The kentucky R%er Favit System fccms the northern tourda-ry of the Roine Trough (a Paleozoic aulacogen) in east-central NURhG/CR 4690 V02: GENE RIC CCMMUNICATIONS

                                              > er'tucky Pa ecroic recunent movement along tNs fault system              INDEx User's        Manus      DE AN.R 3 ;    STEINBRECHER D ,    1 has been cocumented by a number of prevous workers, ho*ev.                 HENNICEA , et at Parameter. Inc Dec ember 1987 20pp er, recogreton of Mescrx and earty Tert.ary @splacement has                8712310211 43874 253                                              i 1

not been posWe due to the absence of preserved post Pa:eo- Th4 repor1 ts a manual for proverg internaton requ. red to ' roic strata Namerous fautts of tre Ventucky River Fault System use a speciat computer program developed ty the NRC for en-are part a4y ovetain by Puocere, Pte stocene terrace deposits deurg genenc communicatons The program is antten en a l l l l

Main Citations and Abstracts 41 rnateN the same cond:t.ons One of our pnncipal concems w,th NUREG/CR 4713: SHUTDOWN DECAY HEAT REMOVAL ANAL-the NNWSI data es that much of their cata man taken w thout YSIS OF A BABCOCK AND WILCOX FRESSURIZED WATER control of cot 2) parut pressure. RE ACTOR Case Study. CnAMOND.W R , E RiCSON.D M ; SANDERS,G A Sandia Natonal Laborator es March 1987. NUREG/CR 4710; SHUTDOWN DECAY HEAT REVOVAL ANAL- 903pp 8704010504 SAND 841832. 40325 245 YSIS OF A CCVBUSTION ENG!NEERING PRESSUR! ZED This is one of S:n case stud es for USI A 45 Decay Heat Re-WATER RE ACTOR Case Study CR AMOND.W R ; moval (DHR) Requirements. The purpose of this study is to ER}CSON D M ; SANDERS G A Sand 4 Natonal Laboratones dent,ty any potent.al vutnerabaties in the DHR systems of a Juh 1987. 775pp= 8708110412 SAND 861797. 42107 282- typical Babcock and Wdcon PWR. to suggest poss>ble modifica-Th<s is one of sa case stud.es for USI A-45 Decay Heat Re- tons to improve DHR Capately, and to assess the value and moval (DHR) Regsements The purpose of this study is to impact of the rnost promising atternatrves to the carsting DHR ident;ty any potental vulneratetes in the DHR systems of a systems The systems anatyss cons +dered smart LOCAs and typical Co nbuston Eng neenng PWR to suggest possible modo trasent internal in teng events, and sersmc, bre, entreme f catons to improve the DHR capabMy, and to assess the value wind. internal and external flood. and bghtnreg external events. and impact of the most promising a'ternatives to the eosting A full-sca!e systems ana'ys.$ was per'ormed w,th detaled fast DHR sistems The systems anaf sis y Consdefed sma:t LOCAs trees and event trees inc'ud ng support s, stern dependencies. and trans4ent snternal ntiatng events, and betsm#c. fee. entreme The system analyses rewits were entrapo'ated into retease cate-

   *ind, internal and enternal f;ood, and lightning estemal events    gones using applicable past PRA phenomenologcal ressts and A futbscaie systems ana!ysis nas periormed

• tn detaded fault improved conta.nment fa;ture mode probabAtes Pubhc conse-trees and event trees including support system dependencies Quences were est< mated using site-specif.c CR AC2 calculatons The system anahsis results were entrapolated into release cate- The value-impact (VI) ana'ys s of poss ble tiernattves consd-gores using apphcabL past PRA phenomenological results and ered both onste and offs,te impacts artrv6ng at several risk imoroved conta,nment fa ture mode probabelies Publ.c conse- measures such as averted popu!aton dose out to a 50-mde quences were estimated using 5.te specibc CRAC2 calculatons- ratus and dona <s per person rem anrted Uncertut'es in the The Value Irrpact (VI) ana'ysts of poss tJe alternatives consid- VI anaFysis are d.scussed and the issues of feed and bieed and ered both onsite and ot+szte impacts amving at several nsk seconda*y blowdown are ana'yted a measures such as averted popu!aton dcse out to a 50-mde radius and dona's per person rem averted Uncerta1nties in the NUREG/CR-4715: AN AGING ASSESSVENT OF RELAYS AND VI analysis are d<scussed and the issues of feed and t1eed and CIRCUIT BREAKERS AND SYSTEM INTE R ACTIONS Secondary bio *down are ana'yred TCMAN G J ; B ACANSKAS,V P , SHOOET A , et at Brookha-ven Natonal Laboratory June 1987.181pp 8711090389 DNL-NUREG/CR 4711: LOW UPPER-SHELF TOUGHNESS H:GH- NUREG-52017 43323 050 TRANSITION TEMPER ATURE TEST INSERT IN HSST PTSE-2 Tha report prevdes an assessment cf the apng of cecwt VESSEL AND WIDE PLATE TEST SPECWENS Final Report areakers and relays wh*ch av v*ta' componets of the nuclear DOM!AN.H A Oak Roge Natona! Laboratory
• Babcock & power plant electncal safety system. and was conducted under W4 con Co Februa*y 1957 85pp 8704 t 3C437 40495 h15 the auspices of the NRC Nucicar Agog Resea+ch (NPAR) Pro.

A p.ece of A397. Grade 22 Class 2 (2-1/4 Cr 1 Mo) steel gram The study included protectse. controt and log *c relays. p; ate speciaily heat treated to produce lo* upp,er.She:t (LUS) and molded case and metal clad s*dchgea' creu;t tweakers toughness and begh-trans t.on temperature was instatted n the The relay faaures were attnbutab!e to cod detenoraten, changes see wall of Heavy Secton Steel Technology (HSST) vessel V 8 in d,mensons of cnt,ca! o<gan.c components and changes n Thes vesset % to be tested by the Oak Rege Natonal Laborato- cha'actenstics of timng d4phrages from therma! detercrat,on ry (ORNL) in the pressur2ed- Thermai-Shock E spenment-2 some of the f ave mcdes au! gevent fad- sale ope aion r The (PTSE 2) pro,ect of the HSST program Compa*arde peces of electncal control and mechan ca: portons of maal-clad s* tch-the plate mere made mto 9: noe plate specimens and other gea' were found to be mor( falur e prone than the mam con-samples for character 2aton test,ng to te performed t'y ORNL tacts and arc citingwshag systems Cecu>t breakers and retays in a PAR satety inyecton system mere evaluated a tn respect to NUREG/CR-4712: REGULATORY ANALYSIS OF REGULATORY the arng induced by system operaton The et4ect of cwcutt GUIDE 135 (REV:SION 3. DRAFT 2) iN-SERVtCE INSPEC- t<eaker and re!ar deteroraten on the araty of the system to TION OF UNGROUTED TENDONS IN PRESTRESSED CON- perform its saiety functons was also evatated CRETE CONTAINVENTS N AUS.D J Oak Roge Natonal Labo-ratory Februa*y 1997 122pp 8704130262 ORNLITM-10163 NUREG/CR 4718. E xFERMENT AL SUPPORT AND DEVELOP-40495 206 VENT OF S!NGLE-ROD FUEL CODE S PROGR AM Summary The otgect'ves of tNs study were to reve* afi the changes in Report. LANN;NG D D Battene Memortal inst tute Pacihc ] the latest verson (Rev 3. Draft 2) of "Regdatory Gude t 35" N orthw est Laborator es Janwy 1997 $#p NO2170067 and to prowde a regdatory ana'ys.s for ad pos tons in the PNL 5972 3%56 051 gu>de Three tasks were undertaken to meet these otgectives Th:s report summar 2es the a: twt es and resv:ts of the 11 (1) rece* of the evoluton of prestressed concrete conta.n- year Eoenmenta' Support and Developet of S*ng'e Rod ments thee p'estresmg systems and the cevelopment of Codes Prog'am sponsored at Pa:Ac Northwest Latoratory by "RegJatory Gude 135". (2) deveiocment of a comparatrve reg the U S Naciear Regu!atory Comemsson The prcgam included vlatory ana'ys:s between Rev 3 (Draft 21 and the current ver- vraiaton of enters +et, mstn,.rrented test fuel assemt+es at son, which is in efieCt (Rev 2), and (3) Conducton of a ba;bt.t the Halden Reactor in Noreay and Cost # rad aton esa%nat on aWysts in conforenance eith the regswements of the Ba:bfatt,ng at Harnell Lato atones m the Un:ted Ungdom ei-rea: tor stud-As!e (Secton 50109) Resu'ts of the study ind,cate that there ees on gao condactance and fael rce mecharncs and model de-are certa n areas where editcnal costs rray te incurred by in- velopment for the F R A PCON 2 fuet pedormece comryter dustry due to implementaten of Rev 3, however, a reassess- ccde S.gnAcant resdts ncluded long term inaea: tor data on ment of reasirements m ether a'eas can produce an estimated toet temperature fiss on gas release, and rod etorgat on Quan-nel Cost saMQs to mdustry in encess of $4 500 000 m tt+ms of tAcston of tN inherent sca'1er in obscesco %I terrrerat;res in net dscou nted future cost impact when a d scount rate cf 5*. is repbcate rods and odnton and modorg of tr+ tema! and used Asso a'though changes m the gu*de were determinea to mechan, cal conseq;ences of tset pehet crachng and t'a rent prodsce an ungsset f.able change m nsk at is antictpated that out*ard relocaton The da'a otdaned a'e used as benchrea'k the changes edl have a pos t we impact on sa'e*y and thus att data 'or bel fettmance codes and mcdA thrNghout the I lower the nsk and shoud enhance conta nment a.a tataty

• ord i

42 M:In Cit tions and Abstracts NUREG/CR 4719; COOLAB!L'TY OF 1TRATIFiED 002 DEBRIS Traff.c flow was usualty described as light to moderate. The IN SODIUM WITH DOWNWARD HE4T REMOVAL.The D13 Ex. Speed of vehcies at the beght of the evacuaton was most penment OTTINGER.C A : MITCHEl L,G W ; REED.A W. Sand:a commonly reported to be in the 25 to 40 mph range. Natonal Laboratones March 187. 67pp 8706150126 SAND 861043. 41301 127. NUREG/CR 4727: SWISS SUSTAINED HEATED METALLIC The LMFBR Debns Coolatory I rogram at Sand.a Natonal ME LT/ CONCRETE INTERACTONS W1TH OVERLvlNG Laboratones rnvestgates the ccoli baty of particle beds that W ATE R POOLS. BLOSE.R.E ; GRONAGER.J E ; SUO-may form following a severe accid ant involving core dasassem- ANTTILA.A; et a!. Sand.a Natonal Laboratones June 1987. bfy n a nuclear reactor. The O ser es expenments wine fisson 267pp 8711170043 SAND 851546 43372153 heatmg of fully ennched UO2 pa't :les submerged in sod'um to The SWISS tests of me't/ concrete interactons with an overty-reahst< ally simulate decay beate i The D13 expenment is the mg water pool are descnbed Each test invoNed 46 Kg of first in the ser,es to study tne er'e ;ts of bottom coohng of straty molten stacless steel sustarned by inducton heating whde in fed debt's, wh,ch could be prov4 sd in an actual accident Condi- contact with hmestone/ common Sand Concrete A water pool tion by structural matenais onto ah.ch the debns might sett;e was formed over the melt in test SWISS 1 after about 12 cm of Additonalty the D13 empenment .vas designec to ach> eve maxi- concrete had been eroded in test SWISS 2. a water pool was mum temperatures in the debns approacheg the metting point 'O'**d '***d'ately a'ter me t contacted the concrete. Concrete of UO2. The expenment was o >erated for ever 40 hours and eroson, temperatures. gas generaton rates, and aerosol gen. investegated do*nnard heat ren oval at specific powers of 0 22 eraton raks are reported. and 2 58 W/g Channeted dryo, t e the debos was achieved at powers from 0 94 to 2 58 W g Maumum temperatures ap- NUREG/CR 4730: EVALUATION OF POTENTIAL MIXED WASTES CONTAINiNG LEAD. CHROMlUM.USED OlL.OR OR. proaching 2700 degrees C were attaned Bottom heat removal GANiC UQUIDS SISKIND.B ; mas up to 750 kW/m2 as corr sared to 450 kW/m2 in the D10 MACKENZIE D R - BOWERMAN.B S : et al Brookhaven Natonal Laboratory Janu5 "P'hment- ary 1987.175pp. 8702270062. BNL NUREG.52019 39759 249 NUREG/CR 4722: SOURCE TEdv ESTIMATION USING MENU. Th.s report presents the resufts of follow-on studies conduct-TACT. SJOREEN.A ; MCKENNA.T ; JULIUS J Oak R4ge Na. ed by Brcokhaven Natonal Laboratory (BNL) for the Nuclear tonal Laboratory. October 1987. 65pp. 8711060294 ORNL/ Regutatory Commiss.on (NRC) on certarn kods of low-level 6314 43311 025 waste (LLW) wh.ch could SIso be classfted as batardous waste MENU-TACT is a comput ir code designed to be used for subject to regulaton by the Environmental Protecton Agency source term est4maton dur y g reactor emergencies The ceae (EPA) Such LLW is termed "mixed maste" Aditonal data aDons the user to dvoe cr ncentratons of the nucides in the have been collected and evaluated on two categones of poten-reactor and the release pat +way and timing Fdte".ng and other tat moed maste. namely LLW contan.ng meta'hc lead and LLW in-plant removal processes may be included MENU-TACT, a containing chromium AdStonai!y. LLW with organic koeds, es-mod;ficaten of the TACT l" code. is simple to use To provce pecially houid scintmaton wastes, are revieaed in kght of a pro-qwck resutts of boundog c Oculatons, it ncorporates orvy those posed EPA rule to bst used oil as hazardous maste. the poten-processes that can make r iapr changes in reactor releases tial maed maste hatard of used 041 contaminated *,th radonu. NUREG/CR 4724: FATIGUE CRACK GROWTH RATES IN PRES-SURE VESSEL ANE FIPtNG STEELS IN LWR NUREG/CR 4731 V01: RESIDUAL LIFE ASSESSMENT OF ENV!AONMENTS Final F eport CULLEN.W H Matena:s Engi. MAJOR LIGHT WATER REACTOR COMPONENTS neereg Associates, inc Jarch 1987. 68pp 8704010118 MEA. OVERVIEW Volume 1. SHAH,V N ; MACDONALD.P E EG&G 2175.40321 347. Idaho. ine (sut.s of EG&G, Inc ) June 1987. 198pp The measurement of 'atigue cra:A groatn rates for pressure e708060423 EGG 2469 42071001. and piping stee!s in he gh temperatu r e pressurged water has This report presents an assessment of the aging (time-de-been camed out useg compact fracture specimens Over the pendent degradaton) of selected major hght water reactor com. last ten years, the prog *ams sponsored by the NRC and carned ponents and structur es The stressors, poss;bie degradaton out at the Naval Rese arch Latoratory and Matenals Engineer. s4tes and mechawsms, potent.al fa. lure modes and currentry ing Associates have p ovided data for over three hundred tests used non-destructive examinatons. in sefwce inspecton (ISI) of these specimens, onch have teen puthshe m a senes of and hfe assessment methods are d<scussed for seven mapr NUREG topica! repo ts and annual reports This is the final hght water rea: tor components pressurged water reactor report e this senes a 4 descnbes bnefly the sagnAcant fMngs (PWR) and toang mater reactor (B AR) pressure vessels. PWR of the program, repe rts on the most recent data nhech have conta rnment structu r es, PW R reactor coolant piping. PWR been acquired, and ind4 cates some directons for future re. steam generators, BAR recirculaton piping. and reactor pres. Search n this area "urther testing of compact specimens have sure vessel supcorts UnresoNed techracalissues related to hfe been nearty phasec out, and the program has tumed more to. entenson of these components, encluding requ.rements for ad-wards apphcatons onented tasks, such as vanable cyche am. vanced l$1 and hfe assessment methods, are also d+5 cussed phtude test;ng. pad through cra:k gemetry tests, and environ-mentat e'fects on f 3e stress- kfe curv es NURE G/CR-4734: SEISMIC TESTING OF TYPICAL CONTAiN-MENT PlPiNG PENE TR ATION SYSTEMS CLOSE,J A ; NUREG/CR-4726: IVALUATION OF PROTECTriE ACTION HILL,R C , STEELE.R EG&G idaho. Inc (subs of EG&G. Inc ) RISKS WITZlG V F., SHtLLENN J K Pennsytvania State Univ . December 1986 4tpp 8702060293 EGG-2470 39527 049 Univers;ty Park PA June 1987 212pp 8707070524 This report provdes the resufts of seesmic tests on three type 41600 074 cal bght mater rea: tor conta,nment penetraton systems to pro-Risk of death and infury dse to evacuaton was estrmated by vde a technical baos for the support and development of studyng 902 ev cuat ons that occurred in the United States t+ equipment ovahticaton procedures The three systems tested tween Janua y I,1973 and Aped 30.19e6 Tne nsk of deatn (a) An eigni.incn gate va've system modehng a containment due to evacust >n es Qu:te small it was est. mated to be equal to spray system. (b) An eight- anch butterf ty va've system modeling the nsk of er[ osure to ra$aton doses of several hundred to a purge and vent system, and (c) A two-inch globe va've system about a thouv rd mdhrems Fey f actcvs for a successful evacu. rnodong the rumercus small tore piping systems that are aton were foi nd to nclude an emergency p!an. good commu- otten character red by h gh vatve to pipe $2e rate The va've rwcatons and coord-naton, pract.ce onHs, and defined authority t, pes s rei peping coabguratons penetratons and supports Few evacuat ons used the emergency broadcasting system or used for the tests are tw.caf of those found n commercial U S marrwng sirer s Reports al panec and tra*t.c 3ams were very few nuciear poner plants for containment isolaton appbcatons The

M:In Cit:tions and Abstr: cts 43 t?ree systems tested were mounted in a future and excited with borne releases Radcactrve aerosols generated by fires were s4mulated seismsc loads The loads imposed durog the tests investgated in empenments in which combust 6e Soids and hq-were equal or greater than those espected dunng U S. operat- uds were conta%nated with radcactrve matenals and burned. ing bases and sa'e shutdown earthquakes The test results inds- Uranium in powder and liqud form was used to contaminate five cate that adverse vatve, penetraton or p< ping system behavor fuel types, polychloroprorse, potystyvene, polymethytmethacry-dunng typcal se'sm c events is very unhkely. late, cenutose, and a mixture of 30% tnbuty1 phosphate (TBP) in Wosem Heat hut, ongen concentraton, av flow, contamenant NUREG/CR 4735 V01: EVALUATION AND COMPILATION OF concentraton, ano type of gniton were vared m the expen-DOE WASTE PACKAGE TEST DATA. B. annual ments The hghest release (7.1 WW) came from burning TBP/ Report December 1985 July 1986 INTERRANTE,C ; kerosene over contaminated nitnc acid Burning cellulose con-ESCALANTE.E : FRAKERA; et al. Commerce, Dept. of Naton- taminated w'th uranyi rutrate hexahydrate liqud gave the lowest al Bureau of Standards March 1987.139pp 8704010532 5 ease 9 01 wW Rate of rease and paWe size distnbution 40325 106 of arborne radcactive partcles were hghly dependent on the TNs report summanzes results to date of NBS evaluatons of hpe cf W bumed Department of Energy (DOE) activities in waste packages de-sgned for conta.nment of ra$oactrve high-level nuciear waste NUREG/CR 4737: INTERPRETATIVE ANALYSIS OF DATA FOR (HLW) The waste package is a proposed engineenng barner SOLUTE TRANSPORT IN THE UNSATURATED ZONE. that is part of a pennanent repos' tory for HLW. Canddate re. FUENTES.H R.; POLZER.W L. Los Alamos Natonal Laboratory pository S.tes include three d fferent media' tuff, basart, and sa't. January 1987. 242pp. 8702170076. LA 10817 MS 39655 003 Metal a!!oys are the pnnc. pal bamers for the proposed canisters in tNs report, the rnovoment of odde, bromde, and lithum and overpacks. In aMtion, borosacate glass and vanous pack' i,,nder unsaturated Fow condtons es modeled usang the comput-ing matsnats have been proposed as components of tNs eng" er code CFITIM. TNs code is a soluton of the one-dimensonal neenng system, Thus, the associated technical problems n- convective- d.spersive equaton when steady state flow exists volve corrosen, teacheg d.ssoluton and transport w: thin the and when interactons berneen the solute and Bandelier tuff waste packages This report grres status reports on waste can be described by the linear isotherm. The model pred, cts package actrot,es related to each of the three host media. Ap well the transport of the solutes cdde, brom#de, and latNum pended to the report are NBS reviews of selected DOE techn" when fbow condtons are near steady state. When assuming av-cal reports and NBS fnp reports of pert:nent meetings, sem" erage steady state flow condtnns he model predicts disper-nars, and workshops attended Also presented in the report is son factors for unsteady flow witNn one to two orders of mag-background informaton on the Matena's Charactenzaton natude of the predictons at steady-state flow. retardaton fac-Center (VCC) as well as d scusson on statistical consderatens lors, on the other hand, are predicted much b6tter than the dis-in f,tting leacNng and corroson moders to measurements The person factors Defferences in the estimated d:sperson coeffi-MCC was establ shed to assess and charactenze waste pack- cients for solutes of two steafy-state pulses ind< ate that the erk age mater,ats for reliable performance for DOE's nuclear waste tended rephcation of those steady state how pulses was not needs och eved dunng empenmentation A companson of breakthrough curves of solutes from one depth to another in the 3-m x 6 m NUREG/CR 4735 V02: EVALUATION AND COVPILATION OF f. eld espenmental catsson md<ates poot conservaton of solute DOE WASTE PACKAGE TEST DATA Biannual Report August 1986 January 1987 TNT ERR ANT E.C ; ESCALANTE.E ; mass dunng transport FRAKER,A ; et al Commerce, Dept. of, Natonal Bureau of NUREG/CR-4739; RAMONA 38 CALCULATICNS FOR BROWNS Standards October 1987 137pp 8711090211. 43315 244 FERRY ATWS STUDY. SAHA.P.; SLOvik,G C ; NEYMOTIN L.Y. This report summantes resutts of the Natonaf Bureau of Brookhaven Netonal Laboratory February 1987, 120pp. Standards (NBS) evaluatons of Department of Energy (DOE) 87M190595 BNbNUREG-52021 40976 071. actnnties on waste packages designed for containment of ra$o. Several aspects of the Anticipated Transent Without Scram active hgh-level nuclear waste (HLW) The waste package is a (ATWS) nt:ated by an inadvertent closure of all Main Steam proposed eng.neered barrer that is part of a perrnanent reposo Isolaton Vanes (MSIV) in a typ+ cal BWR/4 are anatyred in the tory for MLW. Metal anoys are the pnncipal bamers *!tNn the report The analysis is performed using the Brookhaven Naton-engineered system Techrucal d:scussons are gwen for the cor, al Laboratory code. RAMONA 38, whch employs a three-do roson of metals proposed for the canister. particularty carbon menscnal neutron kmetics model coupled *,th a parallel chan-and stainless steets and copper in the secton on tuff, the cur- nel thermal-hydraubes in representing a Boiling Water Reactor rent level of understaeng of several canister matenats is ques. tcned W'tNn the Basa't W aste isolaton Protect (BWIP) secten, (BWR) Core Four different transent scenanos have been inves. 1, gated a) downcomer water krvel and reactor pressure control. d scussons are given on prot / ems concerning ground *ater, b) manual control rod inserton transent, c) hgh pressure to+1-matenats for use in the metathe overpack, and attus4on through off, and d) recaculation pump tnp f a,ture Results of these calcu-the packing For the proposed sa't sde, questons are raised on latons should provde better understa%ng of mitigatrve ef+ects the *ork on both the pnmary canddate matenal (ASTM A216 of operator actons dunng ATWS, thus helping m the develop-Steel) and the alternate aucy (TrCode 12) NBS ncrk related to ment of adequate Emergency Procedure Gudehnes (EPG) re-the vitnficaton of HLW borosilecate g' ass at the West Valley quired for the BWR plant safety A few unresolved questons Demonstraton Project fWVDP) and the Defense Waste Proc- subgect to future investgatons are also 6scussed ess2ng Facuy (DWPF) is covered NBS revens of the Matena's I Charactenraton Center (MCC) rs presented Usirq a database NUREG/CR 4741: FEEDW ATER TRANSIENT AND SMALL mana2ement system, a computenzed database for storage and BREAK LOSS OF COOLANT ACCIDENT ANALYSES FOR THE retteval of reytews and evaluatons of HLW data has been de- BELLEFONTE NUCLE AR PLANT BAYLESS.P D , DOBBE.C A ; veloped and is desenbed CHAMBERS.R EG&G idaho, Inc (subs of EG&G Inc ) March NUREG/CR 4736: COMBUST.ON AEROSOLS FORMED 1987 121pp 8704130238 EGG 2471 40496 015 DURING BURNING OF RADIOACTIVELY CONTAMINATED Specific sequences that may lead to core damage were ana-M ATERI ALS EXPERIMENT AL RESULTS HALVERSON.M A , tyred for the Betlefonte nuclear plant as part of the U S Nucle-BALLINGER,M Y , DENNIS.G W Battelle Memonal Inst:tute, Pa- ar Regulatory Commisson's Severe Accdent Sequence Ana'y-cific Northwest Laboratones March 1987 61pp 8703250500 545 Program The RELAP5. SCDAP. and SCDAP/RELAP5 com-PNL-599) 43234 279 puter codes were used m the ana!,ses The two ma:n irutiating Satery assessments and environmental impact statements for events mvestgated were a loss of all feed *ater to the steam nuc@ar fuel cycle f achties require an estimate of potential at- generators and a small cold leg break loss of cootant accident

44 M2in Citations and Abstracts The trans,ents of pomary interest w, thin these categores were the TMLB' and S(2)D sequences Vanatons on systems ava.h NUREG/CR 4747 V01: AN AGlNG FAILURE SURVEY OF LIGHT abibty were also invest, gated Poss@e operator actons that WATER REACTOR SAFETY SYSTEMS AND COMPONENTS. could prevent or do!ay core damage were identified, and two MEALE B M ; SATTERWHITE.D EG&G idaho. Inc. (subs. of were investigated for a small break transient. All of the tran. EG&G. Inc ) July 1987. 295pp 87090902E4 EGG 2473 42578.129. s,ents were anatyred until either core damage began or ton 9-term decay heat removal was estabbshed The ana!>ses This report describes the methods, ana'yses, results, and showed that for the sequences considered the injecton flow conclusons of two d<fferent ag!ng studies The first analysis from one hgh pressure irtecton pump nas necessary and Sutt'* cons,sts of a su rvey of bght mater reactor component fadures cent to prevent core damage in the absence of operator ac- associated with selected safety and support systems Tables tons Operator actons were able to prevent core damage n the are resented, indicating the systems and the components S(2)D sequence; no operator actons were avadable to prevent n,thn those systems most affected by agtng Also provded are core damage in the TMLB" sequence egneenng insights drawn from the data The second analysis consists of dentifying and categoreng the reported fa4ture NUREG/CR 4742: MELPROG-PW R/ MOO 1 ANALYSIS OF A causes of component f a, lures The systems used in the failure. TMLB' ACCIDENT SEQUENCE KELLY.J E.; HENN3NGER,R.J.; cause ana'ysis were service water systems and Class 1E elec-DE ARING.) F. Sandia Natonal Laboratores. January 1987. 83pp. 8704070501. SAND 86-2175 40437.114- tocal power d<stnbuton systems for Babcock & Wilcox Compa-The fest complete, couple 1 and mechaniste analysis of a ny pressunzed water reactors and service water systems for boang water reactors TMLB' 6taton blackcut) core meltdown accident for the Surry plant has been made wth MELPROG-PWR/ MOD 1. Th s analy-sis has provded the t; ming of the major events occurring en the NUREG/CR-4752: COiNC3 DEN T STEAM GENERATOR TUBE accident, the amount and timing of hydrcgen produced by on- RUPTURE AND STUCK-OPEN SAFETY RELIEF VALVE CAR. daten of the cladd.ng. and tr'e condition and compos. ton of the RYOVER TESTS MB 2 Steam Generator Transaent Response disrupted matenal at the time of vessel 'adure Due to the pre- Test Program GARBELT,K.; YENDLER.O J ; GARDNER,G C.; hminary nature of this first calculaton, a limited number of auni- et al We5t,nghouse Electnc Corp March 1987 686pp. iary calculations have been performed Companson of these re- 8704010141. EPRI NP 4787. 403t 9168 su!ts with prevous calcutatens have provided further insights In PWR steam generator tube rupture (SGTR) faults, a oirect ento this acceent. In pamcular, it is shown that natural convec- athway for the release of radoactrve f'sson products can entst ton reduces the rate of core heating. but increases the rate of if there is a co.ncident stuck-open sa'ety rehef va!ve (SORV) or d heating of upper pienum structures This increased heating can e $ WM N W Ne mM d inhabit f:sson product depos; tion and increase the amount of a dm4 molten strucy! steel in the mett at vessel fah re 11 is also state and transient fautt con $ tons The main conclusons from shown that couphng between vessel flow and pnmary system these tests we'e that moisture carryover nas very low in the ab-flow may lead to earty beat ng and fadure of the pnmary system sence of an SGTR, that there nas no significant increase in Hence, natural circulaton

• thin the vessel wsth couphng to the moisture carryover dJnng an SGTR/SORY lautt and that very pnmary system can corepletely change the course and timing of httie or no primary coolant passed through the steam generator a mendown sequence TNs underknes the importance of a without haeng first completery maed with tne buik secondary mutted4mensona) vessel flow capabAty as provided by MEL. hou>d (pnmary cooiant bypass:ng) Shon term perturbatons to PROG in add. ton, the effect of the modekng of the in.t al fuel steady state cond tons were found to produce trans>ent re-rod metting and relocaton has been studied Vanatons in the leases, wNch could be mainly due to pnmary Coolant bypassing assumptons were found to st'ongly affect hydrogen producton or these releases were the equrvatent of steady state releases and the subsequent course and tim.ng of the acceent over tens of hours, and could be important factors in determin.

NUREG/CR 4744 V01 N1: LONG TERM EMBRITTLEVENT OF '"9 * * ""**U*******@**#"" "

 ';AST       DUPLEX       STAINLESS         STEELS       IN    LWR     l

• maw leve% am recircv!aton adNn the boder could not SYSTEMS Sem4 annual Report.Octoter 1985 March 1986 te ma.ntained, cond tons typical of early stages in an SGTR/

CHOPRA.O K ; CHUNG H M Argonne Natonal Laboratory Jan. SORY fautt produced large trans.ent releases uary 1987. 47pp 8704080064 ANL-86 54 40441290 TNs progress report summar2es work performed by Argonne NUREG/CR 4753 V02: CANADIAN SEISMIC Natonal Laboratory during the s a months from October 1985 t N E MRMR J . WMJ A . March 1986 on long term embntt!ement of cast duplex sta,niess SHANNON W E ; et ai Canad an Commerciat Corp Octoter stee!s used rn 4ght-water reactors 1997 39pP 8711100368 43338 226 TNs is the second report under the terms of the contract. NUREG/CR 4744 V01 N2: LONG TERM EMBRITTLEVENT OF NAC 04 85-110. for a research agtt-emert ent,tled "Canalan CAST DUPLEX STAINLESS STEELS IN LWR SYSTEMS Semiannual Report,Apol Sept (mter 1986 Se smc Ayeemerit ' bet *een the U S Nuclear Regufatory CHOPRA.O K ; CHUNG H M Argonne Natonal Laboratory May Ccmmisson (NRC) and the Canatan Commerciat Corporat.on 1987 54pp 8709040241. ANL-8716 4252610t Activ.t.es undertake n by the Geophys.cs Divison (GO) of the ggoog, cat survey of Canada (GSC) during the perod June TNs progress report summarJes norm per+ormed t y Argonne Natonal Laboratory dunng the sin months frcm Apni September 1966 to Jurie 1997 and supported in part by the NRC ayee. 1986 on long term embreement of cast duplem sta niess steels nt are descoted below under four bcaangs. ECTN and port. used in hght- nater reactors atae networn developmer'ts, data Sb developments. strong moton network developments and earthquake actvty Dunng NUREG/CR 4744 V02 N1: LONG-TERM EV3AITTLEMENT OF the penod of tNs recort, the contract resources were spent on CAST DUPLE x ST AINLE SS STEELS IN LWR SYSTEMS Semiannus Repor10ctoter 1966 operaton and ma ntenance of ECTN servong and mainte. March 1987 nance (by contra:t) of the strong moton . seismograph network. CHOPR A.O K . CHUNG H M Argonne Natonal Latoratory No-vember 1967 52pp 860t 110207 ANL-87-45 43975157 operaton and erpans on cf the Otta*a data lab and earthquake TNs pro <yess report summar2es work performed by Argonne monitonng and report ng The development of specsat purpose network s for Sudtue y and Chanevo;r are a'so reported on here Natonal Lateratory dunng the s u months from October 1966-March 1987 on long term embr twment of cast duples stainless because twe, a e close.1, rotated to ECT N but they are support- . N *% or in paq b, other sou rces l steels used n bght mater reactors l l

f i f i M0ln Citations and Abstracts 45 90UREG/CN750: A RETRAN fAODEL OF THE CALVERT DHR systems. The systems analysis consdered small LOCAs i CLIFFS 1 PRESSURIZED WATER REACTOR FOR ASSESS- and transent internal ntiating events, and seism.c, fire, extreme ING THE SAFETY IMPLICATIONS OF CONTROL SYSTEMS. wind. it;temat and extemal nood, and bghtnmg enternal events, I RENIER,J A.; SMITH.O L. Oak Redge Natonal Laboratory. ' A futt scale systems analyss was performed with detaded fault  ; trees and event trees including support system dependences. March 1987,116pp. 8706030092. ORNL/TM 10236. 41161:126. t The failure mode and effects analyts of CaNert Chffs 1 den- The system analysis results were extrapolated into release Cate-  ! tifed sequences of ever'ts judged suffcientry complex to ment gones useg apptcable past PRA phenomenological results and further analysis in detaded dyname simulations. TNs report de- emproved contamment farlure mode probabihtes Pubhc conse- i i scnbos the RETRAN model developed for this purpose and the Quences were estimated utng $te specific CRAC2 calculatons. h results obtamed The mathematical tool was RETRAN/ Mod 3. The value-impact (Yt) analys.s of possible afternatrves consd-  !. the latest verson of wdely used and extensweiy vaudated ther- ered both onste & ofis.te impacts artwing at several nsk meat-  ; makhydravic producten code. RETRAN2 is based on a first- ures such as averted populaton dose out to a 50 mile radius 4 4 pnnesples methodology that treats two phase flow with shp. and dollars per person tem averted. Uncertaintes in the VI anab , Thermal equdebnum of phases is assumed except in the pres- ysis are dscussed and the issues of feed and bleed and sec- i sunzer, where non-equdibnum processes are wnportant and spe- ondary blowdown are analyzed I csal methodology is used. Heat transfer in solids is obtained ,

                                                                                                                                                        =

from the conventonal conducten equaton Poent or 1 D kinetes NUREG/CN765: MXS CROSS-SECTiON PREPROCESSOR is avadable for the reactor core. The fundamental methodology USER'S MANUAL PARKER.F.; LUCK.L Los Alamos Natonal $ is supplemented with a broad list of process submodels that Laboratory. ISH!KAWA.M. FBR Safety Laboratory, Ibaraki Pre-calculate heat transfer coeffcents, fluid and metal state proner- fecture, Japan. March 1987, 58pp. 8705190577. LA 10856-M. 4 ties, choked flow, form and wait incton losses, and other pa- 40966.217.  ; j rameters. Also supphed are component submodels for vanous The MxS prepocessor has been desgned to reduce the ene-4 types of vanes and pumps, the latter of wNch mcorporate four- cuton tune of programs usmg isotopic cross-secten data and to quadrant charactenstes for cornponents in wNch two phase or both reduce the executon time and improve the accuracy of reverse flow may be expected, and heat versus flow curves for shelcng-factor interpolaton m the SIMMER 41 accdent analyss i' 3 4 others. Extenswa mput anows the code to be hghly partculzed i prograrn. MXS is a dual-purpose preproces9ng code to (1) m,x to a specifc plant The rnator investment m time and manpower isotopes into matenals and (2) f,t ana'ytc functons to the self-j occurs m settmg up the base case, changes are comparat very Sheektng data The program uses the tsotope microscope neu- , t j easy to unplement tron cross-secten data from the CCCC standard interface fde

  '                                                                                   iSOTxS and the isotope Bondarenko self sNeidng data trom NUREG/CN760: TEST                     OF 64N THICK       PRESSURE the CCCC standard mterface file BRKOxS to generate cross-          ,

VESSELS Senes 3 tntermedate Test Vessel V-8A Teanng Be. secten and self sNeiding data for matenals. The materWs may  ! haver Of Low Upper Shelf Matenal BRYAN,A H.; BASS.B R.; be a mature of several esotopes. The self-sNeldng data for the BOLT.S E.; et at Oak Rdge National Laboratory May 1987, matenais may be the actual sNelang factors or a set of coeffe t 404pp 8710060100. ORNL 6f 87. 42920 003 Tests of several 152-mm-tNck vessels have been performed cents for furrtons representing the background dependence of to sturJy the behaver of flaws under stress states smtar to the sNetang factors A set of adotonal data ls gwen to de. those in tull-scale reactor pressure vessels The obrectwo of the senbe the functions necessary to interpolate the shel@ng fac-fatest test, V-8A, mas to provde accurate quantitatrve data con, tors over temperature ,. 1 j corning the growth by ductde teanng and final mstapty of a NUREG/CR 4766: USER S MANUAL FOR THE NEFTRAN COM-ftaw m a low upper shelf toughness we6d located m a cyhnder PUTER CODE LONGSINE'D E ; BONANO E J ; HARLAN C P-  ! { - of reactor vesset steel TNs test is important because there are Sanda Natonal Laboratones September 1987. 230pp. [ vessels in sennce that contae welds wNch, because of Ngh 87f 2280248 SAND 86-2405. 438f 6 051.

 -         copper content, may have ther Charpy upper sheit energy                        TNs document desenbes the NEFTRAN (Network Flow and i

1 values reduced to relatwety low levels by neutron tra$aton Transport) computer code and at is intended to provde the i The results of the V4A test are etended to provee an empen- j reader eth detaded enough informaton in order to use the I mental basis for judging the accuracy of vesset fracture safety code This cade is a successor to NWFT/DvM (Campben et al . analyss procedures for low upper shelf toughness constons M81) and cMains several new capabdities These are 1) gen- > The objectwo of the V 8A test was attained *'th a teareg insta, eraued Nm woon, 2) matnx &Wsc4 3) kg transfer, y [ 1 bdity observed at a pressure of 139 MPa (2 x cesgo pressure) mang ceu, and 5) maple chaos TNs document rs dvded into t The flaw, wNch was initialty a fatque sharpened notch mth an [ four man se: tons desenbing 1) mathematical representabon of j approarnately erkptcal profde, grew in depth and length to [ 101.4 mm and 453 mm, respectivety. Pretest and posttest trac, ground-water flow, radonuctde transport, matna a ttuson, , source term and leg transfer models,2) the program and sub-  ! $ ture-mechancs and stress analyses were made by smptfed programs e the code. 3) the mput to the code; and y sample r i methods, convenient for invest 9ating a wde range of param- probtems N4hhghbng each of the new capa%tes of the code. eters, and by three-d mensional ficute element methods. *Nch j modeled the matenal properties and geometry more precisely NUREG/CR 4.'67: SHUTDOWN DECAY HEAT REMOVAL ANAL. I

 ,          Ductsla ftaw growth and estabMy predictons based upon meas'                 YSIS OF A GENERAL ELECTRIC BWR4/ MARK 1 Case Stuch ured J-resstance and tensde propertes were made Resutts of                  HATCH.S W , ERICSON.D M., SANDERS,G A Sanda Natonal             [

analyses based on J(R) controlled crack growth ayee reaso* Laboratones Jufy 1987 745pp 87t0140105 SAND 86-2419. f abiy well eth expenmental observatons a 3051001. NUREG/CM762: SHUTDOWN DECAY HEAT REMOVAL ANAL- A Generaf Enoctnc Bodeg Water Reactor (BWR4) with a Mark , YSIS OF A WESTINGHOUSE 3 LOOP PRESSURIZED WATER I containment has been evaluated as pad of Task Acbon Plan , REACTOR Case Study SANDERS.G A4 ERICSON D M , A-45. 'Decey Heat Removal Requwements" Probabel.stic nsk . j CRAMOND.W R. Sanda Nationat Laboratones March 19ft7 assessment modets were constructed to determine the dome l 827pp. 6704010158 SAND 66-2377. a0322 055 nant otemaf, randomly rutsated accdent sequences and speoal } TNs is one of six case stu4es for USt A-45 Decay Heat Re- emergency sequences (e g , earthgaakis) The dominant se- L l moval (OHR) Requwements. The purpose of tNs study is to cuences we e reviewed to determine anat mod ficatons might l 1 dent #y any potential vulnerabdites e the DMR systems of a be mace to enhance the plant s aMty to remove decay heat y ', typcal Westinghouse 3 loop PWR, to suggest possat4e mod f.ca- Modfications *Ncn held promise went through a prehminary  ! tons to improve the OHR capaMty, and to assess the salue cost and design anasyss Adotonany, the impact on the proba. [ and impact of the rnost prom. sing attematives to the eust.ng sty of core mest accdents was estimated given vnplementa- t t l l I t i 4  ! 8 I i

46 Miln Chati:ns cnd Abstracts ton of modaCatons in the final step, these results *ere com. This document presents a shortened verson of the proce-txned m a valueampact format according to NRC gudelines dure, mMets, and data for human teltabihty ana?) sis (HRA) The resutts ind< ate that feas:ble modAcatens to enhance *Nch are presented in the "Handbook of Human Rekabsty decay beat re*noval do en,st at the subtect plant. The central Ana'yss With Emphas.s on Nuclear Power Plant Appl.catons" estmates o' the value-.mpact results tended, however, to show (NUREG/CR 1278, August 983) This shortened verson was margsnal ecst eMectaeness under current gudeloes for most of prepared and tre out as part of the Accident Sequence Eval-the rnodAcatons Alternate assumptons envolving source 'erm maptude mere found to 5+gnif< ant'y affect tne resutts. The in- uaton Program (ASEP) f#ded by the U S Nuclear Regulatory Commission and raanaged by Sand a Natonal Laboratones s>gnts gained from ints study *di become part of an informaton The intent of this new HRA procedure, called the "AStfo HAA base nn.ch we be used to develop genenc recommendatons Procedure," :s to ense systems anahsts, with mNnal support regardry the adequacy of decay beat removal systems in bght from experts in hu< nan rehabilty anahses, to rrake estimates of mater reactors the human error protabates and other human performance NUREG/CR 4764 V01: METHODOLOGY AND APPLICATION OF char &ctenst<S that are sufficientry accurate for many probabibb-SURROGATE PLANT FRA ANALYSIS TO THE RANCHO tic nsk assessments The ASEP HRA Procedure consrsts of a SECO POWER PLANT Task 1 Anarysss Of ANO-1 And P'e-Acc4ent Screening HA A, a Pre- Acc4ent Nominaf HRA, a Oconee PR As GORE.B F Battene Memonat Institute. Pacfic Post-Accdent Screening HRA, and a Post Accdent Nomenal Northwest Labc< atones Jury 1997. 75pp 8707310128 PNL, HRA The procedure in this document includes changes mado 60321 4 t 9E 3C4. at;er tryout and evaluation of the procedur e in four nuclear Thts t*woturne report presents the deveopment and fwst pons plants by four different systems ana&ysts and related per-apptcation of a methcdoiogy for usng genenc PRA informaton sonnel, inclad.ng human rehabilty spectahst.s. The changes con-to denth nsk-mportant systems and components at a plant S st of some add: tonal esplanatory matena' Onclud ng exam-lacht.g a PRA. The rnethodoogy requires the detaded ana'ys s ples), and more detaded defotons or some of the terms of both sWattes and d<fferences between related plants it is apphed in ao anaS$ s of the Rancho Seco plant using informa. W TO ELM W4 ton from FRAs for the ANO 1 and Oconee plants it is genene, NATIONAL SAFEGUARDS AT M XED-OXIDE CONVERS:ON draerng upon the functonal and det,sgn smlant.es of B&W F ACIUTIES HARMS.N L ; ROBERTS.F P. Battelle Yemonal ln-p ants. yet rt encorporates consderable plant specificity through Sttute, Pacdc Ncrthwest Laboratones. June 1987 44pp the detaled compa*atrve ana$s;s of systems Volume 1 pre- 8706300252. PNb5194. 41491001. sents the ana!ys s of the surrogate plant PRAS Dominant cut This study for the Nuclear Regulatory Corrmsson dent fies sets lesing to core meft are centifed and ana'pred to deter- at anaWes fadty designs that can fac4 tate Internatonal mine the FussebVesely importance of plant systems in Volume A'omic Energy Agency safeguards for m.ned piutonium uranium 2 the dory, ant cut sets are further anaWed to der'th and cat. once tVOX) conve son p! ants A basehne facetty is defced and egonze important system fa ture modes The Rancho Seco plant the emplementaton of safeguards is ana!yred. Areas a'e denti-es then studied to determine the plausbbty and emportance of I'ed IOf *h'ch special facihty desegn consderaSons can fachtate

                                                $>mear faVe modes for: H gh Pressur e injecton Lo* Pressure           IAEA :nspections for t.me'y detect.on of possrble drverson of in;ection. Emergency Feed *a'er, Sevice Water. V.tal AC pone,        nuclear matenat Desgn features are proposed to enhance n-and DC Power systems Pfant spec'fc snformaton is then pre.           specton capabiktes for venfication of nuclear mater a' f,0*s sented ident4ng Rancho Seco components, power suppbes,                and inventones e rat         es associated *ith the fadute modes for the NUREG/CR 4776: RESPONSE OF SEISM!C CATEGORY I TANKS TO EARTHQUAKE EXCITATION BUTLER,T A; NUREG/CR 4768 V02: METHODOLOGY AND APPLK'ATION OF                        BENNETT.J G , BABCOCK,C D ; et al Los Alamos Natunal SURROGATE PLANT NA ANALYS S TO THE RANCHO                             Laboratory February 1987. 69pp 6703260013 LA 10871 MS SECO         POAER       F1 ANT Final      Report     GORE.B N        40238 043 HUENEFELD.J C Bat'ene Memonal Inst;tute, Paafic Northwest Tre response of vertical, aboy' ground, fluid-twed tanks to Laboratones July 1987 87pp $707310413 PNL-6032 2                      seismic loads is rere*ed and hcenSog entena are recommend-41994 0 t 7 See NUREG/CR-4768,V01 atstra:t                                   ed for use by the U S Nuclear Regulatorr Comm,$$on in as-sessing the safety of seismic Category I tanks Anarys4s rneth.

NUREG/CR 4769: RISK EVALUATIONS OF AGING ods and relevant expenments are fest reue*ed to provde a PHENOMENA The Linear Ag.ng Rehabety Mcdel And its Esten, bass b mcomme%ng anatytical techn> ques that are usets for sons VESELY,W E EGaG laaho. Inc (subs of EG&G. Inc t tad sa'ety evaLaton Neit field damage that has occurred Apnt 1997 176pp 87C8130348 EGG 2476 42154110 dunng several earthquates. Starting

• tn the 1964 Great Alaska A mccel for bght water reactor safety system component fad. Earthquabe. are reviewed and the dama2e rs categonzed This ure rates due to apng mechanrsms has been developed from 'nformaten is then used aiong mth expenmental evdence. to bas.c phenomenoicgcal consderatons in the treatment, the assess the adequacy of current formal desgn codes Fina9y. a occurrences of deteroration are modeled as fono*og a Poes. geocedure for Category I tank evaluaton is recommended and son process The sever:ty of damage is anowed to have any topics that need add tonal research are dent; fed astnouton, ho*ever, the damage is assumed to accumulate in-l dependentty Finan y, the fa-lure rate es modeled as berng pro- NUREG/CR-4779: NEW DATA FOR AEROSOLS GENERATED ,

portonal to tne accumulated damage Using this treatment. the BY RELEASES OF PRESSURIZED POWDERS AND SOLU- ' knear ayng fahe rate model is otta;ned The apphcatory of TIONS IN STATIC AIR BALUNGER M Y - SUTTER S L the knear arna mcdel to vantsus mechanisms is d4 cussed The HODGSON.W H Dattene Vemonal Inst:tute. Phdc Northwest mcoel is a!so er1 ended to cover nonhnear and dependent aging u  % 1987 W 87Wm FWM phenomena The irrpiementaton of the knear apng model rs g demonstra'ed by app'eng rt to tre ayna data cooected in the Safety assessments and ennronrr. ental impact statements for i U S Nuclear RegJatory Commason s N4 ear Piant Agng Re- e fM Wie re e em d WW & sea @ am bome rom Aue prM h amnts n W n vest. gated by Pache Northwest Laboratory to develop radoac NUREG/CR-4772: ACCIDE NT SEQUE1CE EVALUAT6ON PRO- two source term estimaton methods Espenments measunng GRAM HUVAN RE U ABILITY AN ALY SIS PROCEDURE. the mass art >orne and partcle 5::e 0.str.buton of aerosois pro-SWA!N A D Sanga National Laboratones February 1987. duced by pressun2ed re4 eases were run Ca* bon dode was i it7pp e7Ctt20044 SAND 66-19% a1166 280 l used to pressurve uranine solutons to S0. 250. and 500 psg

Main Citations and Abstracts 47 before release The mass attorne from t"ese eipenments was to evaluate the atal:ty of the radoactiv:ty mcotonno system hghor than for comparable ao pressunzed systems, but not as sampM hncs to transmit radcactive elemental sod no dunng great as espected based on the amount of gas d.ssoNed in the tranoent cond tons. The sample hne was tested trut ally *3th houd and the volume of hoved er ected from the release equip- manufacturing contamineten left in the loe, then was cleaned ment Flashing sprays of urance at 60,125, and 240 psq pro- and retested to eva'vate the effect of cleaning on transent per-duced a much larger source term than att other pressunzed re- formance The sampte line tested was of a Sze [2 54 cm (1 in s leases performed under this program. Low-pressure reicases of d ameter and 4572 cm (150 ft) long} that was espected to have depleted uraneum donde at 9.17.5, and 24 5 psg provided acceptable performance deng a nuclear reactor accdent The data in the energy reg on between 3-m sodis and 50-pug pres- tests were conducted in a laboratory where radcactive odoe sunzed releases could be generated safely, test vanables closety controlled. and test data measured NUREG/CR 4781 DRFT: STUDY OF SEVERE ACCIDENT MITI, GATtON SYSTEYS. CHERDACK.R ; HESS.C . LEE,K.; et al- NUREG/CR 4707: CONFERENCE OF RADIATION CONTROL Sande National Laboratones. May 1987. 702pp 8707300021 PROGRAM DIRECTORS' INFORMATION FOR LICENS;NG SAND 87 7064 41977.020 LOW LE%EL RADIOACTIVE WASTE INCINERATORS AND TNs study has been performed as part of the Severe Acco COMPACTORS.

• Conference of Radaton Control Program Di-cent Risk Reducten Prcgram (SARAP) to investgate the feas" rectors Inc January 1987.152pp 8703030822 39866 219-bihty and costs of msta1hng vanous systems desgned to m t" TNs gudance was written to as9tt Agreement States and ap-gate the e*fects of severe accdents in Ight water reactors p% cants addres9ng ic*-level maste processng as regulators or (LWRs). The pnmary functon of the systems is to rnaeta:n the as Icensees The Low-level Radcactrve Waste Management etegnty of the reactor conta>nment in the event of a severe ac- Commttee (E 5) of the Conference of Ra$aton Control Pro-cident one in *Neh substantial core mettng and reactor gram Directors prepared this gudance document aNer evaluat-vessel fa' lure occur. The systems evafuated include (1) a hydro" ing current waste compacton and incineraton practices with gen grvt<n system attn capabAttes for detectog hydrogen con' consderaton of present appbcable regulatory requirements for centiatons, ntiatog hydrogen buming, and avoding the trgger' hcen5ng inc neraton and compacton processes to reduce low-ing of detonabons. (2) a reactor cacty fiooding system capatie temi razoactrve easte volume have teen licensed by Agree-of ntroducing large quant tres of mater in the reactor cauty and ment Sta!es and by the U S Nuclear Regulatory Commess.on adiacent regens; (3) a core debns management system that for o<er 20 years inaneraton volume reducton factors in the would prevent the core debns from a faded reactor vessel from ,ange from 10 to 100 have been ach,eved and compacton can eteract ng with 9gnificant quantites of water and *<th the con- reduce the waste volume by factors from 2 to 10 or more with crete of the cacty. (4) an an(<nate coritaoment spray system accompany.ng reduct on in the costs for waste disposal in that would operate without res y ng on any esisting piant elect" prepa*aSon of tNs gudance. the focus has been on keeping ra-cal power suppl 45 and (5) a passcve conta'nment heat removal diaton esposure 'as low as reasonatty achevable " Compte-system that wou:d remove heat from the containment atmos. ton and inoneratcn in particular to produce a more stable phere by condenung steam. These systems were consdered maste form n'th enhanced performance characternbcs after d:s-for installaton in three types of LWR containments Conceptual posal is a pos.twe step toward that erd TNs document does desgns and associated cost estmates were developed for two nct spedca"y a$tess ncoerator or compactor installabons at propose combinatons of these systems Th s work provdes an war p*er pants oput to the cost benetst aWyses conducted in the S ARRP Pro-gram in support cf NRC's assessment of severe accdent risks NUREG/CR 4788: AN ANALYTICAL AND EtPERIMENTAL IN-to be pubhshed m NUREG 1'50, VESTiGA;lON OF NATURAL CIRCULATICN TRANS!ENTS IN NUREG/CR 4733: ANALYSIS OF BALANCE-OF-PLAN 1 REGU. A MODEL PRESSURIZED WATER REACTOR MASSOUD.M LATORY ISSUE S Final Report LAY.R ; ETTLINGER L ; Margand. Urvv of. Ccuega Park. MD January 1987 271pp SETH.S . et al M.tre Corp June 1987.157pp 8706160138 8702170061. 39656 098 MTR 86 WOO 213 41310 071 The Universty of Varytand Conege Park "2:4 Loop" scaled The MITRE Co<porabon. under contract to the U S Nuckar model f aaty was used to study natural orculaton This faality Regulatory Commesson (NRC) has esamined certaen regulatory simulates a B&W Ic*ered icop type PWR The espenmental n-I and performance aspects of the conventonal, or power conve,. vesbgaton included determinaton of system charactenst cs as son,9de of nuclear plants. often referred to as the Ba!ance of *N as system response to imposed t'an9ents under symmetre Ptant This report ocludes MITRE's charactentat,on and ana'y. and asymmetne cond tons Asymmetnc tran9ents were im.

ses of the Balance- of-Ptant fadures a perspective on the safety posed to study fc* osahaton and pesotJe instataty The ana-Jegnificance of these failures, a descnpton cf current NRC ac. @cai ovesSgaton encompassed development of rnathematcal t:vities and edustry init.atrves that have the potent.al to reduce modd for sye phase steady state, ard t ans.ent natural orcu-these fadures and the formutaton of a set of recommendatons labon as well as mcdhcaton of eming model for two-phase for NRC s consderaton e atres9ng the safety issues ra1 sed fb* anaws of phenomena such as smatt treak LOCA. high by the B!'ance-of Plant in general, the Ba'ance-of Piant prot > Pessue cet nect un. and pump coast down The rnod.hca-tems repr.sent the most frequent reason for unantopated plant ton omlWed aM ton d mcdels for once-through steam genera-Shuttans, and they compromise safety The NRC needs to tor and electoc bever rods The deveinpment included coding bok at tre total power plant facety as a system, and provde N a comNter pr: gram ert t ed ' Symmetnc and Asymmetnc the same level of atterston to reduong chaSenges to the piant ^^8'Y5's of Sog e Phase F le* " Fle* inst ataty resutt.ng in ces-sa ety systems as it ooes to respond.ng and m.tigating those s saton of orcuiaton was not observed Pnmary system average

                                                                                                                            ,r perature rose dunng a s,mmetrr to asymmetre trans.ent chauenges Mif RE bebeves that this can be accorwahed w4tNn the contut of NRC's pesent reguiatory posture                  *Nie the total secordary sade few rate was maintarned NUREG/CR-4746: TRANSPORT BEHAVIOR OF IODINE IN EF-                    NUREG/CR 4789. THE S VULATION OF THE RMOHYDR AULIC FLUENT        RADtOACTIVITY          VONsTORING        SYSTEM $      PHE NOMEN A IN A PRESSUR! ZED W ATER RE ACTOR PRl.

EDSONJ L , DUCE.S W , TKACHYK.J W EG&G Idaho. Inc M AR Y LOOP POPP.M Maryiand. Urvv et, Conege Park, MD (subs of EG1G inc ) Ocbter 1967 35pp 8711100261 EGG- January 1%7 260pp 8702170045 390% 001 2480 43341 253 Severa f9d fce and heat transfer pheromena were nveste This report presents the results of tests conductN on a gatM Scaang ard moeng la s for PWRs are reviewed and a mockup of the sample hne of an emuent radcactvt, morwtorsq ran scaong a; pun focus.ng on tr,e overall loop t+ haver is system at a nuclear poner plant The prpose of tt e 'ests was presented Scakng cntena for one- and two phase natural circu-

48 Main Citations Cnd Abstracts laton are developed Reactor vessel vent vane effects are in- pressure. surface area to-volume rato. and leachate compos >. Ciuded in the ana'ysss Two new d:mensonless numbers. wh4h too on glass teach rates uniquey descree one-phase flow en natural circulaton loops. were deduced and are dscussed A scated model of the pn- NUREG/CR 4797: P90GRESS REVIEWS OF Six SAFETY PA-mary loop of a typical Babock and W4 con reacter was desgned. R AVETER D> SPLAY SYSTLVS UNER.R T. CEBOR.) So-burt, and tested. The modet ope;ates at a manmum pressure of ence Appbcatons International Corp pormerty Sc+nce Appbca-300 psq and has a manimum heat input of 188 kW. It ts about 4 tons, Inc ). March 1987 76pp 870401012) S AIC-86/30(4 times smaPer in heght than the real reactor, with a nominal 40340 241. Volume sca'e of 1500. Eupenment measurements included pn- A pact program of progress renews of Sa ety r Parameter Dis-mary ssde temperatures, hot leg velocatees, snd other pnmary play Systems (SPOSS) n as Carred out through informatco-gath-and secondary loop performance data All test data is com* enng vMs to su plants en the pered June November 1985. The pared to the theoretrca'ly derrved performance prod <tcns and purpose nas to sample industry progress toward the SPDS te-scahng I.ans The capabihty of the model to & mutate reactor omrements stated in NUREG 0737 Supptment i and therety sent valve e'fects and sma:t break loss of coolant accidents is to determine the need for a post imp ementaton a4t program d Scussed Suggested changes to the model and its instrumen-taten are recommended General system scabng witn complete White three pants had to varpng oegrees demonstrated the vu and simultaneous tno-phase fic* and heat transfer s,mulaton in atut=ty of the SPDS concept thsavgh e+fectrve imp;ementatcn, three of the 54: piants. Some having toen declared operatcnal all components is not possue n,th a low pressure loop ustn9 watet for as long as tao years, had encountered maior problems to the extent thit their SPD$s could confuse or mislead op.erators NUREG/CR 4733: RESULTS OF SEM: SCALE VOD-2C SVALL. in an emergency The proban S observed had nct teen appar-BREAK LOSS-OF COOLANT ACCIDENT WITHOUT HPl (S-NH) ent from prcr recens of $atefy Anais>s Repods on the sys-EXPERNENT SERIES STREIT.J E. EG&G Idaho. inc. (subs of tems Ma;or conclusons were that (1) a s.gnd, cant number of EG&G. Inc.) January 1987 61pp 8704080273 EGG 2482 plants may be having probtems with their SPDSs. and (2) assur - 40441;180. ance that any g ven SPDS meets the reasirements cannot te Four expenments samutat.ng smambreak, loss-of-coo l ant acci- determ+ned with reasonable confdence

• thout an on s:te aud t dents of 0 5*. and 21% without begh-pressure inlocton nere and d scussons *'th personne! respons.tse for developing op-performed in the Semiscale Vod-2C facaty These espenments eratng. and ma nta,n ng the 5, stem Th.s report summarises ob-differed in break s;te and recovery procedur es Three of the en servatons from the sis plant v+ts and presents a p!an, with penments had the same break size (0 5*.). but recovery proce- procedses and gudance, for conduct;ng post- implementaten dures were vaned to determine what infivence vanous proce- aud ts of add tenat SPD$s if they a'e undertaken dures had on transient sever.ty The recovery procedores en-cluded secondary steam and-feed ntiaton when a cond tcn of NUREG/CR 4798: IRON OMDE AEROSOL EFERNENTS iN anadequate core coohng was detected, secondary steam and STE AV A'R ATMOSPHERES NSPP TESTS 501-505 AND feed ntiaton when the vessellevel reached the top of the core 511. DATA RECORD REPORT ADAVS R E . TCBIAS.M L Oak (before a Cond-ton of inadequate Core Coohng nas detected). Adge Natonal Latoratory Janu ary 198 7 8)pp 8704130219 and the restart of a pnma'y Coolant pump ahen a cond. ton of ORNL/TM 10301 40497 056 inadequate core coohng was detected The influence of the Thts cra record riport summanzes the resu:ts 1 rom i>ve tests break site on the transient seveftty was s'so studred *-th the envolong Fe(2)C(3) test aerosol in a steam-air environment and incluson of the 21** break transeent n'th seconda7 steam- one test in a dry a.r arvronment TNs reseech sponsored by and-feed nt.aton when Cond.t on of inadequate core cochn9 the U S Nudear Regaatory Commason was corducted in the nas cetected Alt four of the erpenments were pedormed at Nuclear Safety Pdct Plant at the Oak R4;c Natona' Latoratory high pressure and temperature [15 6 VPa (2262 ps=a) pomary The purpose of Ws pic.

system pressure. 37 5 K (67 5 degrees F) core d Nerental tem- t is 'o provde a data t>ase on the be-perature. 587 K (597 degrees F) hot leg fiu+d temperat/e] and

                                                                        % g, p,3syg ,n com nment under cond t<ns assumed to all four empenments had an nt I b, pass flow rate nrrar 3 *.           occur in m'e nJ L AR a:cdont seQsences th.s data base g p, g, ,          ,mentai va4daton of a "osol tet:nacoral ccdes Compansons are made between the four e.penreerts and con-clusons drawn reganhng nhat recovery proced/e to use to                 gg3 . p ent in the report a bnef des:rston is g'ven of prevent heater rod temperature escursons                                s h teg tog (ther n=th the ressts in the form of tatoes and
                                                                            @s          M are data on aerosos trass cencentraton, aero-NUREG/CR-4795: LONG TERM PERrORMANCE Of HtGH-                            sol fanout and pla'eaut rates 10tal mass tanout and plateout.

LEVEL GLASS W ASTE FORVS VEANS.J L . SPINOSA E D , aercsol part>cte sie vessel atrnosphere pressee, vessel at-MARKWORTH A J . et af Battene Memor.al Insttute. Co%mbus m04he'e temceatu res temceatre gratents near the vessel Laboratores Novemter 1967 176pp 8712240049 BVh2143 nau. and steam condensaton rates on the vessel nail 43794 276 This report invest gates the long term performance cf maten- NUREG/CR 4799. RELAP5: MDD2 A5SESSVENT S VULATION a!s used for Nghdevel naste packages Gtass maste fym stad. CF SEV SCALE MOD 2C TEST S-NH a VEGAHEDM M es, the topc of th4 report, focused on toroshcate glasses for EGM Ida50. Inc (sats cf EG&G. inc I Octuber 1967 53pp both de'ense and commercial Ngste.ei mastes Namenc al e7110%336 EGG 2519 43316195 modehng efforts descnbe the onctics of giass d ssoluton. in- TNs report documents an e,avahon of the REtar5 MDD2/ ciudog the eMects of nater chemistry. and the Onet<s of g ass Cyde 36 05 t*erma' hy dra Ac cornputer code for a omsaton of leacNng assuming that saca precotates as a more statie a smal bream less-of cWant acc. cent trans<nt (SBLOCA) The phase subsequent to d ssoluton from the g! ass Gtass 'each ng e n ferimer ta! data t,ase for tne ev6aton is tne resut of Test expenments conducted in tNs task inciuded empenrnenta: vah S NH-3 rettom(d en the Somsca;e VDD 2C test faut, The datcn of the numencar rnodet for g' ass d ssott+on and prec g*- test mode +d a C 5* 58tOCA n th an a:compacyng ta-lur e of laton. an evaNaton of the eMects of two nat/a' cqan c ac.cg the Ng4pressse r;tcton cryge,c, CO'e coOLng sistem The on leach ng of Omulated maste g' ass and an e s penmental test f aWty aN RELAP5 'CD2 mon used in tN caZutatens I study of the teacNng behacor of dev.tr.f+d VCC 76 68 g' ass are descr tes E awat&s of t*e a:cu acy of the catu'atons s l specemens Lrtef at#9 recens a so *ere Corduc40 c<n the ef- a'e fdesented m the brm of CFf Nns d hasJed a,d cah fects Cf both dev inheaton and raj aton on gf ass Iva:Nng te cu'a'ed Nstar+5 ci se M ted pramtees ass:x ed n th the Ed6 haeor Other esc +nments d3cumecaed tne presence cf esp +n m a r, and snonda9 sistems A conc tuon was re a:hed ttat - i rneritgl art.f actg in glags lea;h tegts under c0fta n e mpenmes.tal the cCde is c apab e d man eg SM OCA c a:cu'atons tacer t', con @tcns and enamented the synerg st : cNects CJ temcenture HOntvW, SC*eCIthebMOCAfL'Wd @FN na*W6 hol

Main Citations and listracts 49 proper 1y pred<ted by the code. Suggestog a need for code im- NUREG/CR-4803: THE POSSIB'LITY OF LOCAL DETONATIONS provement DURING DEGR ADED-COPE ACCIDENTS IN THE BELLE-FONTE NUCLEAR POW E F PLAN T. SHERM AN.M P; NUREG/CR 4800; StGPl A USER S VANUAL FOR FAST COM- BERMAN M Sandia Natonal La oratores Jarwary 1987.45pp PUTATION OF THE PROBABILISTIC PERFORMANCE OF 8704080052. SAND 661180. 40446 240 COMPLEX SYSTEvs FATENAUDE.C J Lavence Lwimore it is possible to ob;octively determine whether a detonaton Natonal Laboratory Var 1987. 75pp 8706150086 UCID- can propagate in a gnen geometry (volume, shape and size, 20679 41304 154 obstacle configuraton, degree of confinement) for a g<ven min. Tae SIGP) progf am computes the probabaty of complex sys- ture composton (concentratons of hydrogen air and steam); tems as defined by cut sets or other binary product sets The this is done by conservatrvely equating the detonaton propaga. SIGPt program uses two f ast complementary methods of com. ton entena *<th the cntena for transrion from dettagration to puting the protab.hst< performance of complex systems the II detonaton This paper attempts to reduce the degree of con-method and the ogma rrethod The 11 algonthm exploits the fact servat,5m in this procedure by constructng estimates of the that carefv ay defined system components are otten statistica9y probabilety of transton to detonaton tased on subjective es. independent conditonal to the en vironment in which they are vapom d md @a A me m % $ NM M WM4 W Mm aM gem mW b embedded The Ugma a' gor:thm computes the c<obatal.ty of mc e to transaon to depa-combinat,ons of components produced by the 11 algor!thm by e W eet a ton. The methodology is then appbed to analyring the potential d spnt.ng and part. toning such components. thefeby auowing for local detonatons in the Behefonte reactor containment for a the enact computaton of periormance The program assumes vanery of accident scena'os Based on code-calculated rates input of up to three data types cut set data in dispnt normar and quant.tes of hydrogen generaton and calculated rates In form. tas<c component proba%t es for independent bas;c com- transport and mmng, this methodology indicated a le* potential ponents, and/or mean and covanance data for stat sticany de- for detonaten except for one volume in a few cases pendent ba9c components NUREG/CR 4805 V01: REACTOR SAFETY RESEARCH SEMI-NUREG/CR-4801: CL!VATOLOGY OF EXTREVE WINDS IN ANNUAL REPORT. January-June 1986

• Sand;a Natonal Lab-SOUTHERN CALIFORNIA R AMSCELLJ Va HUBBE.J Y : oratones Vay 1987. 359pp 8707300091. S AND86-2752.

ELLIOTT.D L ; er al Batten e Vemonal Insttute, Paofic North- 41983 130 west Laboratores Ja uary 1987. 104pp 8702170052 PNL. Sand a National Laboratones is conducting under USNRC 6085 39655 307 sponsorship. phenomenolog. cal research related to the sa'ety A chmatology of annual entreme ords in southern Cahfornia of commercial nuclear power reactors The research includes has t+en prepared The chmatoic*;y includes a descnpton of penments to omutate the phenomenotcgy of the accident cond tons and the deve6opment of analy tical mode:s ver fed by entreme end re7 ens. dehned on the bats of observed ends and topography Estreme end d stnbuton parameters ha<e espenment, entch can be used to predict reactor and safety been estimated for 46 locatons usang data obtained from the systems periormance and tehavior under abnormal condtons The ob;ectrve of this work is to provde NRC reou s;te data Natonal Chmat.c Data Center Protatat es assocated *"th es. treme ends have been est. mated for these locations The re. bases aM a%W Me m W MS aN Ma sa% suits of the anaN9s are generaHy contf *ent

• th prevous esto esses, WestaM me msse of nw s AaN am dent sequences, and (3) conduct sa'ety assessments The col-mates of entreme ends in southern Cauornia Atthough, in see * *
• erat instances the current estimates are ograficant'y h*gher than directed at enhancing the techno ncqy base supcorlog hcensing previous est mates Tne data esamined do not ind cate that o,c, song there has t+en a SgnAcant chaNe in tre entreme wind chmate of southern Cauc ma NUREG/CR 4808: M NTEO USER'S MANUAL. PETERSON.S R ;

HOSTETLER C J., DEUTSCH W J ; et af Battelle Memottal insto NUREG/CR 4802: AN EVALUATION OF TRAC-PF1/ MOD 1 COM- tute. Paofic Northwest Laboratones Augast 1987 159pp PUTER CODE PERFORVANCE DURING POSTTEST S MULA 8710220424 PNL.6106 43132130 TiONS OF SEM. SCALE VOD 2C FEEDA ATER LINE BRE AK Th.s MiNTEO user's rnanual was *ntten to aid the user in ap. TRANSIENTS H ALLD G . W ATMNS J C EG&G idaho. Inc p!png the MiNTEO gecchemical computer code to rnodel aque-(subs of EG4G, Inc ) Febr ary a 1987. 204pp 8704270202 ous solutons and the interactons of aaveous solutions with by-EGG 24B6 40681173 potheseed assemtAages c' sohd phases The purpose of the The* report documents an evaluatx n of the TR AC-PF1s MOD 1 user s manuat is teotod (1) to provde a basic understanding of reactor sa'e', ana'ys s compe er ccu duong computer simula. ho* the M.NTEO computer ccde operates and tne important tons o rfeed *ater bne bream t ansents The espenmentat data poropies tnat are incorporated into the code and (2) to inst uct base for the evaluaton included tne rewets of three bottom a user of the M:NTEO code on how to create oput faes to sem-feed *ater hoe teean tests pedormed in the Semisca!e Mod 2C viate a vanety of geochem. cat protdems Chapters 2 through 8 a'e d. rec'ed toward the user who has some empenence with or test fast, The tests modeied 14 3*. (S FS-7L $0% (S FS-11), and 100N (5 FS 68) break s The test f auty and the TR AC, mshes to re,e* tre poropies important to gecchemeat com-PF1/ MOD 1 mc@t used a the catutatons are desent.ed Eva,. pue codes oso contaw m vese chaptes is mformaton on uatons of the a: curacy of tre ca'cu'ates are presented in the the methodology M.NTEQ uses to encorporate these ponc: pies 8 A tcem of compansons of measure 3 and Calculated histories of selected parameters assoc.ated

• th the poma3 and secondag uw * *aMs to We row to create W cata Ws to model

                                                                                                                                                                           * * '*"' D P*

• O' ***

l systems in anton to evalua5ng accuracy of the code catuta-l tons. the computatonal performance of the code danng the NUREG/C R-4010: EVALUATION OF DIESEL UNAVAtLABrLITY l smutat,ons was assessed A conason was rea:hed that the AND RIS$ EHECTrv'E SUAVEILLANCE TEST INTERVALS l code is cacatue of mahng fem *aler one break tran9ent calcu VESELY.W E , DEVOSS G . LOFGREN E et al Brookhaven i latons et%ent!y. but there is rcom for sgnificant ,mpro,ements Natonal L ator atory May 1987 83pp 8708260121 BNL-l in the Omu:atons that At-ce pedor%d Recommendatons are NUREG 52022 4233118'3 max f or 10%* on in,estgatons to detem.ne hen to mpro,e in t%. report ns. and retania, approacnes are p,esented future fe(damier lane break c4Tutatons and for code amf#ove. *Nch ahon risk acceptable test interwa's to be oetermined for ments to make the Code cas.er to use any d esel Data requ+rel to appFy the approaches are also de.

50 M:In Cit:ti:ns and Abstracts Scribed The approaches can te apphed not only to d.esets, but TNs report presents the resur ts of an NRC project to deter. to any cofaponent w.th Setable data incorporaton of the ap- mine whether robotics eqwpment can be cost effectse in por-proaches in personal computer (PC) software rs discussed, forming surgedtance and inspecton work at entstiry nuclear wNch can provee tools for the regu!ator or piant personnel for power plants A metale sunreeltance rotot, caDed SUR60T, was any piant specife or genenc appbcaton. The FRANTIC 111 com- developed by the Remote Technology Corporaten (REMOTEC) puter ccde was run to va!4 ate the approaches and to evaluate to perform usuat, sound, and ra$aton survedlance witNn rooms spec:f.c issues associated with determong nsk effectrve test in- designated as rad.olog+cally hazardous. SURBOT was tested in tersa's for d.esels Us.ng the approaches presented. d+esel acco the turtune buiding of the Browns Ferry Nuclear plant (BFNP) dent unava4abAty can be more efdectvely monitored and con- by TVA personnel for a five-month pered Tne resutts showed trohed on a giant-speedc or genene basis Test eterva!s can be that SURBOT obtains higher quahty data and can periorm more made more risk effectrve than they are now, producing more ac- thorough survedlance w. thin ra1aton areas than workers wear-ceptable accdent unavadatshties, and avo4,ng the possible del- ing protective clotNng SURBOT can be transferred between etenous effects of Regulatory Gu+de 1.108 The methods pre- rooms without releassng contam4naten in the ha3*ays usng a sented are one step toward performance based technical spece- portable enclosure TVA has estimated that over 100 person. f<atons. *Nch recte directly control nsks rem exposure and $100.000 operating costs can be saved an-NUREG/CR 4813: ASSESSUENT OF LEAK OETECTION SYS. nuany at the BFNP using SURBOT for survedlance in 54 turtane TEMS FOR Lw Rs october 1985 September 1986 and reactor bu.htng rooms TVA recommendat ons for improv-KUPPERMAN.D S Argonne Natonal Laboratory. January 1987. og the functon. rehabAty, and maintainabAty have been encor-a6pp. 8704130658. ANL 86-52 40494 324 potated into a producton rnodel of SURBOT *Nch is now com-It has become apparent that no currently available s,ngle mercia4y ava.lable from REMOTEC along w,th other types of 4 lead- detecton method for let water reactors comt=nes opt,. motale robots and manipulators mal teatage detecten sens,tyty, leak locat ng abdity, and the desired level of accuracy in leasiage measurement. In this NUREG/CR 4817: IOD:NE PARTtTION COEFFICIENT MEAS-paper, N AC gudei nes for leak detecten wdl be reve*ed, cur- UREMENTS AT S:MULATED PWR STEAM GENERATOR rent Fact <es descnbed, potent-af safety-related problems dis- CONDITIONS intenm Data Report CLINTON S D; cussed. and potentaat improvements in leak detecton technolo. S!MMONS.C M Oak Redge Natonal Laboratory May 1987. gy (*;th emphas<s on acoustic methods) evaluated Although in. 28pp.8708060384 ORNL/TM-10330 a2075 002. ) formaton presented here is believed to be vahd for most plants. 10d'ne partiton coeffcents (def,ned as the rato of the con-add tenal data are needed to cent.fy exceptona For example. centration of cdine species en the a veous soluton to the a!though Quant.tative leakage determnaton is poss.ble w:th edine concentraton m the vapur phase) were measured at sem. condensate fion monttors, sump monitors, and pnmary coolant ulated PWR steam generator cond. tons (285 degrees C and 6 9 inver. tory tatance, these rrethods do not provde adequate lo. MPa), us ng camer free rascactive 1131 in the form of sodium ) caton infymaton and are not necessanly sens;tive enough to code The odine tracer concentraton was rnanntained at 6 x meet U S Nuclear Regu!atory Commisson Regutatory Gude 10( 11) mol/L, bonc acid concentraten was vared from 0 to 0 4 145 goa:s Leak detecton capatui.ty can be improved at spec,. mol/L; and the soluton pH (measured at 25 degrees C) was ad-fied 5 tes by use of acoustic monrtonng or rnoisture sens.tive justed from 4 to 9 by the addton of litNum hydroside loane tape (MST) Ho*ever, current acoustic morvtoring techneQues part; ton coeffcents decrease w.th increasing bonc acid con-provice no source d senminaton te g , to distinguish between centraton, however, the odine volataty is essentially independ-leaks from ppe cracks and vanes) and no leak rate mformaton ent of tne solution pH for a given bonc acd coacentraton (a smati wak may satvate the system) MST provdes neither Sparging the solutons with air at room temperature increases quantrtative leak rate infor naton not specific locaton mforma- the iodine volataty by an order of magewtude. compared to that ton other than the Locaton of the tape, moreover, its usefulness acNeved with argon sparg ng lodine pa*ttion coeNoent meas-with "soft" insu!atch needs to be demonstrated. urements ranged from a low of 200 (in 0 2 rnoianty bonc acd NUREG/CR 4814: SOURCES OF CORRELATION BETWEEN sparge we air) to 4M MO On puMed waW sparged we E APERTS Empincal Resu!ts From Two Entremes MEYER,M A; eM BOOKER.J M. Los Ala'nos Natonal Laboratory Apol 1987. 61pp 8705190636 LA 10918.MS 40977 256 NUREG/CR 4818: TRANSITION RANGE DROP TOWER J-R Through two stud'es tNs re:crt seeks to dent #y the sources CURVE TESTING OF A106 STEEL JOYCE.J A US Naval i of corte!aton, or dependence, between esperts' estimates Academy. Annapohs, MD HACEETT E M Dayd W. Taylor Empert esnmates are rehed upon as sources of data whenever Naval Research & Development Center Fetsuary 1987.31pp , erpenmentar data is tachng such as in nsk anaPysis and relabil- 87032505 % 40234 246 rty assessments Correlaton terween esperts is a protAem in gg g, gg gg,g the eictaton and subsequent use of subect!ve l estimates Until m ou W r r m m n-now. t*cre has t+en no data confirming sources of correlaticn, pected in the apphcaton of enterest TNs is not usuaPy the case g, g gg i a'though the esperts' bad g'ound is comtnonty speculated to be one Two dNent gopuiatons of e:Perts *ere admnstered scntes a method being used to obta.n JOC), JR curves, and J questons in their areas of entertse Data on their professorial at cleavage for three coint bend tests condacted at drop tower ba9 grounds and mers of soMng the queshons were eloted rates through the ductee 10 bottle trans ton reg:me of the femte using technques from educatenal psychology and ethnog aphy A106 steel being tested The mator concluson is that these The results from both studies ind.cate that the way in *Nch an tests can non be accomt lis%1 though a Ngh degree of exper. espert solves the orcCom is the maior source of correlaton tise and consoerable practical esteence is necessary to The erperts ba9 ground can not te shown to te an important stain good test resu:ts The steel tested hera rs ouste rate de-source of cone:at.on nor to ino vence Ns cho.ce of method f ' pendent as shown both by tensae tests and f acture toughness prob 6em soluton From tu se resutts. some recommendatons tests A load e'evston of 30 to 50% resu'ts in the drop tower a*e gven for the cictat*on and use of espert cpruon 100 m/second tests on th,s matesi in companson with stat < tests wher. teth tests are conducted on the ductie upper shelf NUREG/CR-4815: DEMONSTRATION TESTING OF A SURVEll- Nonethelest for tNs matenal J0c) and J-R curws are not ele-LANCE ROBOT AT BROWNS FERRY NUCLEAR vated by the losang rate aN tNs rather su pns r ng result corre. PLANT Ana!yses Of Costs And Benetts WHITE.J R , sponds to a tendency for c'ack nt aton to occur at a smaHer < HARVEY,H W , FARNSTROVA A. et af Remote Technodgy bend angle for the byn rate tests than for the static tests and a '

 !                                Corp March 1M7 82pp 8704270352 40704117                                                                            correspond >ngry greater amount of crack entenson m the rapid

Main Citations and Abstracts 51 specimen at a g>ven vend angle beyond crack irstaton than 1 the broad band 69.tal seism.c staton SRNY mstaned near the present in the static test Rondeut Associates. Incorporated (ray off.ces in Stone Rdge. NY. Included in the d scusson are the system response func-NUREG/CR 4019 V01: AGING AND SERV CE WEAR OF SOLE. t.ons and an anas ysis of the causes of data losts The second NOiD-OPERATED VALVES USED tN SAFETY SYSTEMS OF secton g.ves detatis of the data anat ysis me* hods used in NUCLE AR POWER PLANTS VoL ee 1 Operating Espenence And Fa4ure Ident;f<aton B ACANJKAS.V.P.; ROBERTS.G C ; studying broad band and array data Arthough several methods have been studed, muc't of tNs secton rs devoted to the TOMAN.G J ; et al. Oak Rd2e Natonal Laboratory. March 1987, adaptive polan2ston method wNch has sho*n prornse as a 69pp 8706030204 41147 287. An assessment of the t@es and uses of solenced operated sogle staton locaton tool The f nal secton ena%nes the no.se charactenstics at SRNY dunng both qset and ncrsy cond. tons vanes (SOV) in nuclear pc*er plant sa'ety retated service is and compares these levels to the Regonal Seism.c Test Net-provded Through a descripton of each SOV's operaton, com. work staton RSNY in the Adirondack Mountan reg on of nortn-hined Eth knomiedge of nuclear power plant apphcatons and ern New Yorit The detecton and locaton capatutes of SRNY operatonal occurrences, the s gnificant stressors responsible are also descrited and smgte-staton locat.ons at SRNr. as nett tot degradaton of SOV performance are centded A reve, of as RSNY, are compared to network locatons. actual operat.ng expenence (fa ture data) leads to identificaton of potental nondestructive m-sity testeg *Nch, if property de- NUREG/CR 4824: EVALUATION OF INTEGRAL CCNTINU;NG veloped, could provde the methodoiogy for detercraton mons- EXPER; MENTAL CAPABillTY (CEC) CONCEPTS FOR LIGHT toring of SOVs, Recommendatons are provced for continuaton WATER REACTOR RESEARCH , PWR SCALING CONCEPTS of the study into the test methcdc ogy development phase COND!E.K G ; DAVtS C Ba LARSON.T K et a!. EG&G Idaho. NUREG/CR 4820: COVPARISON OF THE 19B2 SEADEX DIS- inc (subs of EG8G. Inc ) February 1987.217pp 8704130652 PERSION DATA WITH RESULTS FROM A NUMBER OF DIF- EGG 2494. 40494 046 FERENT MODELS. LEWELLEN.W S , SYKES,R t ; The Un.ted States Nuclear Regulatory Comm<ssion (USNRC) CERASOLI.C P , et at Aeronautical Research Associates of in assesong their future research needs for both sepeate ef-Pnnceton February 1987. 163pp 8703090089 ARAP 575 fects and entegral empenments has req;ested that EG&G 39919 152. Idaho.Inc . ident.fy and technica9y evaivate potent.a concepts The resutts from simulatons by 12 d sperson models are that mil rea,ntain the capabekty to conduct future integral, ther. compared eth observations from an entensive f. eld empenment mabbydravhc fac,Lty expenments of interest to reactor safety. In conducted by the Nuclear Regulatory Commrsson in a shorehn* th s repost reactor transents and thermabhydraubc pheromena environment dunng the earty summer 1982. Ten of these of importance (based on prot,abest c risk assessments and the models are the same as used in the earlier compansons eth intematonal Code Assessment Program) to reactor safety were the 1981 fend tests at Idaho Natonal Eng neenng Laboratory examined and cent fed Estabuhed scahng methodo4oges All the models performed better on th $ SEADEX expenment we,e used to develop potent,a! concepts for integral thermaLhy. Lrttle ditterence between the models es ev4ent wrth hourfy sur- draubc testmg facekties Advantages and disadvantaget Of each face data, with the mcdels able to pred+ct the maximum value in concept are evaluated Anatys 5 is corducted to esawne the the ne.ghborhood of a sampier Ste mtNn a factor of 2 appro"'- scahng of varous phenomena in each of the selected concepts matety 25% of the time TNs is raised to approximatety 40% Resutts general!y suggest that a fac4Lty capable of orerat ng at when the companson is based on 12 hour etegrated dosa Fo' typical reactor operating cond. tons mit scate most phennmena the tenger time Samples the more sopNst>cated modets do reasonabfy well Although many phenomena m isSt es using ' sho* a ostinct advantage when measured by correlation coeff'- Freon or mater at nontypical pressure will sca% reasonably melt. cient and root mean square error. If the data file is assumed in' those phanomena that are heavey dependent on quahty (heat complete, eth h.gher data sampies poss bie betaeen the actual transfer of cntical fo* for eiampie) can te d storted Further-data samp:es. then the test resutts for the hourty samples sho* more, relat on of data produced in fastes operatng a th nonty-over 80% calculated *,th:n a factor of 2 when a 15 degree un- pecal fluds or at nontypcal pressure to large p' arts mill te a d f-certainty in the plume poston is permeted TNs is ra' sed '.o 1,cuit and t1me consummg process 90% for the 12 hour dose on th6 same compar. son ba9s NUREG/CR 4825: A PREll% NARY EVALUATION OF THE ECO-NUREG/CR 4821: REACTOR COOLANT PUMP SHAFT SEAL NOM >C RISK FOR CLEANUP OF NUCLE AR MATER!AL Lb STABfLITY DURiNG STATION BLACKOUT RHODES D B ; CENSEE CONTAMINATION INCIDENTS OSTMEY ER.R M ; H!LLR C ; WENSEL,R G AECL, Chan Rrver Nuclear Laborato-SKINNER D J. Sand,a Natonat Latoratores March 1987 97pp res May 1997. 60pp 8706120189 AECL 9342 41187 201. Resutts are presented from an investigaton into the behaver 8703260083. SAND 66-2108 40245 215 TNs report documents an ana'yses of tre econom.c nsbs from r;f Reactor Coolant Pump sha'1 seats durmg a potential station blackout Ooss of att ac power) at a nuclear po*er plant The in, nuclear matenaf hcensee contam.naton inccents The resur ts of the ana'yses are intended to provde a technical basis for an vestigation assumes loss of cookng to the seals and focuses on NRC rutemahng that would repre nuclear matenal1,censees to the e*fect of Ngh temperature on go>ymer seais located in the demonstrate acequate fcancial means to cover the cleanup shaft seat assembl+5 4"d the dent f>caton of Carameters costs for accidental cr inadvertent release of raloact ve rnaten-haeng the most chuence on overall hydraubc seal perform. a's The impor1 ant products of th s eftyt include (1) a rnethod et ance Predacted seat f av er thresholds are presented for a range of staton blac6out cord tons and shaft sea! geometnes categormng hcensees accordog to the potente cost and fre-Quency of contarrunaton inc4ents. (2) a model for ranking the NUREG/CR 4822: BROAD BAND SEISMIC DATA categones of licensees accoring to potent.at .ncent costs, l ANALYS S September 1984 September 1986 CARTER.J A . and (3) estimates of contaminaton r'sk far the hcensee catego BARSTOW.N ; SUTTON G H ; et al Rondout Associates, 6nc res Apnl 1987 100pp 87042701B4 40682 234 TNs repor1 contains a detawd descrpton cf the SRNY sta- NUREG/CR-4826 V01: SEISMtC M ARG:N REVIEW OF THE ion ecluing its response functon, desenpton of the tech- MAINE YANm E E ATOMtC POA E R ST ATION Votume 1 Summa-naques 3rd sor teare used to anahZe the data and evaivatons ry Report PRASSINOS P G ; MURR AY.R C , CUMV;NGS G E of both the staton and proces* ng methods The staten was La*1ence Lrvermore Natona! Latorebry March 1M7 190pp evaluated through rose sistes urder both quiet aM r@sy Con- 87040)0044 UCID-20948 40464128 d+t ons, rts detecton and locaton threshods, and the frequency. This Summary Report is the fast of twe vcA;rr+s far the duraton, and c suses of data loss The repor1 has been dreded "Seism.c Ma g.n Recew of the Ma no Y an6 ee Atynec Power into three main sectons The brst secton g'ves a descrpton of Staton " Vcau me 2 is the Sptems AnaWs of the test tnaf se4s

52 Main Citatiens and Abstracts mic m.argin review Volume 3 documents the results of the fra- cond tons For those accdents that have h.gher responses, the g+ty screening for the rev+*. The three volumes demonstrate probabatres and potential raiaton esposures of the accdents how the secsme rnarg n rece* go. dance (NUREG/CR 4482) Cf are cortpared *tth those dert:f,ed up the anessments made in the Nuclear Regulatory Commesson (NRC) Se sme Desgn Mar- the ' Final Encronmental Statement on the Tra%portaton of 94ns Program can be apphed The overall othectnes of the tnal Radoattae Material try Air and Other P.Accesy NUREG 0170 rece* Are to assess the seismec marg ns of a partcu ar l pres- Based on infs Companson. it ,s concluded that the falcicqcal sur7ed *atef reactor, and to tesi the ajequacy of this reson nsks from spent fuel under severe hghway and radway accdent approach Quant 4hcaton techn+ ques. anc gudehnes for pedorm- cond tens as dernied in *%s study are less than hsa s prevousN ing the reve* Resu!ts from the tnal reven will be used to estimated in the NUPEG-0170 dxument revise the se.sm.c marg-n methodology and guidehnes so that the NRC and tryf stry can readly apply them to assess the in. NUREG/CR-482^ V02: SH:PPING CONTA:NER RESPONSE TO herent quantitat>ye seismec capacty on nuclear power plar's SEVERE HIGH A AY AND RARWAY ACCIDENT CONDITIONS Append:ces FISCHER.L E , CHOU.C K ; NUREG/CR 4426 V02: SEISVC MARGtN REVIEW OF THE GERHARD.M A : et al Lawrenco tr<ermore Natonal Lateratory. M AINE YANKEE ATOM.C POWER ST ATiON Volume 2 Systems Fetruary 1987. 300pp 8703120299 UCiD-20733 39382 316. Ana'ys s MOORE.D L , JONES.O M ; QUillCLM D ; et at La** See NUREGrCR-4$29.V01 abJ1act rence Lr.ermore Natonal Latoratory March 1997. 201pp 8704090075 UCID-20949 40466 232 NUREG/CR 4830: MELCOR VALIDATION AND VER FiCATION This System Ana%s is the second of three voQmes for the 1986 PAPERS LEf GH.C D Sanda Natonal Latoratores "Seismic Marg;n Reoen of the Ma:ne Ya9ee Atorne Poner March 1987. 223pp 8706120166 SAND 86-2689 41281049 Staten " Volume 1 is the Summary Report of the first tnal sets. MELCOR vaadaton and venhcat.on rirsu!ts from 1986 are mac margin revie* Volume 3 Frapty Ana>ysts. documerts the presented Resu ts of compansons to ana'yt< soiutons and en r results of the fragity screening for the rece* The three voi. penments are included The major areas tested in these com-umes demonstrate how the se smic marg.ns reve* guacance pansons are the cortrol votume hydrod, nam cs and thermody-(NUREG/CR-4462) of the NRC Se sm,c Des,gn Marg.ns Pro. hamics the heat trans'er and tne aerosc4 t>chacor in VELCOR gram can te apphed The overa't ob;ect<ves of the tr al reve* A set of nine standard tests is 6ncluded are to assess the se.snac marg ns of a part,cu'ar pressunted

    *ater reactor and io test the a$equacy of t%s rece* approach,           NUREG/CR 4834 V01: RECOSERY ACTlONS IN PRA FOR THE Quant fication technques, and gudehnes for gerforming the                   RISK METHODS INTEGRATION AND EVALUATION PRO-rev+

• Resutts from the tnal revv* wil be used to rey se the GR AM (RV EP) vow 1 %@M G W M BW Memod WESTON L V ; WHlTE ME AD,D W Sand.a Natonal se.smic ma'g+n methodalogy and gudehnes so that the NRC and industry can readdy apoly them to assess the rnherent L erpre GR AVES N L Energy. Inc June t M 7. 295pp Quant.tatae se sm c capavy of nuclear poner plants g7gg7 gg7p g qq g in a protiataste r4 assessment (FRA) for a nuckar poner  !

j NUREG/CR 4826 V03: SEISM:C MARGIN REVIEW OF THE p'a nt, the ana'yst idea t44 5 a set of retentai core damage MA:NE YAN> EE ATCV!C POWER STATION Vcdume 3 Frapty events cons:st.ng of equ pment f a tores aN human (rrors and Ana'ys,s R AVINDR A.M A . HARD( G S H ASHMDTO.P S , et thcar est mated r>torato-t+s of occurrence it o;+rator recovery al Lawrence Livermore Nat ona! Latoratory March 1987 from an event *, thin some sgn Aed t,me is consdered. the 23600 87040DX3 UCID 20348 40a61139 Vceate cf tNs recovery can t+ included in the PR A T h> s Th:5 Frag hty Anais s is the third of three votames for the report pic.-des PRA amajs:s *:th an improved methodc6cqy for "Seismic Va'g n Rev4 a of the Ma ne Yankee Atomic Po*er includ ra recovery actons in a PRA A recovery acton can te Station " Volume 1 is the Sw r.. mary Repor1 of the fest thal se;s. d:vded ,nto t*o d stinct (Asses a D.agnos s Phase veau.ng mic marg >n reven Voume 2, Systems Anai rs.s. documents the that there is a r<ovem *>th a cr tica' pa*ameter and decc.ng resur ts of the systems screening tar the reven The three vol- upon the correct course of a: ton) a d an Act.on Phase (phys-umes demonstrate how the se smic ma*g ns reven gudance scahr accompMh.ng the reqped acton) in th,s methodoscgy, (NUREG 'CR-4482) of tne NRC Seismic Desgo Varg ns Pro. simv ator data a'e used to est mate recovery pctatat es for gra n can te appne3 Tre overali etwctnes et the toal review the d.a gnosis phase Deent time roat,1tr curves shening the are to assess the seism.c marg as of a particatar pressur .ted pict ataty of f aaure of d agncos as a funcion of time t'om the mater reactor, and to test the a$eam cy of this rev e* approach. compdog cue for the event are presented These curves s'e quart fsaton techmaues and gudeunes f ar pertarming the tased on simdator esercrses and the a: tons are group +d rece* Resa'ts from the tr.at revre *.a tie used to reose the t ased urcn the.t cr+rator.ai s,mear t<s Th s 's an impec-vement - sersm c margin metncdobn and gaones so that the NRC c.er cost.ng d agncs s mcde!s that reiy gre aPy upon sutvec t,ve and industry can read 4 awy thern to assess the inherent p3yneN tc, ot tar such est. mates The a:t.cn phne is mc4 Quant: tat:ve se smec Capa: ty Cf Bucied' p2*ef p' ants e+3 von)estMa'esfrDM ava !atie sourC 0s Ihe Method @cqy

                                                                               *      *          * * ' " "                                                                                          ""* *        d *  'U *D NUREG/CR-4829 V01. SH PPiNG CCNTAAER RESPONSE TO HiGHA AY

• SEVERE ANC R AIL W AY ACCIC(NT CONDtTIONS Va:n R( po'1 FISCHER L E . CHOU C A , NUREG/CR-4841: FRACTURE E V ALU ATON Cf SURFAct GERHARD M A . et ai 1 aarence twermore Natenat Latoratry CRActs E VDE DDE D IN PEACTOR VESSEL F etsuary 1M7 2edep 87031203?t UC:0 20733 3M2 032 CL ADO NG Ur trad a e1 Esend S;cimen Re suts VCC ABE D E This repor1 dacr.t+s a s'Ay r+darm<d t , the L a a r e rst Mater a's ng neenng Aw ,*% inc var tM7 70pp Lnermore Natoral Latoratary to evaLate the level of sa4t, 8 70$t W3 vt . Guu 4097716 7 provded under severe a:ccent cond t,ons derg the shpmert Tre suda:= cra:b e'rted kd in ths cdal ta,er of a rea:10e l of sf+rt fuel from rucitar gr:*er reactors The eva%aton is sessel has t+en dert 4d as a cr,t.ca' tra:tu re sa'ety auess performed u%fsg data from rea* a:c ceFt Nstor.cs and uvng rep- mf nt Cond t on re'ahe to the pr ssp. led t%> mal shoch accn e resentat ve truct and ra ! Cap mM('s that i t e*y mov t 10 C F R dent sc era o T Ns pr:yect
• as in t ated ta detem ne the severs 71 re-gvtatons The resporses of the re presortaSe cases are ty of wh cra:h s e Whmeetan wg arra tavd ma'er al ard calcula!(d for s'r uctur al 4'W the rrral L 4 5s yacr44-5 t y se v er t' 10 dt.r tfy the rrai( r a' p,3 cq aM g*re.s g ( nrg ',ms iri ing.

bgh

• a y and ra '* a, aCCdent CoM tQns Ihe Cash re scGNs k3C al regon Of the c ra:. trat a e s e cant ia the a ass s a e compa'M m th those respomes cat:u a'ed f y the t o C F R BrN t ar usts prowde t% e em nta' smMn c f F+ sst-71 by; cwt.c a' a dent condtons by c c#mc anng the ro fe:t RPV s#a e craJ Ths repor1 Mc rt+s the in t al inv e sti spCeses 1 ts TerrNned that mcst hf e ty aN ra'* a, a:D gat.On ubng un toa l a!rt mMW a.j pew s the ana ,s s te;h cert cord tons f a t
• then the 10 U R 71 b,Ecthet> Cal aCC & f n@t s a n 1 fveWts the i WQi M;4ted t', the e nf+rNetal I

Main Citations and Abstracts 53 resu!ts Charactentaten of the irraf ated matenal edl be pre- techniques to acheve the greatest possble reah24 ton of Ut sented in a subsequent report potent al of the rmcrocomputer and when the needs of the user enceed th,$ potent;al LAR AS PC can catt upon the power of the NUREG/CR 4842: A STUDY OF NATURAL GLASS ANALOGUES "# # 8 ** AS APPUED TO ALTFRATION OF NUCLE AR W ASTE GLASS BYERS.C D. JERCINovtC M J ; EWM R C Argonne Natonat NUREG/CR 4845: AN ANALYSIS OF THE SEM1 SCALE MO42C Laboratory F e bruary 1997. 165pp 870t200253 A N L-66-4 6. S NH 3 TEST USiNG THE TR AC-PF1 COMPUTER PROGRAM. 40984 161 DRISKELLW E , AULLBERG.C M EG&G Idaho, Inc (tuts of A two pa1 study was undertanen on the aleraton of natural EG&G. Inc ) Varch 1987. 45pp 8706030160 EGG 2496 tasa!t and nuclear waste g' asses in the first part, the Urv,ers.tv 41144 203 of New Meiico charactented a nide vanery of natural basa!t.c A caiculation was performed usang the TRAC PF1/ MOO 1 g' asses w,th respect to reacton products, reacton kinet,cs, and computer program to 5.mulate a small break, loss-of coolant en-geo4cge history The impc< tant outcome of this Study was a de- penmut where the hgh pressure enrecton was not used to m,ti-scrcton of the process ahereby natural g' ass a:ters to patagon- gate the fuel rod temperatse escurscri Th s esperenent, dest ste and asthgervc matena:s. includ:ng clays and rechtes in the nated the S-NH 3 Test, simu!ated a 0 5% cok14eg break in a second part, ANL performed laboratory tests to simu' ate the PWR and was ore of a seres of tests conducted in the Sens-natural a'teraton process

• th a synthetic basa! tic g' ass For caie Mod.2C test fachty The pnmary purpose for doing the cal-laboratory tests iri ah.ch the g' ass sampWs were esposed to cu'aton was to evaluate the capabiht, of the TRAC-PF1 code to nater vapor at h.gh temperature ( > 90 degrees CL a close sim- ca:cu' ate the thermathydravhc response observed in the empen-ilanty was fourv3 in the a1eraton of naturat and synthet< g' ass- ment The eva vatson empicys the companson of selected code-es The same a'teraton process nas found fu a nuclear waste ca'culated system responses eth the test data ConcW5cos g455 (SRL 165) !! *as concluded that botn the nat#al s1e6 and recommendatons on improv.ng the quahty of the calcuta-abon of basate g' ass and mater-vapor labc<atory tests can be ton are included used as an anaogue to assess the performance of nuclear

     *sste g' ass under pctent a! repos tory coM tons                                                                                                                                                                                                          NUREG/CR-4846: HtGH-LEVEL W ASTE PRECLOSURE SYS-TEMS SAFETY ANALYSJS Phase 2, Final Report LIGON.D M .

NUREGM4443 Y01: UN!vER$1TY OF MARYLAND AT COL- ST AVATELATOS.M , BARSELL,A W.; et a' Sandia Natonal LEGE PARK (UVCP) 2A 4 LOOP TEST F ACILITY Annual Report Laboratories June 1987. 163pp 8708N176 SANO87 7029 Fce 1995 DN ARZO M : HSU.Y Y-. LPON K ; et al Mayand- 42333 277. U n<v of, Cohege Pam. VD Ma'ch 1987 300vp 87040i0054 The ma;or ef' ort of th.s phase nas the demonstraton of the 40465 020 methodology deveioped in Phase ! A sample prob 6cm consist. The dorts f or the year 1995 cf the invest gators of the Ur"- ing of se scenares was quant.f.ed The purpose cf th s saanple vers ty of MaYand on the UVOP 2 4 Lcop facaty are present- prwem is to check the appbcaton of the assemtded methods, ed These eHorts include add t.ona! mork on the f a:4 ty, theyet. p3,ticWarly the importance ranking scher e All ed the features scal mvest, gator s and empenmertai e,estigatons The 2 4 cf the ccmplete ana'ytica! techr9 ave are appaed includ,ng un-Locp f asty is a non pressure sca ed representaton of a 10*- certa.nty and sensitety ana%s s, common cause failure evalva-ered tocp B&W reactor and once through steam generator The f.cn aN hman error contributon Other topics a33ressed in-report is prepa'ed in three chapters aN Seven appeMees A ciuo, y,ne Aetated Data Development, Human Rehabity Anary-bnei descrtt.on cf the f acity :ncbing the fmai des gn deiads s:S and Common Cause Fa:Ise Anais3s are presented in chapter one Chapter two iroudes the *eoretr cal t, asis for the espenmental rn v estgations Chaper three con. NUREG/CR 4847: CASE HISTORIES OF WEST VALLEY SPENT ta,ns the deia. s of esp %ments test rew<ts. and teal conclu. FUEL SWPVENTS Final Repor1

• Aerospace Corp January 5,ons The append.ces conta n ad%onal deta's about the 1987 239pp 8702270048 WPR 640811) 1. 39760 064 toracs d scossed in the chapters In 1983. NRC/FC tritiated a study on instrtutonal issues re'at-ed to spent fuel sNpments or9nat;ng at the former spent fuel NUREG/CR-4844 DRFT: INTEGRATED REUAB:uTY AND RiSA reproc g f acah'y in W est Va n ey, New York FC sta+f viened ANaLYS'S SYSTEM UAE AS) USER S GU DE SERSiON 10 the sh-p nent campa gns as a one time oprortun.ty to document (DR AFT) RUSSELLA D . SN:DE R O V . SATTiSON M B , et a' tne irst tutonal issues that may ar se
• th a wt.stant.at increase EG&G idaho. Inc (wt s of EG&G. Ire ) Jsn s 1987 149pp in spent fuel sh pp ng a:tyty NRC sut:sequentty contracted 87073X200 EGG 2495 41M 016 ,,th the Aerospace Corpuraton for the West Vaney Study Ths The interated Rehaba t, and R sh Ana',s.s S, stem URR AS) regort conta ns a detaJed descripton of the events *Nch took is an eteysted PR A so'taare taos nn.s gves the user the atA pre pror to and du ing r tne scent twel shipments The report rty to creaie aN anaire f ait trees using an IBV PC Tn s pro- a,so corta ns a d scusson of the shipment issues that arose gearn provdes functons that range from g*apNcat f a/t tree ,y p,,,,ngg g,,,,ai tind ngs Vest of the inst.tutona! essues constructon to cut set QEMaton and Qaant hCaton A!so pro- dTCussed in the report do not fall under NRC s transpor13tcn vded in the 5,$ tem is an inte7a'ed VI. screen ed tor for use asthorfy The case Nstor es proide a reference to agenoes when eterianng a th rem;te compuer systems IRR AS PC is ,y e;n,, inst tutons thar uar be evolved in future spent fset be^g deveioped at the 1NEL as the USNRC S sta'e of the ad ggpp,nge p p,gng m,c roc or*ruter t.a se d pret abasti r9 a s ses vnent FRa) mo$el deietopment and anaAs t:d to 43d'ess 6 ey nuoe ar NUREG/CR 4846. STEAV GENERATOR GROUP piant sa'e ty ssues The AEL roe e the iRR AS Vnam is t*at PROJECT Annu a' Report 1M5 AURTZ R J . LENS V .

of schare devebper aM ete a:er d to the user comm un h m. CLARh R A BaMe Memcoa' trst tute FacAc Northwest Lab-cieng t*a neg &N technology t' a ,5 rer To w;5cr1 t5 s r:.e orator es Aprd 1987 122pp 8704270138 PNL-5 7 71 l tNs user's maNal *as devocped as a gWehne for use of the 4 mbt 051 1RR AS sc+taa e Presented in the man u al is an espianaton of Th,s report is a summa *y of the Steam Generator Group the cSta"4?c9 prcredJes the haMa a'e and sO*'e a'e rQ,,Fe- Project p ryess for

• 185 Stat glical anahses of data from non-ments the forms aN menus uwd ty t*e prcyam aN detaaed destextwe enammaton (NDE) round rob ns performed on the e spiana' ors of the pr>f ams s c apabitnE s AN tunCr0ns The Sur ry gmeator are presented Cotea are hsted for selectcn of level o' det&J prewe ted in th s ma%31 is cieNed to gMe tN tJ.e spe: meng ta be removed 40m the generator for tabdatch tegwg or iM01.#0! us*-r 3RR AS PC tas aH me Caf &Bd te CA the NDE roun d r?t*6 rew1s A samphnQ p'an is descf(tej AN funClong reyed to cf f a9 mel ', reduc e, aN ana',le aon; *@ the en t a steps tMEm to srnfiemert (Ns ptan Sgec.a' f adt tr0e r%1e 4 use16n the ana ,vs of c ar7 e n syvets and taohng f atNated for spepm(n removis rs d.sh.55ed Remo,al faroc esst s WHASF{ wg e j,4N ed 7 @ .c and a u @ca: ct TNee 9 tute sectons Cd 12 e shett is pretteted FWur ary

                                             .        -               .                       . _ ,                         .. ..     ~

54 -lhin Cititi::n3 End Abstracts 1 results from destructive analysis of one section are reported. ceeds the vertical by a rabo of about 3:1 to 5:1, reaching about Vahdabon actrvities were irutiated by metallurgical evaluation of 20 m. Individual events apparently had maxirnum displacements two tubes pulled from the hot leg tube sheet. Results from de-structive measurement of maximum defect depth from these of several meters. The Meers Fault may be part of a larger two tubes indicated that in situ bobbin cosi eddy current meas- active zone. Based on surface expressions, the Washita Valley, urements consistently undersized the defects. Oklahoma and Potter County, Texas Faults may also have rup-tures dunng the late Quaternary, although not as recently as the

   - NUREG/CR-4850: STEAM GENERATOR GROUP PROJECT. Task                             Meets Fault. Low sun angle photography in Southwestern Okla-10 Secondary Side Examination. Final Peport. SCHWENK,E.B.                  homa revealed no evidence of fault activly, other than that of Battelle Memonal Inst tute, Pacific Northwest Laboratones. June             the Meers Fautt, although activity may be concealed by poor 1987.107pp. 8708240213. PNL-6045. 42316:155.

preservation or ductile surface deformabon. This suggests that The Steam Generator Group Project (SGGP) is ussng the re- &dditonal areas of activity may be sparse and rupture infre-tired- from-service Surry 2A press # red water rea;*or steam quently. generator as a test bed to investigate the reliability and effec-trveness of in service nondestructrve eddy current inspection NUREG/CR 4853: APPROXIMATE METHODS FOR FRACTURE equipment and procedures, in addition, servce degraded tubes ANALYSES OF THROUGH WALL CRACKED PIPES. from the generator will be used to vahdate rrodels of remaining BRUST F.W. Battelle Memonal Institute, Columbus Laboratories. 4 tube integnty developed in Phase I of the program, This infor. February 1987.122pp. 8703250491 BMi-2145. 40234:124. mabon will provide the techrucal basis for revision of Regulatory Guides 1.83 and 1.121 goverrung in.serwce inspecton and tube Current leak-before-break analyses involve assessing the plugging cntena, respectively. This report is the second of two load- canying capacity of through wall cracked pipe. Five pre-reports CCr/edng examinabon and characterization of the sec- diction techtvgues were evaluated in this report. The technical ondary side of the Surry unit. It includes a photographsc survey basis for two analysis methods developed in the Degraded of typecal Surry generator matenal and structural condibons, Pip ng Program, LSB BCL1 and LBB.BCL2, are presented in this rnetallurgical failure ana%is of a ruptured U-bend tube, a de- report Other methods evaluated are the G'l/EPRI, NUREG/ senpbon on how secondary side access penetrabons were CR 3464 and L838.NRC analyses. These methods are all based ma e and an expenmental st'ess ana!ysis of a bent Row 1 on the J-integral /teanng modulus theory, As such, they all fall

             '                                                                     under the category of J-estmabon schemes. These J- estma-bon schemes are all relatively simple to be compared to finite NUREG/CR 4851: SEISMICITY 1886-89 IN THE SOUTHEAST-                           element analysis. Predicting the fracture performance can be ERN UNITED STATES.The Aftershock Sequence Of The acheved very quickly, and is done through the use of an IBM Charleston, South Carolina Earthquake. ARMBRUSTERJG ;

PC computer code called NRCPIPE The assessments of the

     - SEEBER,L Lamont Doherty Geological Observatory, May 1987.

202pp. 8709090380. 42569:334. five methods envolved companng the expenmental data to the A search of contemporary newspapers in the Carolinas, Geor- predicted load versus load- point disptacement curves. Th s was gia and Eastern Tennessee dunng the 1886-1889 (inclusive) done for both carbon steel and stacless steel pipes with cracks aftershock sequence of the Charleston earthquake of 1886 has in the base metal, as well as stainless steel pipes with Cracks in provided more than 3000 intensity reports for 522 earthquakes TIG of submerged arc welds. In addibon, both deformabon and L as compared to 144 proviously known earthquakes for the modified J-R curves were used in the assessments. Finally, a same penod. C' these 144 events,138 were felt m Charteston/ sensitivity study was made to show that the reference stress 5 Summerville md had beren assigned epicenters in that area. used in the Ramberg-Osgood retabon could be based on either i The new data provde 112 well-constrained macroseismic epi- Y "9g 4 [ centers. The 1886 1889 seismoty is charactenzed by a linear adjusted. , retabon betwoon log frequency and magnitude with a slope b1, a temporal decay of earthquake frequency proporbonal to bme NUREG/CR-4855: DEVELOPMENT AND APPLICATION OF A ( 1), and a low level of seisnscity pnor to tha main shock. These PWER MODEL FOR LARGE SCALE FLAME ACCELERA. are frequently observed charactenstes of aftershock se- gg g quences. By 1889, the level of seismcry had decreased more July 1987. 80pp. 8801070052. SAND 87 8203. 43943:297. than 2 orders of magnitude, reaching approximately the current A new computational model for large-scale premixed flames level in the same area. The 1886 1889 epicenters delineate a is developed and appl.cd to the simulation of flame accelerabon , large aftershock zone that extends northwest about 250 km expenments. The pomary objective as to circumvent the necessi-from the coast into the Pedmont and at least 100 km along the ty for resolving turbulent flame fronts, this is imperabvo because Fa0 Line. The afters %ck zone occupies the same area as a of the relatrvely coarse computabonal gnds whch must be used zone of recent seismoty with unique charactenstics. The por- in eng:neenng calculabons. The essence of the modelis to arti-tion of tLs zone in the Piedmont is the only area of Southeast- foalty trvcken the flame by increasing the appropnate d.ffusivi-ern United States whers reserve t induced seismicity is unam- tes and decreasing the combustion rate, but to do th S in such l biguously recognrzed. Seismicity elsewhere in the Southeast, a way that the burn velocity vaneJ with pressure, temperature, such as in the Viroinia seismic zone, is deeper and apparently and turbulence intens ty accod , w prespeofed phenomeno-unrelated to reservoir loadmg. logical charactenstics. The model is parbcularly aimed at imple-NUREG/CR-4852: THE MEERS FAULT; TECTONIC ACTIVITY IN mentabon in computer codes wNch samulate compressable SOUTHWESTERN OKLAHOMA. RAMFull,A R.; flows. To this end, it rs appled to the two-dimensional senula-SLEMMONS D.B.: BROCOUM.S J Nevada, Unrv. of, Heno, NV. bon of hydrogen-air flame acceteration expenments in wNch the 1 March 1987. 59pp. 8704090047. 40463:318. flame speeds and gas flow velocsbes attain or exceed the The Meers Fault in Southwestern Oklahoma is capable of speed of sound in the gas. It is shown that many of the features producing large, damtging earthquakes. By companson to Ns. of the flame trafecton-s and pressure Nstores in the expen-toncal events, a mesmum of M = 6 3/4 to 71/4 could be en ments are simnisted quite well by the model Using the compari-pected. The most recent surface rupturng event occurred in the son of expenmental and computabonal results as a guide, some late Holocene, and it appears that one or more pre. Holocene insyht is developed into the processes wbch occur in such ex. events preceded rt Surface rupture length is at least 37 km- penments. Displacements compnsing the present4ay scarp have leftlater-al and Ngh-angle reverse components. Vertcal separabon of NUREG/CR 4856: FEASIBluTY STUDY ON A CATA BASED the ground surface reaches 5 m, whde lateral separabon ex-1

Main Citations and Abstracts 55 SYSTEV FOR DECISIONS REGARDING OCCUPATIONAL RA- an approximate 3-mm (0.1 en ) d< stance along the 20-mm major DIATION PROTECTION MEASURES. WATSON E.C.; length. No flaws were detected by the penetrant examinatcn of FISHER,0 R. Battelle Memonal Institute, Pacific Northwest Lab- the cladding surf ace oratones. February 1987. 71pp. 8703250618. PNL 6137. 40235-087. NUREG/CR 4861: DEVELOPMENT OF SITE SPECIFIC RE-In a study commissoned by the U S. Nuclear Regulatory SPONSE SPECTRA. BERNREUTER,0.J.; CHEN.J C.; SAVY,J B. Commisson, Pacific Northwest Laboratory conducted a study to Lawrence Uvermore National Laboratory. March 1987.140pp. determine the feassbihty of developing data-based protectrve 8704010140 UCID-20980. 40321.189. measure decison levels for assunng uniformity of hcenkng re- For a number of years the USNRC hae employed stte specific quirements for radiaton protection of workers. Eleven facAttes spectra (SSSP) in thetr evaluaton of the adequacy of the Sa'e licensed to work w tri unencapsulated radcactrve matenal were Shutdown Earthquake (SSE) As the data set has constderably visted to collect data for this purpose. Sufficient data were ob-tained from six fac* ties to estimate renase fractons (i e, frac- increased for Eastern North Amenca (ENA) and as more rele-tion of matenal in process released to the workplace environ- vant data has become available from earthquakes occum09 in ment) for tntium tube f4hng opemons (about 10(-5)), tntium other parts of the world (e g , Ita'y), together with the fact that compound preparaton (about 10( /)).1125 radopharmaceutical recent data indicated the irrportance of the vertical component, preparations (about 10( 7)), Am-241 source production (about <t became clear that an update of the SSSP's for ENA was de-10(-11)), and forge filing and incineraton of natural uranium sirable. This study used actual earthquake ground moton data (about 10( 7)) The fracton of matenal in process that may be wrth magnitudes within a certain range and recorded at dis-taken into the bodies of workers involved in these processes tances and at sites simaar to those that would be chr.sen for was estimated to be about 4x10( 8), 4x10( 10), 2x10(-9), 6x10(- the definition o' an SSE. An extenson analysts of the ongen and 14), and (15)x10(-7), respectuely. Frve levels of radiaton pro- see of the uncertainty is an important part of this study The re-tection programs were developed The most feasable approach sults of this analyss of the uncertainties is used to develop cri-to assunng uniform.ty of licensing requirements for these pro. tena for selecting the earthquake records to be used in the den-grams is a technical one based on mathematical relat,onships vaton of the SSSP's. We concluded that the SSSPs were not us ng decision levels developed by a panel of experts. This ap- very sensitNe to the distributon of the source to Ste d. stance of proach, however, requires a consensus among regulators and the earthquake records used in the analys s. That is, the varia-licensees on fundamental values used to determine the need bety (uncertainty) introduced by the range of d+ stances was rel-for specific protectrve measures atNely small compared to the variabaty introduced by other fac-NUREG/CR 4859: SEISMIC FRAGILITY TEST OF A 6-INCH DI. tors We also concluded that the SSSP are somewhat sensitne AMETER PIPE SYSTEM. CHEN,W P.; ONESTO.A.T.; DEvlTA.V. to the distnbuten of the magnitudes of these earthquakes, par-Energy Technology Eng'neenng Center. Februa'y 1987,174pp ticularly at rock 9tes and. by inference. at shanon soil s.tes We 8703260100. 40237.229 found that one important enteren in selecting records to gener-This report contains the test rasults and assessments of seis. ate SSSP is the depth of soil at the sate. mac frag:! sty testa performed on a 6-inch d.ameter prping system. The test was funded by the U S. Nuclear Regulatory Commis- NUREG/CR 4862 V01: COGNITIVE ENVIRCNMENT saon (NRC) and conducted by ETEC. The objectrve of the test S!MULATION AN ARTIFICIAL INTELUGENCE SYSTEM FOR was to invest gate the abaty of a represeGatNe nuclear pipin9 HUMAN PERFORMANCE ASSESSMENT Volume 1 Summary system to withstand hegh level dynamic seismic and other load- And Overview WOODS.D.D.; ROTH,E M ; POPLE.H. Westrng-ings. Levels of loadings ach.eved dunng seismic '.esting were 20 house Electnc Corp. November 1987. 56pp 8712090100. to 30 times larger than normal elastic design evaluabons to 4363 0312 ASME level D tamits would perm't. Based on failure data ob-This report documents the resu!ts of Phase 11 of a thre+ ta ned dunng seismc and other dyname test:ng, it was conclud-ed that nuclear piping systems are inherently able to withstand p em ma'n b w% W me wW 09 g much largbr dynamic Seismic loadings than permitted by current des 4gn practx.:e entena or pred.cted by the probabastic nsk as- (NPP) personnel in Phase 11 a dynamic 9mulation capabAty for sessment (PRA) methods and several proposed nonhnear meth- modehng how people form intentens to act in NPP emergency ods of failure analysis. S'tuatens was developed based on techniques from artitcal in-teligence This modehng tool. Cognitrve Environment Simutaton NUREG/CR 4860: FLAW DENSITY EXAMINATIONS OF A CLAD or CES, Smulates the Cognit ye processes that determene sztua-BOILING WATER REACTOR PRESSURE VESSEL SEGMENT. ton assessment and intention formaton. It can be used to in. COOK K.Va MCCLUNG,R W. Oak Ridge Nat,onal Laboratory. vest: gate ana%cafly what situat ons and factors lead to inten. Apnl 1987. 33pp. 8707310061. ORNL/TM 10364. 41996.179. ton fattures, what actons follow from intention fa:!ures (e g. As part of the Oak Ridge Natonal Laboratory's Heaq-Sec- errors of omisson, error of commission, common mode errors, tion Stee; Technology Program, stud es have been conducted to the abaty to recover from errors or add,teonat machine fanures. determine flaw densty in a secten of reactor pressure vessel and the effects cf changes in the NPP person-machine system cut from the Hope Creek Unit 2 vesset This boAng water reac-tot vessel was never in service One objectue was to evaluate The Cognattve Rehabaty As;essment Technique (or CRE ATE) the approximate 0.7 by 3-m (2 by 10-ft) segment of the vessel was also develo;>ed m Phase ll to specdy how CES can be l provided usng ultrasonic flaw detecton methods performed used to enhance the measurement of the human ccntnbution to

    *,th both ASME Code techniques and supptemental uitrasonc           MSk 'n probabAst>c risk assessment (PR A) stdes The resu!ts i

methods A second objectrve was to evaluate the inner surface am ieported in three self- conta,ned vo&es that descr be the l starnless steel cladding for cracks with a high senstyty pene. rewarch from ddferent perspectues voNme 1 proodes an I trant examinaton. Both obtectives were successfully completed overvew of both CES and CREATE Vevne 2 gaes a detaled l Five Code-recordable indicatons were detected ultrasonecally; desenpton of the structure and content of the CES modekng however, all were found to be anomabes associated w,th the environment and is intended for those who want to knew how cladding One flaw was detected by supplemental ultrasonic CES modeis successful and erroneous intert en formaton tests, and it was anaWed destructvely. This flaw was a pipebk > Volume 3 desertes the CRE ATE methodology for using CES to endication. about 20 mm (0 8 in ) Icog entending a'ong the provide enhanced human rehabaty est; mates Vo'ume 3 is in-length of the longitudinal weld in which it was located and was tended for those who are interested in how the modebry capa-about 20 mm below the cladding surface The f!aw had a bat >es of CES can be utMed in human rehab.uy assessment through-wall dimenson (or length) of about 6 mm (0 24 in ) for and PRA

56 Main Citations and Abstracts NUREG/Ch 4862 V02: COGNITIVE - ENVIRONMENT An evaluaten of zircaloy oxidation and hydrogen generation SIMULATION:AN ARTIFICIAL INTELLIGENCE SYSTEM FOR data is presented for the first two severe fuel damage (SFD) HUMAN PERFORMANCE ASSESSMENT. Volume 2.Modehng tests. SFD-ST and SFD 1 1, conducted in the PBF at the INEL Human Intenten Formulaten. WOODS,D.Da ROTH E M.: The repon presents an assessment of data in terms of the influ-POPLE.H. Wesbnghouse Electnc Corp. November 1987.138pp. ence of zircaloy melting on oxdation behavor and fuel bunde 8712080216. 43588.008. reconfiguraton effects which may alter steam flow and hydro-See NUREG/CR-4862,V01 abstract. gen generaton charactentJcs. A companson of the H(2) gen. NUREG/CR-4862 V03: COGNITIVE ENVIRONMENT eraten and cladding thermocouple data indicates that a signifi-SIMULATION:AN ARTIFICIAL INTELLIGENCE SYSTEM FOR cant amount of hydrogen was produced after the initiation of zir-HUMAN PERFORMANCE ASSESSMENT. Volume 3: Cognitive caloy mett-induced fuel dissoluton (greater than or equal to Rehability Anaysis Technique. WOODS,0.D.; ROTH E M. Wes- 2150 K). Posttest metallographic observations corroborate the tinghouse Electnc Corp. November 1987. 79pp. 8712080200. trend of the omline data Analyses also indicate that essentially 43587:195. complete flow area blockage (> 98%) would be required to di-See NUREG/CR-4862 V01 abstract. minish steam flow through the degraded test bundle, reducing hydrogen producton. Neither on-Isne data nor posttest examina. NUREG/CR 4863: SURFACE SPECTROSCOPY OF PRESSURE ton of the SFD.ST and SFD 11 fuel bundles indicates that VESSEL STEEL FATIGUE FRACTURE SURFACE FILMS such extreme flow area blockages occurred. For the steam-rich FORMED IN PWR ENVIRONMENTS. HANNINEN,H E.; SFD-ST expenrnent, UO(2) fuel oxdaten was also observed, VULLf,M; CULLEN W.H. Matenals Engineenng Associates, Inc. possibly accounting for apprnxamately 20% of the total hydro-suly 1987.100pp. 8708040253. MEA 2194. 42036.227. gen production. Fuel ondaton has also been noted from re-The composton and structure of corrosco products formed tneved TMI-2 core debns samples. Thus, oxdat,on of UO(2) to on corrosion fatque fracture surfaces of pressure vessel steels a hypostoichometM conditen may add to the total hydrogen tested in PWR water conditons have been analyzed by using X- burden for severe a,;cidents. Ray Photoelectron Spectroscopy (XPS) and ALger Electron Spectroscopy (AES) techtvgues. This was the twst time these NUREG/CR-4868: METALLURG1 CAL EVALUATION OF AN 18-electro,n spectroscopic techruques have been apphed to corro-INCH FEEDWATER LINE FAILURE AT THE SURRY UNIT 2 son fabgue tracture surface studies. The oxde phase on the POWER STATION. CZAJKOWSKI.C.J. Brookhaven Nabonal corrosion fatque tracture surfaces was Fe(3)O(4) (magnette) in Laboratory. March 1987. 43pp. 8704090019. BNL-NUREG-all the specimens. Small amounts of sulfur (typically about 3 52057. 40464.016. atomic percent) were present in the oxide film mainly as FeS(2). A metallurgical failure analysis was performed on pieces from in specimens showing the hghest crack growth rates, the a catastrophecally failed 18-inch diameter feedwater hne from amount of sulfur was about doubled near the crack tip com-pared to the value obtained further beNnd the crack tip in the the Surry Unit 2 Nuclear Power Staten. The fa, led pipe had mddle of the fracture surface. It was possble to locate the been globally thinned and had a scalleped appearance on the insde surface. All fractur;s sudaces examined showed a ductile crack t p conditon on the hgh-te.mperature Pourtaix diagram in the area where both magnetite and FeS(2) are stablo phases. failure mode. The matenals of constructon met the appropnate The anticipated crack tip conditions are that the corrosion po- s ecification requirements (both mechinica' and cherrucal). The tentel is about 500 mV(SHE) or less and the pH value is neu- report has as its final concluson that the pipo failed due to ex-tral or sightly acid. XPS and AES analyses cf the corroson fa- cessive thinning by an erosen-corrosen mechanism. tgue fracture surfaces were found to reveal the possbie water chemistry impunt** dunng the corrosson fatque tests, hke Cl, NUREG/CR-4870: AN EVALUATION OF THE EFFt: CTS OF Na, Ca, etc. DESIGN DETAILS ON THE CAPACITY OF LWR STEEL CON-TAINMENT BUILDINGS. GREIMANN La FANOUS F.; NUREG/CR 4865: THE SOLUBILITY OF ELECTRODEPOSITED ROGERS.J4 et al. Sandia Natonal Laboratones. May 1987. TC(IV) OXIDES. MEYER,R E.; ARNOLD.W.D; CASE.F.I. Oak 96pp. 8709090402. SAND 87 7066. 42569.238. Rdge Natonal Laboratory. July 1987. 31pp. 8710010154. As part of their work with severe accident loadings, the Con-ORNL-6374. 42882.060. tainment integrty Davison at Sandia Natonal Laboratones has Solubihties of electrodepoSted Tc(tV) oxides have been de- been conducting a program to evaluate the performance of con-termined in solutions of NaC1, HCI, and synthetc groundwater in tainment buildings mth intemal pressure. Sandia has suggested the pH range O to 10. Oxdes were electrodeposited onto plats- using a strain entenon for predicting rupture of steel contain-num electrodes, and the oxde-covered platinum was then ments; the strain limet used to correlate mth failure rnust be placed into a small stsred cell. Solubshbes were determined by consistent we the level of detail included in the analytical counting the beta radiaton of (99)Tc in the soluton in the modet if detailed 3D models are developed, the strain hmit may stirred cell. The solubMes are approximately constant in the pH be as large as the matenal's ultimate strain. This entenon is ap. range 3 to 10, the values in this region for depos ts from acid pi,ed to strains calculated eth a shell theory whech includes ma-soluton average (1.32 plus or manus 0 68) x 10(-8) mol/L. For tenal and geometnc nonhneantes and is appled to the actual ondes deposted in basic solutons the average is (2 56 plus or nta<nment. In this work, dramngs from nine steel contain-minus 0.54) x 10( 9) mol/L The electrodeposited oxdes are hy* ments were stud >ed and several significant strain concentraton drated and expenments show that they have the composton regens were denthed and classified as: eccentncibes in sbffen-TcO(2).nHt2)O where n has an average value of 1.63 plus or { er patterns around penetrations, eccentncibes in the shell minus 0.28. The oxides appear to vary in structure and/or com- J mddle surface, flat plate covers used on spare penetrations, ' posibon depending on ther method of preparaton and history. containment base connecton details, and ellipsoidal and tons. Solubaty products between 10(-32) and 10( 33) can accourt for phencal heads and covers The 1.8-scale model was analyzed most of the data. These data can be used to estmate solubsh-tes for cases where solubikty hmits transport of technetrum en using the shell frute element in ANSYS, and the results agreed reducing hgh-level waste reposttory environments well eth Sandia's analytical results and the expenmental re-suits Examples of each classafication were analyzed by finite NUREG/CR-4866: AN ASSESSMENT OF HYDROGEN GENERA. element and/or simpir6ed equations. In the case of middle sur- I TION FOR THE PBF SEVERE FUEL DAMAGE SCOPING AND face eccentncities, the strains are self hmeting Although flat 11 TESTS. CRONENBERG.A Wa MILLER.R Wa OSETEK.D J plates have pnmary bending strains, they are typecaffy designed EGSG idaho, Inc. (subs. of EG&G, Inc ). Apnl 1987. 95pp so as not to control. Botts in the base connecton have pnmary 8706120168. EGG 2499 41281.272. straens and may controt

Miln Citati:ns cnd Abstracts 57 NUREG/CR 4871: RESULTS FROM THE DCH 1 EXPERtMENT, indicate sanability and a lack of conservaton of mass in solute TARBELL W.W.; ROSS.J.W.; ARELLANO,F E.; et al. Sand +a Na- transport. The tuff matena!s used in that study were analyzed tional Laboratones. June 1987. 67pp. 8707300035. SAND 86- for the presence of tracers and of freshly precipitated matenal 2483.41983 063. to help explain the vanabihty and lack of conservaton of mass. The DCH 1 (Direct Containment Heating) test was the first ex- Selected tuff samples were charactenzed by neutron activaton penment performed in the Surtsey Direct Heating Test Facility. analysis for tracer identificaton, by x-ray diffracton for mineral The test invoNed 20 kg rA molten core debos simulant elected identrficatan, by petrographic analysis for identificaton of 4esh-into a 1:10 scale model of the Zeon reactor cavity. The melt was ty precipitated matenal, and by x-ray fluorescence analysis for produced by a meta!!othermic reacton of iron oxide and alumi- identification of maior and trace elements. The results of these num powers to yield molten iron and alumina. The cavity model anal ses indicate no obvous presence of freshly precipitatM was placed so that the emerg!ng debns propagated directly up- matenal that would retard tracer movement. The presence of wards along the vertical centerline of the chamber. Results from the nonsoroing tracers (bromide and edide) suggests the reten-the expenrnent showed that the molten matenal was ejected tion of these tracers in immobile water. The presence of sorbing from the cavity as a cloud of particles and aerosol. The dis- and nonsorbing tracers on the tuff at some locations (even at persed debns caused 3 rapid pressunzation of the 103 m(3) the 415-cm depth) and not at others suggests variaoility in chamber atmosphere. Peak pressure from the six transducers tra r, sport. ranged from 0.09 to 0.13 MPa (13 4 to 19 4 psig) above the ini-taal value in the chamber. Posttest debns conection yelded 116 NUREG/CR 4876: SILVER-INDIUM-CADMIUM CONTROL ROD kg of matenal outside the Cavity, of which approximately 1.6 kg BEHAVIOR AND AEROSOL FORMATION IN SEVERE REAC-was attnbuted to the uptake of oxygen by the iron particles. Me. TOR ACCIDENTS. PETTI,D.A. EG?.G Idaho, Inc. (subs. of chanical sieving of the tecnvered debns showed a lognormal EG&G, Inc ). Apol 1987. 185pp. 6703130364. EGG 2501. size d,stnbuten with a mass mean size of 0 55 mm Aerosol 42154 286 measurements indica %d a substantial portion (2 to 16'.) of the Ag-In Cd control rod behavior and aerosol formaton in sesere elected mass was in the size range less than 10 micrometer reactor accidents are examined. Control rod behaver in in p6le aerodynamic equivaient d.ameter and out-of-pde expenments is reviewed. A mechanistic model named VAPOR is developed that calculates downword reloca-NUREG/CR 4872: EXPERIMENTAL AND ANALYTICAL ASSESS- ton and simultaneous vaponzaten behaver of Ag-in-Cd alloy MENT OF CIRCUMFERENTIALLY SURFACE-CRACKED PIPES expected after control rod fa;iure. Although cadmsum is found to UNDER BENDING SCOTT,F M.; AHMAD,J. Battelle Memonal Apnl 167pp. be the most volatile constituent of the alloy, all calculatons Institute, Columbus Laboratones 1987. using VAPOR predict that rapid relocate of the alloy down to 8705190623 BMI-2149 40978152_ c@ portons of the core resulis in a smail release for all This study was performed to assess the vahdity of varcus techniques to predict maximum loads for circumferentia4y sur- three control rod alloy vapors. Potent'al aerosol formation face- cracked pipes under bending Expenmental data were de. mechanisms in severe reactor accidents are reviewed Models veloped for both carbon steel and stainless steel ptpes Predic- for homogeneous, ion-induced, and heterogeneous nucleaton tions of maximum loads were made using the not secton-col- are investigated Exarrunaton of these models indicates that lapse methoo, the IWB 3640 analysis procedures, and a newty aerosol formation occurs in three stages: (1) son induced nucte-developed finitedength surface- cracked pipe J-estimaton ation causes aerosol generaten; (2) ion-induced and heteroge-method. The net secton collapse method gave good maximum. neous nucleaton operate samultaneous'y; and (3) hetcogene-load predictons for certa:n types of pipe However, for pipes ous nucleaton is the dominant mechanism of gas-to-particle w:th large radius to thickness lR(m)/t) ratos and/or low tough, conversion until equ>hbnum is established Prelmnary results of the control rod and aerosol behavor observed ,n PBF Test SFD ness, this anafysis method tended to overpredict the expenmen. tal maximum load A plastic zone screening cntNn was devel. 1-4 are presented Control rod matenal release in the test is oped to show when this method was vahd ar a when elastic. compared to VAPOR predictons. Conclusens from this work plastic fracture mechanics should be used The hmit4oad proce. are presented, and their impact on source term estimaton is as-dures embodied in IWB-3640 provide the desired underpredic. sessed. tion of the fadure stress The average failure stress for the nine NUREG/CR 4877: ASSESSME4T OF DESIGN BASIS FOR stainless steel base metal expenments was 61 percent higher LOAD-CARRYlNG CAPACITY OF WELD-OVERLAY REPAIRS than predicted by Table IWB 36411 and 23 percent higher than SCOTT,P M. Battelle Memonal Inst:tute, Columbus Laboratones. predicted by the Source Equatons For the three stainless stee. Apnl 1987. 81pp. 8704280032. BMI 2150. 40709171. flux weld expenments the pred<ted fa:lur e stresses were adjust' This study was conducted to assess the current load-Carrying ed by a stress mult: plier to accour" for the lower toughness of capacity design bas,s for weld-overlay repairs (WORs). Although the flux welds The average failure stress for the flus weld ex- not specifically addressed in it, the design of WORs is in the penments was 78 percent hgher than predicted by Tab'e IWB- s irit of the ASME Boder and Pressure Vessel Code, Secten XI, 36415 and 39 percent hegher than predicted by the Source Art <le IWB 3640. NUREG-0313 Revision 2 provides guidance Equatons. Pred< ton, from two versons of the new ftnite-length for the implementaten of the procedures outhned in (WB 3640 surface-cracked pipe J-estimaton method were compared to However, neither of these documents specifies the values for expenmental results. One verson is for pipes with large R(m)/t diameter or thickness which are to be used in the WOR design ratos (SC.TNP) whde the other is a more general approach anahs s Throughout this report we have used the Combined (SC,TKP) where the large R(m)/t rat o restncton is re' axed The thickness and d:ameter of the repaired cross secton to calcu. results show that the SC TNP method tends to overest. mate the gg g g g g , g maximum loads by 15 percent on the a<erage whereas the from each of the four WOR proe expenments conducted was SC.TKP method tends to underpred:Cl the maximum loads, as sig ificantly hgher than that predicted by the IWB-3640 anatysS desired, by 32 percent for the des >gn guidehnes set forth in NUREG-0313 Rey,s4on 2 NUREG/CR 4875: CHARACTERIZATION OF CRUSHED TUFF for a "Standard" overlay, the average favure stress was ap-FOR THE EVALUATION OF THE FATE OF TRACERS IN proximately 30 percent higher than the fWB 3640 predicted fail-TRANSPORT STUDIES IN THE UNSATURATED ZONE ure stresses These values do not include the Code safety fac-POLZER.Wi: FUENTESF R ; R AYMOND,R , et at Los tors on stress For a "Standard" overlay, the Na* sizo consid-Alamos Natonal Laboratory March 1987. 46r'p 8704280288 ored in the analysis is completely through the ong nal pipe watl LA 10962 MS 40693 324 fu the entire Circumference of the pipe Such an overlay would Results of field scale (ca ston) transport sod es under un- be suitable for long-term plant operaton- If actual flaw dimen-Saturated moisture and steady and nonsteady fiow cond<t ons s ons were used in the design analysis, then in two of the four

58 Main Cit:tions and Abstr cts expenments the maximum stress was less than that predcted dental irstakes, incJuding tntium, Mn-54, Co-60, St 90, Nb 95, ra-by the IWB-3640 Source Equations. The greatest difference dioiodines, Cs 137, Ce 141, Ce-144, U 233, U Nat, and Am 241. was 8 percent For the flaw Szes evaluated in this study, an oveday design based on actual flaw dimensions would be con- NUREG/CR 4885: SEISMIC HAZARD CHARACTERIZATION OF sidered a "Limited Service" overlay, suitable only for short-term THE EASTERN UNITED STATESComparatue Evaluaton Of plant operaton, not to exceed one fuel cycle. The LLNL And EPRI Studies. BERNREUTER.D.L-; SAVY,J.B.; MENSING,R.W. Lawrence Lrvermore Natonal Laboratory. May NUREG/CR 4878: ANALYSIS OF EXPERIMENTS ON STAIN- 1987. 289pp. 8706160074. UCID-20696. 41311:267. LESS STEEL FLUX WELDS. Topical Report WILKOWSKI,G.; in 1982, the Lawrence Livermore Natonal Laboratory (LLNL) AHMAD,J.; BRUST,F.; et al. Battelle Memonal institute, Colum- was funded by the U.S. Nuclear Regulatory Commisson (NRC) bus Laboratones. Apol 1987.187pp. 8705190355. BMI-2151. to develop a methodology to charactenze the seismc hazard 40975.137. for all sites of the eastern United States (EUS) east of the This report descrbes experimental and analytical efforts to Rocky mountains. The utility soonsored Electne Power Re-evaluate fracture of sta:nless steel flux-welded pipe. Seven pipe search Mststute (EPRI) followed surt in late 1983 with a similar fracture expenments (four with through wall circumferential study. The LLNL methodology was applied at 10 test stes of cracks and three with circumferential internal surface cracks) the EUS and the results reported in 1985 (LLNL Report UCID-were conducted at 550 dcgrees F (288 degrees C). Matenal 20421). The EPRI study was presented in a senes of draft re-charactenzaton efforts involved laboratory specimen tests to ports in 1985 under the protect number P10129. The purpose assess specimen stre effects, effects of solution-annealing, and of this study was to help in understanding the reasons for differ-crack growth behavior in the HAZ, along the fusion kne, and in ences in results between the LLNL and EPRI study. We first in-the weld metal. Efforts involved assesong the net section-col- vestgated poss ble differences in the theones and assumptions lapse analysis, the plaste zone screening entenon, inherent used to develop the hazard models and concluded that all safety margins b th3 IWB-3640 flux weld analyss, through-wall- inputs being equal, the two methods were essentially equ'va-cracked pipe predictue J estimaton schemes for LBB analyses, lent. We anayzed the varcus input parameters, their values and n factor J-R curves calculated from the pipe expenments for the way they were collected, and finally we performed sensituity companson to C(T) specimen results, and finite element analy- analyss. The three main diffrences were found to be (1) the sis of C(T) specimens and one pipe expenment. Th s report also lower bound magnitudes of integration, (2) the ground moton evaluates the techrucal sign #fcance of these results and their models, and (3) the fact that LLNL accounted for a local site

   . sgn6cance relatrve to hcensing decisions.                                        correction and EPRI did not.

NUREG/CR 4883: REVIEW OF RESEARCH ON UNCERTAIN- NUREG/CR 4886: ANALYSIS OF THE NESDiP2 AND NESDiP3 TIES IN ESTIMATES OF SOURCE TERMS FROM SEVERE RADIAL SHIELD AND CAVITY EXPERIMENTS. MAERKER.R E. ACCIDENTS IN NUCLEAR POWER PLANTS. KOUTS H. Brook. Oak Ridge National Laboratory. May 1987. 57pp. 8708060387. haven Nabonal Laboratory. Apol 1987.106pp. 8705190524. ORNL/TM 10389. 42072:274. BNL NUREG-52061. 40977:081. Discrete ordinates calculatons were made of a senes of A review has been undertaken by four panels of experts, of measurements performed using the NESTOR reactor at AEE the sources of uncertainty in source terms from accidents to nu. Winfnth. These measurements are part of the NESDIP experi-clear power plants as presented by the document NUREG. mental program desgneo to benchmark methods and data 0956. These panels contained eminent scientists from the commonty used in interpreting pressure vessel surveillance do. United States, the United Kingdom, and the Federal Repubic of s metry placed 4 either in-vessel or ex vessel locatens. Results Germany. Separate reports by the panels provde detailed dis- obtained using the LEPRICON prmedures and updated ELXSIR l cussons and conclusons regarding the uncertainties and the cross sectons indicate agreement to within 10 percent with NRC research programs for their resoluton. An overall summary measured threshold dosimoter actuities beNnd vanous compo-of the results of panel deliberaton is also guen. nents of a radial shield containing up to 25 cm of water and 24 cm of steel. Segnifcant discrepancies in the energy range be-NUREG/CR-4884: INTERPRETATION OF BIOASSAY MEASURE- tween 0.1 and 2 MeV were found to exist with measurements MENTS. LESSARD.E.T.; YlHUA,X/ SKRABLE,K.W.; et al- made on the center 14ne of a 29.cm wide cavity and at vertical Brookhaven National Laboratory. July 1987. 914pp. locatons considerably above the centerkne of a 21 cm wde 8710080369. BNL-NUREG 52063. 42991:133. cavity, however. A logeal explanaton of the latter descrepancy This is a comprehensive manual desenbing how to compute is the failure of two independent two-dimensonal calculatons to intakes from both in-vrvo and in-vitre biosssay measurements. properly treat the three dimensional effects of vertical cavity To date, interpretatons of intake have been incons stent, par- streaming. No satisfactory explanaton has yet surfaced for the ticularly in the early phases after an 8CCdental intake. This first discrepancy, however, which is more ernportant of the two manual is aimed at completely descnbing a consistent approach in possbly affecting the interpretaton of ex vessel, low thresh-and instructing others on how to compute intakes and commit- old (100 kev) dosimetry. ted organ dose equsvalents. Tables for the interpretaten of bo-l assay results are compiled for sevoral hundred radonuclidet. NUREG/CR 4887: POSTCON.A POSTPROCESSOR AND UNIT Measurements which employ a whole-body counter, a thyrod CONVERSION PROGRAM FOR THE CONTAIN COMPUTER counter, a lung counter, or measurements on excreta can be CODE. WASHINGTON,K.E. Sandia Natonal Laboratones. May converted into eshmates of intake based on the tables preser't. 1987. 230pp. 8711100407. SANO87 0562. 43340 308. ed in the appendices. The values in the tables were determined The numencal predictons from use of the CONTAIN severe by using lung, gastrointestinal tract and systemic retenton reactor acesdent containment a,# fss computer code normally models published by the International Commisson on Radologi- take the form of massue quant: ties of output data. The purpose cal Protecten (ICRP79). In a few cases, pseudo-retenton func- of the POSTCON computer progra n is to provde an easpto-tons, organ retenton functons, and excreton functons were use and effcient method for emuning such results. In this used to generate the tabulated values. The bological and rado- report the capabilities of POSTCCN are descnbed and mstruc-logical input parameters are included in an appender, and a de- tions for the uw of the program are given. In order to clanfy the senpbon of the mathematical approach that was used to denve discusson of the input optons and output format, several exam-the tabulated data is included in the methods secton. Galcula- pies are presented including actual input, output, and vector tons for varcus particle sizes are addressed along wit t meth- fries The summary sectons of this document serve as a user's ods to interpret multiple or conbnuous exposures. Examples of manual and can be consutted for the constructen of smple use are based on actual boassay measurements following acci- POSTCON input files The detaded sections and Appendix A l ____-._.___._-s_ ____ -

~ . . . .- .~ -. . . _ - -- .. - - , Main Citations and Abstracts 59 , serve as a comprehensive reference manual that can be con- minimally with added framing. Numencal results support the ex-suited 'v advanced POSTCON include extracten of all tran- perimental results. Extrapotabon of the results to containment sient data from CONTAIN bina

• plot files, multiple f.le handhn9 constructed under field conditions with prototypc steel materials

          . a flexible urut converson system, snapshot and histogram op-        is discussed and further testing is recommended.

bons, automatic paginaten and labeling of tables, and vector output files for plot program inter

• acing. NUREG/CR 4894: A USER'S GUIDE TO THE NRC'S PIPING NUREG/CR 4889: ZlRCALOY-4 OXIDATION AT 1300 TO 2400 FRACTURE MECHANICS DATA BASE (PIFRAC). HISER,A.L.:

DEGREES C. PRATER J.T.: COURTRIGHT,E.L. Battelle Memo. CALLAHAN.G.M. Materials Engineenng Associates, Inc. May nal Institute, Pacife Northwest Laboratones. April 1987. 41pp. 1987. 82pp. 8706030146. MEA 2210. 41164:278. 8705120087. PNL-6166. 40896 034. This Guide is the reference for use of the NRC's Piping Frac.

              -The oxUabon kinebes of Zrcaloy 4 in steam have been ex.           ture Mechanics Data Base (PIFRAC), a computenzed data base tended to 2400 degrees C. The ZrO(2) and Zr layers esplay           containing the materids property data for steels used in nucle-parabolic growth behaver over the enbre temperature range           ar power plant prping. These data are for use by NRC regulators stud ed A discontinuity in the oxx!aten kinebcs at 1510 degrees     as requeed for structural integnty assessments of safety mar-C causes rates to increase above those previously established       gins in nuclear piping. The data of pnmary utility in such assess.

by the Baker Just relatonship. This increase coincides with the , monts are fracture toughness (pnncipally J-R curve) and tensile ' tetragonal-to-cue phase transformabon in ZrO(2 x). No addi- (stress strain) data, but other characteriste data such as chemi-tonal discontinuity in the oxide growth rate was observed when the metal phase melted. The effects of temperature gradients cat compositen and Charpy V data are also provided where were taken into account, and corrected values representative of available. This Guide desenbes PIFRAC as presently config-neaNsothermal conditons were computed. Oxide growth was ured. Revisens, updates, and correctons to PIFRAC will requee also measured in varcus steam-hydrogen matures at 1565 de- revisens to this Guide. grees C and 1815 degrees C. Hydrogen concentratons up to 90 mol% had no effect on oxidation kinetcs. The rate-controlling NUREG/CR 4896: CONTAINMENT LOADS DUE TO DIRECT factor appears to be diffusion through the oxide layer. Finally, CONTAINMENT HEATING AND ASSOCIATED HYDROGEN the ondaton kinebes of prereacted Zrcaloy 15 mol% UO(2) CEHAVIOR. Analysis And Calculatons With The CONTAIN were measured at 1400 to 2150 degrees C. The rates were Code. WILLIAMS D.C.: BERGERON.K.D.; CARROLL.D.E.: et at-comparable to thoso obtained for Zrcaloy above 1500 degrees Sandia Natonal Laboratones. May 1987.164pp. 8708060351. C. SAND 87-0633. 42071:261.

                                                                                                           *"                     #* "O "

NUREG/CR 4890: HEAT OF REACTION OF MOLTEN ZlRCONI-UM WITH UO2. BRIMHALL J.L; PRATER.J.T. Battene Memonal many ar pww ants des tM @nme caw institute, Pacife Northwest Laboratones. Apnl 1987. 32pp. @eci comannent Natog A, o M R H posMaN mat 8705120091. PNL-0165. 40896 225. molten conum ejected under high pressure from the reactor The heat of reaction for the dissolubon of UO(2) by motten vessel is dispersed into the containment atmosphere, thereby ' zirconium has been rneasured at 1980 degrees C using differen- causing suffeient heating and presmnzaten to threaten con- , tial thermal analysis. The dissoluton of 25 wt% UO(2) by zrco. tainment integnty. Models for the calculabon of potential DCH nium was determined to be an exothermsc reachon with a heat loads have been daveloped and inccrporated into the CONTAIN release of approximately 20 kcal/mol UO(2). Expenmental diff,- code for severe accident analysis. Using CONTAIN, DCH sce- t culbes encountered at these high temperaturos precluded a pre- nares in PWR plants having three different representative con. cise determinaten of the heat of reacton, tainment types have been analyzed: Surry (subatmosphenc NUREG/CR-4891: PROPERTIES OF REACTOR FUEL ROD MA. arge W c anneW Wyah W cWser contamM TERIALS AT HIGH TEMP!RATURES Final Summary Report . and Bellefonte (atmosphac large dry containment). A large Severe Core Damage Property Tests Program. PRATER.J.T.: number of parameter vanaten and phenomenological uncertam- , COURTRIGHT,E.L. Batteue Memonal Institute, Pacific North, ty studies were performed Response of DCH loads to these t west Laboratones. July 1987. 45pp. 8708240077. PNL-6164. vanatons was found to be qui % complex; often the results dffer 42316:110. substantia!!y from what has oeen prevously assumed concern. -[ This report summanus work sponsored by the U.S. Nuclear ing DCH. Containment compartmentalizaton offers the potenbal , Regulatory Commisson Drvison of Accident Evaluaten to in. of greatly rnogabng DCH loads relative to what might be calcu- , vesbgate those physical properties that are needed to predct lated using single-cell representabons of contanenents, but the the behavior of fuel-rod assemblies dunng a loss of-coolant ac- actual degree of mrtsgaton to be expected is sensitive to many cident. The results include a determinaten of the oxidabon ki- uncertaint:es. Dominant uncertanties include hydrogen combus-netics of Zacaloy and Zacaloy uranium oxide mrxtures n steam ton phenomena in the extreme envron; rents produced by DCH and steam hydrogen gas mixtures at 1300 to 2400 degrees C, scenanos, and factors which affect the rate of transport of DCH v:scosity measurements of zirconsum-oxide mixtures at 1800 to energy to the upper containmenL The anportance of hydrogen 2100 degrees C, an estimate of the heat of reacten for the dis- d behavior is partly due to the fact that most of the metalic con- s soluton of uraneum oxide by molten zircorsum at 2000 degrees C, and thermal diffusivity measurements on prereacted Zrcatoy-tent of the disporsed conum is calculated to react rapidly with < steam in the orygen-starved lower containtnent; hence, the im- D uranium oxide mixtures at 800 to 1500 degrees C. mediate energy release is reduced (relative to oxygen reactions) NUREG/CR-4892: A STUDY OF THE EFFECTS OF PENETRA. but targe quantsbes of hydrogen are rapidty generated. In add-TION FRAMING ON STEEL CONTAINMENT BUCKLING CA- ton, DCH loads can be aggravated by rapid blowdown of the PACITY. BAKER W.E.; BUTLER T.A. Los Alamos Natonal Labo. pnmary system, co despersal of moderate quantities of water ratory. May 1987. 59pp. 8707300287. LA-10977 MS. 41981:309 with the debns, and quenchog of de-entrained debns in water; Polycarbonate cylinders modeling steel containment struc- these factors act by increasog steam flows which, in turn, ac-tures were tested to study the effects of different frameng de- celerates enegy transport. Assessment of the actual contribu-signs around large penetratons on the static bucklog capacity tion of DCH scenanos to plant nsk would require substantial ad-of containments. Two of the four models had equipment hatch ditiona! work but it may be noted that containment-threatening ' penetrations and two had personnel arlock penetrations. Both loads were calculated for a substanbal porton of the scenarios types of models were tested with axial and shear loads as fram-treated for some o1 the plants cons 4ered. ing was merementally added. Results indicate that. for the models constructed of polycarbonate, buckfrng is influenced

     ---          ,u,.

60 Main Citations and Abstracts NUREG/CR-4897: LOW LEVEL WASTE SOURCE TERM Seisrnec capacities were developed for each device on the basis EVALUATION.Rewew of Pubhst ed Modehng And Expenmental of local input moton required to cause chatter; these results Work.And Presentaton Of Low-Level Waste Source Term Mod- were then apphed to develop probabikste fragility curves for ) eling Framework And Prehminary Model Development- each type of device, including estimates of the "high-confidence SULLIVAN,T.; KEMPF.C R. Brookhaven Nabonal Laboratory. 6ow probabihty of f ailure" capacity of each. Febncary 1987. 105pp. 8708060330. BNL NUREG.52066. 42072 065 NUREG/CR 4900 V02: COMPONENT FRAGILITY RESEARCH This report Contsins informaton on the efforts performed to PROGRAM Phase i Demonstraton Tests Appendices. date on the Low Level Waste Source Term Evaluaten Project. HOLMAN,G S.; CHOU.C K. Lawrence Livermore Natonal Labo-the objective of which is development of a model to predict ra. ratory, SHIPWAY,G D.; et al. Wyle Laboratones. August 1987. donuchde release rates from a low level waste disposal unit. 316pp 8709090300. UCID-21002. 42573.006. The approach for model development has been based on a See NUREGICR-4900,V01 abstract. compartmentahzed scheme focused on the four major process-es of water flow, conta#ner degradat3on, waste teaching and NUREG/CR 4901: EFFECTS FROM INFLUENT BOUNDARY waste radonochde transport to the trench boundanes. This CONDITIONS ON TRACER MIGRATION AND SPATIAL VARIA-stage of the project is focused pnmanly on modehng release BILITY FEATURES IN INTERMEDIATE. SCALE EXPERIMENTS. rates from snaBow and bunal as currently practiced. Research FUENTES.H.R.; POLZER,W.L - SPRINGER.E.P. Los Alamos efforts to this point include chamlemation work (of bunal Natonal Laboratory. Apol 1987".131pp 8706030186. LA 10981-trenches themseNes, of soils and structural features, and of waste forms and containers), review of pubbshed modehng W 41W U2 work, review of several waste package performance system In prevous unsc!Wated transport studies at Los Alamos, dis-models, and developm3nt of onginal container degradaten and person coefficients were estinated to be h.igher close to the waste teaching models. Charactenzaton of the wastes, contain. tracer source than at greater distances from the tource. Injec-ers, and of the site (trench soils and structure) has been based ton of tracers through discrete influent outlets could havt, cc-on the premese that NRC gudance has been put into effect. counted for those higher dispersons. Also, a lack of conserva-t>on of mass of the tracers was observed and suspected to be NUREG/CR 4899: CCMPONENT F R AGILITY RESEARCH due to spatial vanability in transport. In the present study, ex-PROGRAM Phase l Component Prontizaton. HOLM A N.G.S ; penments were performed under uniform influent (ponded) con-CHOU.C K. Lawrence Livermore Natonal Laboratory. June ditons in which breakthrough of tracers wern ...onitored at four 1987.177pp 8706300007. UCID-21003. 41491:118. Current probabeste nsk assessment (PRA) methods f ar nu. locatons at each of four depths. All other conditions were same-dear power plants utAre seismic ' fragaties" probab,lmes of lar to those of the unsaturated transport expenments. A com-failure cond,tioned on the seventy of seismic input moton - that panson of results from these two sets of expenments indicates ate based largely on 1,m2ted test data and on engencenng judg- differences in the parameter estimates. Estimates were made ment Under the NRC Component Fraglity Researcn Program for the drsperscn coeffcient and the retardaten factor by the (CFRP), the Lawrence Lrvermore Natonal Laboratory (LLNL) one-dimensenal steady flow computer code, CFITIM. istimates has developed and demonstrated procedures for using test data were also made for mass and for velocity and the disperson to denve probabAstic fragaty descrrptons for mechancal and ;oettgeent by the method of moments. The disperson coeffi. electncal comoonents. As part of its CFRP activitses. LLNL sys- cient decreased with depth under discrete influent apphcaton tematically ivent. feed and categonzed compenents influencmg and increased with depth under ponded influent apphcaten. Dif-plant safety in order to identdy ' cand date" components fcr ferences in breakthroughs and in estimated parameters among future NRC teshrg Plant systems relevant to safety were first locatens at the same depth were observed under ponded influ-identified. within each system cornponents were then ranked ac' ent applicaton. Those differences indicate that there is a lack of cording to their importance to overall system functon and their g g g anticipated seismic capacity Highest pronty for future testing - was assgned to those "very smoortant" components hav;ng "low" seismic capacity. This report describes the LLNL pnont$ NUREG/CR 4903 V01: SELECTION OF EARTHOUAKE RESIST. ration effort. abch also included appkcaton of "high level ANT DESIGN CRITERIA FOR NUCLEAR POWER PLANTS - quahficaton data as an alternate means of developing probabi- METHODOLOGY AND TECHNICAL CASES. Direct Empincal hstic fragaty descr,ptons for PRA apphcatons. Scahng Of Response Spectral Amphtudes From Vanous Sete NUREG/CR 4900 V01: COMPONENT FRAG!LITY RESEARCH And Earthquake Parameters LEE,V.Wa TRIFUNAC.M D. Struc-PROGRAM Phase i Demonstraton Tests Summary Report tural & Earthquake Engineenng Consultants. May 1987.343pp. HOLMAN.G S ; CHOU,C K. Lawrence Lrvermore Natonal Labo- 8706120186 41284 232 ratory SH!PWAY.G Da et af. Wyle Lcboratones August 1987. New frequency dependent attenuation functon of Founer am- ) 210pp 8709090542. UCID-21002 42563 001' phtude spectra of recorded strong earthquake ground accelera. l This report descr,bes tests periormed in Phase I of the NRC ton has been developed The iteratrve regresson analyses I j Component Fragaty Research Program The purpose of these g gg g gg gggg tests was to cemonstrate procedures for characteriz.ng the seism.c fragaty of a selected component. invest gat'ng how van-ous parameters ar fect frag hty, and f:raity usag test data to de-ve!op practical fragd ty descnptons su;tabis for apphcaten in moton it has been found that for distances less than about 100 km there is clear frequency dependent vanation of attenu-probabastic nsk assessments A three-column motor control ation functons. With high frequency amp %tudes attenuating center hovs ng motor cortroders of varcus f> pes and sizes as well as reiars of d,fferent trpes and manufactu rers was subject. faster with distance Our prevous empincat scaling model for ed to seismic input mot ons up to 2 Sg zero percd acceteraton Pseudo Relative Velocity (PSV) spectrum amplitudes has been To investgate the effect of base fieobety on the structural be. refined by introducog this new frequency deperdent attenuaton havor of the MCC and on the functonal trctaver of the electn. of amphtudes with distance The new model also considers the cal devises, mult-ofe tests were periormed on each of four depth of earthquake focus and the approximate charactenzaton mount.ng conf gur atens four botts per column w th internal de of the source size to compute the "representative" source to agonal brac ng and two boits per column with no top or intefnal t,tation distances en additon to all other scaling parameters bracing Device frag +ty was charactenzed by contact chatter used prevously correlated to hxal in-cabinet response at the device locaton. 1 k

Main Citations and Abstracts 61 NUREG/CR 4903 V02: SELECTION OF EARTHOUAKE RESIST- Show that the detonation cell width is reduced (detonability is ANT DESIGN CRITERIA FOR NUCLEAR POWER PLANTS increased) for increased initial temperature and/or pressure. METHODOLOGY AND TECHNICAL CASES Methods For intro-duction Of Geological Data Into Charactenzaton Of Active NUREG/CR 4909: MELPROG-PWR/MODOS MECHANISTIC Fav!!s And Seismic 2ty And. .. ANDERSON,J G ; LEE V.W.: CODE FOR ANALYSIS OF REACTOR CORE MELT PRO-TRIFUNAC M D. Structural & Ea thquake Engineenng Consult. GRESS!ON AND VESSEL ATTACK UNDER SEVERE ACCl-ants. May 1987.197pp 8706120163. 41289 020. DENT CONDITIONS CAMP,W.J.; YOUNG.M F.; TOMKINS.J L.; This report reviews the physrcal and expenmental bases for a et al. Sandia National Laboratones. Apnl 1987. 156pp. quantitatrve relationship between earthquake occurrence rates 8711100095 SAND 85-0237. 43339.008. and geological deformaSon rates These relatonships are well Since the Three Mile Island accident, increased emphasis has founded on mathemat cal statements of the elastic rebound been placed on the analysis of severe reactor accidents since theory, and well supported by cbservatons. The concept of uni- such accidents represent the dominant pubhc nsk from nuclear form risk spectra of Anderson and Trifunac (1977) is general. reactors. The U S. Nuclear Regulatory Commisson has made ized to include (1) more refined desenption of earthquake the development of mechanistic models for severe accident source zones. (2) the uncertainties in estimating seismicity pa. progresson a major pnonty. The purpose of these models is to rameters a and b in log (10)N - a-bM, (3) the uncertainties in Prov'de detailed, best estimate, coupled analyses of all the estimation of marimum earthquake size in each source zone, major phenomena involved in the course of the accident. To and (4) the most recent results or empincal scaling of strong meet this objectrve, the MELPROG computer code is being de-moton ampi;tudes at a s,te. Enamples of using the new NEO. veloped. The initial verson of this code, MELPROG PWR/ RISK program are presented and compared with the corre. MODO. is desenbed in this report. The purpose of MELPROG is sponding case stud es of Anderson and Tnfunac (1977). The or. to provide at any time dunng an accident sequence a descnp. ganizaton of the computer program NEORISK is also boef'y de. ton of (1) the state of the reactor core and surround >ng in-scnbed vessel envvonment, and (2) the disposition of core matenals (in part>cular, f,sson prcducts) contained within the reactor coolant NUREG/CR 4903 V03: SELECTION OF EARTHOUAKE RESIST- system boundary. MELPROG is coupled to the TRAC-PF1 RCS ANT DESIGN CRITERIA FOR NUCLEAR POWER PLANTS thermal-hydrauhes code to provide an integrated ana'ysis of the METHODOLOGY AND TECHN! CAL CASES Dislocaton Models behavior of core, vessel, and reactor coolant system during Of Near Source Earthquake Ground Moton. A Review

• Struc. Severe acc> dents. MELPROG treats core degradation and toss tural & E9rthquake Engineenng Consuttants LUCO.J E. Cahfor- of geometry, debns formaton. core melting. attack on support-naa. Univ. of, Sc. rhego, CA. May 1987.177pp. 8706120158 ing structures, slumping, mett/ water interactions and vcsel fa6 41288 203. ure. The key element in MELPROG is the use of detailed mod.

The solutcns ava:lable for a i.pher of theoretical fault ehng for the entire damage progresson and failure sequence models are examined in an attempt at estabeng some of the Emphasis is also placed on the rates of hydrogen, steam and expected charactenstics of earthquake ground motx.m in the fisson product formaton, and transport to containment during near source reg,on in part.cular, solvtcr's for two-dimens orui damage progressen. anteplane shear and plane-stra+n frodeis as well as for three-dimensonal favit models in full spa:e. uniform ha:f-space and NUREG/CR 4910: RELAY CHATTER AND OPERATOR RE. tayered haif-space media are reviewed SPONSE AFTER A LARGE EARTHOUAKE An improved PRA Methodology With Case Stud es BUDNIT2.R J ; NUREG/CR 4904: INVESTIGATION OF STEEL CONTAINMENT LAMBERT.H.E.; HILLE E. Futua Resources Associates, Inc. BUCKLING FROM DY N AMIC LOADS BUTLER T A; August 1987. 204pp. 8708270393 42330117. BAKER W E , BABCOCK.C D. Los Alamos Natonal Laboratory. The report addresses methodological weaknces in the PRA May 1987. 54pp 87C8170218 LA-10985-MS. 42171076 systems ana'ysis used for studying post-earthquake reby Chat-Buckhng of free stand ng nuclear steel containment buildings ter and for quantdying human response under high stress. An from dynamic base etc taten was investigated in a comb nei mproved PRA methodology for relay-chatter analysis is devel-expenmental/numencal program A polycarbonate scale mocel oped, and its use is demor'st,ated through ana'ysis of the Zon-of a conta,nment bulding was escated eth scaled earthquake 1 and LaSaHe-2 reactors as case stud,es. This demonstraton trans,ents and sing:e-frequency harmonic transients to deter- analysis is intended to show that the methodology can be ap-mine the peak base acceleraton levels required to induce buck- phed in actual cases The ana'ysis rebes on S$MRP-based ling Bucung *as identif>ed uSng recorded signa!s from stratn mvinodolog:es and data bases For both Zon 1 and LaSalle-2. gages and accelerome'ers, with high-speed vdeo records, and it is assumed that loss of offs:te power (LOSP) occurs after a I by audMty Expenmental rnsu:ts are compared w th numencal large earthquake and that there are no operator recovery ac. results obta:ned using a freezingan-time technique Results inde- tons The report a!so presents an improved PRA methodology cate that, depend =ng on the cr teron used. pred< tens can for quantifying operator error under high-stress Conditons such range from being quae conservative to be'ng unconservative It as after a large earthquake Eng>e-operator error rates are de-was also found that escitoon of higher stee! harrnonics may in. veloped, and a case study involving an 8. step procedure (estab-fluence the buckkng capac:ty of conta.nments Results of this hshing feed-and-bleed in a PWR a'ter an earthquake-intt.ated study are consdered prehm1 nary in that actcnal tests need to accdent) is used to demonstrate the methodology. be performed using models fabncated from steel rather than po-lycartonate NUREG/CR 4912: DATING GROUND WATER AND THE EVAL-UATION OF REPOSITORIES FOR RADIOACTIVE WASTE NUR EG/CR-4905: DETONABILITY OF H2 A:R OlLUENT mix- DAVIS,S N , MURPHY,E. Anzona, Unry. of. Tucson. AZ. Apnl TURES TIESZEN.S R , SHERMAN M P ; BENEDICK.W Ba et al. 1987.197pp. 8705190537. 40977.315 Sandia Natona! Laboratones June 1987 215pp 8707300370 The age of ground water es the length of t<me that tne water SAND 85-1263 41985133 has been isolated from the atmosphenc porton of the hydrolog-This report desenbes the Heated Octonaton Tube (HDT) ic cycie it is a theoreto.1 concept only. because afl ground Detonaten cen width and velocity results are presented for water to some extent is a mature of waters of d:fferent ages in H(h-a:r matures undMed and dduted *tth CO(2) and H(2)O s,mple systems. however, relative ages of ground water from for a range of H(2) concentra!cn. in>t:al terrporature and pres- d#erent portons of an aquifer can te determ,ned by d.fferent sure The resvits show that the anton of e,thtr CO(2) or methods. and the dates obta:ned are commonly in accord with H(2)O sgnAcantly increases the detonat on cell *dth and each other and reflect systematic increases of water ages in hence reduces two detonab+ty of tne mature The resu!ts a'so downgrad.ent drectons At least nine independent methods can

62 Main Citations and Abstracts be used to approximate ground water ages. The methods vary This technical report desenbes in-s;tu flow tests on bentonite widely in precision but all give useful informaton. In complex and cement borehole plugs installed in granite, and laboratory ground water systems, as many dating methods as possible back up expenments on similar pfugs Poor to seahng. the hy-should be used. Discordant "dates" mil result which, when draulic conductivity of the boreholes is tested. These measure-properly interpreted, will not give a single water age but mil g've ments, together eth core and borehole videologs, permit the valuable informaton concerning the hydrodynamecs of the selecton of seal test it'terva!s. Commercial enpansive cement ground-water system. Dat:ng methods which use isotopic and and standard waterwell sealing bentonite products and em-other geochemical techruques will read the actual history of the placement procedures are used. Transient (shcrt term) and water and mil give direct informaton on average ground-water steady state (long-term) tests determine the seakng perform-conditons over long perods of time if these perods exceed ance of the plugs under varcus stress condit.ons. Laboratory several hundred years, geochemical methods whch use past and field expenments confirm the difficulty of obtaining even conditons to predict the future are superor to hydrodynamic moderately accurate performance values for bentonite plugs as methods which use an extrapolat on of short-term data to pre- installed here, due to the simultaneous saturation, sweihng, and dict long-term hydrogeolog c cond,tions. consohdaton Nevertheless, conventonal instartaton of readdy avadable seals can provide adequate borehole seafs (i e , seats NUREG/CR 4913: ROUND ROBIN PRETEST ANALYSES OF A with a hydrauhc conductivity of about the same magnitude as 16 SCALE REINFORCED CONCRETE CONTAINVENT that of intact granite). Bentonite plugs of this type are beteroge-MODEL SUBJECT TO STATIC INTERNAL PRESSURIZATION neous and weak. Improved testing procedures and analyses are CLAUSS.D B. Sandia Natonal Laboratones May 1987 532pp. 8710050162. SAND 87-0891, 42908.037. needed if actual conductivity values are to be obta:ned in a rea-sonable testing time (e g , months) Laboratory invest gabons on Analyses of a 1.6-scale reinforced ccncrete containment failure mechanisms in cementit,ous and bentonitic plugs, not model that will be tested to fa: lure at Sandia Nabonal Laborato-covered in th s research study, are needed in ident;fy and pre-nes in the spnng of 1987 were conduced by the following orga-nizatons in the United states and Europe: Sandia Natonal Lab- vent plug failure. oratones (USA), Argonne Natonal Laboratory (USA) Electnc NUREG/CR 4921: ENGINEERING AND OUALITY ASGURANCE Power Research Inst,tute (USA), Commissanat a L'Energte Ato. COST FACTORS ASSOCIATED WITH NUCLEAR PLANT mique (France), HM Nuclear Installatons inspectorate (U.K )* MODIFICATION SMITH,M H., ZlEGLER.E J United Engineers Comitato Nazionale por la ncera e per lo syduppo dell Energia & Constructors, Inc. (subs. of Raytheon Co ) Apnl 1987.59pp Nucleare e delle Energie Alternatrve (Itafy), U K. Atomic Energy 8706240192. 41452 001. Authonty, Safety & Rehabibty Directorate (U K.), Gesellschaft Thts study provides genenc est; mates of engineenng and fuer Reaktorsicherheit (FRG), Brookhaven Natonal Laboratory Quakty Assurance (OA) costs based upon the development and (USA), Central Electncity Generating Board (U K ) Each organ" analysis of new and existing data The es$ mates are cost fac-zaton was supphed eth a standard informat on package, whsCh tors, not absolute dollar values, expressed as a percentage of included construction dramngs and actua, ma'enal properties the direct cost of implementeng the p! ant mod <ficaton These for most of the matenals used in the modet Each organizaton factors vary sgnificantly depending upon the work environment worked independent!y us4ng their own anatytical methods Th s at the time of the mod.f cat on. Generalty the work environment report refers to two groupings of plants. the first relates to require-NUREG/CR-4918 VO1: CONTROL OF WATEG iNFILTPATION ments affecting structures and systems already in place. whde INTO NEAR SURFACE LLW DISPOSAL UNITS Annual the second rotates to new constructen requirements which may Repc<t, October 1985 September 1986. SCHUL 2,R.K ; be apphcab;e to future plants, plants under constructen, and/or RIDKY,R.Wa O'DONNELL E.; et at Cahfornia, Un#v. of, Be ko, operating plants The types of mod,ficabons this study address-ley, CA Apnl 1987,30pp 8705t20092. 40896.196. es are the physeal modificatens to the structurcs/ systems of in the humid eastern part of the United States, trench covers nuclear power plants as opposed to ana'ytcal or procedural have, in general, failed to prevent some of the incident prec2pi. changes. The deaved estimates, when mutt;pMd by the direct taten from percolating downwa-1 to buned wastes. It is the pur. cost (i e , equ pment, matenal, and instattaten labor) or insta:hng pose of the present work to investigate and demonstrate a pro, specific structures, systems, and pieces of equ:pment at a nu-cedure ot techruque that will coctral water infiltration to buned clear power plant wdl generate a reasonable order of-magnitude wastes regardless of above or below ground d,sposat Results estimate of the eng:neenng O/A costs assoc.ated eth a physs to date show the proposed procedure to be very promising and cal modificaton are apphcable to shallow land bunal as well as above ground NUREG/CR 4922: STEAM SEPARATOR MODELING FOR VARI-oisposal (e g Tumutus). In essence, the technique combines OUS NUCLEAR REACTOR TR ANSIE NTS PAM,C.Y; sngineered or postive control of run-off, along eth a vegetatrve MULLE N,G.; KNCESS.C ; et al. Massachusetts inst,tute of cover, end is named "bcengineenng management' . To invest" Technology, Cambndge, MA June 1987. 226pp 8706240352 gate contn.J of infdtraton, lysemeters are being used to make EPRI NP.5272. 41439 289. comp!ete water Mance measurements The studes have been Expenments were performed us ng a r and water on three dif-underway at the Maxe Flats, Kentucky, low-level waste d:Spos- ferent types of centnfugal separators a cyclone as a genenc al facihty for the past thre seasonal years When the orgtnal separator, a Combuston Engineenng type stationary s*:rl vane Maxey Flats 5 te closure proc 9 dure is followed, it is necessay sem% W a Westinghouse type separator. The cyclone to pump targe amounts of water out Of the ty9 meters to prevent se arator system has three stages of separaton f,rst the cy-the watw table from n9ng closer than 2 meters from the sur- clone, then a gravity separator, and finany a chevron plate sep-face. Using the bioengineenng management procedure, no arator. The other systems have only a centnfugat separator to pumping is required As a resuft of the encourag:nq inst:al find- isolate the effect of the pomary separator. Experiments were ings in the rather smarl-scate lysmeters at Maxey Flatt a large- a!so done in MIT blowdown rg. eth and ethout a separator, scale facMy for demonstraton of the bioeng:neenng meage- using steam and water. The separators appear to perform wen ment technique has been constructed at Beltsvdle, Maryland at flow rates well above the de9gn va!ues as long as the down-This facibty is now operatonal eth the demonstraton and data comer water level is not high. H gh downcorner water level collecton underway. rather ttan hgh flow rates appear to be the pnmay cause of NUREG/CR-4919: FIELD TESTING OF BENTONITE AND degraded performance Appreciable carry-over from the separa-CEMENT BOREHOLE PLUGS IN GRANITE. KtMBRELL,A F , for section of a steam generator occurs when the dra n hnes AVERY,T.S ; DAEMEN.J.J. Anzona, Unw of. Tucson, AZ. July from three stage of separaton are unable to carry off the Iquid 1987 342pp 8708110501. 42123 253. flow

Main Citations and Abstracts 63 NUREG/CR 4925: FISSION PRODUCT BEHAVIOR DURING THE This report concludes a six month Phase i protect performed for PBF SEVERE FUEL DAMAGE TEST 1-1. HARTWELL.J K.; the Nuclear Regulat~v Commisson under the SBIR program. PETTI,D A ; HAGRMAN.D L.; et al. EG&G Idaho, Inc. (subs of EG&G. Inc.) May 1987. 672pp. 8708t40041. E GG-2462. NUREG/CR 4930: CRACK ARREST BEHAVIOR IN SEN WIDE 42159 038. PLATES OF OUENCHED AND TEMPERED A 533 GRADE B in response to the accident at Three Mae Island Unit 2, the STEEL TESTED UNDER NON:SOTHERMAL CONDITIONS. United States Nuclear Regulatory Commesson init:ated a senes NAUS.DJ.; BASS.B R.; PUGH,C E.; et al. Oak Ridge National of Severe Fuel Damage (SFD) tests that were performed in the Laboratory. August 1987 210pp. 8711160022. ORNL-6388. Power Burst Facihty (PBF) at the Idaho Natonal Engeneenn9 43361:147. Laboratory to obtarri data necessary to understand (a) fisson product release, tr6nsport. and deposition, (b) hydrogen genera- The first senes of six wide plate crack arrest tests (WP 1 Senes) are discussed in this report Each test utihzed a 1-m x 1-tion, and (c) fuel / cladding matenal behavor dunng degraded core accidents. Dunng the second expenment of this senes, the m x 0.1-m-thick single-edge notch specimen (a/w = 0.2), fabn. SFD Test 1 1, real-time release and transport data of certarn fis- cated from A533 grade B class I steel, that was subjected to a son products were obtained from on-hne gamma spectroscopy linear thermal grad ent alcng the plane of C-ack propagaton. measurements. Liqued and gas effluent grab samples were col- The tests were conducted at the Natonal Bureau of Standards lected at selected perods dunng the test transient. Additonal gg g , oug information was obtained from steamhne deposrton analysis. measurements at temperatures approaching of above the onset From these and other data fisson product release rates and of the Charpy upper shelf regime, in a nsing toughness regon total release fractions are estimated and compared with pred>ct- and with an increasing driving force. Results from this series of ed release be%vor using current models, f;ssion product destn. tests produced crack-arrest toughness values well above the butons and a mass balance are summanzed, and certain prob. limit recognized by current ASME Code guidehnes(220MPa.VT6) able chemical forms are predrcted for odine. cesium, and tellun. with arrest occurnng at 52 degrees C to 115 degrees C above um. Anatysis indicates that volatde release from fuel is strongly the matenal RT(NOT) (-23 degrees C). The fracture data sup-influenced by parameters other than fuel tempera'ure, these are port (1) the use of current LEFM concepts to analyze cleavage fuel /fisson product morphology fuel and cladding oxidaten run-arrest events, (2) the treatment of cleavage run arrest and state, extent of fuel liquefacton and shattenng Teilunum re- ductde fracture modes as separate events, and (3) the fact that lease behavor rs examined relattve to the extent of zircatoy cleavage arrest occurs above the ASME Imt. cladding oxidaten NUREG/CR 4931: RESPONSE OF CENTRIFUGAL AND AXI-NUREG/CR 4926: AN ASSESSMENT OF LOSS-OF-CONTAIN-MENT POTEN11AL BECAUSE OF KNUCKLE BUCKLING FO" VANE BLOWERS TO LARGE PRESS'JRE TRANSIENTS. 4.1 STEEL CONTAINMENT HEADS BENNETT.J G. Los GREGORY,W.S; SMITH,P.R Los Alamos National Laboratory. Alarnos Natonal Laboratory Apol 1987. 22 App. 8712010143 June 1987. 619pp. 8709090188. LA-11019 MS. 42561.102. LA 109/2 MS. 43485153. The effect of large pressure pulses on the operaton of Cen-4:1 diameter to-height nse ratio tonsphencal nuclear steel infugal and axi-vane blowers of th9 tyoes found in ventilaton contarnment head geometnes were investenMed expenmentany systems used in the mnng and nuclear industnes was investi-and analyticany for effects of knuckv gated using the Los Alamos Natonal Laboratory /New Mexico irom internal pressure The particular focus of the - to assess the State Unrversity fluid dynamics test facihty. Three blowers were loss-of containment potential Se t' . *ere camed tested for both quast-steady and transient pressures a 24an. to rupture when feas.bie Results o. we tests ar'd and a 12an. centnfugal blower and a 33an. axi-vane blower two large-scale (1/8) tests are reporteo ::rgnAcant rates of were subt ected to pressure pulses at their exhaust and net, knuckle buckhng to design pressures were found (1.6-2 4) in wnich caused backflow and outrunneng flow, raspectively. Per-add, ton, very large rupture pressure to design pressu.e rateos formance curves were obtained for the first, secord and fourth (7 7 5) indicate adequate reserve margn for ioss-of-conta.nment quadrants for these geometnes and matenals NUREG/CR 4936: AN INTEGR ATED NUREG/CR 4928: CEGRADATION OF NUCLEAR PLANT TEM- GEOLOGICAL GEOPHYSICAL,AND GEOCHEMICAL INVESTI-PERATURE SENSORS HASHEM1AN.H M.; PETERSEN.K M.: GATION OF THE MAJOR FRACTURES ON THE EAST SIDE KERLIN.T W.; et af Analys2s & Measurement Services Corp OF THE NEW MADRID EARTHOUAKE ZONE STEARNS.R G ; June 1987. 85pp 8707020108. 41568 281. A program was estabbshed and ntia! tests were performed to REESMAN.A L Vanderbdt Unrv.. Nashvde, TN May 1987. 36pp. 8705290297 41115 261. evaluate K)ng term pedormance of resistance temperature de-tectors (RTDs) of the type used in U S nuclear power plants. The eastern edge of the M4ss,ssippi VaHey graben (Reelfoot The effort addressed the effect of ag:ng on RTD cabbraton ac- nft) is a senes of offset segments marked by offset "ndges" of curacy and response tee. This Phase i effort included expo- gravity anomary. The most prominent offsetting fault is the sure of thirteen nuclear safety system grade RTD e!ements to Dyersburg hne that is at least 60 mdes long and cuts completely simulated LWR temperatures Full cabbratons were performed through the 9raben The Dyersburg line is traced by earth-ntially and monthly, sensors were monttored and cross quakes, the pattern of the geothermal grad.ent offset grav:ty checked conbnuous!y dunng esposure. and response time tests aroma %s, and sWace Mears Compos. ton of ground water were performed before and after exposure Short term cahbra- from the Cretaceous McNairy Formaton, the Eocene Wacox ten dnfts of as much as 1.8 degrees F (1 degree C) were ob. and Cla: borne formatons, and Holocene alluvium are a!I sign.h-served Response t4mes were essent:a9y unaffected by this cant for the structure of the rift. Trends for some chemical spe-testing This program shows that thefe is a sound reason for C'es are parallel to the rift or the Dyersburg line (and probably concern about the accuracy of temperature measurements in the pre-Cretaceous Pascola arch) Banum and hthium show par-nuclear power plants These hmited tests stuuld be erpanded allebsm to both, strontium isotope ratos trend parallel to the rift in a Phase ll program to invoNe more sensors and longer espo- whereas ca' bon isotope ratos trend para:lel to the Pascola sures to simulated LWR cond trons in order to obtain statist >ca!!y arch Upward leabage along faults of minerabzed and h,gh pres-

$>gnificant data This data is needed to estabhsh meannful            sure water from the McNairy is the 14ely explanaton for locah test,ng or replacement intervals for safety system RTDs An im-       ized occurrence of minerabzed water in younger aquifers The portant corollary benefit from this expanded program *di be a        best exampie is chlonde water in Holocene a9uvium on the better defnton of achevable accuracies in RID cabbrabon              Dyersburg 1.ne.

64 Main Citations and Abstracts NUREG/CR 493h INVESTIGATION OF THE MEERS FAULT IN moratona (4) the inter. relat on of V l ana!ysts and possible use SOUTHWESTERN OKLAHOMA. LUZA.K.Va MADOLE.R.F4 of quantif ed desgn objectives for the probability of core mert CRONE.A.J. Oklahoma. Unrv. of Norman, OK. August 1987. and other safety parameters, and (5) the application of V l anal-65pp. 8709150280. 42680.291. ysis to regulatory decisons in relaton to specrfic problems. The Meers Fault is part of a maior system of NW-trending faults that form the boundary between the Wschsta Mountains NUREG/CR-4942: EQUIPMENT OPERABILITY DURING STA. TION BLACKOUT EVENTS. JACOBUS.M J ; NICOLETTE,V.F.; and the Anadarko basin in southwestern Oklahoma. The Meers Fault is exp^ sed at the surface over a length of at least 26 km; PAYNE.A.C. Sandia Natonal Laboratones October 1987.51pp. It stnkes N 60 degrees W and offsets Permian conglomerate 8711030077. SAND 87-0750. 43243:285. and shate. The fau!t is consistentry down to the south, with a This report is an initiallook at a possible analysis method for maximum rehef of 5 m near the center of the fault trace. Qua. determining if equipment expected to operate dunng and after a ternary stratigraphy and 10 (14)C age dates constra n the age station blackout can be "reasonabfy" expected to survrve envi-of the last rnovement of the Meers Fauft. The last movement ronrnents generated as a result of the station blackout. The postdates the Browns Creek Alluvium late Plestocene to early general concluson is that, given the Current quahficaton levels Holocene, and predates the East Cache Alivviurn, 100-800 yr of representatsve equipment, "reasonable" assurance of oper. B.P. Fan alluvium, produced by the last fautt movement. buned ai%ty should be demonstrable for rnost equipment in most loca-a soil that dates between 1,400 and 1,100 yr B P. Two trenches tions. excavated across the scarp near Canyon Creek document the NUREG/CR-4943: PREPARATION OF DESIGN SPECIFICA-near surface deformaton and provide some informat3on on re- TIONS AND DESIGN REPORTS FOR currence. Flexing and warping was the dominant mode of defor. PUVPS. VALVES. PIPING.AND PlPING SUPPORTS USED IN rnation. The strattgraphy in both trenches indicate? one surface- SAFETY-RELATED PORTIONS OF NUCLEAR POWER faulting event, which imphes a lengthy recurrence interval for PLANTS RODABAUGH.E.Ca MOORE S E. Oak R dge Natonal surface faulting en this part of the fault. Two samr:es that post- Laboratory Jtne 1987. 78pp. 8710060234. ORNL/ TM-10425-date the last fault movement yielded (14)C ages between 1.600 and 1,300 yr B P. These dates are in agreement wdh dates ob- dM+ tarned from the soel buned by f ault-related f an alluvium. IdNM B P quires the preparation of Des gn Specihcatons and Des >gn Re-NUREG/CR-4938: OCCUPATIONAL RADIATION EXPOSURES ports as part of the des 9n process leading to constructon of a ASSOCIATED WITH ALTERNATIVE METHODS OF LOW- nuclear power plant, in comphance with provisons of Title 10 of LEVEL WASTE DISPOSAL. HERRINGTON.W N ; HARTY R ; the Code of Federal Regulations (10 CFR) Guidelines for pre-MERWIN.S E. Battelle Memonal Inst:tute, Pactfic Northy st panng this documentation are contained in nonmandatory Ap-Laboratones. May 1987. 90pp. 8706240313 PNL & 17. pendixes B and C of the ASME Cc4e. This repod gives an in-41450.176- depth review of the ASME Code requirements and guidance. The Low-Level Radioactive Waste F ohcy Amendments beginning with the frrst ed< ton of the Code in 1963 through the (LLRWFA) Act of 1985 mandates that the U S. Nuclear Reguta- 1983 ed tons, Summer 1985 Addenda Recommendatons for tory Commissaon (NRC), in consultaton w+th states and other in- substant:al revisons to the Code are presented based on the terested part>es, ident:fy disposal rnethods other than shNio* authors' expenence in conducting design documentabon audits land bunal (SLB). the method curranJy used at the three icw' cf pumps, valves, pipog and p+ ping supports for nuclear power level waste (LLW) disposal sites operatng in the United States plants undergoing NRC review for Operating Licenses it is con. We compared projected occupatonal exposures associated cluded that adequate Desgo Specificatons and Design Reports with the SLB rnethod and f've alternative disposal methods in- are absolutely necessary for the normal operating hfe of a plant cludsng below ground vaults (BGV). above ground vaults (AGV). and are vital if plant bfe extenson is planned earth mounded concrete bunkers (EMCB) augured holes (AH), and mined cavit>es (MC) MC facit.t.es were stud,ed in less detaa NUREG/CR 4944: CONTAINMENT PENETRATION ELASTOMER because this d'sposal method is not betng act:yely considered SEAL LEAK RATE TESTS. BRIDGES.T L Sand:a Natonal Lab-Reference facthty designs and a hst o' probable tasks requ. red oratones BRIDGES.T.L EG&G Idaho. Inc. (subs of EG&G. at each site for receiving and d:spos,ng of the law-level waste inc ) July 1987. 58pp 8712020035 SAND 87 7118. 43519 282. were developed. Each task was anatyred by worker require- Tests were performed on three elastomer seal designs com-ments, t;me requ rements, distances between workers and the monly used for nuclear plant conta:nment mechanical penetra-waste, and exposure rates at those d. stances This informat,on tons The objectue of this research project is to obta:n an un-was used to estrmate the dose recewed by workers dunng d.s. derstand6ng of the integnty and leakage behaver of these seal posal of four types of *aste packag ng drums, wood bores, designs under severe accident temperature and pressure condo resin liners, and dumpsters The resu:ts of this study suggest tons The three designs tested and the seal matenals used in that, of the methods stud,ed in detait, occupatonal dose equiva. the tests were (a) double tongue and-groove des.gn *dh sik-lents would be highest for the EMCB method (181 person. cone rutber sea's. (t) double-O-nng design w,th neoprene and mrem /m(3) of waste dtsposed) The icwest occupatonal dose ethylene-propylene (EPDM) seals, and (c) double gumdrop equiva!ents would occur for the AH method (129 person. design with neoprene and EPCM seals The effects of thermal mrem /m(3)) Protected occupatoral one equwa;ents for SLB. aging and angu ar rotatons of IIange mat:ng surfaces were de-BGV, and AGV d sposal methods a'e 138, 147. and 1 61 termined The test resu;ts provide informabon rcqu; red to char-person-mrem /m(3).respectrvely. actenze the leasage behacor of penetratvns under severe aC-c M co e ns. NUREG/CR 4941: THE APPUCATION OF VALUEaVPACT ANALYS!S TO U$l A 45 Summary Report Cf UCLA Stad.es On NUREG/CR 4945: SUMVARY OF THE SEM: SCALE PROGRAM Vatue-Impact Analysis in Relat.on To USI A -4 5 CAVE.L : (1965-1986) LOOMIS.G G EG&G Idaho, Inc (subs. of EG&G. KASTENBERG W E Sand.a Natonal Laboratones

• Cahtomia, inc ) Ju'y 1987 273pp 87C8140083 EGG 2509 42161001 Univ. of, Los Angeles. CA September 1987. 226pp This document summar:zes significant resu'ts from the Semis-8711160040 SAND 87 7116 43363 045 cate Program, wh+ch esamined pressur; zed water rearor (PWR)

Value impact ana yses of potent.at resol!cns to USi A-45 safety issues from 1965 to 1986 Most cf these issues were re-were an essent<al part of the program This report descnbes (1) lated to plant responso danng loss-of-coolant accidents and development of a V 1 anaiys s methodology for thc esa pie operabonaf trans ents The Sem.sca!e program utazed a senes plant case studies. (2) the ma+n sources or uncertaety in V-l of non nuclear, scated PWR plant simulators to provde ther. anaYses and their treatment in USI A 45 (3) tre in<est. gabon of rrathydraukc data at prototypical pressures and temperatures add. tonal aver 1 ave costs such as r-conomc cpact of noc! car for a *ide range of nuclev sa'ety issues Presented are a has-

Main Citations and Abstracts 65 toncal perspective of the Semiscafo Program relatrve to reactor NUREG/CR-4951: NEPHROTOXICITY OF URANYL FLUORIDE safety with a catalog of the Semiscale expenmental facdities AND REVERSIBILITY OF RENAL INJURY IN THE RAT. and data bases, the relationship of Semiscale results to 10 CFR DIAMOND.G L; GELEINAM ; MORROW.P E.; et al. Rochester, Pa.t 50 (Appendix K), the impact of Semiscale results on scal- Unnt of, Rochester, NY. September 1987.104pp. 8710060148. ing expenmental results to full s:ze operating plants, a summary 42921:137. of safety issues that were addressed in Semiscale testing as The objective of the study was to examine the seventy and

• they arouse throughout the operatonal lifet,me of Semiscale, duration of renal inlury produced in the rat from exposure to low the contnbutons ni the Semiscale Program to safety technolo- levels of uranyl fluonde (UO(2)F(2)). Rats received mult91e i p.

gy, a desenpton of phenomena observed during Semiscate injectons of UO(2)F(2) (Cumulatrve dose: 0 66 or 1.32 mg U/kg testing. the impact of Semiscale data on code developmcat and body wt). Renaf injury was charactenzed pnmanfy by cellular assessment, and finatly, major conclusons and accomphsh- and tubular necrosas of the pars recta of the proximal tubule ments of the Semiscale program. (S(2) and S(3)), with less severe cellular injury to the thick as7 NUREG/CR 4946: DAVIS-BESSE UNCERTAINTY STUDY. cWng limb of the loop of Henie and collecting tubule. Th? DAVIS.C B. EG&G Idaho, Inc. (subs of EG&G, Inc ) August injury was apparent erty in the dosing phase of the study, at a 1987. 83pp. 8709090483. EGG-2510. 42564.099 time when renal uranium levels were between 0.7 1.4 ug U/g, The uncertainties of calculatons of loss-of-feedwater tran- and was most severe when the renal uranium burden was be-sients at Davis-Besse Unit 1 were determined to address con-tween 3 4 5 6 og U/g Repair of the injury was rapid, with complete restoraton within 35 days after the exposure. Associ-cerns of the U S Nuclear Regulatory Commissen relative to the effectrveness of feed and bleed coohng. Davis Besse Unit 1 is a aW wnh the injury were numerous abnormahties in kidney func-pressunzed water reactor of the raised-loop Babcock & Wricon ton, includ.ng impaired tubutar reabsorption, proteinuna and en-design. A de'aded, quahty assured RELAP5/ MOD 2 model of Omuna, which appear to be temporally related, to vanable de-Daos-Besse was developed at the Idaho Natonal Engineenng grees, to the progresson of renal injury. Renal injury preceded Laboratory The model was used to perform an ana!ysis of the aN MasW bnctonal aWmahties as assessed by unnalysis and cMarance measurements. loss of-feed *ater transient tha' occurred at Davis. Besse on June 9.1985. A loss-of-feedwater trans;ent followed by feed NUREG/CR 4952: EXPER! MENTAL STUDY OF FILLET WELD and bleed coohng was also calculated The evaluaten of uncer* UNDERCUT EFFECTS ON WELDED TUBING STRUCTURES l tainty was based on the compansons of calculatons and data. UNDER CENTRIC AND ECCENTRIC CYCLIC LOADINGS. compansons of d1tferent cctculations of the same transsent. sen- OKAILY,A A. Caispan Corp (subs Arvin Industres/Frankhn Re. sitroty calculatons, and the propagaton of the estimated uncer- search Center). June 1987. 85pp 8708170121. 42171:131. tainty in initial and boundary cond; tons to the final calculated The effects of weld undercut defects on the structu<al behav-results or cf twelve welded tubing test specimens subjected to centnc NUREG/CR-4950 VO1: THE SHORELINE ENVlRONMENT AT. and eccentnc cyche loa $ngs were evaluated. The test program MOSPHERIC DISPERSION EXPERIVE N r included the design, fabncatcq. and testing of one group of six (SE ADEX) Espenment Descnpton CANTRELL.B K ; fittet-*elded tubing spec; mens and one group of six reinforced JOHNSON W Br MORLEY,B M ; et at SRI interratonal. June part at-penetraton, groove-welded tutwg specimens under ccn 1987. 40pp 8707130162. 41684.136 inc and eccentnc load.ng Each group consisted of three Centn-The SE ADEX atmosphenc d<spers on field st A was conduct. cally loaded toecimens with 0,1/32, and 1/16an undercuts ed during the pered May June 8.1982, in northeastern Wiscon- and three ec:entocally loaded specimens w,th 0,1/32, and 1/ ssn, in the vicinity of the kewaunee Power Plant c,. the western 16-in unde; cuts. Permanent deflecton, d, was recorded after 1, shore of Lake M,chigan. The specific objectrves of SEADEX 5, and 10 load cycles at 10*. neremento r/ th3 calculated yield were to charactenze (1) the atmosphenc disperson ar.d (2) the loa 1 P(y), starting at 50*. r) ,). through inc v4; mate load, P(u) meteorolog* cal cond. tens influencing th s d:sperscn as com- Permanent de'lecton ratios, c!do, of a defective specimen pietely as possible dunng the test perod This f eld study includ- versus that of a sim*Iar, but sound specimen (i e, no undercut-ed a senes of controlled tracer tests utilizing state-of-the-art ting) at the same load level and number of cycles were then tracer measurement technology to determine honzontal and ver. calcutated Ana!ys s of test res.'ts 'sd to several conclusons re-tscal disperson over both land and water Extens ve meteorutog- lated to the effects of f.Ilet welo undercut on permanent deflec-ICal measurements were obtained to thoroughly Charactenze the ton rate and ultimate load values of welded tubing structural three-dimensional structure of the atmospherc bounday layer members under centnc and eccentnc cyclic loa $ng controlkng the dispersion process This volume desenbes the expenmental design for, and conduct of. the study. NUREG/CR 4953: CORRE LATION OF RADIOlODiNL RESU. SPENSION WITH TEMPERATURE AT TMI-2 DAN!EL.J A ; NUREG/CR 4950 V02: THE SHORELINE ENVIRONVENT AT- DAN!E; ,E A : SETH.E L D;:ntel & Assoc ates, Inc. July 1987. MOSPHERIC OISPER$10N EXPERiVENT 137pp 6708040231 DA.TR/8705 42037 054 (SE ADEX) Meteorological And Cas Tracer Data This report addresses the observed long term behaver of ra-JOHNSON,W B ; CANTRELLB K . MORLEY B M , et al. SRI dood,ne in specific locatons in the TMI-2 Auxil:ary and Fuel Internatonal. October 1987. 495pp 8711180047. 43387 241. Handling Bud $ngs, and provdes data on the behaaor of l-131 The SEADEX atmosphenc disperson f e:d sody was conduct- at re!atsery low temperatures. (50 degrees 85 degrees F) and ed dunng the perod May 28 June 8,1972, in northeastern non equebrium cond,tions, s.nce the budd4ng vent, laten sys-Wiscons:n, in the vicinty of the Kewaunee Power Plant on the tems were in operat on This report also d:scusses the observed wester 9 shore of Lake V chigan. The specific objectives of effect of changes in the dady concentration of radoodine due SEADEX were to charaCtenze (1) the atmosphenc d,sperson to d urnal temperatur e Cycles, and establ shes a numerical rela. and (2) the meteorolog> cal cond tons influencing this d;sperson t onship between radoodene concer9traton and ambient temper-as comple*ely as possib:e dunng the test penod This field study ature included a senes of contro!!ed tracer tests utaz ng state of-the. art tracer measurement technology to determine honzontal and NUREG/CR 4954: LCNG TERM PERFOR M ANCE OF SPENT vert: cal desperson over both land and water. Extensrve meteco FUEL SASTE FORMS VEANS ) L , M AR KWORTH,A J , Ological measurements were otta ned to thoroughly character. MOCO. ,J K , et al Ba'tene Memonal Inst:tute. Columbus lab-tze the three d menscnal structure of the atmosphenC boundary oratones September 1997. 162pp 8710090161 BMI 2154 layer contro!I:ng the d,spers on process Th4s volume presents 43009 058 the meteorolog,ca! and gas tracer data conected dunng the f eld TNs repod descr.bes the resutts of a 2 year espenmental pro. study gram to invesbgate the leachtng/d ssoluton charattenst>cs of

f T 2 66 Main Citations and Abstracts spent fuel in sirrntateu grourCuaten E per.n eat = were con- Nn G JO(2) may be influenced significantly by solut on pe and datert to evaluah the eaung of ut.cra-ha%J UO(2) in simukt- chlonde concentraten. ed groundwaters uotr. in the presence and absence d an etter. nal rau.aton field. Otner ~ penmen .naric*r nz }1 the Mcole NUREG/CR 4957: SURVEY OF GEOPHYSICAL TECHNIQUES tion beavior of went wel under the same cond, tons 's fy FOR SITE CHARACTERIZATION tN BASALT. SALT AND TUFF. JONES,G M ; BLACKEY.M.E.; RICE.J.E ; et al Weston Geo-00(2). Lea <t <ta *g; irWroreteo rt tFms of rites and wch-anisrM of rsdonuchde re' ease, tnes prowding indght on leach physical Corp. Jufy 1987.149pp 8709110098 42609.161. behavior under reahstic rcpos. tory conditons. Urantur' release This report surveys varcus geophysecal techniques that would from both unstra9ated and irradiated 40(2) appeared to be sol. have appbcaton dunng sate charactenzation activ6 ties in connec-v'oihty controlled with only minor leacnate composibonal effects ten wrth the high-level waste storage project. Geophysical tech-on the urhrwum crwentrations When leached in the presence niques may help determine the nature and extent of faulting in of i radiaton f*!d, unirrad 114 UCh2) produced elevated urani- the target areas, along with structural information which would um coxentrat,s only in tne br;ne teachates The leaching of be relevant to questons concerning tne future integnty of a both cesium and cdine from spent fuel was rapid and hnear high-leve! waste repository. FoHowing an introductory chapter with the surface-area-to-volume (S/V) rato. Sim;Iar to cesium which descobes the var,ety of geophysical techniques available, and odine, strontium release was strong'y a'fected by leachate subsequent chapters focus on particular geophys4 cal appbcc compositon, wsth greater release associated mth lower pH A tions to four rock types - basaft, bedded satt, domal salt and tuff model descrdng spent fuet/UO(2) dissoluton was developed. - charactenstic of the $4tes onginalty proposed for Ste charac-complement:ng the expenmental stud.es. tert 2aten No cne geophysica; method can adequately charac-tenze the geological structure beneath any site. A combinaten NUREG/CR 4955: LONG-TERM PERFORVANCE OF CONTAIN- of techn, ques is required The seismic reflection method, which ER MATERIALS FOR HIGH LEVEL WASTE. is generaRy cons,dered to be the most incisive of the geophyse MARKWORTH A.J.; CIALONE.H J ; MAJUMDAR.B S , et al Bat- cal techn# ques. has to date provided only marg +nal information telle Memonal Institute Columbus Laboratones November on structure at the depth of the proposed repostory at the Han-1987. 426pp. 8712280053 BMh2155 43821037. ford, Washington,9te, and no useful results at all at the Yucca This report desenbes the results of expenmental and analyte Mountain, Nevada, site. Th:s result appears to be partially due cal studies of high-level waste container degradation Corrosion to geolog, cal complexity beneath these sites, but may also be and hydrogen embntt!ement tests were conducted on selected partia9y attnbuted to the use of inappropnate acquisiten and matenals to identify environmental and meta 9urgical factors that processing parameters it appears that to adequately character-promote matenal degradation, especialty stress-corroson crack- 12e a site u9ng geophys<s, modificatons will have to be made ing. A maior emphats on overpack matena?s focused en :ast to standard techniques to errphas42e stTUClural detaJs at the and wrought low-carbon steels Results of the corrosa 9 work depths of .nterest Show that, to more completely ident.fy potent.al fadure modes, exposure environments mus: be further def,ned Predictons of NUREG/CR 4958: IMPACT OF PROPOSED FINANCIAL ASSUR-pitting rates based on modds utizing nonreactrve watts may ANCC AEOUIREMENTS ON NUCLEAR MATEP'ALS LICENS-lead to rejecton of carbon steci as a viable overpack matenM EM #NDRICKSON P.; SCOTT.M J ; MULLEN.M F.; et al. Rat-when, on the basis of performance. it may Mvm satisf actouy tehe Mernonal Institute. Pacihc Northwest Laborator.es Sepam-Hyd' ogen embntilement was shown to be promoted en regions ber 198L 136pp 8710070036 PNL-6233 42965 018 of microstructural ct ange such as the weld heat affected zone. The NRC is cons.de'ing a pos9ble ruiemaking that would re. Those findings shcw that hydrogeri embntt;ernert is important quire certam matena's I.censees to demonstrate Snanc6al atAty to container integr ty. A small porton cf this task was devoted to dest up acc&nta' reieases of rad.oactive tratenars The to studying the pc asible i.'terna: corrosion c' the canister. It was rulemakeg would octenha!!y affect appronrnate416 350 NRC found that Type $04L statn:sss steel wdl hkely c snia<n h4gNevel ard Agcement Sta'e 14censees This report was prepared to waste g! ass for tne retneval penod and procabh the thermal provide tukground .nformaicn and ana'y9s for the potential penod Modehng stud +es focused m general corrocco are p,t. rutemaking Spec'f.c topcs exam:ned in the report incrude- 1) t.ng corroson, mth the modeis being extended to acccont fo- chara:.tenstcs of potentiaMy affected I,censees. 2) the a<adabit more reatistic cond: tons. Results show that p.t wall reactiv4y is ety and cost of varous f,nancel assurance mechanisms, 3) the an important cces.deraton in pred.ct>ng corros,on rates. financ al impacts to kcensees Onclud.ng :.censees c!assif ed as small busmesces) of p'ovdnq $2V of assurance per kcensee NUREG/CR 4956: SYSTEM PERFORMANCE OF HIGH-LEVEL and a sidng nount of assu'rance tied to nsk, 4) the cost of WASTE PACKAGE COVPONENTS NtCOLOSI.S L . aaministenng a firancial assurance rute. and 5) overa!I benefits KURTH.R.E ; OUAYLE S F ; et al. Battele Memonal Inst 4tute and costs. Tabular informaton on past matenal hcensee acci-September 1987. 279pp. 8710060258 EMi 2156 42921-241- dents and c!eanup efforts is also inctuded The financial assur-This repe 1 presents results of ana'ytca! and expenuentet ance mechanism that appears to be most suitable for provdng studos tha', can be integrated to cescr:be the performance of the desired f,nancial assurance es one or more neMy formed nuclear waste packages at the system level Several water captae insurance companies. Potential benefits of the rutemab l Chem @y modules were developed, and groundwater 4adot ySs ing include administratr,e t:me to secure such funds, and the studies were periormed to esamine the production of rad o%c possbbty of more rapid cleanup with correspond,ng'y reduced species at the outside surf ace of waste packages Uncertainty occupatonal and publ,c exposure to ratoa:tive matena's anatysas stud.es w th a UO(2) water chemis'ry model assessed the importance of input parameters on the vanab6ty of calculat. NUREG/CR 4959: PERFORMANCE TESTING OF EXTREMITY ed solubitties A shell for a corrputer code was developed that DOSIMETERS H ARTY,R ; REECE.W D ; HOOKER.C D. BatteHe provides an attematere method for eramn ng the system pen Memonal Instatute Pacifec Northwest Laboratones June 1987 formance of h>gh levd waste packa;es Ir.tegral espenments 65pp. 8707020364 PNL-6218 41566 202 were conducted to rearnne interact:ons betuen components The Health Physics Society Stand,ng Comm:ttee (HPSSC) of the waste package and repos tc<y hnng ng together ete. Worong G'ovp on Performance Test ng of Entrem'ty Dosimeters ments of reposdorf environments w th ccenponerts of spent fuel has issued a draft cf a preposed standard for citremity do9-waste forms. The system performance invest gatons showed meters The draft standard proposes rnethods to be used for that radclys2s effects are not s,gn,ficant *Nn the gamma test >ng entrem.ty dovmetry systems and the performance cr<te. source is shielded by the o<erpack it was observed that the ron used to determine comphance Th.s study evaluates the producten of oratate is related to the b4 carbonate concentraton draft standard s proposed periormance cr,teron (absolute vaive and dose rate Other modong stud es showed that tre d:swu- of 8 4 S less than or equai 0 35 where B is the bias and S is

Main Citations and Abstracts 67 the standard deviaton) against the periormance of extremity do- in 1974. Table S-3 of the report "Environmental Survey of the simeter processors Twenty-one types of entrernity dosimeters Uranrum Fuel Cycle" was pubbshed as a technical basis for from 11 processors were irrad ated by the Pacific Northwest cons deration of the environmental effects of the uranium fuel Laboratory (PNL) to specAc dose levels in one or more of cycle supporting operaton of light water reactors. A reference seven categores. The processors evaluated the doses and re- reactor cooled with hght. or ordinary, water was establashed to turned the results to PNL for ana:ysis Approx:mately 60% of reduce the bu< den on the Nuclear Regulatory Commisson tho dos 2 meters met the performance critenon. Two-thirds of the (NRC) sta'f, reactor license appbcants, and other interested per. re%ning dosameters had large biases (ranging from 0 25 to sons by removing the necessrty to relitigate the environmental 0.80) but small standard deviatons (less than 015). Recom- effects attnbutable to the fuel cycte, effects that are not within rnendatons to improve the biases include providing cabbratons an appl. cant's control, in every and vidual reactor licensing pro-(usang appropnate irradiaton standards and phantoms) fo!! owed ceed ng In a 1984 evaluaton of a hcense application, it was by another set of performance tests, as well as visrting proces- demonstrated that the Table S-3 estimate of annual effluent of sors to sdentify other possible sources of error. It is further rec- coal part>culates is larger, poss,bly by as much as a factor of ommended that the draft standard be re-evaluated to ensure 100. than actual current values. Partially as a result of this eval-that rt is appropnate for the performance testing of extremity do- uaton, the NRC initiated e study to update all of the ma;or non-simeters, radiological values in Table S-3. The results of the study are documented in tNs update. The report evaluates orVy the NUREG/CR 4962: METHODE TOR THE ELICITATION AND USE mining, mang. and isotopic-enochment components of the fuel OF EXPERT OPiN:ON IN RISK ASSESSMENT. Phase 1 A Cnt'- cycle's environmental parameters since these are the areas en cal Evaluaton And Caectons For Future Research- which the greatest changes from the onginal study could be an-MOSLEHA; BIER V.M.; APOSTOLAKIS.G. Packa'd. Lowe & t>ccated Ganick, Inc. August 1987. 95pp 8709090358 PLG-0533 42566 268. NUREG/CR 4965: TRAC-PF1/ MOD 1 US/sAPANESE PWR CON-The purpose of this work is to entca4y review and evaluate SERVATIVE LOCA PREDICTION GRUEN.G E.; FISHER.J E. the shc1taten and use of espert opirvon in probabilistic nsk as. EG&G idaho, Inc (subs of EG&G. Inc ) November 1987.81pp. sessment (PRA) in bght of he ava' fable emptncal and theoFeta- 8712240021 EGG-2513. 43794:197 cal results on expert opincn use, PRA pra:t<e is reresented This report documents the results of a 200% double-ended, by five case studies selected to represent a vanety of aspects cold- leg break. loss-of-coolant-accdent (LOCA) calcu!aton of the probiom; (1) Assessments of component fa, lure rates and using the TRAC. PF1/ MODI computer code. The reactor maintenance data. (2) Recent assessments of seismic hazard system represen'ed a typical United States / Japanese pressur-rates. (3) Assessments of conta;nment phenomenology. (4) As- tied water rescu with a 15 x 15 fuel bundle arrangement 12 ft sessments of human error rates. and (5) Accdent precursor long. four loops, and cold-leg Emergency Core Coohng (ECC) studies. The review has yicided rmsed results On the negatrve Sy sterns Conservative boundary and inrtial cond: tons were sde, there appears to be httle rehance on normatrve espertise used Reactor power was 102% of the 3250 VWt rated power, in structunng the process of expert opinen elicitaten and use. decay heat was se' to 120*. of Amencan Nuclear Society most appbcations instead rely primanly on the common sense Standard 51. hgMst core lifet me values for power peaking of the experts envolved in the anafysis. which is not always an and fuel stured enny were used. and the LOCA occurred se adequate gwde On the pos.trve sde, however, there is ev>- multaneous'y with a loss of offs >te gewer Best estimate as-donce that expert opinions can in fast be used well in practical sumptons were used for the break flow model, fuel rod heat settings. Suggestons are given for Phase 11 work to ershance transfer and metaLwater reactor correlatons, and steady-state the apphcabety and use of appropnate expert opanon methods. fuel temperature prefdes A fiow blockage model having the; ca-pabaty to account for the effects of cla%ng bafloorung o rup. NUREG/CR 4963. BORCN CARB:DE STEAM REACTIONS tunng. was not used Except for t5ese best estimate assump-WITH CESIUM HYDROXiDi AND WITH CESrVM IODIDE AT tons, the boundary and initial cond t;ons were consistent with 1270K IN AN INCONE'. 600 SYSTEM. ELRtCK.R M.; . nose used in licens4ng calculatons Manmum fuel rod tempera-SALLACH,R.A.; OUELLETTE.A L; et al Santa Natonal Lab- tures were 1380 K (2020 degrees F) and 1040 K (1410 degreet oratones August 1987. 82pp 8712010140, SAND 871491. F) on the hottest evaluaton model rod and hottest best esb 43486 017- mate rod. respectrvely The high reported values for fuel clad-Three laboratory sca:e tests examined the effect of boron d,ng temperature were a direct consecuence of the conserva-carbde. used for the control of some nucicar power reactors. trve boundary and init.al cond. tons used for the calculaton. pn-on reactor accdent co-Stions The tests conducted in steam manty the 2% overpower cond: ton, the core decay heat as. at 1270K in an inconel 600 system examined the boron arbde sumpton, and the degraded ECCS. The calculation demorstrat-

   - steam system and then that ,ystem with an additen of cessum        ed successful core refiood.ng before 1478 K (2200 degrees F) hydronde or ceseum cd.de vapor. Extensive reacton was dem-           clanng tempe<ature was exceeded on any fuel r+.L onstrated between the boron carbide and steam to produce B(2)O(3) and bonc acds in a two step Onetc process Average          NUREG/CR 4966 V01: EVALUATION OF OPERATIONAL l   rates of producton for the orde and acids were caict. lated for      SAFETY AT BABCOCK AND WILCOX PLANTS. Volume 1 Re.

the three tests These rates are funct,ons of time, temperature, su,ts Overvew. HANSON.0 J.; MEYER,0.R ; BLACKMAN.H S.; B(4)C geometry. and patal pressure of tho steam and the bonc et al. EG&G Idaho, Inc. (subs of EG&G. Inc ). October 1987. acd Sqnif, cant reactons were cbserved between the bonc 198pp 8712280204 EGG-2515 43817 061. onde formed on the B(4)C and both the CsOH vapor and the A methodology was deveioped ;o assess the operational per. Csl vapor, d ssociatng the cesium and cdine in the tamer case. forrnance of nuc' ear power plants through an integraton of ther. The cesium reacton product in both cases was probatdy mal-hydravhc and human factors ana'ysis techniques together CsBO(2), w.th the cd2ne forming Hl. Surf ace reacton rate con- w:th inputs from enformaton used in the assessment of nsk. stants were estimated for the CsOH and Csl reactors This methodology was appled to evaluate the extent to which pfant systems and/or operator actons are effectrve in lessening NUREG/CR 4964: UPDATE OF TABLE S-3 NONRAD:OLOGICAL the seventy of selected trans.ents for Babcock and Wilcox ENVIRONVENTAL PARAVETERS FOR A REFERENCE (B&W) plants Ccmpansons *cre also performed to assess dif-LIGHT WATER REACTOR Uranrum M ning Mung And Enr,ch- ferences in operat onal cerformance capabitties and Imstatens ment HABEGGER.L J ; CARSTEA.D D . OPELKA.) H Argonne tetacen seiected Combuston Eng'neenng West;nghouse, and Natonal Laboratory June 1987 6 App. 8707010655 ANL/EES- B&W plants Dota l:1 resuns from the methodology app 4 cation TM 332. 41545 268 are presented in t*o volumes Volume 1 presents an ovr;rview

68 Main Citatbns and Abstracts of the results with emphasis on the systems and operator per- m:1secton of the cyhnder exceeds the ultimate strength of the formance Volume 2 presents detaded results from thermabby- bar sphces. drauhc calculatons. NUREG/CR-4970: STAINLESS STEEL ROUND ROBIN NUREG/CR 4966 V02: EVALUATION OF OPERATIONAL TEST.Centnfugany Cast Statniess Steel Screening Phase SAFETY AT BABCOCK AND WILCOX PLANTS. Volume 2 BATES,0 Ja DOCTOR,S R : HEASLER.P.G.; et al. Battelle Me-Thermal-Hydraulic Results. WHEATLEY P D.; DAVIS C.B4 nonal Institute, Pacific Northwest Laboratones October 1987. CALLOW.RA; et at EG&G Idaho, tnc. (subs. of EG&G. Inc ) 264pp. 8710290281. PNL 6266. 43216 260. November 1987,284pp. 8712310121. EGG-2515. 43869 088. This report presents the results of the Centnfugally Cast The Nuclear Regulatory Commisson has initiated a research prograrr. to develop a mc*-dology to assess the operat.onal Stainless Steel Round Robin Test (CCSSART). The CCSSART is the first phase of an effort to investigate and improve the ca-performance of Babcou ar.d Wilcor piants and to apply this pabihty and reliabihty of NDE inspectons of CCSS This phase methodology on a tnal bas.s. The methodology developed for was a screening test to ident;fy the most promismg procedures anatyring Babcock and Wilcox plants integrated methods used presently available for CCSS The next phase will be a more in-in both thermal-hydraubcs and human factors and compared re- depth program Fifteen centnfuga4y cast stainless sleel pipe suits with information used n the assessment of nsk. The inte* sections containing welds and laboratory-grown thenTul fatigue grated methodology involved an evaluaton of a selected plant cracks in both columriar and equiaxed base matenal were used. for each pressunzed water reactor vendor dunng a lim >ted These pipe specimens were inspected by a total of 18 teams number of transsents. A plant was selected to represent each from Europe and the United States using a vanery of NDE tech-vendor, and the three transients were ident fied for anarysis. nques, mostly U'trasonic. It was anticipated that the anisotropic The plants were Oconee Unst 1 for Babcock and Wilcos, H B. and coarse-gra'ned structure of the specimans would present Robinson Urvt 2 for Westrnghouse, and CaNert Chffs Unit 1 for the inspecting teams w1tn the problem of not only detectog the Combuston Engineenng The three transients were a complete cracks but also of property classifying uncracked matenal Thus, loss of all feed *ater, a smat break loss-of-coolant accident, measurement of team performance included results in both and a steam-generator overfoi with aurihary feed *ater included cracked and uncracked matenal. Some procedures showed in the integrated methodology was an assessment of thermal- promise, however, becane of the high number of f alse crack hydraulic behavor, including event timing, of the plants dunng calls reported by many of the inspecting teams it was difficult to the three tranuents. Thermabhydrauhc results are presented in demonstrate that some of tne procedures could effectively dis-this volume (Volume 2) of the report An overwew of a!! results-enmenate between thermal fategue cracks and uncracked CCSS. with emphasis on operator and hardware performance, is pre. The results of the CCSSRAT make it apparent that a mort. de-sented in Volume 1. tarted study on the capabitty and rehabihty of procedures to in. NUREG/CR 4968: EVALUATION OF UNCERTAINTTE .N IRRA- spect stain ess stael matenals is needed to better understand DIATED HARDWARE CHARACTER!ZATION. GEDOM N ; the specif,c matenal and flaw properties and how they affect the LEVlN.A ; TUITE,P. Waste Management Group, Inc October outcome of an inspecten 1987.102pp. 8711030139. 43242 062 This report evaluates the technques used 5y industry h char- NUREG/CR-4972: TWO-PHASE FLOW REG lME TRANSITION actenze and classify irra6ated hard*a'e components for d>s. CRITERIA IN POST-DRYOUT REGION BASED ON FLOW VIS-postl in accordance w<tn the requiremen!! of 10CFR ? art 61 UAll2ATION EXPERIMENTS OBOT,N T , ISHil,M. Argonne Na. and the uncertainties associated *:th appbcaton of these tech. tonal Laboratory M e 1987 56pp 8709030565. ANL-87 27, rbques. It descnbes current methods and practices. >dentif.es 4 the uncertarnties associated with the methods and practices A visual study of film boikng usag photographic and high censdered, and recommends areas for improvement which ipeed moton-picture m3thods was camed out to determine the could reduce uncertainty. Two d:fierent charactenrat,on meth. flow reg +me transton criter a in the post CHF region. An deal-orjs are desenbed The first uses a combirator. of gamma god inverted annutar flow was obtained by introducing a Iquid sm g. direct saraphng, underwater rad.aten profihr,r, and ra- let of Freon 113 through a nozzle, precisonly centered with re-docNmical ana'yos to determine radenuchde content. whde spect to the internal dameter of the test sectron, with an annu-the second uses a form of activaton anahsis in conjuncton lar gas flow The respect <ve ranges for Iquid and gas exit ve-with underwater rad.aten prohnng Both methods employ two loc t.es were 0 05-0 5 and 0 03 7 9 m/s Nitrogen and hehum distinct steps; (1) the determinaton of Cobatt-60 content and (2) were used in the study For the present conf.guratcq, there are the detemmaton of scahng factors for hard-to-detect Pa'161 four twc fiow reg,mes Beg:ne ng from the nozzle esit. there is radonuddes Current uncerta.nt es in Coba:t 50 determ naton smooth, inverted annu!ar flow sect.on with liqud in the cu e and l can be reduced by improving underwater ra$at on prothng gas in the annutut., fo!! owed by the rough navy secton witn an equipment and techniques The ca!cu!atenal techn+ ques used intact howd core, the ag:tated and the d,spersed flow reg +mes. for actrvaten analysis can a!so be rehned to reduce the uncer- For a gwen houd jet velocity. the anal extent of each flow taint.es **th Coba't 60 determ.raton. Improved rad ochemical reg me decreases *:th increasing gas velocity through the annu-ana'yts techniques, and the development of a stabsticaly s>g- lus Generabzed trans;t,on entena and simphfied correlatons for n6 cant set of component compos: tion data would e'.m:nate the antal hmits of the varcus flow regimes have been devel-some of the conservatsm in current scahng f actor determina. oped. by entend ng the results of prevous stud.es on adiabat>c ta inver1ed annular f;ow NUREG/CR 4969: ArSYYYETRIC ANALYSIS OF 16. SCALE NUREG/CR 4973: INTRAPLATE SEISWCITY OUTS!DE OF THE REINFORCED CONCRETE CONTA!NVENT BU LDiNG US;NG UNITED STATES SCH AEITZER.J ; GLOVER.L. wrg1nia Poly. A DISTRIBUTED CRACKING MODEL FOR THE CC'NCRETE technic Institute & State Unw Blacksburg VA Ju!y 1987.88pp WEATHERBY,J R Sandia Natonal Laboratones September 6708040243 42036 327

 ?987. S0pp 8712260239 SAND 871670 43820 204                           A survey cf intraplate se smicity in eastern Canada, Austraha, Resu5 of ansymmetnc structural ana'yses of a 16-scc e            and western Eurcpe was unde ta=en Eastern Canada has been model of a reinforced concrete nuc! car conta-nment budd ng are     dmded into four seismic zones, namely. LaVaiba e (Ovebec).

presented Both a fate element shell ana'ysts and a sepkf ed westem Oucbec, New Bru ns*ick. and Ba" n Island Austraha, a membrane analys;s were made to predict the structural re- relatwefy ase,sm>c cont.nent surrounded by very seisinicaUy sponse and ultimate pressure capacsty of the model MaWcal actwe areas has been d vdad into three seismic zones, west-results ar@cate that the model wdl f arl at an intemal pressure of ern Austraha. south Aust'aha and rf astern Austraba intraplate 187 p9g

• ten the stress level in the hoop reinforcement at the se<smicity in western Europe is concentrated in central and

Main Citations and Abstracts 69 northern Europe Based on this survey, several general obser. Native vegetation associated with commerciallow-level waste vatons about intraplate se smcty can be made Much of the o sposal s:tes has the potential for mod >fying the soil chemical seismic activity in these intraprate reg:ons is re!atrvely sha3cw eneronment over the long term and, consequently, the mobdity and is frequently locahzed in basement rocks Seismic events of radonochdes These effects were assessed for coneferous are frequently attributed to movement along pre-existing fatts, and hardwood tree spec.es by using plants grown in lystmeter although surface faJting rarely accompanies these eadh- systems and examining their influence on sod soluton chemistry quakes Paleo-nft zones seem to be particularly suscept.ble to us>ng advanced analytical and geochemical modeling tech. reactivaton. Plate interactons and asthenosphere drag both niques The study demonstrated formation of highly mobile ani-play a role in development of a reg <onal honzonal maomum onic radonuchde complexes w'th amino acids, peptides, and or-poncipal compressive stress, but the actual tnggenng mecha- ganic ac<ds or9nat;ng from plant leaf I;tter and roots. The pro-nism and locahzaton cause for this fault reactivation in intra. duction of Complex ng agents was related to season and tree p! ate regions is st;li only poorfy understood speces, suggest ng that vegetaten management and excluson NUREq/CR 4974: INTRAPLATE SEISMICITY IN THE EASTERN may N annate a% a site is closed This research pro-UNITED STATES. BOLLINGER.G A: EHLERS.E G ; vdes a basis for focusing on mey compleang agents in future MOSES M J V.rgna Po!ytechnic institute & State Unry . Blacks- Me m mm mM a% mes W m upam burg, V . July 1987. 28pp. 8708040340. 42036.001. si rmaton into mathematical models descnbing biological Causes for intrap! ate carthquakes in the eastern United " "'"d " C * * #Y States are indeed complex On a regonal sca'e. eartnquakes NUREG/CR 4378: THE COOLDOWN ASPECTS OF THE TMI 2 are spat.a4y and tempora 4y stat;ona y. at least on a scale of ACCIDENT. THECFANOUS.T G Cahfornia, Unrv. of. Santa Bar-decades. Spat aPy. the setsmcty occurs in distinct zones super- bara. CA August 1987. 63pp 8709150313. 42678 239. posed on a less act:ve reg onal background level Histoncany, The cocMun of the TM!-2 reactor vessel due to high pres. moderate to large earthquakes hase occurred within the seismic su r e ingt.on that occurred at 200 minuters into the accident is zones defined by microse:smoty Recent pa!eoseismic@ stud- re- examined Flow regimes and condensaton heat transfer in ies suggest that these larger earthquakes can reasonably be the cold legs and downcomer are consdered The presence of expected to occur into the future Earthqua'e loca: depths in nor'condens:btes (hydrogen) and a mechanism leading to its ac-the eastern U S tend to be w' thin the upper crust w th 14ttie rela-tion to surfcai ;eatures Because most castern U S se'sm.c cumutaton a*ound the condensaten interf aces lead to conclu-sors that are matena9y d tierent from those of a prevous study zones are buned in the subsurf ace, geophysical methods are that dd not consder these effects. used to infer the presence of poss.ble causa! geolog'c st uc-tures at depth Gracty data are useful in locating ders.ty (htho- NUREG/CR-4981: A SAFETY ASSESSVENT OF THE USE OF Mc) changes *: thin the crust and seismic act:vity tends to GRAPHITE IN NUCLEAR REACTORS LICENSED BY THE U S. concentrate w th.n grarty sadd:es formed at the intersect on of N9C SCHWEITZER D G.. GURINSAY.D H ; KAPLAN.Ea et at northeast and roewest trend ng graety ancmakes Seesmicary Brco haven Naticnal Laboratory September 1987. 42pp important plutons ed Tnassic basins wh<h are associated w.th 89 w,0161 BNL-NUREG-52092 42921096 seismic actrvity ha<e been located by their magnetic s>gnatures Tw repcxt revic*s costing Lterature and knowledge on The eastern U S is intepreted to be composed of a tes&c of graphte burrang ard on stored energy accumulaten and rm a!1ochthonous suspect terranes Th s hypothesas suggests that leases n e der to assess what role. if any, a stored energy re-block boundar+es are zwes of crusts weeness lease can have in in tiating or contribut.ng to hypothetica! graph. NUREG/Cm4975: A PEviEW OF THE RESOLVING POWER OF te burn:rg scenarcs in resear;h reactors it a'so addresses the REFLECTICN SEISYCLOGY VETHODS TO DETECT S U B. gest n el graphae ign ton sad sc:f sustained combustion in SURFACE FAULTS AND/CR CHANGES IN LAYER TNCK- the event cf a less-of coolant acc dent (LOCA) The cond. tons NESS COSTA!N.J K . CORUH C Virg>nia Poly 1echnic inst.tute & necessary to otiate an1 ma nta n graphite burning are scmma-State Unry . Blach sburg, VA JJy 1987 37pp 8706050045 nzed and discussed From anaby ses of onst,ng informaton it is 42062 110 concluded that on'y stored ereg, accumuiatons and releases Aspects of the reservir.g power of se:smic reflection data in be c* the bu+ning temperatur e (650 degrees C) are pertinent it detecting sutsurface fautts are revewed Resolut,on by refac. rs shewn that trere is no e<dence from the Cherncbyl event ton seis'nolCgy of d<splacements across subsurface f adts is tha! Stored energy re! eases played a role e,ther ntiating or Con-coup;ed *.tn the detect <n and resciut on of th-n beds Limts of intutag to tNs acc. cent The conclus ons from these andyses detal that can be derNed from sersm*c data are greatty affected are that the pctent a1 to At>3te or ma<nta n a graphito burning by data acquis tecn and process.ng parameters Ternporat and 'nce 91 is essent.aby indmcndent of the stored energy in the spat <al band *4tns as keys for seismrc resotuton are deter, grapha ard depends en other f actors that are unque for each mined by source, record ng system, absorpt>on. pa". erns. tempo- '05ed'ch reacts aro f or Fort St Vra n There is no new evi-ral frequency range, group interval. temporat and spat!al rose dor.ce assoc ated *.th ener the W'ndsca'e A:cdent or the Opt. mum t,me wavetets are irrportant for manmum resobt.cn in Chernce,i A:c dent tra' rd. cates a credib!e potent 1al for a time *Nch a'so adects resoyt'on in t*e spat al domain Re gra;Me burmg accdem in any o' the reactors cons dered in sponse of v brators and the use cf fc<co control units are re. W5'e"'A viewed a'ong a th the eFects of source and recever array s N U R EG /CR-4982: SEVERE ACC4DE NTS .N SPENT FUEL used dunng data a:Qu s,t cn Phase changes due to decoupung and phase compersaten are tocbded rn tre d scussicn The FOCLS IN SUPFCRT OF GENERIC SAF ETY ISSUE 82. SA1C4 'v L PERCNS A R , ' EE AS J R et af Broothaven importance of ta anctng the eMeets of mt'.nsic dampag before N E onal Latc a cry uy 1987 Itfpp 8708120084 BNL-e stack is d'sct ssed as are the e"ects cf data

• ndwng m t>me pg gg g g and space Parameers a"ectmg resch tan a;ong t+me and spa TM megeon provces an assesswnt of the Mehhood t al aves are g ven to show trat tre Fresnel zone mtroduces an g cy, important I.maa:on on tre detal that can be dermed from se s , a d a we C&r t m a wt W s'org mic data p.g . gg gy.pte m mng o' the fool Pctent a! rrechamsms and core t er-s for f ave cf the spent fuet and the subsequent NUREG/CR-4976: PLAM FMZCSWERE FROCESSES INFLU- recas d *e 'ss on recuts are demud Two c: der PWR ENCiNG RADiONUCUCE VCB UT v W SO:L CAT AL DO D A . anj B A R scert V storago EW des gns are consdered based COWAN C E . UCF ACDEN K V . et a Baven e Memonal Instr on a p'emne< screen ng stud, wren toed to dent $ wnera-ffe. Pave N orth
• est Latcatones OcMer 1%7 7Erp t Mes inw na- a^d edernai c<ents and a certs are as-8711160184 FNL E277 43371242 se w d Camrs *Ncn cWd 4 a1 to fadure of tN spent fo l a

70 Main Citations and Abstracts Zi caloy cladding as a result of cladding rupture or as a result of estnbuton of ra6aton dose in tissues of three species of ani-a self susta:ning oxidaten reactron are presented. Propagation mais exposed to representative aerosols collected from the in-c, a cladding fee to older stored fuel assembles is evaluated. dustr,al faciht>es. These inhalation studies provide a basis for

 ' pent fuel pool fissaon product inventory is estimated and the        comparison of the influence of physical chemical form of the in-releases and consequences for the vanous cladding failure sce-        haled particulates and the vanabikty among species of animal in nares are novided. Possible preventrve or mitigatue measures           the radiaton dose to t ssue. The third chapter details the rela-are qualitatrvely evaluated. The uncertainties in the nsk estimate     tonship between radaton dose and bological response in rats are large, and areas where additonal evaluatons are needed to          exposed to two aerosol forms each at three levels of initial pul-reduce uncertainty are identfied.

monary burden. TNs study, conducted over the lifespan of the NUREG/CR-4983: THE SEALING PERFORMANCE OF BENTON. rats and assuming results to be applicable to humans, indicates ITE/ CRUSHED BASALT BOREHOLE PLUGS. WILLIAMS,J R.; that the hazard to health due to inhalaton of these industnal DAEMEN.J J. Anzona, Unrv. of, Tucson, AZ. November 1987. aerosols is not different than previously determined for laborato-273pp. 8712240101. 43795 321. ry produced aerosol of PuO(2) Mixtures of crushed rock and bentonrte are considered for back filhng and seahng high level nuclear waste repositones. NUREG/CR 4987: SIMULATED SEISMIC TESTS ON 1/42 AND Many vanables affect the hydraulic conductmty of such mix- 1/14-SCALE CATEGORY 1, AUXILIARY BUILDING. tures, including the size and shape of the rock particles, method BENNETT,J.G ; DOVE,R C.; DUNWOODY,W E.; et al. Lc4 of mix:ng and emplacement, water content and dens;ty of the Alamos Natonal Laboratory. Oceber 1987. 42pp. 8712020016. clay, and the weight rato of rock to clay. Mixtures of crushed LA-11093-MS 43521:138. basalt and bentonite have been tested in two types of permea- Two scale-model structures representing an ideahzed auxiiiary meters, 20 cm (8 in) dtameter stainless steel permeameters and building were seismically tested The scales (1/42,1/14) were 10 cm (4 in) diameter PVC permeameters. Plugs were installed chosen so that both structures were models of the prototype, as a ssngle lift or in many hfts; the water content of the clay and 1/42-scale model was a 1/3-scale model of the 1/14 scale ranged from air-dry (in most cases) to as high as 200%. Prelime- structure. Both models were constructed out of microconcrete. nary results show that mixture of 75% crushed basalt and 25% The 1/42-scate used wire mesh to simulate reinforcing, and the bentonite has a hydraulic conductmty between 1 x 10( 9) cm/s 1/14 scale used model deformed bars. The general result ven-and 2.5 4 1008) cm/s. In some cases, preferential flow oaths fed prevous test expenence in this program: the frequency re-have devebped (possibly as a result of the rnontmonllonste sponse of these structures. when subjected to seismic design washing out :;f the Crushed rock matnx), gmng hydrauhc con- loads, will be below that predicted from the ctructural analysis. ductmties as Ngh as 1 x 10(-4) cm/s, Other catos of rock to The imphcaton of this resutt for equipment & pipeg is under in-clay have s4melar banodal resutts The probabihty of failure is de- vestigatiort The recummendaten of tNs program, based on creased by including a Ngher percentage of clay in tne plu9 testing thus far, es to verify the conclusons on larger real con-crushing the rock frer, and evenly mixing the crushed rock and crete structures of a geometry that ett be agreed upon by the ciaf technical review group for this program. NUREG/CR 4985: INDIAN POINT 2 REACTOR COOLANT PUMP SEAL EVALUATIONS. SUBUDHl,M.; TAYLOR.J H. Brookhaven NUREG/CR-4988: A TR AC-PF1/ MODI ANALYS!S OF THE Natonal Laboratory. August 1987. 96pp. 8712160083. BNL. GINNA TUBE RUPTURE EVENT ON JANUARY 25,1982. NUREG 52095. 43729.184 LIME J F.; JENKS.R P. Lor. Alamos National Laboratory. Octo-TNs report summanzes the find.ngs on Westinghouse Reac. bor 1987. 61pp. 87120202vh LA 11094. 43521:186. tor Coolant Fump Seal Performance at the Indian Point 2 Nucle. The R E. Genna steam-generator tube <upture (SGTR) event ar Power Staton. The study was conducted under the joint on January 25,1982, was simulated using the Transient Reac-sponsorshp of Consolidated Edison of New York and the U S tor Analysas Code TRAC-PF1/ MOO 1, verson 12 3. A complete Nuclear Regulatory Commisson Off>ce of Research. The con. TRAC model of the Genna piant was developed and the SGTR clusaons and recommendations herein are based on the review event was calculated to 5000 s. The overall plant behaver was of the plant operatonal and maintenance data on seals, consul- simulated, mth excellent to reasonable agreement obtained be-taton with Westinghouse and Utilities, rev>ew of pnor studies, taeen calculated results and measured data. A pomary obt ec-and visual as well as in-depth examinaton of service exposed trv e of calculating and matching the actual reactor tnp time was seals recewed from the plant. acNeved. The analys's demonstrates that TRAC can accurately NUREG/CR-4986: RADIATION DOSE ESTIMATES AND simulate Mscale plant SGTR transents. HAZARD EVALUATIONS FOR .NHALED AIRBOANE RADIONUCLtDES Foal Report. MEWHiNNEY,J A Lovelace NUREG/CR 4990: HEAVY-SECTION STEEL TECHNOLOGY B & vw arch Institute September 1987 PROGRAM Frve Year Plan FY 1986 1990. PUGH'C E. Oak Rdge Natonal Labo'atory September 1987. 189pp. TNs is the final report for a project whose obrective was to GEN NUEN6 W4M conduct confirmatory research on physscal chemical charactens. 1he fourth in an annual senes of five-year program. plan docu-tics of aerosols produced dunng manufacture of mixed plutons- ments is presented for the Heavy-Secton Steel Technology um and uransum orde nuclear fuel, to determine the rad 4aton Program. The program is carnad out by the Oak Rdge Natonal dose distnbuton in trssues of animals after inhalaton exposure Laboratory for the Matenais Engineenng Branch, Dmsaon of En-to representatrve aerosols of these matenals, and to provde es. gmeenng. OMice of Nuclear Regulatory Research of thc U S timates of the relatonsNp of radiation dose and bolog<al re. Nuclear Regulatory Commisson. The program is aamed at ad-sponse in animals after such inha!aton exposure. Th s report is vancing the understandog and va;daten of matenals and struc-duded into three chapters wh.ch summanze the results of tures behaver as they relate to hght water reactor pressure. these investigatons. The f,rst report chapter summanzes the vessel intognty. The program has eleven technical tasks and a physcal chemical charactenzation of samples of aerosols col. management functon. A background statement and a plan- of-lected from gloveboxes at industnat facdit>os dunng normal ep. acton is grven for each The eleven technical tasks address eratons TNs chapter provdes insights into liey aerosol chara - fracture methodology and ana'ys.s. matenats charactenzaton, tenstics wNch are of potential importance in determirung thJ bi- crack growth, crack arrest, trradaton effects, claddrng evalua-ological fate of specific radonuchdes contained in the partcu- tons, intermed+ ate. vessel testing. thermabshock testing, pres. late that would be chaled by humans following accidental re- Sunted thermabshock expenments, pressure vessel research lease The second chapter desenbes the spatial and temporal users' facihty, and sNpf*ng-cask matenal evaluatons

Main Citations and Abstracts 71 NUREG/CR 4995: EXPER! MENTAL ASSESSMENT OF THE NUREG/CR 5006: PRA APPLICATION PROGRAM FOR INSPEC-SEAUNG PERFORMANCE OF BENTONITE BOREHOLE TION AT OCONEE UNIT 3. GORE B F.; VO,T.V.; HARRIS,M S. PLUGS. SAWYER,W.Da DAEMEN.J J. Arzona. Urw. of, Battelle Memonal Institute, Pacific Northwest Laboratones. Oc-Tucson, AZ. October 1987. 307pp. 8711100270. 43343.010. tober 1987. 65pp. 8710290130. PNL-6291. 43220:101. Bentorste, which contains the clay mineral montmonilonite, is The extensrve Oconee-3 PRA performed by EPRI has t~ an being considered as part of a multi-component engineered bar. anatyzed to identJy plant systems and components important to ner whsch will seal geological repositones of hgh-level radioac. minimizing public nsk, and to dentify the primary failure modes tue wastes. Four phases of laboratory testing were conducted of these components. This informaton has been tabulated, and to quantfy bentonite strength and seahng properties. Chemical correlated with inspecton modules from the NRC Inspection analysis revealed a

• de range of compositons for commercial and Enforcement Manual. The report presents a senes of well-seahng grade bentonites such that bentonite Quality control tables, organized by system and prontized by puble nsk (in or specifcatons may be necessary. Reference test 2ng of seven person-rem per year), which dentify components associated bentonite samp!es revealed senous testing problems that make with 98% of the inspectable nsk due to plant operaton. Exter-bentonite charactenzaton difficult using standard tests. Perme, nal events (earthquakes, tornadoes, fires and floods) are not abihty testing compared the water flow through bentonite to 'ddressed because inspections cannot directly minimize the water flow through intact rock. Compacted bentonite seats ex. nsks from these events, however, flooding caused by the hibited hydraul< conductmties in the 10(.9) to 10( 11) cm/s breach of internal systems is addressed. The systems ad-range, which is one to hvo orders of magnitude greater than dressed, in descending order of nsk importance, are: Reactor that of some intact Columbia plateau basalt specimens. Me. Busiding Spray, R B Cooling Condenser Circutating Water, chanical testing included direct shear strength and swelling Safety Rehef Vafves Low Pressure Injecton, Standby Shutdown pressure tests. Direct shearing of compacted bentonites re. Facility High Pressure injection, Low-Pressure Service Water, veaied that for both unsaturated and saturated test conditions, and Emergency Feedwater. Thss ranking is based on the the bentonite / basalt interface wdl fail in shear before the intact Fussel Vesely measure of nsk importance, i e., the fracton of bentonite plug itself fads. Sweihng pressures generated by hy, the total risk which involves fadures of the system of interest.

drating bentonites depend upon dry dens 4ty, maing and saturat-ing flud, and method of pressure measurement. Swelling pres- NUREG/CR 5007: PREDICTION AND MITIGATION OF ERO-sures in excess of 1.7 MPa (?50 psi) were measured. All re- SIVE-CORROSIVE WEAR IN SECONDARY PIPING SYSTEMS OF NUCLEAR POWER PLANTS. KECK,R G.: GRIF FITH,P. suits, espectaHy numencal ones, depend on numerous instafla-ton and test parameters. The sensitmty can be quite hegh. Van- Massachusetts Inst,tute of Technology, Cambodge, MA. Sep-tember 1987. 46pp. 8710050583. 42911:163. atons of several orders of magnitude in hydraulic conductmty This report presents equatons and parametnc curves to pre-can be expected for relatuely small vanatons in some installa-ton or test procedure aspects. $ct erosmorrosive wear rates in low carbon steel secondary piping s/ stems of nuclear power plants. Two mechanisms caus. NUREG/CR 5002: METHODS FOR RECURRING LOSS TESTS ing the wear are dent; fed and anatyt,c egy %ons to pred<t the wear are presented One mechanism, we due to oxde JOHNSTON.J W ; LITTLEFIELD.J; KINNISON R.R.; Et al. Bat-telle Memonal Inst 1ute, Pacac Northwest Laboratones Septem- dissoluton, is present in single and two-phan flow lines; the ber 1987. 58pp 8710080312. PNL-6249. 42990.261. oths, wear by dNplet impact induced f atgue, is only applicable for two-phase flows Parametric curves are presented to predict Dwetopment of a program to use matenal control and ac- the essoluten wear as a functor o' 'emperature, OH and char-counting data for detecting recurnng losses of nuclear matenaf is desenbed and some potential statistical methods are dis- attenstic (fncton) velocity. An alg *braic exprespor, is used for cussed A moving sum test, including a moving vanaton for droplet impact wear predictons as ra ancton of weicial gas fafse a' arm control, is desenbed. Three non-parametnc tests are velocity and thermodynamic quahty. Four mit9aton strateges incorporated into the models (alloyino, pH increase, moisture re-d'scussed because of simplicity of use and because an estima-moval and velocity decrease) are in'roduced and the effective-t.on of the varance of the process difference is not required ness of each is discussed. The model= wear predictons are not Consderatons for a computer system to collect and process re-curnog loss test data are ident; fed and discussed. expected to be quantitatuely exact. bu' *hould yield accurate Quaktatue rankings of systems susceptible to erosue-corrosue damage NUREG/CR 5003: DESIGN OF A MATERIAL CONTROL AND ACCOUNTING SYSTEM TO PROTECT AGAINST CONCEAL

• NUREG/CR 5008: DEVELOPMENT OF A TESTING AND ANALY.

l MENT OF DIVERSION BY FALSIFICATION AND COLLUSION- SIS METHODOLOGY TO PETERMiNE THE FUNCTIONAL I SMITH,8 W.; LEWIS.P.M ; BvERS,K.R.; et al. Batteile Memonal CONDITION OF SOLENOID OPERATED VALVES. Insttute, Pacac Northwest Laboratones. October 1987. 69pp- MEININGER R D ; WEIR,T.J. Pentek, Inc. September 1987. 8710270061 PNL-6308. 43188 309- 35pp. 8710060130 42921.060. This report provdes guidance for incorporating checks and This report descrees the Phase i SBIR research conducted ba!ances in a nuclear matenal control and accounting (MC&A) to develop and test a techniqus to deterrane the functonality of system to control and detect faisificaton of data and reports solenod operated vanes (SOVs) in a nuclear plant based on that could Conceal diversson of nuclear matenal. Data f alsifica- the measurement and anafysis of inrush current. The technique tons may be ddfacutt to d stinguish from mistakes in the data. developed uses a chp on current probe, thus enabling ail meas. The elements of control for data fa@f<aten are similar to exist- urements to be made from outsde tha reactor building without ing secunty and account;ng internal controls Potential mecha- disturbing any electncal connections. The inrush current to the nisms for data fa!sif<aton are dentified and intemal controls so!enod operated vane is analyzed in real time using a person-are d.scussed Process monitonng systems supplement trad> al computer and Fast Founer Transform (FF1) techno;es tonal MCA A by proveng more time'y detecton of dryerson and improved locahzaten of losses, thereby providing add <tenal NUREG/CR 5010 RELAPS/ MOD 2 ASSESSMENT US!NG SE. Controls aga:nst data fa!ssfecaton However, there is a tradeoff MISCALE EXPERIMENTS S.NH 1 AND S-LH-2. YUANN.R.; in that personnel who have access to matenal are generating LIANG,K ; JACOBSON J L. EG8G Idaho. Inc (subs of EG&G, data for MC&A Possibates for colluson invoNing a person inc ) October 1987. 73pp 8711230401. EGG-2520, 43425.231 having bon physical protecton and MC& A responstehties and This report presents the results of the RELAP5/ MOD 2 post-another person haeng MC& A responstatres are identified. test assessment utMzing two small break loss-of coolant acci-Methods for protect 3ng the system aga,nst a cotiuscn threat are dent (LOCA) tests (S-NH 1 and S-LH 2) *'hich were performed d<scussed in the Semiscale Mod-2C facaty Test S-NH.1 was a 0 SN

72 Main Citations and Abstracts small break LOCA where the hsgh pressure intecton system NUREG/CR 5017: LIMESTONE CONCRETE AEROSOL EXPERl-(HPIS) was inoperable throughout the transient. Test S-LH-2 MENTS IN STEAM AIR ATMDSPHERES NSPP Tests was a 5% small break LOCA invofving a relatrvely high upper- 521,522.And 531. Data Record Report. TOBIAS.M La head-to-downcomer insteal bypass flow and nominal emergency ADAMS.R E. Oak R<ge Natonal Lacoratory. October 1987. core cooling. Through compansons between data and best esti. 64pp.8712080385. ORNLM M 10587. 43590.131. mate RELAPS calculations, the capabihties of RELAP5 to calcu. This data record report summanzes the results from two tests late the transient phenomena are assessed. For S-NH 1, em- involving limestone concrete test aerosol in a steam-air environ-phasis was placed on the capabihty of the code to calculate ment and one test in a dry air enveonment. This research spon-varcus operator actons to initiate core heatup in the absence sored by the U S. Nuclear Regulatory Commisson was conduct-of HP!S. For S LH-2, the capability of the code to calculate ed in the Nuclear Safety Pilot Plant at the Oak Rdge Natonal basic small break system response, such as vessel level dunng Laboratcry. The purpose of this project is to provde a data loop seal formaton and cleanng, break uncovery, and pnmary base on the behaver of aerosols in containment under conde pressure response following accumulator injecton, was as- tons assumed to occur in postulated LWR accident sequences; sessed. this data base will provde expenmental validation of aerosol be-havoral codes under development in the report a brief oescnp-NUREG/CR 5011: APPLICATION OF THE ADAPTIVE.PREDIC. tion is grven of each test together w,th the resuits in the form of TlVE CONTROLLERS TO PLANT SAFETY SURVEILLANCE tables and graphs. Included are data on aerosol mass concen-UTILIZING ON LINE PLANT ANALYZER. FABIC.S. Dynatrek, tration, aerosol fallout, and plateout rates. total mass fallout and inc. October 1987.141pp. 8711250160. 43461:002 plateout, aerosol particle size. vessel atmosphere pressure, The plant safety surveillance concept described herein aims vessel atmosphere temperatures, temperature grad.ents near at ccit;nuously providing informaton which is not accessible the vessel wa!I. and steam condensaton rates on the vessel wal through measurements and which, in conjunction with existing plant data, offers promise for a thorough understanding of the NUREG/CR 5025: EXPERA8 ENTAL STUDIES OF THE EARLY plant status and of the causes of upsets when they occur. The EFFECTS OF INHALED BETA-EMITTING RADIONUCLIDES concept is based on using the Plant Ana!yrer Controller, which FOR NUCLEAR ACCIDENT RISK ASSESSMENT. Phase ll works in tandem with the Plant Anatyrer, to control inputs to the Report SCOTT,8 R ; HAHN.F F ; NEWTON G J ; et al Inha!a. Plant Analyzer so that its outputs continuously track the select' ton Toricology Research Inst: tate November 1987. 119pp. ed plant measurements The bas +c premise is that, if the kPY 8712170204 43748 256 plant measurements are being weH reproduced (traclied) b) the This report summanzes a senes of empenments concerning Plant Anatyrer, the informaton which is being continuously corn- the effect of linear energy transfer and temporal radiaton dose r'uted (most of which cannot be measured). can be used to as- p, ttern to the lung from inhated beta-em'tting radonuclides The cor'ein the plant status. Research results presented in this resusts wre used to test the vahd.ty of a hazard-functon math-report show that h continuous tracking uncovers upset condi- emata model for predictang death from rad;ation pneumen4 tis tons which are, otherwise, uther r'ot amendabM b measure- Both morodty and mortaity *: thin 18 months after exposure ment or eludes tirraly detecton using conventenal methods were examined in rats exposed to beta emitting radonuckdes, The Platt Analyzer (a systems safety code capaDe of running g'ving bnef or protracted irraj aton of the lung or having weak in reai time on a plant computer). anc tw Plant Ana!yzer Con. or strong beta emissons Protractcn of the raGaton dose to troller, would be used "on-hne ' i e , connected to the plant the lung f'em a lung ha'f t,me of less than 3 days to a lung half computer whch prov> des information on plant measurements. t;me of 150 03ys has a sg:anng effect *,th a factor of 1.7. Low Their outputs would be graphically displayed in a Comprehen. energy beta em4sions have a similar effectweness in producing sive and easay understood manner. The verson of the Plant lethat injury as hgh energy beta em>ssons The hazard functon Analyzer Controller described in this report is baser. on the model for pred.ct.ng death adequately pred cted the med,an Adapt ve Preoective, dig >tal control theory lethal doses for rats NUREG/CR 5014: PARAMETRIC STUDY OF PlPE WHIP ANALY- NUREG/CR 5028: ON THE MELTING AND REFREEZING OF SIS CHUN.R Ca CHUANG.T.Y Lawrence Livermore National POROUS MEDIA DOSANJH.S S Sand a Nat:onal Laboratones Laboratory October 1987. 50pp 8711250003 UCRL 21177. October 1987. 80pp 8712280280. SAND 871976 43818 269 43449 327. A model of melt formaton and re!ocat,on in a one-dimension-In the Energy Balance Analysis Model (Standard Review Plan al core rubble bed is developed The ana'ysis includes mass (USNRC,1981) Secton 3 6 2. "Determinaten of Rupture Loca. conservaten equatons for the spec,es of ir.terest (UO2 and tons and Etynamic Effects Associated w,th the Postulated Rup. ZrO2); a momentum equat,on for wh.ch represents a ba!ance ture of PtpengT) time dependence is not considered, and a con. among drag. capWary and g'avity forces, and an energy equa-stant blowdown thrust force is assumed This force includes an 140 *h'Ch 'ncorporates the ef4ects of convect on by the meit. amphficaton factor of 11 to account for potent.al effects of re. ratatcn and conductren through the bed. and the energy re-bound Many of the assumptons used in estabbshing the ac. Wase asmaM we tsson product decay An equibnum ceptance entena, as stated in the Standard Rev>ew Plan. were UO2-ZrO2 phase d;agram is incorporated ut iz.ng a tempera-ture-dependent therma! conductivity A parametnc study is con-based on eng:neenng judgement and logic intended to assure ducted in wh<ch the heght cf the ted, the average partce di-upper bound design rather than on a mechanistic assessment a! cmm N Mal M w a m M e, a of actual pipe rupture phenomena and their effects As a result of the current pract<e an exceedinqty conservatrve desgn may a am d m @aw Garam am waw psds hom os be introduced This report represerts a parametnc study of the MELPROG computer code Pa-twar attenhen is grven to the ampi ficaten factor to account for rebound effects in the Ener7/ semi-emp.ncal me t reiocaten mcoe s in DEBRIS Espenments Balance Method Of the 71 distinct cases ne chose for ou' needed both to va4date the currect rubb!e ted model and to parametoc study, the amphfication factor of 1.1 seems suffoert he's gMe fuure recre' cat won are d scussed except in frve cases where the carbon steel p: pes are sma!! or ha<e very sm41 gaps between the prpes and the p pe *h,p re. NUREG/CR 5034: AN UPDATE OF VtDCONT%ENT TECTCN-stra nts We conclude that the amptfcaton factor generaHy de- ISM HtNZE W J ; BR AILE L W .

• ELLER G R . et al Purdue creases as the parameters gap size, hinge to-break distance Unv . West La'a reite. iN October 1997 62pp 8711180060.

and o<erhang increase 43394 001

Main Citations and Abstracts 73 The nature of the tectonism and geodynamcal processes of NUREG/CR 5037: FIRE ENVIRONMENT DETERMINATION IN the midcontnent regon of the United States is poody under- THE LASALLE NUCLEAR POWER FLANT CONTROL ROOM. stood because of the rnasking effect of relatuely undisturbed USHER.J L.; BOCCIO,J L. Brookhaven Natonal Laboratory. Oc-Phanerozoic sediments, the short histoncal record of seismcity tober 1987. 31pp. 8712090097. BNL-NUREG-52106. and the long earthquake recurrence interval. However, dunng 43631:272. the past decade, progress has been made in attacking these One of the objectues of the Fire Protecton Research Pro-problems as a result of an improved data base which permits gram (FPRP) of the U.S. NRC is to improve the modeling of en. integraton of seismcsty data mth ancient crustal structures and vironmerts caused by fires in typical nuclear power plant enclo-current stress onentatens. Surface geophyscal data together sures. A three- dimensenal flued dynamics computer code with seismcity, stress determinatons and data from a few cnt,. (PHOENCS) has been adapted as a field-model fire code (SAF-cally located deep dnll holes have led to a much improved FIRE) fer this purpose. The model has been applied to simulate knowledge of the geological history of the crust and its physical two dis *.inct fires in the control room of the LaSatie County attnbutes. Combining our knowledge of crustal structures, power plant. The environments determined illustrate hazardous stresses, and seismicity, it is possible to relate current seismicity potential for both personnel and equipment. and tectonism to one of two models. Increasing evidence from NUREG/CR 5040: RADIONUCLIDE MIGRATION AROUND URA-across the midcontinent supports reactrvaton of pre-existing NIUM ORE BODIES ANALOGUE OF RADIOACTIVE WASTE zones of crustal weakness that are appropnately onented with REPOSITORIES. Annual Report For 1984-1985. AIREY,P.L; resect to the stress field the ' zone of weakness moder as DUERDEN.P.; ROMAN.D.: et al. Austrahan Atome Energy Com-the model for the dominant contemporary tectonism and the mission. November 1987. 217pp. 8711180064. AAEC/C55.

                                 ' local basement inhomogeneity model' as the mechanism for                                        43394 065.

[ minor, low energy release earthquake actutty. Evaluaton of the uranium ore bodies in the Northern Terntory of Ausuaha as natural analogues of high-level waste repositor-NUMEG/CR 5035: DATA BASE OF SYSTEM-AVERAGE DOSE ses ms cmum to me mife W fy N W RATES AT NUCLEAR POWER PLANTS Final Report. enn pe f rahW mgraton, to asuss the assump BEALS K.; BRITZ,W.L; COHEN S.C.: et al Science & Engi- tion undertying geochemicai transport codes and to dentify noenng Associates, Inc. October 1987. 79pp. 8711060148- those orocess<-s &ch are wgraficant for long-term predicton. 43309 0R but are not oLServed over laboratory timescales. An open l Radiaton exposure to workers is one of the indirect costs system model has been used to calculate the rate of redistnbu-that must be considered in a regulatory analysis. Radiaton ex- tion of uranium ethin the secondary mineralizaton. and rado-posure may be estimated from the product of the estimated nuclide transport equatons have been used to calculata retard-man-hours to perform a job and the dose rate in the area in ed warNm travel t>mes in the Koongarra ore bod /. A mue which 'he job is performed. In previous work, a methodology range of techniqueJ auch as high gradtent magnetic 56paraton has been developed for estimating the man-hours required to and sequential extre-ton procedurn were used to study dnti perform jobs in operating nuclear power plants The methodolo- core and sod samples; other techniques such as fissco and gy uses the Energy Economic Data Base (EEDB) as a startog a'pha recoil track analysis, proton induceo X ray and garnma-ray point, in this work a data base is denved of area dose rates for ommisson and electron microprobe analysis have been used to systems and components hsted in the EEDB. The data base is examire thin sectons of the dnll core. Consderable effort has derrved from area surveys obtained dunng outages at four boil- been rnade in the last yes' !o extend the analogue to the study ing watw reactors (BWRs) at three statons and eight pressur- of transuranics and fisson products. Supphes of doll Core and ized water reactors (PWRs) at four statons. Separate tables are groundaater collods were collected in the field for 1129 and g.sen for BWRs and PWRs These tables rrwy be combined Fu 239 analyses and a comprehensive model for the producton  ! j eth estimates of labor hours to provide order-of magnitude esti. of I-129 in the uranium ore body was developed.

 ~

mates of exposure for purposes of regulatory analysis. Cauton

]                                 should be exercised in the wanton use of these tables, howev-                                  NUREG/CR 5041 V01: RECOMMENDATIONS TO THE NRC 1                                 er. They are only uled for work involving entire systems or com.                                 FOR REVIEW CRITERIA FOR ALTERNATfvE METHODS OF i                                ponents The estimates of labor hours used in con; unction uth                                    LOW LEVEL RADIOACTIVE WASTE DISPOSAL                                                            Task   ,

2a Bebw4M Vads DENSON M -; BENNETT.R 0; ' the dose rates to estimate exposure must be adusted t to ac-WAMSLEY,R M ; et at Army, Dept of, Army Engineer Water-count for in-held time. Finatty, the dose rates given in the data ways Expenment Staton. December 1987.162pp 8801070150 base do not reflect ALARA considerations. 43944 190. j NUREG/CR 5036: COST ANALYSIS FOR IMPLEMENTATION OF Recommendations are provded for general design critena PROPOSED CHANGES IN VITAL AREA REQUIREMENTS. and specific design review cntena covenng the design, con. l struebon and operaton of the below-ground vault (BGV) a4terna. CLAIBORNE.E.; WATLINGTON.B ; SIMION.G; et al. Scence & tive method of low level ra$cactrve waste (LLW) disposal A Engineenng Associates. :nc. October 1987. 122pp. BGV is a reinforced concrete vault for LLW disposal that would 8711100260. 43342.060. be piaced underground, below the frost hne and above the The Vital Area Committee (VAC) recently recommended water table, surrounded by fdter and drainage systems and cov- , changes to vital area requirements of nuclear power plants- ered over with a low permeabrhty earth layer Eight maior review Vital areas are those areas which contain vital equipment and cntena categones are dentifred in the report. The categones in-therefore must be protected against radclogical sabotage. In clude (1) the loads and load comt:anatons to be used in des >gn, general, these recommendatons are more relaxed than the cur- (2) structural des,gn and anaWcal methods, (3) construction rent entena contained in Review Gude 17 (RG 17) Before the matenal quakty and durability, (4) constructon and coeratens, VAC recommendatons can be amplemented, the NRC must per- ($) quakty assurance, (6) structural performance morwtonng, t7) form a regulatory anatysis. This study is a cost analysis of the f,!ter and drainage systems. and (8) waste cover system RG 17 cntena and VAC recommendatchs to serve as one input to the regulatory anaPysis. The approach was to apporton the NUREG/CR 5042: EVALUATION OF EXTERNAL HAZARDS TO nuclear power industry into groups of samilar plants, perform the NUCLEAR POWER PLANTS IN THE UNITED STATES-cost analysts on selected plants from the groups, and entrapo. KIMURA C Y. Lawrence Lrvermore Natonal Laboratory late the results to the entire industry. BUDNIT2,R J Future Resources Associates, Inc December , 1987 231pp 8712240077 UCID 21223 43795 091. i a

                   --- - - , .           .-n, . - - . , - - -   ---n_    . - , - - ,               , . - , . , - - , _ , - - _ -                   __.-n        ,, , . - , , . , , . - - - - - - - , , . - - , - - - -                  .

74 M In Citati:ns and Abstrccts As part of the research program supporting the implementa- NUREG/CR 5060: AN APPROACH TO THE MATHEMATICAL ton of the NRC Pobey Statement on Severe Accidents, the MODELLING OF THE URANIUM SERIES REDISTRIBUTION Lawrence Livermore Natonal Laboratory (LLNL) has periormed WITH;N ORE BODIES. A! REY,P.L ; GOLIAN.C.; LEVER.D A a study of the nsk of core damage to nuclear power plants in Austraban Atomec Energy Commisson December 1987.116pp. the United States due to externaMy inmated events The broad 8801110206 AAEC/C49. 43975 041. objective has been to gain an understanding of whether or not The distnbutens of the uranium senes isotopes in the Koon-each external nt,ator is among the major potert:al accdent ini- garra ore body were "pred:cted" by a simple one dimensonal trators that may pose a threat of severe reactor core damage or model of isotopic migraton parameters. Controlhng the "predic. of large radcactive release to the environment from the reactor. tions" were the retardaton factors and the groundwater flow Four enernal hazards were investigated in th s report These rates The cond tons modeHed were a groundwater flow rate of external hazards are internal fires, high winds / tornadoes, exter- 1 meter per year, retardaten factors of 1 x 10(4) for 238U and nal floods, and transportaten accidents. Analys:s was based on of 12 x 10(4) for 234U, and 230Th is immobde. For tNs set of I two figures-of-ment, one based on core damage frequency and the other based on the frequency of large rad oact've releases Using these two figures-of-ment as evaluaton entena. it has been feasible to ascertain whether the ruk from externaby nti-conditions, an exceptona9y good agreement was observed be-tween field-measured cotope ratos and "predicted" tsotope ratos. A muttiphase rnodel adequately desenbes the redistnbu-ton of uranium and daughter radonuchdes in the weathered ated accidents is, or is not. an important contnbutor to overall zone of the ore bodies It redistnbutes U, Th and Ra isotopes nsk for the U S. nuclear power piants stua>ed. Th s has been among an aqueous Dhase, an amorphous tron phase, a Crystal-accomphshed for each inmator separately. hne phase and a "phase" of Clay and Qua't2 NUREG/CR 5059: VO!D FRACTION MEASUREVENT LIQUlO NUREGUA-0004: THERMAL MIXING TESTS IN A SEMIANNU-LEVEL DETECTION CONCEPT ASSESSMENT AND DEVELOP- LAR DOWNCCVER WITH INTERACTING FLOWS FROM MENT. MOHR.C L.; RElCH.F R.; BER AETT,M K ; et al Mohr & COLO LEGS TUOM;STO.H ; MUSTONEN.P. Finland, Govt of. Associates. November 1987. 86pp. 8712240093 43809 242. October 1986. 343pp 8703090081. 39907 230. The Coolant Inventory Monitor System for measunng the This report desCnbes the test f acihty and test program for amount and the d<streuton of coolant in the pnmary system studying thermal remng of high-pressure inject.on (HPI) water in under acceent cond; tons of a nuclear power plant is descr bed the two-faths scate model of three cold legs, semiannular down-in tNs report This system is based on rneasurtng the local vod Comer and lower plenum of a pressurr2ed water reactor. This fracton of the coolant at selected points in the vessel and test senes has been carned out by mutual agreement on the pping system and then estimat;ng the coo! ant inventory Th s pressunzed thermal shock (PTS) informaton exchange between report summanzes the development of the measurerrert instru- the U S Nuclear Reguatory Commesson and Imatran Voima ment. the supporting tests and the development of the suppo't. Oy. The test facMy was oog nany designed to model the Fnsh ing software. Accurages of plus minus 2*. as compa*e1 w:th Lovusa piant but it was redes,gned and modAed for tNs test detta pressure ceUs can be obta ned cver vod fract ons rang ng prograrn The faobty can be operated at atmosphenc pressure from 0 to 90% The system can provce tccal measurements of w>th loop and HPI Dows from different coid legs in the area of vo+d fracten and uses proces as smal! as 0.015 x 10 X 0 3 in interest to PTS iranspa ent matena!s were used to anow flo* (0 038 X 2 54 X 0 76 cm) Expenmental test data are shovu for esuahzat.on ounng the tests The choce of transparent maten-temperatures up to 570 degrees F (572K) The sysitro CM be a's kmit the uppe temperature to 75 degrees C The fu!! buoy. r used up to the entica! point The grapNcs d splay shows a real arcy e"ect was induced by salt add ton and the HPI tempera-time display of void fracton for up to fifteen channels and g*ves Nre was wsed as a tracer. The test matnx cons sts of 20 tests. the instantaneous as well as a runn'ng average for each chan- The vaned parameters were f!cw rates and the number and nel. Tnis instrument is beheved to meet the intent of the NRC cof.gsaton of cold legs w.t5 HPl and loop flows Four tests be being able to measure the amount of water 3bove the reac- were done w.th decreas ng bop flow temperature to simdate for core ander a!l types of accdents pnmary fions dunng steam f.ne break 5

Secondary Report Number index

'      This index lists, in alphabetical order, the performing organization issued report codes for the NRC contractor and international agreement reports in this compilation. Each code is cross-referenced to the NUREG number for the report and to the 10-digit NRC Document Control System accession number.

1 SECONDARY REPORT NUMBER REPORT NUMSER SECONDARY REPORT NUMBER REPORT NUMBER AA50-2 032 NUREG-1280 EGG-2488 NVAEG/CR4457 AA50-2 033 NUREG/CR-4695 EGG-2492 NUREG/CR-4821 AAEC/C49 NUREG/CR-5060 EGG-2494 NUREG/CR4824 AAEC/ CSS NUREG/CR-5040 EGG-2495 NUAEG/CR-4844 DRFT AECb9342 NUA E G /CR-4821 EGG-2496 NUREG/CR4945 ANL-86-33 NUREG/CR-4704 V01 EGG 2499 NUAEGICR-4866 ANL46-33 NUREG/CR4704 V02 EGG-2501 NUREG/CR-4876 ! ANbe6-46 NUREG/CR4842 EGG-2509 NUREG/CR4945 ANL-86 52 NUREG/CR4813 EGG 2510 NUREG/CR4946 a ANL-86 54 NUREG/CR-4744 V01 N1 EGG-2513 NUREG /CR4965 ' ANL-8716 NUAEG/CR-4744 V01 N2 EGG-2515 NUAEG/CR-4966 V01 ANb87 27 NUREG/CR4972 EGG-2515 NVAEG/CR4966 V02 l NUREG/CR4799 ' ANL47 37 NUREG/CR4667 V03 EGG-2519 ANL 8745 NUAEG/CR-4744 V02 N1 EGG-2520 NUAEG/CR-5010 ANL-AA 30 NUREG/CR4012 V02 EPRI NP 4787 NURE G/CR-4752 ANL/ E ES-T M-332 NUREG/CR4954 EPRI NP 5272 NUREGICR4922 ARAP 575 NUAEG/CR4520 FEMA REP 1 NUAEG 0684 S01 ROI  ; BMh2120 NUREG/CR4032 V05 HEDbTME 85 3 NU9tEG/CR-3319 RO1 BW-2143 NUREG/CR4795 HEDLTME 86-2 NUNEG/CR4307 V03 SML2145 NUR EG/CR4853 HEDb?VE 87 3 NUREG/CR-3320 V03 bub 2147 NUAEG/CR-3861 HEDbTME 874 NUREGICR 3320 V04 SVL2149 NVAEG/CR4872 IEB-8044 NUREGICR 4524 BVL2150 NUAEG/CR4877 IE tL8341 NUAEG/CR-4663 BMb2151 NUREGICR4878 CB4344 NUREGICA #%4 OMk?154 NUAEG/CR-4954 t A-10730-M NUREG/CR-4615 V02 BUL2155 NUAEG/CR4955 LA 10817 M5 NUAEG/CR47? i UML2156 NVAEG!CR 4956 LA 10856 M NUREG/CR4765 1 BNL NUREG 51454 NUREG/C42331 V06 N2 LA 10871 MS NUAEG/CR 4776 BNL NUAEG-51454 NUAEG/CRMJ1 V06 N3 LA 10918 MS NUAEG/CR-4814 BNL-NUAEG 51454 NUREG/CR 2331 V06 N4 LA-10962-MS NVAEG/CR4875 BNL-NUAEG-51454 NUAEG/C42331 V07 N1 LA 10972 MS NUAEG/CR4926 i BNbNUAEG-51581 NUAEG/C42907 V05 LA '097 7-M5 NUREG/CR4892 i 83NL#JREG-51699 NUAEGICR-3444 V04 LA 10981-MS NUAEG /CR4901 BNL NUAEG 51708 NVAEG/CR 3469 V03 LA 10985-MS NVA EG /CR4904 BNbNUREG-51828 NUAEG/CA-4016 V02 LA 11019-MS NUREG /CR 4931 BNL NUAEG-51931 NUAEG/CR4405 LA 11093 MS NUAEG/CR4987 BNL-NU A E G-51934 NUAEG/CR4409 V02 LA 11094 NUAEG/CR 49%8 , BNL-NUREG 51961 NUAEG/CR-4552 LBL-20700 NUAEG /CR4645 < BNbNU AEG-52011 NVAE G/CP4054 M E A-2122 NUREG/CR-4491 BNbNUREG-52017 NUREG/CR 4715 ME A-2175 NUREG/CR4724 , BNbNUAEG-52019 NURE G/CR4730 M E A-2194 NUREG /CR4B63

• BNL-NUAE G42021 NUAEG/CR4739 MEA 2200 NUAEG/CR4841 BNL-NUAEG 52022 NUAE G /CR4810 ME A 2207 NUREG/CR3228 V05 ,

BNbNUREG 52044 NURE G/CP4084 ME A 2210 NURE G/CR4894 , I BNbNUREG 52057 NV AEG /CR4868 M TR46 WOO 213 NVAEG/CA 4783 BNbNUREG 52061 NVAEGICR4883 OANL-6187 NURE G/CR4760 BNbNUAEG-52063 NUREG/CA-4884 OANb6374 NVAEG/CR4665  ; BNbNUAEG-52066 NUREG /CA 4897 OANb6388 NUREG/CR4930 BNUNUAEG 52092 NUR EGICR-4981 ORNL/6314 NUAEG/CR 4722 BNbNUAEG-52093 NUAEG)CR-4982 ORNUNOAC-232 NVAEG/CR-4674 V04 BNUNUREG 52095 NUAEG/CR-4985 ORNUNOAC 233 NUAEG/CR 4692 BNbNUAEG-52106 NURE G /C45037 OANU NOAC 242 NUREG/CR4674 V03 CONF 460920 NUAEG/CPK66 V02 ORNL/ NSC200 NUREG/CR 2000 V05N12 , CONF 460820 NU AEG/CP 0086 V01 OANUNSC200 NUREG/CR 2000 V06 N1 ' f DA TR/8705 NURE G/CA4953 ORNU NSC200 NUAEG/CR-2000 V06 N6 EGG-2379 NVAEG/CR 4165 OANL/NSC200 NUREG/CR 2000 V06 N7 EGG-2421 NUREG/CR4407 ORNUNSC200 NUPEG/CA 2000 V06 N8 EGG 2440 NU A EG/CA-4531 OANUNSC200 NUAEG/CR-2000 V06 N9 EGG 2443 NVAEG/CR 39'4 OANUNSC200 NVAEG/CR-2000 V06N10 EGG 2455 NVA E G /CR-4616 ORNUNSC200 NUAEG/CR 2000 V06N11 EGG 2456 NUAEG/CR4617 ORNU NSC200 NUAEG/CR 20C0 VC6 N2 EGG 2461 NUAEG /CR4672 ORNUNSC200 NUAEG/CR 2(00 VO6 N3 EGG 2462 NUAEG/CR4925 ORNUNSC200 NUAEG/CA 2000 VC6 N4 EGG 2464 NUREG /CA4696 OANUNSC200 NUREG/CR 2000 VC6 N5 EGG-2465 NUAEG/CR4701 V02 OANUT M-10015 NUAE G/CR-4577 E GG 2469 NUREG/CR-4731 V01 ORNUTM 10057 NUAEG/CR-4610 EGG 2470 NUAEG/C44734 OANUTM-10100 NURE G/CR-4651 EGG 2471 NUREG/CR4741 ORNUTM 10117 NUAE G /CR4689 E GG44 73 NUAEGICA-4747 V01 ORNUTM 10147 NUAEG/CA 4708 Voi N1 EGG 24?6 NUREGICR4769 ORNUT M-10163 NUAE G /CR4712 l EGG-2480 NUAEG/C44766 OANUTU.10236 NUAE G/C44 754 i EGG 2482 NVA E G /CR-4733 OANUTM 10301 NUAEG/CR4798 , E GG-2456 NUA E G /CR4802 CANUTM-10330 NUAEG/CR4817 75

49 socsupCA uodop NnwqaJ tupox S3OONOVWA W3dOH1 NOM 83H 83dOH1 NAW83W S3OONOVBA 83dOH1 Nnn83W W3dOH1 NAM 83W OUND1WUOC9F Nnu30/Ot990 EYNC9$ 2CIC Nnd30/08rtt9 OWNniWUOC06 NA830/06-7699 SYN 095-2t 69 Nnd30/OHrt59 OdN A1WP0r2S Nnb 30 /08-P 6P C SYNC 99-OC L 1 NnH30/OB 9946 OUNniWP0929 NnH30/Our660 SYN 099-OCC9 Nnd30/08rS22 AOL OWNniWP OS02 NA830/O SOLI SYNC 99-OC99 NnH30/CutSCO A02 OUNniW'6522 Nnu30/C PLCPdOL SYN 099-ot 6 6 NOH30/OBtSCF OdNdiW 6960 Nnd30/08r2L6 A00 NE SYNC 99P 0tC Nnd30/OBriL 6 OUNA1W 6960 Nnd30/OW-7216 AGt NL SYN 099-L L CS Nnd30/OW-P400 AL JM dtsO m 83di C NOH30/CP6lO SYNC 99PLCS Nnd30/OHr200 A2 083 d70-0 SCC Nnb30/Obt 692 SYN 009 L L CS Nns30/08-7400 At 083 dN9tOSP Nn830 /O C920 S02 SYNC 99P t 90 Nn830/OWt900 dN17221 Nnd30/08-29SO AOS SYNC 99P 269 Nnd30/C P99L dNI 92LO Nnd30/OU-0650 AOC SYN 099PC06 NOH30/OWrSSL AC diL dN1';SS L L Nnu30/CPC00 AOC N2 SYN 099PC06 N0630/OBtSSL AC d12 dN1 SSlL NOH30/OFC00 A09 NL SYN 099P C06 Nnd30/OHPSSL AL 003 dN7 M Nnd30/08hS A02 SYNC 99 LC06 N0830/OU-tSSL AZ 083 dN1,99 6 0 N0830/ -ttiS SYN 099-L C06 Nnd30/OWrSSL AV Cdd dN199t9 NnH 30/OW-0699 SYN 099P 264 Nnd30/OBriL 0 dNqStiL NdB30/ Ort 96 AOF SYN 099P 002 Nnd 30 /OrlL C SYN 099P 669 Nnd30/Guti/2 dN954 L & NI 830/08rt96 AOS SYN 099&099 Nnd3D/08-t950 AOL dNOSa L & Nnd30/06rr96 A09 SYNC 99-209t NnO30/GutSSO AOP dNOSLL L NS830 /08r979 SYN 099209F Nnd30/08-tSSO AOC dN19426 Nnb30/OU-C2CL SYN 099209t

 ! dN19499                    Nnd3 OiOB-ygyc                                    NA630108r590 AOS SYNC 99&099               Nnd30/OB-tSSO A09diL h dN99906 dN19922 Nnd30/O-PCCO AOC Nnd30/O ys9CA02         SYN 099-2099              Nnd30/Ob-PSSO A09d12 dN95922 SYNC 99-2609              NFd 30 /080925 Nnd30/08r59C AOC        SYNC 99 2L ZS             NnH30/08-tir2 dN19902                    NCb30/08-t960 AOL       SYNC 99 2041              Nnd30/08-Pt92 dN159C2                    Nnu30/O PS60 A02        SYN 099-270S              Nn83OiO P499 dNOSGSE                    Nnd30/ON09 6 C          SYNC 99-27 L 6            Nnd30/d r494 dN99929                    NCH30/ Cut 929 A02      SVNC99-279 C              N0830/00F041 dN13960                    Nn830/OBP965            SYNC 99&996               Nnd30/OU-t 9CO dNqS&6P                    NA830/OrtiC             SYNC 99 2/92              Nnd30/OuP9OS AOL dN19604                    Nnd30/Obt99C            SYNC 94ll0F               Nnu30/Out9tS dit19642                   Nnd30/O tt89            SYNC 94OL26               Nnd30/O-79CP A06 dNqS666                    Nnd30/OuriC9            SYN 094-0%2               NnO30/OuP992 dN19002P                   NnB30/08r299 AOL        Sf NC9109CC               NOB 30/Ob-7969 dN19002-2                  Nnd30/ owr 299 A02      SYN 092 0zSO              Nnd 30/Out 672 dN190FS                    Nnd30/OH t9SO           SYNC 94 006 L             Nnd3b/Ot6 L C dN1909$                    Nnd30/OdellE            SYNC 9tPt6L               NnO30/O-t69C dN190B S                   N A630 / OHt9O L        SYNC 9463lO               Nnd30 / O-P 696 dNd9 L 09                  Nnd30/O-t909            SYNC 9 ZP 649             NnH30/Gu-9029 dN19 L C 4                 NnO30/06F9M            SYNOSI 4026                NnH 3 0/Ot979 dN19 69F                   Nnd30/C P96L            SYNC 04 2099              nod 30/O r29LC031 dN19 L 95                  Nnd30/06r640            SYNC 04-4099              Nnd30/ Cut 940 dN19 L 99                  Nnd3 0/Ord86           SYNC 9 4-Z L l 9           NOH 30 /OB-F 6t i dN192!I                    Nna30/Out609           SYNC 91 iL LS              Nnd30/08r6tt dN1926 9                   NAH30/Ot696            SY NC04-92OC               NA930/Out9SS dN 1920C                   Nnd30/O 7659           t seG/1/C006 / 899         Nnd 30/O-t 252 dN19276                    Nnd30/OB 5002          000-20062                  Nnd30/Ob-P L9L A02 dN19?%                     Nnd30/Obt620           000-20062                  Nnd30/OWtL9L AOC dN992ll                    Nne30/08 P 649         nOC209C6                   NnO30 /O-C699 dN9926 L                   Nnd30'08 5009          nO C20946                  Nnd 30 /O-7900 dN19C09                    Nnd30/Ob SOOC          0 0 0-20969                Nnd3 0 /06-999S sytO-99/C099               Nnd3 0/ OH-t z64       00 0 20200                 Nnd30/Ob-P926 A02 SYNC 9L294C                Nnd30/OH 2792          00 0-202CC                 Nnd30/Ot926 AOL SYNC 92 2749               Nnd30/OH C029          0 0 0 20670                NOH30/OWt829 AOL j

SYNC 90-OC26 Nnd 3 0 /Ob-Ct 65 nOC20Et 9 Nnd30/OBt929 AOC SYNC 9CPt92 Nnd30 OU 07L2 A02 nOC 206t9 nob 30/OU 7929 A02 SY NC9t-0090 Nnd30/OU 0799 00C-20690 Nnb 30/CP99 6 SYNC 97 L %9 Nnd30/OH-C625 d3A 00 G-2 L 002 Nnu30/O-t600 A02 SYN 09t29CL Nnu 30/Ou r C69 0 0 0 26002 Nn830/OB-t600 AOL SYN 09S}204 Nnd3 0 / O-7 606 00 0 2100C Nnd30 /Gu-7666 l SYNC 95-0 z60 Nnd30/O 7269 00 0 260C6 Nn830/Od 0092 l SYNC 9 SP 290 Nnd30 O tXS nOC2 L 2lC Nnd 30 /OW-SOP 2 SYNOSSP C06 Nnd30/O rfOL 007 2 L L 11 Nnd3O! O -SOLP SYNC 95 itt 6 Nnd30/OHFC2O VOV dP 1229 Nnd30/ Obr 492 SYNC 95 L St9 Nnd30/O tilz .Y d8-99199 L L H Nnd30/O-t9ti

Personal Author Index This index lists the personal authors of NRC staff, contractor, and international agreement r@ ports in alphabetical order. Each name is followed by the NUREG number and the title of ' the report (s) prepared by the author. If further information is needed, refer to the main cita' tion by the NUREG number. ABT,S.R. ANDE RSON.N.R. NUREGICA-4651: DEVELOPVENT OF R!PRAP DESIGN CRITERIA BY NUREG-1211- AEGULATOAY ANALYSIS FOR RESOLUTION OF UNAE. AIPAAP TESTING IN FLUMES Phase L SOLVED SAFETY ISSUE A-46. SEISMIC OVALIFICATON OF EQUIP. MENT IN OPERATING PLANTS.

• ADAMSJ.W.
• NUAEG/CA-3444 V04. THE IMPACT OF LWA DECONTAM. NATIONS ANDE RSON.RL
• ON SOLOtFCATON. WASTE OtSPOSAL.AND ASSOCIATED OCCU- NUAEG/CR4928. OEGRADATON OF NUCLEAR PLANT TEMPERA-
• PATONAL EXPOSURE Annual Report. Fiscal Year 1986 TURE SENSOAS *i RE'G/CA4798, IAON OxCE AEROSOL EXPER MENTS IN STEAM- ANDREW #.D.

NUREG/CA 4753 V02 CANADIAN SEISMC AGREEVENT. Annual AIR ATMOSPHERES NSPP TESTS $01505 AND 511. DATA AECOAD Report AEPOAT NUAEG/CR-5017. LIVESTONE CONCAETE AEROSOL EXPERiVENTS A TOLA S,0 IN STEAM ATMOSPHEAES NSPP Nts 521.522.And 531. Data a EXPERT OPINON IN AISK ASSESSMENT Phase f - A Cntical Evalua AGR AW AL.A.K. ton And Drections For Future Research. NUAEG/CR4552 A AEoEW OF THE SEABROOK STATON PAOBABI-LISTIC SAFETY ASSESSMENT Ccetanment Fadure Modes And Ra3 AR E LL ANO.F.E. olopeal Source Terras NUDCG/CR-487 f. RESULTS FROM THE DCH-1 EXPERIMENT. AHMAD.J. ARMBRUSTER,J.G. NUAEG/CR4082 V05 DEGRADED PtPING PROGRAM PHASE NUAEG/CR 4851 SEISMICITY 1886-89 IN THE SOUMASTERN 11 Serrmannual Aeport. Apre. temtor 1986 UNITED STATES The Ahershoch Sequence Of The Charkr.lon. South NUAEG/CA4672 EXPERIMEP TAL AND ANALYTCAL ASSESSMENT Carohns Earthquake OF CIRCUMFERENTIALLY SURF ACE-CRACKE D P1 PES UNDER 1 BENDING AR NOLD,W.D. < NURE G/CA-4878 ANALYSIS OF ExPEA1 VENTS 04 ST AINLESS NUAEG/CA-4708 V01 N1 PROGRESS IN EWLUATON OF AADONU-STEEL FLUX WELDS Topical Aeport CLOE GEOCHEMICAL INFORMATON DEVILOPED Br DOC HlGH-LEVEL NUCLEAR WASTE REFOSITORY SITE NU E /C 41 V01: RECOUVENDATONS TO THE NAC FOR NL E A 486 i T EC S TE TCCV) REVIEW CRITERIA FOA ALTERNATIVE VETHODS OF LOWLEVEL RADIOACTIVE WASTE DISPOSAL Tap 2a Be+cw-Ground vasts OxOES AIREY P L. A R RIET A.L NUREG/CA-5040. RADONUCLCE M GRATION AROUND URANIUM NUREG/CA 4405 PROBABILISTO RISK ASSESSMENT (PRA) IN-OAE BOD (ES ANALOGUE OF RADICACTivE W ASTE SIGHTS AEPOSITOR!ES Annual Aeport For 1984 1985  ! 4 AUSTIN,P.N. NUREG/CR 5060. AN APPROACH TO THE MATHEMAT CAL MODEL. LING OF THE URAN!UM SER:ES AEDISTA'BUTON WITH!N ORE NUREG/CA-4674 V03 PRECURSOAS TO POTENTIAL SEVERE CORE BODIES. DAVAGE ACCOENTS 1984 A STATUS REPORT Main Report Arx1 Ap. pendres A And B OLDRECHT,KA NUREG/CA4674 V04 PRECURSORS TO POTENTIAL SEVE AE CORE NUAEG/CR.2476 V03 A STUDY OF TAENCH COVERS TO M N MtZE DAYAGE ACCOENTS 1984.A STATUS AEPORT Appendmes C.D And INFILTRATON AT WASTE D&OSAL SlTES Fral Rept g ALZHEIMER.J M. A VER Y,T.S. NUREG/CR 3231. PtPE TO P1PE IMPACT PROGAAM NUA E G /CA-4919 FIELD TESTING OF BENTONITE AND CEVENT AMOS,C.N. BOREHOLE PLUGS IN GRANtTE NUREG/CR-4551 V3 PT1 EVALUATON Or SENE AE ACCOENT A!SAS BABCOCK C.D. AND THE POTENTlAL FOR RISK AEDUCTON PE ACH NUREG/CR4776 RESPONSE OF SEISM:C CATEGOAY I TANKS TO BOTTOM. UNIT 2 Man Aeport Dra't For Commeet NUAEG/CR4551 V3 PT2. EVALUATON OF SEVEDE ACCOENT A'SFS E ARTHOUAKE EXCITATON NU A EG/ CR-4904 INVESTIGATION OF STEEL CONTAINVENT BUCK. AND THE POT ENTIAL FOA RtSK A EDUCT:CN PE ACH LING FROM DYNAMC LOADS BOTTOM UNIT 2 Accendices Drvt For Cornrve't NUAEG/CR4551 V4 DA F . EVA LU ATON OF SEVEAE ACCCENT B ACANSK AS V,P. RISKS AND THE POTENTIAL FOR R:SK A E DUCTION GR AND GutF UN:t t Dra*t For Corm +nt NUAEG/CA-4715 AN AG:NG ASSESSVENT OF HELAYS AND CfA. NVAEG/CR4700 V4 CAF CONTA'NVENT EVENT ANALYSIS FOA CUTT BAE AuERS AND SYSTEM INTERACTONS POSTULATED SEVERE ACCOENT S GRAND GULF NUCLEAR NVAEG/CA4819 V01 AG'NG AND SERVCE WEAR OF SOLEPOD-STAtON.UNif 1 Dra+t For Cowt OPF.AATED VALVES USED IN SAFETY SYSTEUS OF NUCLEAR POWER PLANTS Vo8ume 1 Cterateg Ergerence And Fadure ide%h. ANDERSON.J.G. ca5on NUAEG/CA-4903 V02 SELECTON OF E ARTHOUAkE AESiSTANT DESGN CRITERIA FOR NUCLEAR POWE A PL ANTS . VE THODOLO. BAGGS.A B. GY AND TECHNCAL CASES Methods For int /oduchon C4 Gecdopcal NUAE G /CA 4 951 NEPHROTO2 CITY OF UAANfL FLOORIDE AND AE-Data into Cha'actecrahon Of Actue Fad's And Sa s%#, And VERS.B'LITY OF RE N AL INJUAY IN THE AAT 77

78 P;rson*l Auth:r Index SAILE Y,W.J. SEAN.D.L NUREG/CR-3950 V03 FUEL PERFORMANCE ANNUAL REPORT FOR NUREG/CR 5041 V01: RECOMVENDATONS TO THE NRC FOR 1985. REVIEW CRITERIA FOR ALTERNATIVE METHODS OF LOW-LEVEL RADIOACTIVE WASTE DISPOSAL Task 2a Below-Ground Vaults. NUREG/CR4623. IN SITU STRESS MEASUREMENTS IN THE BEAVERS,J.A. EARTH'S CRUST IN THE EASTERN UNITED STATES. 4 NUREG/CR-3861: STRESS-CORROSON CRACKING OF LOW. STRENGTH CARBON STEELS IN CANDOATE HIGH-LEVEL WASTE NURE /CR-2850 V05: POPULATCN DOSE COMMITMENTS DUE TO RE $' gypE /CR-4955 L M ERFORMANCE OF CONTAINER MA-RADCACTfVE RELEASES FROM NUCLEAR POWER PLANT SITES IN 1983 TER!ALS FOR HIGH-LEVEL WASTE. BAK ER.W.E. SEDORE,N. NUREG/CR-4892: A STUDY OF THE EFFECTS OF PENETRATON NUREG/CR4968. EVALUATON OF UNCERTAINTIES IN 1RRADIATED FRAM:NG ON STEEL CONTAINMENT BUCKUNG CAPACITY. HARDW ARE CHARACTERf2ATON NUREG/CR4904 INVESTIGATCN OF STEEL CONTAINMENT BUCK. UNG FROM DYNAMC LOADS. EE BALLINGER.M.Y.

SUMMARY

REPORT Data As Of August 31.1986 (Gray Boon I) NUREG/CR4736: COMBUSTON AEROSOLS FORMED DUR:NG NUREG-0020 V10 N10. UCENSED OPERATING REACTORS STATUS BURN:NG OF RADCACTIVELY CONTAMINATED MATERIALS Ex.

SUMMARY

REPORT Data As Of September 30.1986 (Gray Book l} , PER: MENTAL RESULTS NUREG-0020 V10 N11: UCENSED OPERATING REACTORS STATUS NUREG/CR 4779 NEW DATA FOR AEROSOLS GENERATED BY RE-

SUMMARY

REPORT. Data As Of October 31.1986 (Gray Book i) LEASES OF PRESSURIZED POWDERS AND SOLUTIONS IN STATIC 4 AlR. BE E LM AN.R.J. BAMP10N.M.C. NUREG/CR4966 V02 EVALUATON OF OPERATONAL SAFETY AT BABCOCK AND WILCOX PLANTS Volume 2. Thermal-Hydradic Re. NUREG/CR 3231: PIPE.TO P1PE IMPACT PROGRAM sufts

• SANDE R,T.J.

BEHR.V.L NUREG/CR4653 GASPAR 11. TECHNICAL REFERENCE AND USER GUOE. NUREG/CR4700 V1 DRF. CONTAINVENT EVENT ANALYSIS FOR POSTULATED SEVERE ACCOENTS SURRY POWER STATON UNIT BARNE S,C.R. 1 Dram For Comment NUREG/CR4082 VCS: DEGRADED PIPING PROGRAM PHASE NOREG/CR-4700 V2 DAF: CONTAtNMENT EVENT ANALYSi$ FOR il Semiannual Report. Aprd-September 1986. POSTutATED SEVERE ACCOENTS SEQUOYAH POWER STAT!ON. UNIT 1. Draft Reprt For Comrrent BARNE3 V E AA PLANTS a ce A N R G/ MS4. INTERPRETATON OF BOASSAY MEASUREMENTS. , NUREG/CR4613. EVALUATON OF NUCLEAR POWER PLANT OPER. ATING PROCEDURES CLASSiFICATONS AND BENEDICK W.G.  !

                                                                                                                                                                                                                                                                      ^

INTERF ACES Problems Alid Technques For improvement NUREG/CR4905 ?ETONAB:LITY OF H2 AIR DILUENT MATURES BARSELLA.W. BENJAMIN.A S. NUREGICR-4 546. HIGH-LEVEL WASTE PRECLOSURE SYSTEMS NUREG 'CR4551 V1 DRF: EVALUATON OF SEVERE 4CCIDE NT SAFETY ANALYSIS Phase 2. Final Report RISKS AND THE POTENTIAL FOR RISK REDUCTCN SURR Y POWER STATON. UNIT 1 Dram For Comment. PARSTOW,N. NUREG/CR4551 V2 DRF. EVALUATION OF SEVERE ACCIDENT NUREG/CR4822: BROAD BAND SEISMC DATA ANALYSJS Septemoer ArSKS AND THE POTENTIAL FOR RISK REDUCTON SEQUOYAH

,                    1984 September 1986                                                                                                           POWER STATION. UNIT 1 Dratt For Comment SASS.B.R.                                                                                                                       NUREGICR4551 V3 PT1: EVALUATON OF SEVERE ACCOENT RISKS 4'

AND THE POTENTIAL FOR RISK REDUCTCN PE ACH NUREG/CR4760: TEST OF 6-IN.THCK PRES $UF4 VESSELS Ser*S BOTTOM. UNIT 2 Ma'n ReportDraft For Comment 31ntermedtate Test Vesset V4A.Teanng Behaver Of Low Upper Shelf Matenal NUREG/CR4551 V3 PT2. EVALUATON OF SEVERE ACCCENT RISKS i NUREG/CR-492 CRACK. ARREST BEHAVOR IN SEN W1DE PLATES AND THE POTENTIAL FOR RtSK REDUCTON PEACH BOTTOM. UNIT 2 Appendices Draft For Comment. OF QUENCHED AND TEMPERED A $33 GRADE B STEEL TESTED NUREG/CR4551 V4 DRF: EVALUATON OF SEVERE ACCIDENT UNDER NON!SOTHERMAL CONDITIONS RISKS AND THE POTENTIAL FOR RISK REDUCTON GRAND SA TE S.DJ. GULF. UNIT 1 Draft For Comment NUREG/CR4469 V04: NONDESTRUCTIVE EXAMINATION (NDE) REU- NUREG/CR4700 V1 DAF. CONTAINVENT EVENT ANALYSIS FOR ABruTY FOR INSERVICE INSPECTION OF UGHT WATER POSTULATED SEVERE ACCOENTS SURRY POWER STATON UNIT 1 Dre For W i NURE /C 44 N EE M NA NDE) REU- NUREG/CR-4700 V2 DRF. CONTAINMENT EVENT ANALYSIS FOR 1 ABluTY FOR INSERVICE INSPECTCN OF UGHT W ATER POSTULATED SEVERE ACCCENTS SEOUOYAH POWER 4 ) REACTORS Serrmannual Report Apr4-September 1986. STATON W 1 Dram RepM 6 Comnent I i NUREG/CR.4970- STAINLESS STEEL ROUND ROBtN a TEST.Centnfugasy Cast Stawess Steel Screening Phase BENNET'U G NUREG/CR 4776. RESPONSE OF SEISMC CATEGORY I TANKS TO SAUM.J.W. E ARTHOUAKE EXCITATON I NUREG/CR-3464 V03. OCCUPATONAL DOSE REDUCTION AT NU. NUREG/CR 4926 AN ASSESSMENT OF LOSSOF CONTAINVENT PO-CLEAR POFiR PLANTS Annotated B&cgraphy Of Selveted Road. TENTIAL BECAUSE OF KNUCKLE BUCKLING FOR 41 STEEL CON-NU G/ 09 DA A ASE i NUCLEAR POWER PLANT NUR G 4987 S MULATED SEISMC TESTS ON 1/42. AND 1/14-DOSE PEDUCTON RESEARCH PROJECTS SCALE CATEGORY 1. AUXIUAAY BUILD'NG B AYLE SS.P.O. BENNETTAD. NUREG/CW4741. FEEDWATER TRANSIENT AND SMALL BREAK NUAEG/CR 5041 V01. RECOMMENDATONS TO THE NRC FOR LOSS OF COOLANT ACCCENT ANALYSES FOR THE BELLEFONTE REV1EW CRITERtA FOR ALTERNATfvE METHODS OF LOW 1EVEL NUCLEAR

• TANT. RAOf0ACT1YE W ASTE DISPOSAL Tao 2a Below Ground Vauts SE ALS.K. BENSON.S M.

HUREG/CR-5035 DATA BASE OF SYSTEM AVERAGE DOSE RATES NUREG/CR-4161 V02 CRiTCAL PARAMETERS FO4 A HtGH LEVEL AT NUCLEAR POWER PLANTS Fea! Report WASTE REPOSJTORY Volume 2 Tuff

               .       . _ _ _ _ _ _ _ . . _                --_.__._--,,._____.m_..,_.,__,_                                               r        _ - . , , , , . . . - _ _ . . . _ _ _ _ ,                    . _ _ . _ _ . _ ~ - _ . . . - _ - - . _ _ _ . , . _ .

Personal Author index- 79 NUREG/CR 4161 V03: CRITICAL PARAMETERS FOR A HIGH4EVEL LEVEL NUCLEAR WASTE REPOSITORY SITE WASTE REPOSITORY. Volume 3 Salt . PROJECTS Semiannual Report For October 1985 March 1986. SERC TRON.K.D. 8 LOSE,R.E. NUREG/CR-4896 CONTAfNMENT LOADS DUE TO D! RECT CONTAIN- NUREG/CR-3024. SUSTAINED CONCRETE ATTACK BY LOW- ' MENT HEATING AND ASSOCIATED HYOROGEN BEHAVIOR Anarysis TEMPERATUREfRAGMENTED CORE DEBRIS. s And Calcutabons Wtth The CONTA!N Code. NUREG/CR4727: SWISS SUST AtNED HEATED METALUC MELT / CON. CRETE INTERACT 04S W1TH OVERLYING WATER POOLS. SE RMAN.M. NUREG/CR-4803. THE POSS18fUTY OF LOCAL DETONATONS B LUHM.D. DURING DEGRADED-CCAE ACCCENTS IN THE BELLEFONTE NU- NUREG/CR4870; AN EVALUATON OF THE EFFECTS OF DESIGN CLEAR POWER PLANT. OETAILS ON THE CAPACITY OF LWR STEEL CONTAINMENT NUREG/CR4905: DETONABluTY OF H2-AIR-OtLUENT MIXTURES. BUILDINGS. BERNREUTER.D.L  ! BOCCIO.J. NUREG/CR4461. DEVELOPMENT OF SITE SPECIFIC RESPONSE NUREG/CR-4810 EVALUATON OF DIESEL UNAVAILABluTY AND SPECTRA RISK EFFECTIVE SURVEILLANCE TEST INTERVALS. i BE RNREUTER.D.L BOCClo.JL ' NUREG/CP-0087:

SUMMARY

REPORT OF THE SYMPOSIUM ON SEIS- NUREGICR-5037. FIRE ENVIRONMENT DETERMWATON IN THE LA-MC AND GEOLOGC SITING CRITERIA FOR NUCLEAR PCWER SALLE NUCLEAR POWER PLANT CONTROL ROOM i PLANTS NUREG/CR-4835 SEISMC HAZARD CHARACTER!ZATON OF THE BOECK E R,8.B. EASTERN UNtTED STATES Comparative Evaluabon Of The LLNL And NUREG/CR-5025. EXPERIMENTAL STUDIES OF THE EARLY EFFECTS r EPRI Studies OF INHALED BETA-EMITTING RADONUCUDES FOR NUCLEAR AC. l COENT RISK ASSESSMENT Phase il Report SERRETT,M.K. NUREG/CR 5059' VOC FRACTON MEASUREMENT LOOO LEVEL SOLANDER.MA . DETECTON CONCEPT ASSESSMENT AND DEVELOPMENT

• NUREG/CR-4672. ANALYSIS OF INSTRUMENT TUBE RUPTURES IN WEST lNGHOUSE 4-LOOP PRESSURIZED WATER REACTORS.

BERTUCIO,R.C. NUREG 1150 DAF V1 FC: REACTOR RISK REFERENCE BOLtG.C.A. NUREGICA-4846. HIGH. LEVEL WASTE PRECt OSURE SYSTEMS NU / 550 V03 ALYSiS OF DAMAGE FREQUENCY SAFETY ANALYSIS Faas4 2. Foat Repert, , FROM tNTERNAL EVENTS SURRY UNIT 1 " NUREG/CR4550 VOS ANALYSIS OF CORE DAMAGE FREQUENCY 50LUh0ER.GA FROM INTERNAL EVENTS SEQUOYAH, UNIT 1. NUREG/CR4974- INTRAPLATE SEISMICITY IN THE EASTERN UNITED STATES u EESSETTE.D. NUREG-1271: GUOEUNES AND PROCEDURES FOR THE INTERN + 8~ j TIONAL CODE ASSESSMENT AND APPUCATONS PROGRAM E /CR4760 TEST OF 6-IN THICK PRESSURE VESSELS Seres 3 Intermed6 ate Test Vesset V.8A Teanng Behaver Of Low Upper-Shelf , CE VAN.R. NUREG 1285- NRC STAFF EVALUATON OF THE GENERAL ELECTRIC Math i COMPANY NUCLEAR REACTOR STUDY rREED REPORT 7 BONANOLJ. I NUREG/CR 3925 REY: SWIFT 11 SELF. TEACHING CIE R.V.M.  ! NUREG/CR4962 METHOOS FOR THE EUCITATON AND USE OF CURP.CULUM m u stratrve Problems For The Sand.a Wasie-boiabon

!                                   EXPERT OPINON IN RISK ASSESSMENT. Phase 1 A Croal Evalue.                                              Flow And Transoort Model For Fractured Media                       i bon And Drectons For Future Research.                                                                NUREG/CR-4766. USER S MANUAL FOR THE NEFTRAN COMPUTER CODE.                                                              }

CINNALLE.P. i NUREG/CR4161 V02 CRITCAL PARAMETERS FOR A HCH. LEVEL DON 2ON.LL W ASTE REPOSITORY Voiume 2 Tu,g NUREG/CR-4098 SEISMC-FRAGIUTY TESTS OF NEW AND ACCEL-NUREG/CR4161 V03 CRITCAL PARAVETERS FOR A hCH4EVEL ERATED-AGED CLASS 1E BATTERY CELLS j WASTE REPOSITORY. Volume 3 Sa:t NUREG/CR4301: STATUS REPORT ON EQUtPMENT OUAUFICATION

• ISSUES RN ARCH AND RESOLUTON  ;

SISH.0L NUREGICR-4875 CHARACTERIZATION OF CRUSHED TUFF FOR THE BOOKER.J M. , EVALUATON OF THE FATE OF TRACERS IN TRANSPORT STUDIES NUREG/CR4814 SOURCES OF CORRELA rON BETWEEN f EXPERTS Empecal Resuits From Tao Ertromet  ; IN THE UNSATURATED ZONE l CLAC K.D.A. BOWE RM AN.B.S. , NUREG/CR4098 SEISMC-FRAGIUTY TESTS OF NEW AND ACCEL. NUREGICR-4730 EVALUATION OF oTENTIAL MIXED WASTES CON. F ERATED. AGED CLASS 1E BATTERY CELLS. TAIN1NG LEAD. CHROMlVM.USED 04 LOR ORGANC UOuiDS. [ SLACKEY,M E. BOYD.O.J. NUREG/CR-4957. $URVEY OF GEOPHYSCAL TECHNOVES FOR NUREG/CR4551 V1 DRF: EVALVATON OF SEVERE ACCOENT SITE CMARACTERt2ATON tN BASALT. SALT ANO TUFF. AtSKS AND THE POTENTIAL FOR RISK REDUCTION SURRY POWER STATON UNIT I Drait For Comment NUREG/CR 4551 v3 PT1: EVALUATON OF SEVERE ACCOENT R:SKS  ! SLAC KM AN.H.S. NUREG/CR-4617. ONSITE ASSESSMENTS OF THE EFFECTIVENESS AND THE POTENTIAL FOR RfSK REDUCTION PEACr1 AND IMPACTS OF UPGRADED EMERGENCY OPERATING PROCE. BOTTOM UNIT 2 Mac RecortDraM For Cernment DURES NUREG/CR 4551 V3 PT2: EVALUATON OF SEVERE ACCCENT RISKS e NUREG/CR.4696 CONTA:NVENT VENTING ANALYSl3 FOR THE AND m-c. POTENTIAL FOR RISK REDUCTON PEACP l PEACH BOTTOM ATOMC POWER STATON BOTTOM UN'T 2 Appendaces Dram For Corrvnent NUREG/CR4966 vot: EVALUATION OF OPERATONAL SAFETY AT NUREG/CR455 : V4 DRF: EVALUATON OF SEVERE ACCtDENT BABCOCK AND W1LCOx PLANTS Volurm 1 Resuitt Oterwew R:SKS AND THE POTENTIAL FOR RISK REDUCTO 4 GRAND OUtF. UNIT 1 Dran For Comrwnt , BLEJWAS.T.E. NUREG/CR-3412 V02 CONTA:NVENT INT EGR1TY BR ADLE Y,0.R. + PROGRAM Progress Report. Aped 1983 -December 1984 NUREG/CR-3024 SUSTA:NED CONCRETE ATTACK BY LOW. 8 TE MPER ATURE J RAG'4WTED CORE DEBRIS i CLE NCOE.J.G  ; r NVAEG/CR 4706 V01 N1 PROGRESS IN EVALVATON OF F.ADONU- SRAfLE.LW. CUDE GEOCHEMCAL INFORMATON DEVELOPED BY DOC MH- NUREG/CR-f 014 AN UrDATE OF M DCONTINENT TECTONISM j t

w i 80 Personal Author indOx SRIDGES.T.L BUTLER.T.A. NUREG/CR4944 CONTAINMENT PENETRATON ELASTOMER SEAL NUREG/CR-4776 RESPONSE OF SEISMC CATEGORY t TANKS TO LEAK RATE TESTS- EARTHOUAKE EXCITATON. ' BRIMHALLJ L NUREG/CR4892. A STUDY OF THE EFFECTS OF PENETRATON FRAM;NG ON STEEL CONTAINMENT BUCKUNG CAPACJTY. NUREG/CR4890- HEAT OF REACTION OF MOLTEN ZlRCONiUM NUREG/CR4904: :NVESTIGATON OF STEEL CONTAINMENT BUCK-WITH UO2. ' UNG FROM OYNAMC LOADS "UW ' BYERS C.D

                                                           ^             8 ^                                                                                              '

AT N R ER TS - NUREG/CR4842: A STUDY OF NATURAL GLASS ANALOGUES AS APPUED TO ALTERATON OF NUCLEAR WASTE GLASS. BROCKMANN,J.E. NUREG/CR4727: SWISS SUSTA!NED F 'METALLC MELT / CON. 8YERS.K.R. CRETE INTERACTONS WITH OVER 4TER POOLS NUREG/CR-5003 DES GN OF A MATERIAL CONTROL AND AC-NUREG/CR-4471: RESULTS FROM Tt EXPERtMENT. COUNTING SYSTEM TO PROTECT AGAINST TVNCEALMENT OF DIVERSON BY FALSIFICATION ANO COLLUSON SROCOUM.S.J. NUREG/CR4852- THE MEERS FAULT.TECTONC ACTIVITY IN CADWALLADER,L SOUTHWESTERN OKLAHOMA. NUREG/CR4616- ROOT CAUSES OF COMPONENT FAILURES PROGRAM Methods And Apphcatons NUREGICR-4957. SURVEY OF GEOPHYSCAL TECHNOUES FOR C ALLAHAN.G M. SITE CHARACTERIZATON IN BASALT. SALT AND TUFF- NUREG/CR4894 A USER S GUIDE TO THE NRC'S PIPtNG FRAC. MOUNSM TURE MECHANICS DATA BASE (P1 FRAC) NUREG/CR-4695. MATERIAL CONTROL AND ACCOUNTING (VC&A) CALLOW,R.A. LOSS DETECTON DURING TRANSITON PERODS AND PROCESS UPSET CONDITONS. NUREG/CR4966 V02 EVALUATION OF OPERATIONAL SAFETY AT BABCOCK AND WILCOx PLANTS Volume 2 ThermahHydraube Re- L 4 DROW2tN.B.S. suHs , NUREG/CP-0088- TRANSACTONS OF THE 97H INTERNATONAL CONFERENCE ON STRUCTURAL MECHANCS IN REACTOR CAMP AL TECHNOLOGY.Panet Sesson JK: Seuctural And Mechanal Engreer- NUREG/CR4550 V01: ANALYS:S OF CORE DAMAGE FREQUENCY wig Research At The U S. Nuclear Regulatory Commssort ' AOM INTERNAL EVENTS METHODOLOGY GUOEUNES NUREG/CR4550 V05 ANALYSIS OF CORE DAMAGE FREOVENCY i DRVST,F. FROM INTERNAL EVENTS SEOUOYAH. UNIT 1. NUREG/CR-4082 V05. DEGRADED PIPtNG PROGRAM PHASE 11 Serrsannual Report. Apr4-Sep* ember 1986 CAUP.W J-NUREG/CR4878 ANALYSIS OF EXPERIVENTS ON STAINLEs3 NUREG/CR-4909 MELPROG-PWR/MCOO A MECHAN:STC CODE FOR STEEL FLUX WELOS. Topical Report. ANALYSTS OF REACTOR CORE MELT PROCnESSON AND VESSEL ATTACK UNDER SEVERE ACCOENT CONDITO45 SAUST,F.W. NUREG/CR-4853 APPROxlVATE VETHOOS FOR FRACTURE ANALY- C A MPVE LL.J.E. SES OF THROUGH-W ALL CRACKED PtPES NUREdiCR 2452. RISK METHODOLOGY FOR GEOLOGC DISPOSAL t i

   ,,ygg g g,                                                                                             & WAN WASTE W W NUREG/CR4760- TEST OF 6-IN TH1CK PRESSURd VESSELS Senes                                        C ANT R E LL8.K.                                                     f 3 IntermeJate Test Vessel V4ATeanng Behaver Of Low Upper Shelf 1       Matenal-NUREG/CR4950 V01: THE SHOREUNE ENVIRONVENT A T MOS.

PHERC DISPERSON EXPER. MENT (SEADEM Esperment Desenp- I DAYANT.J L # 4 NUREG/CR4640 HANDBOOK OF SOFTW ARE QUAUTY ASSURANCE NUREG/CR 4950 V02 THE SHOREUNE ENVIRONMENT ATMOS-PHERC OtSPERSON EXPER MENT (SE ADE9 Meteorolog. cal And TECHNOVES APPLCABLE TO THE NUCLEAR INDUSTRY. , Gas Tracer Data DR YSON.J.W. C A RUN.F. [ NUREG/CR4760 TEST OF 64N THCK PRESSURE VESSELS Senes , 3 intermedate Test Yessei V-8A Teanng Behaver Of Lew Upper-She9 NUREG/CR4530 V02. U S / FRENCH JO:NT RESEARCH PROGRAM ' Matenat REGARDiNC THE BEHAVOR OF POOMER BASE MATERIALS SUB-JECTED TO BETA RADIATON Volume 2 Phase-24 Sueenirq Tests - BUCKALEW.WR NUREGICR4530 V02. V S / FRENCH JO:NT RESEARCH PROGRAM CARNES.8A. , l REGARO4NG THE BEHAVOR OF POLYMER BASE MATERIALS SUB- NUREGICR4704 V01 RELATIVE BOLOGCAL EFFECTINENESS (RBE)

 . JECTED TO BETA RADIATCN Volume 2. Phase la Screerung Tests                                         OF FtSSON NEUTRONS AND GAMMA RAYS AT OCCUoATONAL
!                                                                                                         EXPOSURE LEVELS Volume 1 Studes On The Genet;c Er'ects in BUDNITZAJ.                                                                                             M,ce Of 60 Ep Once WeeW Esposures To Fesson Neutrons And NUREG-1150 DAF v1 FC REACTOR RISK REFERENCE                                                         Gamera Rays DOCUVENT Mac Repor1 Dra*t For Comment NUREG/CR 4910 RELAY CHATTER AND OPERATOR RESPONSE                                              C ARROLLD E.

AFTER A LAAGE EARTHOUAKE An improved PAA Methodology W th NUREG/CR 49% CONTAINVENT LOADS DUE TO DIRECT CONTA:N-N E%/CR 5042 EVALUATON OF EXTERNAL HAZARDS TO NUCLE- A T A I AA POWER PLANTS IN THE UNITED STATES ' ! BUEHRING.W.A. C ARSTE A.D.D MJREG/CR4012 V02 REPLACEMENT ENERGf COSTS FOR NUCLE. NUREG/CR-4964 UPCATE OF TABLE 5 3 NONRACOLOGCAL (Nyg. AR ELECTRCITY4ENERAT'NG UNITS IN THE UNIT E D RONVENTAL PARAMETERS FOR A REFERENCE UGHT. WATER STATE S 19971991. RE ACTOR Urarwum M reg M,ang And Enremer t DURCK.E. C A R T E R.J.A. , NUREG/CR4970 STAINLESS STEEL ROUND ROB;N NUREG/CR4522 BROAD BAND SEiSMC CATA ANALYSIS Sep+ ember TEST CentMvgany Cast Statwess Steel Screerwng %e 1964. Septembe 1986 j i DVSTARD.LD. C AR TWRIGHT,K. , NURE G/CR 4301 STATUS REPORT ON EOU+ VENT QUAUFCATO4 NUREG/CR 2478 V03 A STUDY OF TRENCH COVERS TO U.N M.2E j ISSUES RESE ARCH ANO RESOLUTON iNFILTR ATIC/d AT W ASTE D:SPOS4 SITE $ Fea! Rept i l _ _ _

Personal Author Index 81 CASE F L CHOU.C.K. NUREG/CR 4708 V01 N1. PROGRESS IN EVALUATON OF RADIONU- NURE G/CR4829 V01 - SHiPP:NG CONTAINER RESPONSE TO CLOE GEOCHEMICAL INFORMATON DEVELOPED BY DOE HIGH- SEVERE HIGHW AY AND RAILWAY ACCOENT CONDITCNS Marn LEVEL NUCLEAR WASTE RE POSITORY SITE Report PROJECTS Semaanual Report For October 1985 March 1986 NUR EG/CR4829 V02 SH!PPING CONTAINER RESPONSE TO NUREG/CR4865 THE SOLU 8fLITY OF ELECTRODEPOSITED TC(IV) SEVEF6 H!GHWAY AND RAILW AY ACCCENT OxCE S. CONDITONS Appen6ces NUAEG/CR4899 COMPONENT F R AG'LITY RESEARCH CATALDO,0.A. PROGRAM Phase 1 Component Pnor taaton NUREG/CR4976 PLANT RHi2OSPHERE PROCEFSES INFLUENCING NUREG/CA 4900 V01: COMPONENT FRAGtLITY RESEARCH HADCNUCLCE MOB!LITY IN SOIL PAOGRAM Phase i Demonstraton Tests Summary Report NUAEG/CR4900 V02. COVPONENT r R AGILITY RESEARCH CATHEY,N G. PROGR AM Phase i Demonstraton Tests Appendices NUAEG/CA-4550 V04 ANALYSIS OF COAE DAMAGE FAEOUENCY CHRISTENSEN,0. MOM INTERNAL EVENTS PEACH BOTTOM UNIT 2 NUR EG 'CR-3145 V05 GEOPHYSICAL INVESTIGATONS OF THE CAVE.L WESTERN OHO 4NDIANA REGON Final Report October 1981 Sep-NUREG/CR 4941: THE APPLCATON OF VALUE4VPACT AN ALYSIS tember 1986 TO USl A45 Sumrna9 Report Of UCLA Stud'es On Vatue-tmpact Anal C HU ANG,T.Y. ys:s in Re4aton To USi A45 NUAEG/CR-5014 PARAVETRIC STUDY OF P:PE Whip ANALYSIS C E R ASOLI.C.P. CHUN.R.C. NUREG'CR4720 COMPARISON OF THE 1982 SEADEX DISPERSCN NUAEG/CR 3964 METHODS FOR IMPACT ANALYSfS OF C.HIPP1NG DAT A WITH AESULTS FROM A NUVBER OF DiFFERENT MODELS CONTA!NE RS CERVEN F. NUREG/CR 5014 PARAVETRC STUDY OF PIPS WHIP %NALYStS NUAEG/CR-4701 V02 SAFETY ASSESSVENT OF ALTERNAT;VE0 TO CH "

                                                                                                 .NALLOW LAND                                                 RURIAl   OF   LOW LEVEL AADCACTIVE        NUAE CA4744 V01 Nt LONG-TEAM EV8RITTLEVENT OF CAST STE volume 2 Enwonmental Cond tons ANecting Rehability Of En-DUPLE X ST A.NLE SS STEELS IN LWR 3YSTEMS Sersannual AeoortOctober 1985 - March 1986 CHABOT,G E.

NURE G/ CR-4744 Q1 N2 LONG-TERV EVBRITTLEVENT OF CAST DUPLE X STA:NLES-S STEELS IN LWR SYSTEMS Semannua' NVAEG/CR4684 lNTE APAETATION OF BCASSAY MEASUREVENT3 Report Apr4-Sectember 1966 CHAMBERS,R. NUREG/CA-474r V02 N1 LONG TERM EVBRITTLEVENT OF CAST DUPLE X ST AINLE SS STEELS IN LWR SYSTEVS Semiannual NU AE G /CR4741 FEEDW ATER TRANS2ENT AND SMALL BAEAK Aeport Ocuber 1985 March 1987 LOSS OF COOLANT ACCCENT AN ALYSTS FOR THE BELLEFONTE NUCLEAR PLANT CI ALONE.H.J. CH ANG,T.Y. NVAEG/CR4955 LONG TERM PERFORVANCE CF CONTA!NE A VA. TEH;ALS COR H!GH-LEVEL W ASTE NUAEG 1030 SEISVC QUAL F' CATION OF EQUtPVENT IN OPERAT. ING NUCLE AR POWE R PLANTS JnresoNed Sa'ety issue A46 CLAIBORNE E NUREG 1211 REGULATORY ANALYSi% FOR RESOLUTON OF UNAE. NUREG/CR 5036 COST AN*. lysis FOR IMPLEVENTATON OF PRO-SOLVED SAFETY ISSUE A 46.SEISV C OUALIFCATON OF EOU1P- gg ggg g ym gg pgggg VENT IN OPERATING PLANTS CHAVEZ,JM CWBN.HC. A WEMA6 NW NUREG/CR 4527 V01 AN EXPE A VENT AL 6%ESTG ATON OF IN-TEANALLY GNtT:ED FiAES IN NUCLEAR JOWER PLANT CONTROL ANCE OF HIGH LES EL W ASTE PACKAGES (BASALT, TUFF AND CAB: NETS Part i cat net ENe;ts Tests SALT) C LA R K,R. A. CNUAEGi AE N.J C' CA-4 B61 DEVELOPVENT OF SITE SPECIFIC RESPONSE NUAEG/CA 4849 STEAV GENERATOR GROUP PAOJECT Annual SPECTRA F%rt . ! H 5 CHEN W.P. cgAUS$,0 8. NUAEG/CR4859 SEtSVC FA AGLITY TEST OF A 6 INCH OtAVETER NUREG /CR w 3 ROUND-AOB N PAETEST ANALYSES OF A 16-l PIPE SYSTEM SCALE REIN 70 ACED CONCRETE CONT A<NVENT MODEL SUBJECT l TO STATC tNTERNAL PRESSUR:ZATON 1 CHEN,Y S-NV AEG 12 4 PROGAAM PLAN FOR COAAE CTON OF V S INSTAU- CLETCHER.J W. VENT DEGAADATCN OR FA'LUAE IN THE UPPE A PLENUM TEST NUREG<CR 4674 V03 PAECURSOAS TO POTENTIAL SEVEnE COWE FACILITY (UPTF)iN THE FEDER"4 AEPUBLO OF GEHMANr DAV AGE ACC4 DENTS 1994.A ST ATUS AEPORT Van A# ort AN Ap-perdues A And B CH E NION.J- NUAEG/CR-4674 V04 PAECURSOF S TO POTENW SEVE AE CORE NUAEG'CR-4530 V02 U $ rF AENCH JO'NT AESE ARCH PROGAAb DAM AGE ACCCENTS 1984 A ST A*US AF!W Accendaes C D And AEGARD'NG THE BEHAVCR OF PO.LYVER BASE V ATE A' ALS SUB- E JECTED TO BETA A ADIATON vow 2 Ptase-2a Screening Tests NUAEG/CR 4692 OcE AATING EXPT *ENCE PEV,E A C5 F AiLURES OF POWER OPER ATED FErEt W AiVES AND BLOCK VALVES IN C H E R D A C K.R. NUCLE AR POW E A PLAYi S NUAEG/CA-4781 DAFT STUDY Cf SEVERE ACCCENT V TG ATION SYSTEUS CLlWTON,$ O. NUAEGeCA 4u 7 OO NE PARTITCN CCEFFC ENT VE ASUAEVENTS CHOPR A,0.K. AT S.WL ATED 5%R STE AV GENE AATOR CChDITCNS trqenm NUAEG/CR-4744 Voi N1 LONG-TE AM EVB AITTLEVENT OF CAST Cea Aepe DUPLE x ST A tNL E SS STEELS IN LWR SrSTE US Semawai Report.Octcte 1985. Varch 1986 CLOSEJ A-NU AE G/CR-4 744 VO1 N2 LONG-TE AM EVBAtTTLEVENT OF CAST NUAiG'CA 4 734 SE2SV C TEST NG OF TYPCAL COr4T A NVENT DUPLE x S t A:Nt E SS STEELS IN LWA SYSTE46,5em4 M PtPAG PENETRATCN SYSTEVS Report Apre Seciemt+r IM6 NVAEG/CR 4744 V02 N1 LONG TERV EVBR!TTLEVENT CA C AST

• 0HE N.L DUPL E x ST A.NLESS STEELS IN LWR S YSTEMS SesamrNal NVAEG C837 YM N33 NAC TLD D AECT A AD:ATCN VCYTOAAG Report. October 1986 March 1947 NETAOR* Pwess Accort July Segiemte iM6

a 4

                                                                                                                                                                                                         +

82 Personal Author index ' t NUREG4837 V06 N04 NRC TLD D! RECT RADAT10N MONITORING CREWSJ.L.  ! NETWORK Progress Raport. October December 1986 NUREG 1269- LOSS OF RESIDUAL HEAT REMOVAL SYSTEM Deblo NUREG4837 YO7 NOI: NRC TLD DIRECT RADIATON MONITORING Canyon Urrt 2. Aprd 10.1987. NETWORK Progress Report, JarNary-March 1987 NUREG 0837 V0/ NO2: NRC TLD DIRECT RADIATION MONITORING CROFF.A.G. NETWORK Progress Report, Aprd-June 1987. NUREG/CR-4134 R01: REPOSITORY ENViRONWNTAL PARAM, NUREG-0837 V07 N01. NRC TLD OtRECT RAD (ATON McNITORING ETERS ANO MODELS RELEVANT TO ASSESSWG YHE PERFORM- ' NETWORK Progress Report, JuPy-September 1987. ANCE OF HIGH-LEVEL WASTE PACKAGES (BASALT. TUFF AND COHE N.S. NUREG/CR-5036. COST ANALYSIS FOR IMPLEMENTATON OF PRO

• CRONE.A.J. 1 POSED CH ANGES IN VITAL AREA REQUIREMENTS.

NUREGICR-4937. INVESTIGATION OF THE MEERS FAULT IN SOUTH-COME N WESTERN OKLAHOMA. NUREG/CR-5035 DATA BASE OF SYSTEM-AVERAGE DOSE RATES CRONENSERG.A.W. AT NUCLEAR POWER PLANTS Fryd Report NUREG/CR-4866. AN ASSESSMENT OF HYDROGEN GENERN. % CONDIE,K.G. FOR THE PBF SEVERE FUEL DAMAGE SCOPtNG AND 11 TESe . NUREGICR4824. EVALUATION OF INTEGRAL CONTINVING EXPERI. NUREG/CR-4925: FISSON PRODUCT BEHAVOR DURING THE PBF SEVERE FUEL DAMAGE TEST 11. i MENTAL CAPABILITY (CEC) CONCEPTS FOR LIGHT WATER REAC. TOR RESEARCH PWR SCALING CONCEPTS- CULLEN.W.H. CONGEMI.J NU EGW724. FATIGUE CRACK GROWTH RATES IN PRESSURE NUREG/CR 2907 V05 RADtOACTIVE MATFRtALS RELEASED FROM NUCLEAR POWER PLANTS. Anrual Report 1964 NU E RF R ENV ONVE S g ; VESSEL STEEL FATIGUE FRACTURE SURFACE FILMS FORMED IN CONNELL H.R. PWR ENVIRONMENTS. NUREGICR-4982: SEVERE ACCOENTS IN SPENT FUEL POOLS IN gygggggg,gg , SUPPORT OF GENERC SAFETY ISSUE 82 NUREG/CP-0087 SUVMARY REPORT OF THE SYMPOStVM ON SEIS-COOK.K.V. MC AND GEOLOGC SITING CRITERIA FOR NUCLEAR POWER NUREG/CR4860 FLAW DENSITY EXAulNATIONS OF A CLAD BOfL. PLANTS. ING WATER REACTOR PRESSURE VESSEL SEGMENT. NUREG/CR4826 vot: SEISMC MARGIN REVIEW OF THE MAINE Y ANKEE ATOM C POWER STATON Volume 1 Summary Report CORUH.C. ' i NUREG/CR-4975: A REVIEW OF THE RESOLVWG POWER OF RE. CUNNINGHAM,MA FLECTON SEIT.90 LOGY METHOOS TO DETECT SUBSUR5 ACE NUREG 1150 ORF V1 FC: REACTOR RISK REFERENCE FAULTS AND/OR CHANGES IN LAYER THCKNESS DOCUMENT Mom Report Draq For Cornnent CORWIN.W.R. CZAJKOWSKI C.J. NUREf. 'CR-4930 CRACK. ARREST BEHAVOR IN SEN WIDE PLATES NUREGICR4868. METALLURGCAL EVALUATON OF AN 16-INCH OF OUENCHED AND TEMPERED A 533 GRADE B STEEL TE3TED FEEDWATER LINE FAILURE AT THE SURRY UNIT 2 POWER STA. UNDER NON'SOTHERMAL CONDITIONS. TON. COSTAIN.J.K. DAE ME N.J.J. r NUREG/CR4975. A REVIEW OF THE RESOLVtNG POWER OF RE. NUREG/CR-4541: EXPERENTAL ASSESSMENT OF THE SEALING FLECTON SEISMOLOGY METHODS TO DETECT SUBSURFACE EFFECTIVENESS OF ROCK FRACTURE GROUTING FAVI,TS AND/OR CHANGES IN LAYER THICKNESS. NUREG/CR-4919 FIELD TESTING OF BENTONITE AND CEMF.NT BOREHOLE PLUGS IN GRANITL COURTRIGHT.E.L NUREG/CR4963: THE SEAUNG PERFORMANCE OF BENTONITE / NUREG/CR4889 ZlRCALOY-4 OxlDATON AT 1300 TO 2400 DE. CRUSHED BASALT BOREHOLE

• LUGS.

GREES C NUREG/CR-4995: EXPERIMENTAL ASSESSMENT OF THE SEAUNG NUREG/CR4e91. PROPERTIES OF RE ACTOR FUEL ROD MATERIALS PERFORMANCE OF BENTONITE BOREHOLE PLUGS AT H'GH TEMPERATURES Foat Summary he%rt . $evere Core l Damage Property Tests Program OA A - COWAN.C.E. GRAM . ANTCIPATED TRANSIENT WITHOUT SCRAM SIMULA-NUREG/CR4808 MiNTEO USER *$ MANUAL TONS FOR BROWN' FEARY NUCLEAR PLAN 1 L AIT 1. NUREG/CR-4976. PLANT RH120 SPHERE PROCESSES INFLUENCING RADIONUCLCE MOBluTY IN SO4L DAMONI.G. NUREG/CR 5025 EXPERIMENTAL STUDIES OF THE EARLY EFFECTS CRAMOND.WA OF INHALED BETA-EMWTING RADONUCLCES FOR NUCLEAR AC. NUREG/CR4458 SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF COENT RISK ASSESSMENT Pha e il Report. A WESTWGHOUSE 2-LOOP PRESSURIZED WATER REACTOR. Case i i Study DANIEL,EA J NUREG/CR4710 SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF NUREG/CR4953 CORRELATON OF RADOOOINE RESUSPENSON l A COMBUSTON ENGINEERING PRESSURf2ED WATEFI WITH TEMPERATURE AT tmh 2.  ! RE ACTOR Case Study 1 NUREG/CR4713 SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF DANIEL.JA . A BABCOCK AND WILCOX PRESSURIZED WATER REACTOR Case NUREG/CR4953 CORRELATION OF RADCO9tnE RESUSPENSON Study. WITH TEMPERATURE AT TMb2 NUREG/CR4762. SHUTDOWN DECAY HEAT REMOVAL ANALY?iS OF A WES TINGHOUSE 3-LOOP PRESSURIZED WATER REACTOR Case DAYlS,C.S. i Study NUREG /CR4824 EVALUATON OF INTEGRAL CONTINUING EXPERI-1 MENTAL CAPABiUT4 (CEC) CONCEPTS FOR LGHT WATFR RE AC-1 CRANWELL R.M. TOR RESEARCH . PWR SCAUNG CONCEPTS NUREG/CR 2452 PISK METHOOOLOGY FOR GEOLOGC DISFOSAL NUREG/CR-4946 DAVIS-BESSE UNCERTAINTY STUDY. . OF RADCACTivE W ASTE. Fool Report NUREG/CR-4966 VQ2. EVALUATON OF OPERATIONAL SAFETY AT ' BABCOCK AND WtLCOx PLAN"S volume ? . ThermakHyd slic Re. CRAWFORD.SL s its NURFG/CR4583 V02. DEVELOPMENT AND VALOATON OF A REAL TIME SAFT.UT SYSTEM FOR THE INSPECTON OF UGHT WATER DAVIS.P. . REACTOR COMPONENTS Annual ReportOctober 1964 . September NUREG/CR 4405 PROBABfLISTC RISK ASM SSMENT (PRA) IN-1985 SIGHTS r

  - _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ -                           - _ - _ _ = _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _                   _ _ _ _ _   _____               _ __ _ ___                       _- _                             _______

Personal Author index 83 davit.P.A. 08NGEE.D A. NUREG/3R 3925 R EV. SWIFT 11 SELF. TEACHING NUREGICR4590 V01. AGING OF NUCLEAR STATON DIESEL CURRCULUMittustratwo Probkoms For The Sarda Waste 4solaten GENEPATORS Evaivaten of Operatng And Empert Esperence Phase Flow And Transport Model For Fractured Meda l Study. l DAVIS.S.N. 06NSE L.M.R-NUREG/CR4912: DATING GROUND WATER AND THE EVALUATON NUREG/CR 3956. IN SITU TESTING OF THE SHiPPtNGPORT ATOMC r OF REPOSITORIES FOR RADCACTIVE WASTE- POWER STATON ELECTRCAL CtRCU4TS. DEAN.R.S. DOSSE.C A. NUREG/CR4524. CLOSEOUT OF iE BULLETIN 8G 24 PREVENTON NUREG/CR4741: FEEDWATER TRAN$ TENT AND SMALL BREAK OF DAMAGE DUE TO WeTEA LEAKAGE INSOE CONTAINMENT LOSS OF COOLANT ACCCENT ANALYSES FOR THE BELLEFONTE (OCTOBER 171980 INDIAN POINT 2 EVENTL NUCLE AR PLANT NUREGICR-4663 CLOSEOUT OF IE BULLETIN 83 01. FAILURE OF RE. NUREG/CR4966 V02 EVALUATON OF OPERATONAL SAFETY AT , ACTOR TR!P BREAKERS (WEST 6NGHOUSE 08-50) TO OPEN ON BABCOCK AND WILCOX PLANTS Volurne 2 Therrnal-Hydraulic Re-AUTOMATIC TR*P SGN AL sums. NUREG/CR-4664: CLOSEOUT U IE BULLETIN 83-04 FAILURE OF THE UNDERVOLTAGE Trip FUNCTION OF REACTOR TR:P BREAK. DOCTOR.S.R.  ! N REGICR4690 V01 N1: GENERC COMMUNICATONS NUREG/CR4469 V04. NONDES'RUCTNE EXAMWATON (NDE) REU-INDEX bstegs Of commurucahons (19711986). ABluTY FOR INSERitCE INSPECTION OF LIGHT W ATER I NUREG/CR4690 V02 GENERC COMMUNICATIONS INDEX User's REACTORS Semannual Recort October 1985 March 1986. I Manual NUREG/CR4469 V05. NONDESTRUCTIVE EXAM; NATION (NDE) REll. ABruTY FOR INSERVICE INSPECTON OF UGHT WATER DEARING,1F. REACTORS Sernannual Report. Aprt$eptember 1986 NUREGICR-4742. MELPROG PWR/ MOD 1 ANALYSl$ OF A TMLB AC. NUREG/CR4469 V06: NONDESTRUCTfVE EXAMiNATON (NDE) REU-UlOENT SEQUENCE ABluTY FOR INSERVICE INSPECTON OF UGHT WATER REACTORS Semiannual Report. October 1986 March 1987. DE DOR.J. NUREGICA-4583 V02- DEVELOPMENT ANU VALOATON OF A REAL. NUREG/CA-4797. PROGRESS REVIEWS OF SIX SAFETY PARAME- TIME SAFT-UT SYSTEM FOR THE INSPECTON OF UGHT WATER TER DISPLAY SYSTEMS REACTOR COMPONENTS Annual Report. October 19A4 . September DEFFENSAUGH,1 1985 NUREG/CR4563 V03- DEVELOPMENT AND VALCATION OF A REAL. NUREG/CR-4469 V04. NONDESTRUCTIVE EXAM 1NATON (NDE) REU-ABluTY FOR INSERVICE INSPECTON OF LCHT WATER TIME SAFT-UT SYSTEM FOR THE INSPECTON OF UGHT WATER < RFACTC43 Sefnannual Report, October 1985. March 1986 REACTOR COMPONENTS Annual ReportOctober 1985 September 1966 NVREG/CR4469 V05: NONDESTRUCTIVE ExAMrNATON (NDE) REU. NUREGICA 4970- STAINLESS STEEL ROUND 'OBIN ABluTY FOR INSERVCE INSPECT 60N OF LGHT WATER REACTORS Sernannual Roport Apr6 September 1966 TEST.Contntugalty Cast Staniess Steel Screeneg Phase r NuaEGICR4469 vo6. NONDESTRUCTIVE EXAMINATION (NDE) REL'. DOMam AB;UTY FOR INSERVICE INSPECTION OF UGHT WATER REACTORS Sem. annual Report, October 1986 March 1987. NUREG/CR-4711: LOW UPPER SHELF TOUGHNESS.HIGH-TRANSI. TON TEMPERATURE TEST INSERT IN HSST PTSE 2 YELSEL AND 1 DEMOSS.G. WOE-PLATE TEST SPECIMENS Fenal Report i NUREG/CR48'O. EVALVATON OF O'ESEL UNAVAILABluTY AND A RISK EFFECTIVE SURVEtLLANCE TEST INTERVALS ' E -  : IN SITU TESTING OF THE SHIPPINGPORT ATOMIC DENNIG,R.L POWER STATON ELECTRCAL CIRCUITS NUREG-1275: OPERATING EXPERIENCE FEEDBACK REPORT . NEW PLANTS Commercial Power Reactors I 4 DENNING.R.S. MEDIA 4 ' NUREG 1150 ORF V1 FC: REACTOR RISK REFERENCE > DOCUMENT Mac Report L aM For Comment DOUGLAS.S.C. ' NUREG 1150 DRF Y2 FC: REACTOR RISK REFERENCE NUREG/CR4963 BORON CARBCE STEAM REACTIONS WITH DOCUMENT Appendices A lOraft For Comment CES1UM HYDROXCE AND WITH CEStVM 000E AT 1270K LN AN DE NNIS.G.W. i NUREG/CR-473s COMBUSTON AEROSOLS FORMED DURiNG poyt,R.c, i BURNING OF RADtOACTIVELY CONTAM!NATED MATERIALS EX- ' NUREGICR4987. SIMULATED SEISMC TESTS ON 1/42. AND 1/14 PER MENTAt RESULTS SCALE CATEGORY L AUxlUARY ButLDING DE NSON,R.H. DRtSK ELL,W.E. } 4 NUREG/CR-5041 V01. RECOMMENDATONS TO THE NFsC FOR NUREG/CR4845. AN ANALYSIS OF THE SEMfSCALE MOO 2C S-NH-3 I REVIEW CRITERIA FOR ALTERNATIVE METHODS OF LOW-LEVEL TEST UstNG THE TRAC PF1 COMPUTER PROGRAM RADCACTrVE W ASTE OtSPOSAL Task 2a Beso* Ground Vaults DROUIN M.T. DEUTSCH,W.4 NUREG/CR-4550 V01: ANALYSIS OF CORE DAMAGE FREQU'.NCY NUREG/CR4808 M:NTEO USER'S MANUAL FROM NTERNAL EVENTS METHODOLOGY GUCELINES MTA,Y NUREG/Ci 455C' V0$PTI: ANALYSIS OF CORE DAMAGE FREQUEN-NUREG/CR-4859 SEISMIC FRAGIUTY TEST OF A 6-INCH DIAMETER CY F TR EVENTS R G NT 8 A g PtPE SYSTEM CY FROM INTERNAL EVENTS GR AND GULF, UNIT 1 Appereces DIAMOND.G L SBIT RENALI RY N E RA NU EG/ 4753 V02 CANADIAN SEISMC AGREEME NT>anual [ Report ' DfDWALLE.M. NUREC/CR-416v V02. CRITICAL PARAMETERS FOR A HGHLEVEL DUCE.S A WJTE REPUSITORY Volume 2 Tun NUREG/L ' # f86 TRANSPORT BEHAVOR OF OOtNE IN EFFLUENT NUREGICR-4161 V03 CRITICAL PARAMETER *, FCR A HGH-LEVEL RADv F ' (ITY MONITORING SYSTEMS. W ASTE REPOSITORY. Volume 3 Sait DIMA.*420.M. NURE i A-5040. RAOiONUCLOE MGRATION AROUND URANIUM NUREG/CR4843 V01: UNfvERSITY OF MARYLAND AT COLLEGE ort BOOiES ANALOGUE OF RADCACTivE WASTE PARK (UMCP) 2x4 LOOP TEST FACIUTY Arnuel Report For 1985 REPOSITOR!ES Annuat Report For 1984-1965

84 Personal Author index DUNKE LMAN,M.M. E WING.M.C. NUREG 1213 R01: PLANS AND SCHEDULES FOR IMPLEMENTATON NUREG/CR4842. A STUDY OF NATURAL GLASS ANALOGUES AS OF U S. NUCLEAR REGULATORY COMMJSSION RESPONSIBillTIES APPUED TO ALTERATON OF NUCLEAR WASTE GLASS. UNDER THE LOW LEVEL RADICACTIVE WASTE POUCY AMEND-MENTS ACT OF 1985 (PL 99-240). F AB6C.S. DUNWOODY,W.E. NUREG/CR 5011: APPLICATCN OF THE ADAPTIVE-PREDICTIVE CONTROLLERS TO PLANT SAFETY SURVEILLANCE UTIU2iNG ON-NUREG/CR4987. SIMULATED SEISM C TESTS ON 1/42- AND 1/14- LINE PLANT ANALYZER. i . SCALE CATEGORY 1, AUXIUARY BUILD 6N3 F AILE Y,M.P.

                                                                                                                                                           '           LONG TERM PERFORMANCE OF SPENT FUEL EG CR4457: AGING OF CLASS 1E BATTERIES IN SAFETY SYS-ASTE TEMS OF NUCLEAR POWER PLANTS NUREG/CR-4786: TRANSPORT BEHAVCR OF COINE IN EFFLUENT RADiOAC~lVITY MONITORING SYSTEMS-FANOUS.F[CR4870-NUREG                                        AN EVALUATCN OF THE EFF EHLERS.E.G.                                                                                                                                        DETAILS ON THE CAPACITY OF LWR STEEL CONTAINMENT NUREG/CR4974. INTRAPLATE SEtSMCITY IN THE EASTERN                                                                                                BUILDINGS UNITED STATES FARNSTROM.K.A.

ELUOTT,DL NUREG/CR4815 DEMONSTRATON TESTING OF A SURVEILLANCE NUREG/CR4801: CUMATOLOGY OF EXTREME WINDS IN SOUTH. FOBOT AT BROWNS FERRY NUCLEAR Pt. ANT 1na4 sis Of Costs ERN CALIFORN!A. And Benefits. [ ELRICK.R.M. FARRAR,C. I NUREG/CR-4963 BORON CARBCE - STEAM REACTCNS WITH NUREG/CR4987. SIMULATED SEISMC TESTS ON 1/42. AND 1/14 i' CESIUM HYDROXtDE A) D WITH CESIW CDCE AT 1270K IN AN SCALE CATEGORY 1, AUXtUARY BUILDlNG LHCONEL 600 SYSTEM. 4 F E LTM AN.A. E MSAE Y,0.E. q NUREG/CR-4016 V02. APPUCATICW OF SUM MAUD A TEST OF AN NUREG/CR4815 DEMONSTRATCN TESTING OF A SURVEILLANCE RODOT AT BROWNS FERRY NUCLEAR PLANT Anaysis Of Costs INTERACTIVE COVPUTER-BASEi) METHOD FOR ORGAN 121NG A/v3 Benefits. i EXPERT ASSESSMENT OF HUMAN PERFORMANCE AND l REUABfUTY. Volume II Appen$ces FERRELL WL I NUREG/CR4550 V04 ANALYSIS OF CORE DAMAGE FREQUENCY l . NU 1 0 STANDARD FORMAT AND CONTENT ACCEPTANCE INTERM EVENTS PEACH BOMOM UNJ 2. CRITERtA FOR THE MATERIAL CONTROL AND ACCOUNTING piggy,M w, (MC& A) REFORM AMENDMENT,10 CFR Part 74 Setcart E NUREGICP 0086 vot- PROCEEDINGS OF THE 19TH DOE /NRC NU. EMRIT'R CLEAR AIR CLEAN'NG CONFE RENCE . Held in NUREG4933 S06 A PRORitt2ATON OF GENERC SAFETY ISSUES yya y on 82 ( 86 GS OF THE 197H DOE /NRC NU. i ENDE DROCK.E. CLEAR AIR CLEANING CONFERENCE Held in

   ' NUREGICR-4987 S MULATED SEISMC TESTS ON 1/42. AND 1/14                                                                                         Seattle.Washogton, August 18 21,1986.

SCALE CATEGORY t, AUXfuARY BUILDING ERICSON D.M. NUREG/CR4829 V01: SHIPPING CONTAINER RESPONSE TO NUREG/CR 4448 SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF SEVERE HIGHW AY AND RAILWAY ACCCENT CONDITCN$ Mac f A GENERAL ELECTAC BWR3 MARK ICase Study Report. NUREG/CR-4458 SHUTDOWN DECAY MEAT REwVAL ANALYSIS OF NUREG/CR4829 VC2 SHIPPING CONTAINER RESPONSE TO A WESTINGHOUSE 2400P PRES $Ur. ZED WATER REACTOR Case SEVERE HIGHW AY AND R AILW AY ACCCENT NA /CR-4710 SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF A COUBUSTON ENGINEER!NG PRESSURt2ED WATER FISHE R.D.R. RE ACTOR Case Stuoy NUREG/CR-4713 SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF NUREG/CR-4856 FEASIBILITY STUDY ON A DATA-BASED SYSTEM A BABCOCK AND WILCOX PRESSURIZED WATER REACTOR Case FOR DECISONS REGARDiNG OCCUPATCNAL RADIATON PRO- l TECTCN MEASURES A #

• NUR /CR-4762. SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF A WESTINGHOUSE 3 LOOP PRESSUR12ED W ATER REACTOR Case FISHER,J E.

NUR /CR4767. SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF ThE OA RE T A GENERAL ELECTRC BWR4/ MARK 1 Case Study FISK,P.S. ERNST.ML NUREG 1150 DRF V1 FC REACTOR WSK 'EFERENCE NUF EG/CR4957 $URVEY OF GEOPH Y SeC AL TECHNCUES FOR DOCUMENT Vain Report Dra't For Comment SITE CHARACTER!2ATION IN BASALT. SALT AND TUFF ESCALANTE.E FITZPADtlCK R. NUREG/CRUT35 V01 EVALUATON AND COMPILATON OF DOE NUREG/CR-4405 PROBAB'USTC RISK ASSESSMENT (PRA) IN. WASTE PACKME TEST DATA B$ annual Report Decemtier 1985 - SIGHTS NU CR4735 V02 EVALUATON AND COMPILATON OF DOE FLETCHE R.C.D. WASTE PACKAGE TEST DATA B. annual Report August 1936 Janu- NUREG/CR4672 ANALYSIS OF INSTRUVENT TUBE RUPTURES IN ( 87 1967' WESTINGHOUSE 4 LOOP PRESSURIZED WATER REACTORS MIREG/CR-4966 V02 EVALUATON OF OPERATONAL SAFETY AT ETTUNGERL h>BCCCK AND WILCOx PLANTS Volume 2 ThermatHydrauhe Re-1 NUREG/CA 4783 ANALYS:S OF BALANCE OF PLANT REGULATORY sun F OLE Y,W.J.

'j E V ANS.D.D.                                                                                                                      NUREG/CR-4.04 CLOSEOUT OF IE BULLETIN 80-24 PREVENTON NUREG/CR 4654        RADONUCUDE                      TRANSPORT AS VAPOR                                                                    OF DAMAGE DUE TO W ATER LE AKAGE INS DE CONTAINMENT i       THROUGH UNSATURATED FRACTURED ROCK                                                                                                     (OCTOBE R 17.1980 iNDI AN POINT 2 EVENT)

{ NUREG/GR-4655 UNSATURATEC FLOW AND TRANSPORT NUREG/CR-4663 CLOSEOUT OF IE BULLETIN 8341 F AILURE OF RE-THROUGH FRACTURED ROCK RELATED TO HGH-LEVEL W ASTE ACTOR TRIP BREAnERS (WESTINGHOUSE DB 50) TO OPEN ON

;        REPOSITORtES Fnal Report Pnase it.                                                                                                     AUTOMAT:C TRIP SIGNAL i

d J

                                  , . , _ . _ _ _ _ _ _ .                  _          .m                    ._                                                                     --             --

Personal Author index 85 NUR E G / CR-4664 CLOSEOUT OF IE BULLET:N 83-04 FA! LURE OF NUREG-1710 V02. PILOT PROGRAM NRC SEVERE REACTOR ACCI. THE UNDERv0LTAGE TR,P FUNCTION OF REACTOR T AiP BREAK- DENT INL OENT RESPONSE TRA:NiNG MANUALSevere Reactor % ERS cdent Ov sven NUREG-12 1 V03 PILOT PROGRAM NRC SEVERE REACTOR ACCb FORD.R E. DENT .. ACENT RESPONSE TRAlN NG MANUALResponse of Lu NUAEG/CR-4617 ONSITE ASSESSVENTS OF THE EFFECTIVENESS censee Ana 6 tate And Local Off cia's AND :UPACTS OF UPGRADED EMERGENCY OPcRATiNG PROCE- NUREG 1210 V04 PILOT PROGRAM NRC SEVERE REACTOR ACCI-DURES

• DENT \NCCENT RESPONSE TRAIN'NG MANUAL Public Protective Actions . Predeterrmt ed Crrtera And Irhtial Actions F R A K E R.A. NUAEG-1210 V; 5- PILOT PROGRAM NRC SEVERE REACTOR ACCI-NVAEGiCR-4735 V01 EVALUATON AND CCVPitATION OF DOE DENT INCIDE H RESPONSE TRAINtNG MANUAL U S Nuclear Regs.

WASTE PACKAGE TEST CATA. B annual Report December 19a'i ' latory Comm.ss,or) Resconse Jul 19A6 NUR G/CR-4735 V02 EVALUATION AND COMP:LAllON OF DOE GtL BE RT,0.W. W ASTE PACKAGE TEST DAT A B< annual Foport August 1986 - Janu- NUREGICR-3024 SUST AlNE D CONCRETE ATTACK BY LOW-ary 193T TEVPERATUAE,FRAGVENTED CORE DEBRIS F R E NC H,C.S. GILBERT.R.W. NUREG /CR-4Bs4 INTERPRETATION OF '., CASE AY ME ASUREVENTS NUREG/CR-4583 V02 DEVELOPVENT AND VAUDATION OF A REAL-FRIESELM A. TIVE SAFT-UT SYSTEM FOR THE INSPE"TION OF UGHT WATER REACTOR COMPONENTS Annual I pportOctober 1964 - September NUAEG/CR-4300 V04 N1 ACOUSTFC EM S$ON/ FLAW RELATON SH P FOR IN-SERVICE VONfTORiNG OF NUCLE AR PRESSURE 1995 VESSELS Progress Report. Octcter 1986 March 19>37 F" LEY,J R. NUREG'CR.4301. STATUS REPORT ON EOViPMENT OUALIFICATION NMEGCR 3231 PIPE-TO PIPE iVF ACT PROG A AM ISSUES RESEARCH AND RESOLUTCN FUENTES,H R. GINZBURG,T. NUREG/CR-4615 V02 VODEUN3 STUDY OF SOLUTE TRANSPORT NUR E G / CR-4810 EVALUATION OF OtESEL UNAVAILABiUTY AND IN THE UNSATUR ATED ZONE Workshop Proceesngs R:Sv EFFECTIVE SURVE'LLANCE TEST INTERVALS NUREG'CR-4737 LNTE RPRE T ATivE AN A LY sis OF DATA FOR SO: UTE TR ANSPORT tN THE UNS ATUAATED ZONE GLA DN E Y,E.S. NUAEG'CA 4975 CHARACTER:ZATON OF CRUSHED TUFF FOR THE NUREG/CR-4875 CHAAACTER:ZATION OF CRUSHED TUFF FOR THE EVALUATION OF THE F ATE OF TRACERS IN TRANSPORT STUD.ES EVALUATICN OF THE FATE OF TRACERS IN TRANSPORT STUDIES IN THE UNSATUAATED ZONE iN THE UNSATURATED ZONE NL A E G ICR-4 901 EFF ECTS F ADV INFLUENT BOUNDARY CONDb TCNS ON TRACER V.GRATON AND SPATIAL VAR!ABlUTY FE A- GLOVE R.L TVAE S IN INTERVEDiATE-SCALE E)PE A VENTS NUR E G J C A-4973 INTRAPLATE SEISViCITY OUTSCE OF YHE UNITED ST ATES NUAEG'CR 4752 CO NCIDENT STEAM GENERATOR TUBE AVPTURE GLO2M AN.V. AND STUCK-OPE N SAFETY REUEF VALVE CARRYOVER NUAEG/CR 4900 Voi COVDONENT FR AGIUTY RESEARCH TESTS VB 2 Steam Generator Transient Resconse Test Proyam F'ROGR AM Phase i Demonstra$on Tests Summary Report NUREG'CR 4900 VC2 COVPONENT FRAGrUTY RESEARCH

                                                                                         * ** I          *                     "

REG 4752 CO:NCCENT STE AV GENERATOR TLBE RUPTUAE AND STUCK OPEN SAFETY REUEF VALVE CARRv0iER GLYNN J C' TESTS VB 2 Steam Generator Transet Respor'se Test Proyam gp h- t 150 DAF V1 FC REACTOR RISK REFERENCE DOCUVENT Maen Report Dra.t For Cownent G A RLA N D,T.R. NUREG%A 4976 PLANT RH'20SPnERE PROCESSES INFLUENC.N3 GOMRE M R ADIONUCLCE VOB'UTv rN Soit NUAEG7CA-5036 COST AN ALYS!S FOR IVPLEMENTATCN OF PRO-POSED CHANGES IN VIT AL ARE A REQU;REVENTS GARNSEY.R NJAEG CA-4752 CONCCENT STE AV GENERATOR TueE RUPTURE AND STUC COPE N SAFETY REUEF V Alv E CAARYOvER G/CR 3320 V03 LWR PRESSURE VESSEL SURVEtLLAUCE DO-TE STS M9 2 Steam Generator Trarsient Response Test Proyam SVETRY JVPROV E VE NT PROGR AV PSF Phys <s Desamet9 Pro-G ASSE R.R D. 9 am NVAEG'CR 496 CONTAAVENT LOADS DUE TO DIRECT CONTA4 NUAEGrCR-3320 V04 L AR PRESSURE VESSEL SURVEfLLANCE DO. S'UE TRY tMPRON EVENT PROGR A / PSF Veta!!urgy Program MENT HE AT.NG AND ASSOCIATED HYDROGEN BEHAVCR Anaws And Ca*cu'abens W.to The CONT A!N Code G A USS E NS,G, NVAEG'CR 5035 DATA BASE OF SYSTEM AVERAGE DOSE RATES AT NUCLEAR POWER PLANTS Fenal Report NUREG'CR 4530 V02 U S < F RENCH JOAT RESE ARCH PROGRAu REG ARD NG THE EEHaviOA OF POLYVER B ASE VATER ALS SUB JECTED TO BET A R AD' ATION VoVrne 2 Pnase 2a Screenmg Tes's GOLDIN.DJ. NUAEG/CR-5035 DAT A B ASE OF SYSTEM AVER AGE DOSE RATES AT NUCLE AA POWER PLANTS Fnat Report GELEIN.R M. NU AEG'CA 4951 NEPHROTOoC!TY OF UA ANyL FLUOR DE AND RE-GOLDM AN,P. VERS 8'UTY OF REN AL INJURY IN THE RAT NVAEG'CA 4997 S VULATED SEtSV.C TESTS ON 1/42 AND 1/14 GERH ARD M.A. SCALE CATEGORY t. AUCUARY BU!LD:NG NVAEG,CR 4829 V01 SH PPING CONT A AE R AE SPONSE TO GOLt AN,C. SEiE RE H6GHW AY AND A AILW AY ACC'DE N T CONDITCNS Va.n R eport NUAiG CR 5043 A AD)ONUCUDE V'GRATION AROUND UA ANtVM NUAEG'CR 4929 VC2 SH. PPM CONT AINE R AE SPON SE TO OAE BODES AN ALOGUE OF R A DC ACTIVt. W ASTE SEVERE H'GH W A Y AND RA:LWAY ACC'DE NT AEPOSiTOA E S Annva' Report For 1994 1945 CONDmONS AppeMges NVAE G 'CR 5%0 AN APPROACH TO T HE V ATHEV ATlCA( y)CE (. UNG CA THE UAANtV SER'ES REDiSTR'BUTION WITH N ORE GNTTE R.J G BOD ES NURE G 1210 V01 PiL CT PROGA AV NAC SEVERE RE ACTOR ACCI DE NT INCIDE NT RE SPONSE TR A:N'NG M ANU AL CNew. AM Sam- GOMEZ,R D. ma y O' Vaor PoiNs NUAEG/C A 4871 RE SULTS FROV THE DCH I E WER VENT

88 Persord Author Index GOh2ALEZ.R.C. GRIESMEYERJ.M. NUREG/CR4577: AUTOMATED LONG TERM SUHvEfLLANCE OF A NUREG/CR4551 V3 PT1: EVALUATON OF SEVERE ACCOENT RISKS COMMERCIAL NUCLEAR POWER PLANT. AND THE POTENTIAL FOR RISK REDUCTON PEACH BOTTOM. UNIT 2.Mac Report Dre't For Comment. GOOO.ES- NUREG/CR4551 V3 PT2. EVALUATON OF SEVERE ACCIDENT RISKS NUREG/CR4469 V04: NONDESTRUCTIVE EXAMiNATON (NDE) REU- AND THE POTENTIAL - FOR- RISK REDUCTON PEACH ABILITY FOR INSERVICE INSPECTON OF LIGHT WATER BOTTOM. UNIT 2 Appereces Uraft For Comment. REACTORS Semannual Report, October 1985 March 1966 NUREG/CR4469 V05: NONDESTRUCTIVE EXAMiNATON (NDE) REll- GRIESS).C. ABluTY FOR INSERVICE INSPECTON OF . LIGHT WATER NUREG/CR4134 R01: REPOSITORY ENYlRONMENTAL PARAM. REACTORS Somannual Report. AprWLSeptember 1986 ETERS AND MODELS RELEVANT TO ASSESLNG THE PERFORM. NUREG/CR4469 V06- NONDESTRUCTIVE EXAMINATION (NDE) REU- ANCE OF HIGH-LEVEL WASTE PACKAGES (BASALT, TUFF AND ABluTY FOR INSERVCE tNSPECTION OF LIGHT WATEri SALTL RE ACTORS Semannual Report. October 1986 March 1987. GRIFFIN,E.A. UR 1258. EVALUATON PROCEDURE FOR SIMULATION FAClu- NUREG/CR-4e95: MATERIAL CONTROL AND ACCOUNTING (MC&A) TIES CERTIFIED UNDER 10 CFR 55 Foot Report.

                                                                                              "         b          b        bb NUREG/CR-4768 V01: METHODOLOGY AND APPUCATON OF SUR-               UPSET CONDITONS ROGATE PLANT PRA ANALYSIS TO THE RANCHO SECO POWER           GRIFFINJ.J*

PLANT. Task 1 - Anayses Of ANO 1 And Oconee PRAs NUREG/CR-4768 V02: METHODOLOGY AND APPUCATON OF SUR, NUREG/CR4826 V03 SEtSMC MARGIN REVIEW OF THE MAINE POGATE PLANT PRA ANALYSIS TO THE RANCHO SECO POWER YANKEE ATOMC POWER STATON Volume 3 Fraglaty Analyses. PLANT Feal Ap GRIFFITH.P NURE APPUCATON PROGRAM FOR INSPECTON NUREG/CR-4922. STEAM SEPARATOR MODELING FOR VAROUS NUCLEAR REACTOR TRANSIENTS. GOTCHY.R.L NUREG/CR 5007. PREDCTON AND MITIGATON OF EROSIVECOR. NUREG 0332: POTENTIAL HEALTH AND ENVIRONVENTAL IMPACTS ROSIVE WEAR IN SECONDARY PIPING SYSTEMS OF NUCLEAR ATTRIBUTABLE TO THE NUCLEAR AND COAL FUEL CYCLES Fma; POWER PLANTS. GRONAGERJE. GOTTULA.R.C. NUREG/CR-4727. SWISS SUSTAINED HEATED METALLC MELT / CON. NUREG/CR4165: SEVERE ACCIDENT SEOUENCE ANALYSIS PRO. CRETE INTERACTONS WITH OVERT YlNG W ATER POOLS. GRAM ANTCIPATED TRANSIENT WITHOUT SCRAM S:MULA-TONS FOR BROWNS FERRY NUCLEAR PLANT UNIT 1. GRUEN.G.E. NUREG/CR4965. TRAC.PF1/ MOD 1 US/ JAPANESE PWR CONSERVA. GRAHN.D. TlVE LOC A PREDICTON NUREG/CR4704 VQ1: RELATIVE BIOLOGCAL EFFECTIVENESS (RBE) OF FISSON NEUTRONS AND GAMMA RAYS AT OCCUPATIONAL GUERRIERI.D. EXPOSURE LEVELSvolume 1. Stees On The Genetic ENects in NUREG/CR-4082 V05. DEGRADED PIPING PROGRAM . PHASE Mice Of 60 Equal Once-Weeuy Exposures To Fason Neutrons And 11 Semiannual Report. Aprs September 1966 Gamma Rays. NUREG/CR-4704 V02. RELATIVE BOLOGCAL EFFECTIVENESS (RBE) GURINSKY.D.H. OF FISSION NEUTRONS AND GAMMA RAYS AT OCCUPATONAL NUREG/CR4981: A SAFETY ASSESWENT OF THE USE OF GRAPH-EXPOSURE LEVELSVolume II. Stuoes On The Enects Of 60 Equal ITE IN NUCLEAR REACTORS IOENSED BY THE U S NRC. Once-Weeuy Exposures to Fesson Neutrons Ard Gamma Rays On Swvival Of Mice GUZIE L,K.A. NUREG/CR4012 V07. REPLACEMENT ENERGY COSTS FOR NUCLE-GRAMANNS.H. AR ELECTRTY GENERATING UN'TS IN THE UNITED NUREG-0525 R12 SAFEGUARDS

SUMMARY

EVENT UST (SSEL) STATE S 19C1991. I GR AVE S.H.L HABEGGEM.LJ. l NUREG /CP4054 PROCEEDlNGS OF THE WORKSHOP ON SOIL- Nup2G/CR-4964. UPDATE OF TABLE S-3 NONRADOLOGICAL ENV1-STRUCTURE INTERACTON. HONMENTAL PARAMETERS FOR A REFERENCE LIGHT WATER l l GRAVES,N.L anun Ennc h I NUREG/CR4834 V01. REGOVERY ACTONS IN PRA FOR THE RISK HACK E TT.E.M. k METHODS INTEGRATION AND EVALUATON PROGRAM NUREGICR4818 TRANSITON RANGE DROP TOWER 1R CURVE sRM'EP). Volume 1 Deve6opment Of The Data-Based Methoi1 TESTING OF A106 STEEL HAGE N.E'W* 0"AI'EN'CR-5025 NUREG/ EXPER: MENTAL STUDIES OF THE EARLY EFFECTS NUREGICR-4674 V03: PRECURSORS TO POTENTIAL SEVERE CORE OF INHALED BETA-EMITTING RADONUCUDES FOR NUCLEAR AC-CtDENT RISK ASSESSMENT Phase il Ap DAMAGE ACCCENTS 1984.A STATUS REPO"T Man Report And Ap-pendnes A And 8 GRE EN.E.R. NUREG/CR-4674 V04 PRECURSORS TO POTENTIAL SEVERE CORE NUREG/CR4469 V06. NONDESTRUCTIVE EXAMiNATON (NDE) REll. DAMAGE ACCCENTS 1984.A STATUS REPORT Appermes C.D And AB;UTY FOR INSFRV)CE INSPECTION OF LIGHT W ATER E. REACTORS Sem6 annual Report October 1986 - March 1987. g3ggggg,g,L GRE EN.R.T. NUREG/CR.4925 FISSON PRODUCT BEHAVIOR DURING THE PBF NUREG/CR4654: RADONJCL OE TRANSPORT AS VAPOR SEVERE FUEL DAMAGE TEST 11. THROUGH UNSATURATED FRACTURED ROCK. GRE GOR Y,W.S. NUREG/CR-5025 EXPER: MENTAL STUDIES OF THE EARLY EFFECTS NUREG/CR4931: RESPONSE OF CENT RIFUGAL AND AKi VANE OF INHALED BETA-EMITTING RADIONUCUDES FOR NUCLEAR AC-BLOWERS TO LARGE PRCi.A)RE TRANSIENTS CIDENT RISK ASSESSMENT Phase il Report GREIMANN.L HALLD.G. NUREGICR-4870 AN EVALUATON OF THE EFFECTS OF DESON NUREG/CR4802' AN EVALUATION OF TRAC.PFliMODI COMPUTER DETAILS ON THE CAPACITY OF LWR STEEL CONTAINMENT CODE PERFORMANCE DURtNG POSTTEST SIMULATONS OF SE. BUILDINGS M; SCALE MOC 2C FEEDWATER UNE BREAK TRANSIENTS

Personal Author index 87 i L HALL.T.E. HARRISON.S. NUREG/CR4583 V02: DEVELOPMENT AND VALOATION OF A REAL. NUREG/CR4735 V02: EVALUATON AND COMPILATON OF DOE . TIME SAFT.UT SYSTEM FOR THE INSPECTION OF UGHT WATER WASTE PACKAGE TEST DATA. B. annual Report August 1986. Janu- t l REAC ** COMPONENTS Annual Report. October 1984 September a/y 1987. I 1985. I r NOREG CR-4583 V03 DEVELOPMENT AND VAUDATION OF A REAL- H AR TWE L L.J.K. TIME SAFT.dT SYSTEM FOR THE INSPECTON OF UGHT WATER NUREG/CR4925 FISSION PRODUCT BEHAVOR DURING THE PBF [ REACTOR COMPONENTS Annual Report. October 1985 - September SEVERE FUEL DAMAGE TEST 11-1986. HARTY,R. HALLSERT.B.P. NUREG/CR4938. OCCUPATONAL RADIATON EXPOSURES ASSOCl- l NUREG/CR4966 V01: EVALUATION OF OPERATONAL SAFETY AT ATED WITH ALTERNATIVE METHODS OF LOW LEVEL WASTE DIS-BABCOCK AND WILCOX PLANTS. Volume 1. Results Overview poSAL H ALVE RSON.W.A. METERS E NUREG/CR.4736: COMBUSTON AEROSOLS FORMED DURtNG BURN 2NG OF RADCACTivELY CONTAMINATED MATERIALS EX- HAnygy,g.w, PERiMENTAL RESULTS- NUREG/CR4815: DEMONSTRATON TESTING OF A SURVEtLLANCE HAMILTON.S.P. ROBOT AT BROWNS FERRY NUCLEAR PLANT.AnaWs Of Costs NUREG/CR-4012 V02. REPLACEMENT ENERGY COSTS FOR NUCLE. And Benehts. AR ELECTRCITY GENERATING UNITS LN THE UNITED gaggggigg,g g, i STATES 1987 1991- NUREG/CR4928 DEGRADATION OF NUCLEAR PLANT TEMPERA. H ANEY.LN. 1DGE SCNSORS r NUREG/CR4617. ONSITE ASSESSMENTS OF THE EFFECTIVENESS A tMPACTS OF UPGRADED EMERGENCY OFERATING PROCE. HASH T P . g YANKEE ATOMIC POWER STATON Volume 3 Frapty Analysis HANNINEN,H.E. NUREG/CR4663, SURFACE SPECTROSCOPY OF PRESSURE HASKIN,F.E. VESSEL STEEL FAtlGUE FRACTURE SURFACE FILMS FORMED IN NUREG/CR-4551 V3 PT1: EVALUATON OF SEVERE ACCOENT RISKS PWR ENVIRONMENTS. AND THE POTENTIAL FOR RISK REDUCTON PEACH BOTIOM. UNIT 2.Mm ReportDraft For Comment HANSON.D.J. NUREG/CR4551 V3 PT2 EVALUATON OF SEVERE ACCOENT RISKS NUREGICR4696 CONTAINMENT VENTING ANALYSIS FOR THE AND THE POTENTIAL FOR RISK REDUCTON PEACH  ! PEACH BOTTOM ATOMC POWER STATON BOTTOM. UNIT 2 Append ces Dra't For Comment NUREG/CR-4966 V01. EVALUATON OF OPERATONAL SAFETY AT BABCOCK AND WILCOX PLANTS Volume 1 Resuts r Overv.ew HATCH,$.W. NUREG/CR4448 SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF HANSON,R. A GENERAL ELECTRC BAR3/ MARK ICase Study NUREG 1270 V01: INTERNATONAL CODE ASSESSMENT AND APPU. NUREG/CR4767. SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF

                                                                                                                                                          ^0"           '                   "' # "#   

• NUREG 71 G ID N WOCEDURES FOR THE INTERNA-TONAL CODE ASSESSVENT AND APPLCATONS PROGRAM. Hg A g(g g,p,q, NUREG/CR.4469 V04: NONDESTRUCTIVE EXAM: NATION (NDE) REU-1 HARDIN.JNUREG/C E'R 4457: AGtNG OF CLASS 1E BATTER:ES IN SAFETY ABluTY FOR INSERVCE INSPECTON OF UGHT WATER SYS-l TEMS OF NUCLEAR POWER PLANTS REANS Semaw Re*Ocw W March 1986 e

                                                                                                                                                                                                                                    +

NUREG/CR 4469 VOS NONDESTRUCTIVE EXAMINATON iNDE) REU. HARDY,0.S. AB!UTY FOR INSERVCE INSPECTON OF UGHT W ATER NUREG/CR4826 V03. SEISMC MARGIN REVIEW OF THE MAINE RE ACTORS Semannual Report. Apnt-September 1986 YANKEE ATOM C POWER STATON Volume 3 Frapty Anavsrs NUREG/CR-4469 V06 NONDESTRUCTIVE EXAV;NATON (NDE) REU-ABluTY FOR INSERVICE INSPECTON OF UGHT WATER HA R LAN.C.P. REACTORS Semannual Report. October 1986 Ma*ch 1987. NUREG/CR4766 USER S MANUAL FOR THE NEFTRAN COMPUTER NUREG/CR4970: STAINLESS STEEL ROUND ROB:N i CODE. TEST Centntugany Cast Stainless Steet Screemng Phase HARMS.N L HE LD.J.T. NVPEG/CR 4773 DESIGN FEATURES TO FACIUTATE INTERNATON- NUREG/CR-4550 V05 ANALYSIS OF CORE DAMAGE FREQUENCY AL SAF EGUARSS AT MJED OxOE CONVERSON FACIUTIES FROM INTERNAL EVENTS: SEQUOYAH. UNIT 1. H AF #E R.F.T. HELTON,J.C. NUREG/CR4550 V01: ANALYSIS OF CORE DAMAGE FREQUENCY NUREG/CR 2452: RISK HETHODOLOGY FOR GEOLOGC DISPOSAL FROM INTERNAL EVENTS METHOOOLOGY GUOELINES OF RADOACTIVE W ASTE. Final Report. l NUREG/CR4550 V03 ANALYSIS OF CORE DAMAGE FREQUENCY NUREG/CA-4551 V3 PT1: EVALUATON OF SEVERE ACCOENT RISKS r FROM INTERNAL EVENTS SURRY. UNIT i- AND THE POTENTIAL FOR RISK REDUCTON PEACH i l NUREG/CR4550 V04 ANALYSIS OF CORE DAMAGE FREQUENCY BOTTOM. UNIT 2 Main ReportDraft For Comment , FROM tNTERNAL EVENTS PEACH BOTTOM UNIT 2 NUREG/CR4551 V3 PT2. EVALUATON OF SEVERE ACCOENT RISKS ' t NUREG/CR4550 VOS ANALYSIS OF CORE DAMAGE FREQUENCY AND THE POT ENTIAL FOR RISK REDUCTION PEACH BOTTOM. UNIT 2 Appereces Draft For Comment i NURE /C 55 NAL C E DAMAGE FREQUEN. CY FROM INTERNAL EVENTS GRAND GULFMNIT 1 Mac Report HENDRfCKSON'P NUREG/CR4550 V06PT2- ANALYSi$ OF 09RE CAMAGE FREOVEN-CY FROM INTERNAL EVENTS GR\ND GULF. UNIT 1.Appereces NUREG/CR-4958 IMPACT OF PROPOSED FINANCIAL ASSURANCE REQU:REMENTS ON NUCLEAR M ATERIALS LICENSEES. HARRIS.Jf NUREG/CR-4674 V03 PRECURSOAS TO POTENTIAL SEVERE CORE HENNICK.A. DAMtGE ACCOENTS 1964.A STATUS REPORT Main Report And Ap- NUREGICR4524 CLOSEOUT OF IE BULLET 4N 80-24 PREVENTON . percies A And g OF DAMAGE DUE TO WATER LEAKAGE INSOE CONTAINUENT f NUREG/CR-46?4 V04 PRECURSORS TO POTENTIAL SEVERE CORE (OCTOBER 17,1980 INDIAN POtNT 2 EVENT). DAMAGE ACCOENTS 1964.A STATUS REPORT Apperdnes C.D And NUREG/CR4663. CLOSEOUT OF IE BULLEnN E34tJAiLURE OF RE-E. ACTOR TRIP BREAKERS (WESTINGHOUSE 08-50) TO OPEN ON AUTOM ATIC TRIP $8GNAL HARRIS,M.S. NUREG/CR4664 CLOSEOUT OF lE BULLETIN 83-04 FAILURE OF NUREG/CR5006 PRA APPLCATION PROGRAM FOR INSPECTON THE UNDERVOLTAGE TA:P FUNCTION OF REACTOR TRIP BREAK. AT OCONCE UNIT 3 ERS

88 Personal Author index NUREGICR4690 V01 N1- GENERC COVMUNICAT ONS HOLM AN,0.S. INDE x Ustngs Of Commun.catons (t 971 19561 NUREG/C.R 4899 COMPONENT FRAGILITY RESEARCH NUREG/CR-4690 V02 GENERIC COVMUN CATCNS INDE x User's PROGRAM Phase l Component Pnorttabon Manual. NUREG/CR 4900 V01 COMPONENT F RAGILITY RESEARCH PROGR AM Phase i Demonstraton Tests Summary Report HENNINGER R.J. NUREG/CR4900 V02 COMPONENT FRAGruTY RESEARCH NUREG/CR4742 VELPROG PWRiMOD1 ANALYS!S OF A TMLB' AC- PROGR AM Phase 1 Demonstraton Tests Appendices CIDENT SEQUENCE NUREG/CR4909 MELPROG PWR/ MODO A VECHANISTIC CODE FOR HOOKER.C.D. ANALYSIS OF REACTOR CORE MELT PROGRESSON AND NESSEL NUREG/ CR-4959 PERFORMANCE TESTING OF EXTREMITY DOSI-ATTACK UNDER SEVERE ACCIDENT CONDITCNS METERS HERRINGTON,W N. HOOPING AR N E R.K. NUREG/CR4938 OCCUPATONAL RADIATION E APOSURES ASSOCI. NUREG /CR-4590 V01 - AGtNG OF NUCLEAR STATCN O'ESEL ATED WITH ALTERNATIVE VETHODS OF LOW-LEVEL WASTE Ots- GENERATORS Eva'uat.on 01 Operating And Empert Experence Phase POSAL i Study NUREG/CR4590 V02 AGING OF NUCLEAR STATION DtESEL RG 2478 V03 A STUDY OF TRENCH COVERS TO M.N V'2E 6AWS Evawon O OperaW And Exped INFtLTRATCN A*. W ASTE DISPOSAL SITES Foal Rept *" H E SS,C. HORSCHELES. NUREG/CR4781 DRFT STUDY OF SEVERE ACCIDENT MtTIGATON NURE G/CR-3412 V02 CONTA:NVENT INTEGRITY SYSTEVS PROGR AV Progress Report.Apnl 1983 -Decemter 1984 n gs,o,a, HOSPODOR,$. NUREG/CR49S6 SYSTEM PERFORMANCE OF HIGH-LEVEL W ASTE NUREGC980 R03 NUCLE AR REGL*LATORY LEGISLAtlON PACKAGE CCMDONENTS HOST ETLE R,C.J. HILLE.E. NUREG/CR 4608 M NTEO USER'S MANUAL NUREG/CR 4910 RELAY CH ATTE R AND OPERATOR RESPONSE AFTER A LARGE EARTHOUAKE An Irnproved PAA Methodolcgy W.th HOW ARD.R. Case Sthes NUREG/CR4815 DEVONSTRATCN TESTING OF A SURVEILLANCE ROBOT AT BROWNS FERRY NUCLEAR PLANT Ana'ys<s Of Costs HILLR.C. And Benetts NUREG/OR4734 OEtSMIC TESTING OF T Y PiCAL CONT A%VE NT PIPING PENFTRATtON SYSTEUS HSU,Y.Y. NURE GICR4521 RE ACTOR COOLANT PUMP SHAFT SE AL STABru. NUREG/CR-4643 V01 UNfVERSITY OF MARYLAND AT COLLEGE TV DUR.NG STATION BLACKOUT. PARK (UVCP) 2x4 LOOP TEST FACIUTY Anrbal Report For 1985 HINKLE N.E. HUB 6E.J M. NUREG /CR4651 DEVELOPVENT OF R;PRAP DES 1GN CRITERIA By NUR E G 'CR J"01 CUV ATOLOGY OF EXTREME W:NDS IN SOU'H-AlPRAP TEST lNG IN FLUVES Phase f ERN CAUFORN1 A HINZE,W.J. HUENEFELD.J C. NUREG/CR 5034 AN UPDATE OF V DCONTINENT TECTONtSM NUREG'CR-4768 V02 UETHOOOLOGY AND APPUCATION OF SUR. ROGATE PLANT PRA ANALYSIS TO THE RANCHO SECO POWER HISERAL PLANT Foal Report l ' NUREG'CR 4894 A USER S GUCE TO THE NRC S PIPING FRAC-TURE VECHANICS DATA BASE (PiFRAC) HUM PHR E YS.P.C. HlVELY,LM. NUREG/CR 4016 V02 APPUCATiON OF SUM MAUD A TEST OF AN INTERACTIVE COVPUTER BAdED METHOD FOR ORGANtZiNG NUREG-1210 V01 PILOT PROGRAV NRC SEVERE RE ACTOR ACCb DENT INCCENT RESPONSE TRAlN;NG MANUAL Overviem And Sum- EzPERT ASSESSVENT OF HUMAN PE RFORM ANCE AND REUABiUTY Volume ll Appereces maey Of Maior Points NUAEG-1210 V02 PILOT PROGR AV NRC SEVERE REACTOR ACCT' HUTTON.P.H. DENT INCIDENT RESPONSE TRAIN NG M ANU AL Severe Reactor Ac-NUREGiCR 4300 V03 N2 ACOUSTC EM:SSON/ FLAW RELATCN. NUR 1 03 PILOT PROGRAM NRC SEVERE REACTOR ACCb S K QTNNG OF NUCLEAR PRESSURE DENT INCCENT RESPONSE TRAIN NG M ANUAL Resconse Of Le p 3[ h*P'$$*T g CN/ FLAW RELATCN. SH:P FOR IN SERVICE MON! TOR:NG OF NUCLEAR PRESSURE NURE 1217 04 P O P RA NRC SEVERE RE ACTOR ACCb DENT INCCENT RESPONSE TRAIN.NG M ANU AL Putmc Protectsve VESSE LS Prcgress Report. October 1986 Varch 1987. Act.ons . Predeterma ed Cntena And in bal A: tons HVM AN.C R NUREG 1210 VCS P! LOT PROGAaM NRC SEVERE RE ACTOR ACCb DENT iNCCENT RESPONSE TRAINING MANU AL U S Nxtear Rep NUREGI CA.4610 EFFECTS OF LATERAL SEPARATCN OF O*CIC 14% hston Response AND VETALUC CORE DE6Ris ON THE B AR Mk I CONTAiNVENT DRrAELL FLCCR HODGSON.W H. NUREG/CR-4779 Nb'. f.,A1 A FOR AEROSOLS GENERATED B f RE. IM AN H L LE ASES OF PRES $U.u2ED POWDERS AND SOLUTIONS IN ST ATiC NUREG/CR 2452 R:SK METHOOOLOGY FOR GEOLOGC OtSPOSAL AIR 05 A ADCACTIVE W ASTE Fenal Report HOLBERT K.E. IN T E RR ANTE,C. NUREG/CR 4926 Cf GRADAT)ON OF NUCLE AR PLANT TEVPER A. NUREG/CR 4735 V01 E VALUATCN AND COVPfLATION OF DOE TURE SENSORS W ASTE PAC

• AGE TEST DATA B annual Report December 1985 -

JJy 1M6 HOLCOMB.E.E. NUREG!CR 4735 V02 EV ALUATON AND COMPILATION OF DOE NURE G/CR 4165 SEVE RE ACCCENT SEQUENCE ANAL Y%s PHO. W ASTE PACP AGE TEST DAT A Bannual Repor1 Aqst 1986 Janu-GRAV ANTCPATED TRANS'ENT WIT HOUT SCRAM S<M JLA- a"y 1 % 7 TONS FOR BROANS FERRY NUCLE AR PLANT UNIT 1 ISACHSEN,Y.W HOLLADAY,C G NUREG'CH 3212 DE T AILED STUDIES OF SELECTED.WELL E xPOSED NUR E G /CH 401 CL:MATOLCx'iY OF E XTRE ME WlNDS LN SOUTH F RACTURE 2ONE S IN THE AD4RONDACK MOUNTA,NS DOVE NEW ERN CAUFORY A YCm

P rt:nal Auth:r Index 89 ISNel,M. JONES,0 M. NUREGiCR4972. TWO-PHASE FLOW REGtME TRANSITCN CRITE. NUREGrCR4826 V02 SEISMC MARGIN REVIEW OF THE MAINE ' RtA IN POST DAYOUT REGON BASED ON FLOW VISUALt2ATON YANKEE ATOMC POWER STATON Votume 2 Sgtems Ana%is FXPERIMENTS. JONES G.W. ISNBEAWA M. NUREGICR4957. SURVEY OF GEOPHYS CAL TECHNiOUES FOR NUREGICR-4765: MxS CROSS-SECTON PREPROCESSOR USER S SITE CHARACTER 12ATON IN BASALT,$ ALT AND TUFF. MANUAL. JOUSE,W.C. JACOSSG4 NUREG/Cr 3165 SEVERE ACCCENT SEQUENCE ANALYSIS PRO-NUREG/CR4708 V01 N1: PROGRESS IN EVALUATON OF RADONU. GRAM ANTCIPATED TRANS ENT WITHOUT SCRAM $NULA. CLtDE GEOCHEMCAL INFORMATON DEVELOPED BY DOE HIGH. TONS FGR BROWNS FERRY NUCLEAR PLANT UNIT 1 LEVEL NUCLEAR WASTE REPOSITORY SITE PROJECTS Somsannual Report For October 1965 March 1986 JOYCE).A. NUREG/CR-4616 TRANSITCN RANGE DROP TOWER J-R CURVE JACOSSONJ.L TESTING OF A106 STEEL NUREG/CR-5010 RELAPS/ MOO 2 ASSESSMENT USING SEMiSCALE EXPERIMENTS S NH 1 AND S.LH-2 JULIUSJ, JAC0005.M J. NUREG/CR4722 SOURCE TERM ESTIMATION USiNG MENU TACT. NUREG/CR-4942: EQUIPMENT OPERABluTY DURING STATION # BLACKOUT EVENTS. NU EG CR4981: A SAFETY ASSESSMENT OF THE USE OF GRAPH-JAMISON.J.D, iTE IN NUCLEAR REACTORS LCENSED BY THE U S. NRC. NUREG/CR4330 V03. REvtEW OF LIGHT W ATER REACTOR REGU- KASSN E R,T.F. LATORY REQUIREMENTS Assessment Of Selected Regulatory Re. Clurements That May Have Marginal importance To R4h Postacc4ent NL' REG /CR4667 V03 ENVIRONVENTALLY ASSISTED CRACMNG IN Samping System. Turt>ne M;ssaes. Combust 6e Gas Control.Charcoaj UGHT WATER RE ACTORS Semiannual Report,Aptd-Sec<tember 1986. KASTEN8 ERG,W,E. JANGJ. NUREGrCR4941. THE APPLICATON OF VALUE-lMPACT ANALYSIS NVREG 0837 V06 NO3 NRC TLD DRECT RAD ATON MONITOR:NG TO USI A45 Summary Report Of UCLA Stuses On vaive tropact Anal. NETWOAK Prooress Report, JuYSeptember 1986 yks in Relaton To USI A45 NVREG 0837 V06 NQ4 NRC TLD DIRECT RADIATON MONITORING NETWORK Progress Report. October Decemter 1966 K AUF M AN,M. NUREG-0837 V07 N01: NRC TLD OtRECT RADIATION MONITOR;NG NUREG/CR4735 Vh EVALUATCN AND COMPILATON OF DOE P

                                                                                                                                                                                                                                                                           ~

NETWORK Progress Report, JanuayMarch 1987. WASTE PACKAF : TEST DATA B annual Report December 1995 - NUREG 0837 V07 NO2 NRC TLD DRECT RADIATON MONITORING Juty 1966 NETWORK. Progress Report. Apnt-June 1987. K E CK,R.G-JAN45 WJ* NURF.G/CR 5007 PREDICTION AND M:T GATCN OF EROSlVE COR. NUREG/CR-4098 SEISMC-FRAGIUTY TESTS OF NEW AND ACCEL- ROSfvE WE AR IN SECONDARY PIPING SYSTEMS OF NUCLEAR ERATED AGEO CLASS 1E BATTERY CELLS POWER PLANTS JENESA K E E F E R.D.A NUREG 1270 V01: INTERNATIONAL CODE ASSESSMENT AND APPU. NU;iEG/CR 2478 V03 A STUOY OF TRENCH COVERS TO min Mi2E < CATONS PROGRAM Annual Report INFILTRATION AT W ASTE DISPOSAL SITES Feel Rept. 4 JENESAP. K E LLE R.G _R. + NUREG/CR4968 A TRAC-PF1/ MOO 1 ANALYSIS OF THE GiNNA TU8E RUPTURE EVENT ON JANUARY 25.1962 NUREG/CR 5034 AN UPDATE OF MOCONTINENT TECTONISM JENSE N.S.M. KELLYJ E. NUREGICA-4925 FtSSON PROOUCT BEHAVCR DURING THE PBF NUREG/CR4742. MELPROG-PWR/ MOO 1 ANALYSIS OF A TMLB' AC- F SEVERE FUEL DAMAGE TEST 11. CCENT SEQUENCE i NUREG/CR4909. MELPROG-PWR/ MODO A MECHAN'STC CODE FOa j JERCINOVIC,MJ, ANALYSIS OF REACTOR CORE MELT PROGRESSON AND VESSEL I NUREG/CR4842 A STUDY OF NATURAL GLAS$ ANALOGUES AS ATTACK UNDER SEVERE ACCCENT CONDITCNS APPUED TO ALTERATON OF NUCLEAR WASTE GLASS 1 KEMPF.C R-

!   JOHNSONJ.R.                                                                                                                                                                 NUREG/CR47N) EVALUATON OF POTENTIAL M0ED TASTES CON.

NUREG/CR4884 INTERPRETATON OF BCASSAY MEASUREMENTS T AINtNG LEAD. CHROM!UM.USED Olt.OR ORGANIC LCUCS NUREG/CR.4897 LOW-L EVE L WASTE SOURCE TERM

                                                                                                                                                                                                   #                     #                                         "    8'
               /   -46M V02 IMPROVtNG THE REUABluTY OF OPEN-CYCLE WATER SYSTEMS Apphcaton Of Botceng Surveittance And Control Technques To Seement And Corroson Fouhng At Nuclear h       )[g[pf,[(, h             [         ["                                      W i          PO*er Ptams                                                                                                                                                         K E NNE DY,W.E.

NUREG 1101 V02 ON$tTE OtSPOSAL OF RADIOACTIVE J0MNSON,M,R' WASTE Methodology For The Ra$olc9 cal Assessment Of Disposal By l NUREG 1214 Rot HISTORCAL  : DATA

SUMMARY

OF THE SYSTEMAT, IC ASSESSMENT OF UCENSEE PERFORM ANCE NU C 3 2 INTRUDER DOSE PATHA AY ANALYSIS FOR JoHwgON,T.M. THE ONSITE DISPOSAL OF RADCACTIVE W ASTES The ONS TEI j NUREG/CR 2478 V03 A STUOY OF TRENCH COVERS TO M,N'M:2E MAxl1 Compu1er Program INFILTRATCN AT W ASTE DSPOSAL SITES Final Rept JONNSON,W.S. NUREG/CR-4485 V02 THE IMPACT OF FUEL CLADDING F AILURE NUREG/CR-4950 V01. THE SHOREUNE ENVIRONME NT ATMOS- EVENTS ON OCCUPATCNAL R ADIATON EXPOSURES AT NUCLE- , , PHERC DISPERSON EXPERMENT (SEADEN)Espenment Descnp. AR PCrAER PLANTS Case Study PWR Dunng An Outage 1 ten , i NUREG/CR4950 V02 THE SHORELINE ENVIRONMENT A T MOS- KE RLEY T.E. i PHERC DISPERSON EXPERMENT (SE ADEX)Meteorolog. cal And NUREG/CR 4871 RESULTS FROM THE DCH 1 twEHNLN T. J K E R LIN,T.W. I JONNSTONJ.W. NURE GICR 4928 DEGRADATCN OF NUCLE AR PLANT TkMPERA. 1 NUREG/CR 5002 METHODS FOR RECURRlNG LOSS TESTS TURE SEN5 ORS i l 1 i j e 1 I . . - _ - .

90 Personal Author Index KHAN,TA NUREGICR-4551 V3 PT1: EVALUATON OF SEVERE ACCOENT RISKS NUREG/CR-3469 V03: OCCUPATONAL DOSE REDUCTON AT NU, AND THE POTENTlAL FOR - RISK REDUCTION PEACH CLEAR POWER PLANTS, Annotated Bibbography Of Selected Read- BOTTOM. UNIT 2 Mac Report Dram For Comment. mgs in Ra$aton Protecten And ALARA. NUREG/CR-4551 V3 PT2. EVALUATON OF SEVERE ACCOENT RISKS NUREG/CR4409 V02 DATA BASE ON NUCLEAR POWER PLANT AND THE POTENTIAL FOR RISK REDUCTON PEACH DOSE REDUCTON RESEARCH PROJECTS. BOTTOM. UNIT 2 Appendices Draft For Comment  ! NUREG/CR4551 V4 DRF: EVALUATION OF SEVERE ACCOENT KHATIS RAHOAR RISKS AND THE POTEN'tAL FOR RISK REDUCTON GRAND NUREG/CR-4552 A REVIEW OF THE SEABROOK STATON PROBABI- GULF. UNIT 1. Draft For Comment LISTIC SAFETY ASSESSMENT.Contamment Fahe Modes And Ra$- NUREG/CR-4700 V1 DRF: CONTAINMENT EVENT ANALYSIS FOR ological Source Terms. POSTULATED SEVERE ACCIDENTS. SURRY POWER STATION. UNIT 1 Draft For Comment KHATTAK,M.S. NUREG/CR-4700 V2 DAF: CONTAINMENT EVENT ANALYSIS FOR NUREG/CR4651: DEVELOPMENT OF RIPRAP DESIGN CRITERIA BY POSTULATED SEVERE ACCCENTS SEQUOYAH POWER RIPRAP TESTING IN FLUMES Phase L STATON. UNIT 1. Draft Report For Comment KIEFNERJ. KUPPE RM AN.D.S. NUREG/CR4082 V05: DEGRADED PlPING PROGRAM . PHASE NUREG/CR4813: ASSESSMENT OF LEAK DET7CTON SYSTEMS 11 Sermannual Raport, Apni-September 1983. FOR LWRs October 1985. September 1986 KlW8mELL.A F. KURTH.R.E. NVAEG/CR 4919- FIELD TESTING OF BENTONITE AND CEMENT NUREG/CR4795 LONG TERM PERFORMANCE OF HGH-LEVEL BOREHOLE PLUGS IN GRANITE. GLASS WASTE FORMS. NUREG/CR4956: SYSTEM PERFORMANCE OF HGHsEVEL WASTE KlWURA,C.V. " PACKAGE COMPONENTS NUREG/CR4829 V0t SHIPPING CONTAtNER RESPONSE TO . SEVERE HIGHWAY AND RAILWAY ACCIDENT CONDITONS Masn KURTZ,RJ. Report NUREG/CR4848. ST EAM GENERATOR GROUP PROJECT. Annual NUREG'CR4829 V02- SHIPPING CONTAINER RESPONSE TO Report 1985. SEVERE HIGHWAY AND RAILWAY ACCIDENT CONDITONS Appendhces LA80NE.TA NUREGICR.5042 EVALUATON OF EXTERNAL HAZARDS TO NUCLE. NUREG/CR-4884: INTERPRETATON OF BOASSAY MEASUREMENTS. AR POWER PLANTS IN THE UNITED STATES. LACHANCE).L. KINNISON.R.R. NUREG/CR4550 V06PT1: ANALYSIS OF CORE DAMAGE FREQUEN-NUREGICR 5002: METHODS FOR RECURRING LOSS TESTS- CY FROM INTERNAL EVENTS GRAND GULF. UNIT 1 Ma,n Report. NUREG/CR4550 YO6PT2 ANALYS!S OF CORE DAMAGE FREQUEN-KNOESS.C- CY FROM INTERNAL EVENTS GRAND GULF. UNIT 1 Appendices. NUREG/CR-4922. STEAM SEPARATOR MODEUNG FOR VARIOUS NUCLEAR REACTOR TRANSJEfvTS LADLOW.C.C. NUREG/CR4715 AN AGING ASSESSVENT OF RELAYS AND CtR. KOENIG,LN. CL"Y BREAKERS AND SYSTEM INTERACTIONS. NUREG/CR4216 EXPERIMENTAL RESULTS FOR A 18-SCALE STEEL MODEL NUCLEAR POWER PLANT CONTAINMENT PRESSURIZED LAWSERT,H.E. TO FAILURE NUREG/CR4910 RELAY CHATTER AND OPERATOR RESPONSE AFTER A LARGE EARTHOUAKE.An improved PRA Met %dology With KOHLI.R. Case Studies NUREG/CR-4954 LONG TERM PERFORMANCE OF SPENT FUEL WASTE FORMS. LAWSRIGHTJA NUREG/CR4550 V04: ANALYSIS OF CORE DAMAGE FREQUENCY KOLAC2KOWSKIA FROM INTERNAL EVENTS PEACH BOTTOM UNIT 2. NUREG/CR-4550 V04 ANALYS!S OF CORE DAMAGE FREQUENCY FROM INTE ANAL EVENTS PEACH BOTTOM UNIT 2 LAMONTAGNE.M. NUREG/CR4700 V4 DRF: CONTAfNMENT EVENT ANALYSS FOR NUREG/CR-4753 V02: CANADIAN SEISMC AGREE ME NT, Annual POSTULATED SEVERE ACCIDENTS GRAND GULF NUCLEAR Report i STATON. UNIT 1 Dratt For Comment. LANOJ.F. KORNEGAY.F.C, NUREG/CR-4708 V01 N1 PROGRESS IN EVALUATON OF RADONU. NUREG/CR4820. COMPARISON OF THE 1982 SEADEX DSPERSION CLOE GEOCHEM CAL INFORMATON DEVELOPED BY DOE HIGH-DATA WITH RESULTS FROM A NUMBER OF DIFFERENT MODELS. LEVEL NUCLEAR WASTE REPOSITORY SITE j PROJECTS Sermannual Report For October 1985 March 1986 j KOUTSH.  ! NUREG/CR-4881 PEV1EW OF RESEARCH ON UNCERTAINTIES IN LANDOW.M. ' ESTIMATES OF SOURCE TERMS FROM SEVERE ACCIDENTS IN NUREG/CR4082 V05 OEGRADED PIPING PROGRAM PHASE NUCLEAR POWER PLAr,TS II Semiannual Report, Apr(September 1986. { K RA14 R,G. LANNING,0.0. NUREG/CR4082 V05- DEGRADED PIPING PROGRAM - PHASE NUREG/CR-4718 EXPERtMENTAL SUPPORT AND DEVELOPVENT OF 11 Sermannual Report AprSSeptember 1986 SINGLE ROD FUEL CODES PROGRAM Summary Report KULHOWVICK.G. LARSON,T.H. NUREG/CR4082 V05 DEGRADED pip 1NG PROGRAM PHASE NUREG/CR-2478 V03 A STUDY OF TRENCH COVERS TO M:N M2E 11 Semiannudi Report, Apre$eptember 1986. INFILTRATON AT W ASTE DISPOSAL STES Foal Rept K ULL5E RG,C.M. LARSON,T.K. NUREG/CR4845 AN ANALYSIS OF THE SEMISCALE MOD 2C S-NH-3 NUREG/CR-4531 AN INVESTGATON OF INTEGRAL FACILITY SCAL. ] TEST USING THE TRAC-PF1 COMPUTER PROGRAM ING AND DATA RELATON METHODS ONTEGRAL SYSTEM TEST ! PROGRAM) KUNSM AN.D.M. NUREG/CR4824 EVALUATON OF INTEGRAL CONTINUING EXPERI. NUREGICA-4551 V1 DRF. EVALUATON OF SEVERE ACCOENT MENTAL CAFABluTY (CEC) CONCEPTS FOR LIGHT WATER REAC-RISKS AND THE POTENTIAL FOR RISK REDUCTON SURRY TOR RESEARCH PWA SCALING CONCEPTS POWER ST ATION UNIT 1.Dra9 For Comment . NUREGICR4551 V2 ORF. E V Al.UAT ON OF SEVERE ACCIDENT LAUGHERY,K.R. ] R!SAS AND THE POTENTIAL FOR RtSK REDUCTION SEQUOYAH NUREG-1258 EVALUATON PROCEDURE FOR S:MULATON FAClll-j POWER STATON. UNIT 1 Dra9 For Comment TIES CERTIFIED UNDER 10 CFR 55 Final Report I

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

L Personal Author index 91 a NUREG 1258 DAFT EVALUATON PROCEDURE FOR S MULATON LEWIS.SA , FACluTIES CERTIFIED UNDER 10 CFR 55 Drs't Report NUREG/CR4551 V2 DAF: EVALUATON OF SEVERE ACCCENT < RISKS AND THE POTENTLAL FOR RISK REDUCTION SEOVOYAH . LAY.R. POWER ST ATON. UNIT 1 Dra't For Comment t i NUREG/CR-4783 ANALYSIS OF BALANCE OF PLANT REGULATORY NUREG/CR-4551 V3 PT1: EVALUATION OF SEVERE ACCOENT RISKS i t ISSUES Feal Report AND THE POTENTIAL . FOR RISK REDUCTON PEACH BOTTOM. UNIT 2 Ma.n Report Drart For Comment LAY,T. NUREGICR-4551 V3 PT2: EVALUATON OF SEVERE ACCOENT RtSKS e NUREG/CR 3145 V05: GEOPHYSCAL INVESilGATON$ OF THE AND THE POTENTIAL FOR RISK REDUCTON PEACH WESTERN OHC4NDLANA REGON Fnal ReportOctober 1981. Sep- BOTTOM. UNIT 2 Appendees Dra't For Comment tomber 1986. NUREG/CR-4551 V4 DAF: EVALUATON OF SEVERE ACCOENT

• RISKS AND THE POTENTIAL FOR RISK REDUCTON GRAND LE MEUR.M- GULF, UNIT 1.Drai For Comment NUREG/CP4530 V02 U SJFRENCH JOINT RESEARCH PROGRAM NUREG/CR-4700 V2 DRF: CONTAINMENT EVENT ANALYSIS FOR
• REGARDNG THE BEHAVCR OF POLYMER BASE MATERIALS SUB- POSTULATED SEVERE ACCOENTS. SEQUOYAH POWER
• JECTED TO BETA RADIATON Volume 2: Phase 2a screenog itsts STATON. UNIT 1. Dram Report For Comment r

4 ' LE TUTOUR.P. UANG.K. NUREG/CR-4530 V02: U.S / FRENCH JOtNT RESEARCH PROGRAM NUREGICR-5010. RELAPS/ MOD 2 ASSESSMENT USING SEMISCALE i REGARDING THE BEHAVOR OF POLYMER BASE MATERIALS SUS- EXPER;MENTS S NH-1 AND S-LH-2. JECTED TO BETA RADIATON Volume 2. Phase-2a Screenog Tests. t LEAHY,T.J. NUREG/CR 5034. AN UPDATE OF MOCONTINENT TECTONISM. NUREG/CR4550 V05: ANALYSIS OF CORE DAMAGE FREQUENCY FROM INTERNAL EVENTS SEQUOYAH. UNIT 1. UO - CR4735 VOI: EVALUATCN AND COMPtLATCN OF DOE LE E.D.W. WASTE PACKAGE TEST DATA. B. annual ReportDecember 1985

      ' NUREG/CR-4651: DEVELOPMENT OF RIPRAP DES GN CRITERIA BY                               Juh1986.

RIPRAP TESTING IN FLUMES Phase 1. UGON.D.M. LEE.K. NUREG/CR 4846. HIGH-LEVEL WASTE PRECLOSURE SYSTEMS  ! 2 NUREG/CR-4781 DAFT: STUDY OF SEVERE ACCCENT MITlGATON SAFETY ANALYSIS Phase 2, Fnal Report. UME,J.F. LE E,Y.W. NUREG/CR-4988: A TRAC.PF1/ MOD 1 ANALYSIS OF THE GINNA  ; i NUREG/CR4903 V01: SELECTON OF EARTHOUAKE RESISTANT TUBE-RUPTURE EVENT ON JANUARY 25,1982. DESIGN CRITERIA FOR NUCLEAR POWER PLANTS METHODOLO' LIN,W K { GY AND TECHNICAL CASES. Drect Empocal Scateg Of Response NUREG/CR4843 V01: UNIVERSITY OF MARYLAND AT COLLEGE L NU / R4 3 2 ELE lON OF E HOUAK TANT PARK (UMCP) 2X4 LOOP TEST FACILITY. Annual Report For 1985. l

• l DESIGN CRITERIA FOR NUCLEAR POWER PLANTS METHODOLO- U N E R.R.T.

GY AND TECHNCAL CASES Methods For Introduchon Of Geologeal i Data into Charactenration of Actrve Faults And Seistmcey And - NUREG/CR-4797: PROGRESS REVIEWS OF StX SAFETY PARAME-TER DISPLAY SYSTEMS. I W GH.C.0- UNZER,M. l NUREG/CR-4830 MELCOR VALIDATION AND VER FICATON 1986 NUREG/CR4735 V02. EVALUATON AND COMPILATON OF DOE , PAPERS. WASTE PACKAGE TEST DATA Biannual Report August 1986 Janu-

• LEONARD,M. ary 87.

7 , NUREG-1150 DAF V2 FC: REACTOR RISK REFERENCE UPSZTEIN.JL

DOCUMENT. Appendices A-l Draft For Comment i

NUREG/CR-4884 INTERPRETATlON OF BCASSAY MEASUREMENTS LESSARD.E.T. UTTLEFlELD,J. NUREG/CR4884 INTERPRETATON OF BCASSAY MEASUREMENTS NUREG/CN 5002. METHODS FOR RECURRING LOSS TESTS LEVER.DA UTTLEFIELD,R. NUREGICR-5060. AN APPROACH TO THE MATHEMATICAL MODEL- NUREG/CR-4583 V02 DEVELOPMENT AND VAllOATON OF A REAL. UNG OF THE URANIUM SERIES REDSTRIBUTCN WITH:N ORE TIME SAFT UT SYSTEM FOR THE ',NSPECTON OF UGHT WATER BODES REACTOR COMPONENTS Annual eteporLOctober 1984 . September LEVINA NUREG/CR4968 EVALUAttON OF UNCERTArNTIES IN IRRADIATED LLEWELLYN.P. HARDWARE CHARACTER 12ATION. NUREG/CR4815: DEMONSTRATION TESTING OF A SURVEILLANCE , LEVINE EX ROBOT AT BROWNS FERRY NUCLEAR PLANT.AnaYsis Of Costs And Benehts NUREG/CR4957: SURVEY OF GEOPHYSCAL TECHNOUES FOR SITE CHARACTERIZATON IN BASALT. SALT AND TUFF. LOFGREN,E. LE WE LLE N,W.S. NUREG/CR4810 EVALUATON OF DIESEL UNAVAILABILITY AND 5 RISK EFFECTIVE SURVEILLANCE TEST INTERVALS NUREG/CR4R20. COMPARISON OF THE 1982 SEADEX DISPERSION DATA WITH RESULTS FROM A NUMBER OF DFFERENT MODELS LONGSINE D E. LEWIS,G-NUREG/CR 2452 RrSK METHODOLOGY FOR GEOLOGC DISPOSAL OF RADCACTIVE W ASTE Fnal Report NUREG 1278. VOGTLE UNIT 1 READ 1 NESS REVIEW Assessment Of NUREG/CR-4766 USER'S MANUAL FOR THE NEFTRAN COMPUTER Georpa Power Company Readness Revew Pilot Program. CODE. LE Wi$,M. LOOMIS,G.G. NUREG/CR4848 STEAM GENERATOR GROUP PROJECT Annual NUREG/CR4945.

SUMMARY

OF THE SEMtSCALE PROGRAM (196N Report .1985 1986) LE WIS,P.M. LOPE 2.EA NUREG/CR 5003. DESGN OF A MATERIAL CONTROL AND AC- NUREG/CR 4875 CHARACTER!2ATCN OF CRUSHEC TUFF FOR THE COUNTING SYSTEM TO PROTECT AGatNST CONCE ALMENT OF EVALUATON OF THE F ATE OF TRACERS IN TRANSPORT STUOiES . DVERSON BY FALS$1CATON AND COLLUSON IN THE UNSATURATED ZONE  !

92 Personal Author index LOSS,F.J. MART G.A. NUREG/CA 3228 V05: STRUCTURAL INTEGRITY OF WATER REAC- NUREG/CR4469 YO4 NONDESTRUCTIVE EXAM 6 NATION (NDE) RELb TOR PRESSURE BOUNDARY COMPONENTS Annual Report For ABILITY FOR INSERVCE INSPECTION OF LGHT WATER 1966, REACTORS Sermannual Report. October 1985 March 1966. NUREG/CR4469 V05: NONDESTRUCTIVE EXAMAATON (NDE) RELL LUCERO.DA ABluTY FOR INSERVICE INSPECTON OF LGHT WATER NUREG/CR4871:RESULTS FROM THE DCH-1 EXPERtMENT. REACTORS Sernannual Report. Apr4-September 1966 NUREG/CR4469 V06: NONDESTRUCTIVE EXAMINATION (NDE) RELb LUCKL ASluTY FOR INSERVICE INSPECTION OF LGHT WATER NUREG/CR-4765 MXS CROSS-SECTION PREPROCESSOR USER'S REACTORS Semsannual Report. October 1986 March 1987-MANUAL NUREG/CR4583 V03. DEVELOPMENT AND VALCATION OF A REAL. TIME SAFT UT SYSTEM FOR THE INSPECTON OF UGHT WATER CTOR COMPONENTS Annual Report. October 1965 . September V EG/CR-4903 V03: SELECTON OF EARTHOUAKE RESISTANT ' DESIGN CRITERIA FOR NUCLEAR POWER PLANTS . METHODOLO-GY AND TECHNICAL CASES Dssocation Models Of Near-Source uAnytu,g.p, Earthquake Ground Motion. A Revie* NUREG/CR4485 V02: THE IMPACT OF FUEL CLADDING FAILURE EVENTS ON OCCUPATONAL RADIATON EXPOSURES AT NUCLE. AR POWER PLANTS Case Study PWR Dunng An Outa9e. NUREG/CR-4552: A REVIEW CS THE SEABROOK STATON PROBABb USTiC SAFETY ASSESSMENT Contamment Failure Modes And Radi- MARTIN,JA o'09' cal Source Terms NUREG 1210 V01: PILOT PROGRAM NRC SEVERE REACTOR ACCH DENT INCCENT RESPONSE TRAINtNG MANUALovennow And Sum. NU E'G/CR-4937. INVESTIGATON OF THE MEERS FAULT IN SOUTH- NU G 210 02 P1 Of PROGRAM.NRC SEVERE REACTOR ACCb WESTERN OKLAHOVA. DENT INCCENT RESPONSE TRAINING MANUAL $evere Reccior Ac. LYON,W C em Omew NUREG 1210 V04 PILOT PROGRAM NRC SEVERE REACTOR ACCb NUREG 1269 LOSS OF RESCUAL HEAT REMOVAL SYSTEM Diablo DENT INCIDENT RESPONSE TRAINING MANUALPubhc Protective Canyon Urvt 2, Apnl 10,1987. g ,p ,4 g g gg, LYONS.JA MARTIN,R.W. NUREG/CR-4753 VC2 CANADIAN SEISMC AGREEMENT. Annual Report NUREG/CR4829 V01. SHIPPING CONTAINER RESPONSE TO SEVERE HGHWAY AND RAILWAY ACCCENT CONDITIONS Mac MACD0N ALD,P E, Report NUREG/CR4731 V01: RESOUAL UFE ASSESSMENT OF MAJOR NUREG/CR4829 V02- SH)PPING CONTAINER RESPONSE TO UGHT WATER REACTOR COMPONENTS OVERVIEW Yolume 1. SEVERE MfGHWAY AND RAILWAY ACCCENT CONDITONS Appereces M AC KENZIE.D.R. M A R K,K.D. NUREG/CR-4730: EVALUATON OF POTENTIAL M3ED WASTES CON. TAIN:NG LEAD, CHROMlUM.USED OILOR ORGANIC LOUCS NUREG/CR4855 DEVELOPMENT AND APPLCATON OF A COMPUT. ER MODEL FOR LARGE SCALE FLAME ACCELERATON EXPERI. MADOLE,R.F. MENTS. NUREG/CR4937. INVESTIGATON OF THE MEERS FAULT IN SOUTH-WESTERN OKLAHOMA MASSOUD,M. NUREG/CR-4788, AN ANALYTCAL AND EXPERIMENTAL INVESTGA-MAERKER.R.E. TON OF NATURAL CIRCULATON TRANSIENTS IN A MODEL PRES-NUREG/CR4BB6 ANALYSIS OF THE NESDtP2 AND NESDiP3 RADIAL SURt2ED WATER REACTOR SHIELD AND CAVITY EXPERIMENTS NUREG/CR4843 V01: UNfVERSITY OF MARYLAND AT COLLEGE

                                                                                                                              . Annual  ut 6 N MAlY A.P.S.-

NUREG'CR4667 V03 ENVtRONMENTALLY ASS 2STED CRACKING IN MATTHEWS.S.D. LIGHT W ATER REACTORS Sermannual ReportAprASeptemter 1966 NUREG/CR4844 DRFT. INTEGRATED RELtABluTY AND RISK ANALY. MAJUMDAR,8.S. NUREG/CR4955 LONG TERM PERFORMANCE OF CONTA>NER MA. MAUDERLY,J L. TERIALS FOR HIGH-LEVEL WASTE. NUREG/CR-5025. EXPERIMENTAL STUDIES OF THE EARLY EFFECTS OF INHALED BETA EMITTING RADONUCUDES FOR NUCLEAR AC. CCENT RISK ASSESSMENT Phase ll Report NUREG-1 50 DAF V1 FC: REACTOR RISK REFERENCE DOCUVENT Mac Report Oran For Comment MAUDLIN.P.J. NUREG/CR-4909 MELPROG-PWR/ MODO A MECHANISTC CODE FOR ANALYSIS OF REACTOR CORE MELT PROGRESSON AND YESSEL NUREG CR-4783 ANA!.YSIS OF BALANCE OF PLANT REGULATORY ^ ISSUES Final Report M AUPIN,C. MARKWORTH,A.J. NUREG/CP-0085 MEETING WITH GTATES ON THE LOW-LEVEL RA. NUREG /CR4795 LONG-TE RM PERFORMANCE OF HGH-LEV E L GLASS W ASTE FORMS DiOACTIVE WASTE POLCY AMENDMENTS ACT (LLAWPAA) OF NUREG/CR 4954 LONG-TERM PERFORMANCE OF SPENT FUEL 1985 W ASTE FORMS M A X E Y,W. NUREGICR-4955 LONG-TERM PERFORMANCE OF CONTAINER MA. TERIALS FOR MGH LEVEL WASTE NUREG/CR-4382 V05 DEGRADED PIPING PROGRAM PHASE NUREG/CR-4956 SYSTEM PERFORMANCE OF HGH-LEVEL W ASTE H Sermannual Report, Apni-September 1986. PACKAGE COMPONENTS MARSCHALLC.W. NUREG/CR-4841: FRACTURE EV ALUATON OF SURFACE CRACKS NUREG/CR4082 V05 DEGRADED PtPING PROGRAM PHASE EMBEDDED IN REACTOR VESSEL CLADDING Urwrradated Bond 11 Seemannual Report, AprASeptember 1986 Specimen Resutts M A RSH A I.L,8.W. MCCLUNG,R.W. NUREG/CR 3468 HYDROGEN AIR STEAM FLAMMABluTY UMiTS NUREG/CR 4860- FLAW DENSITY EXAM! NATIONS OF A CLAD BOIL-AND COMBUSTON CHARACTERiSTCS IN THE FITS VESSEL ING W ATER REACTOR PRESSURE VESSEL SEGMENT.

i Personal Author index 93 MCCOYJ.K. MENDLER.O.J. NUREG/CR4795 LONG-TERM PERFORMANCE OF HIGH-LEVEL NUREG/CR4752. COtNCOENT STEAM GENERATOR TUBE RUPTURE GLASS WASTE FORMS AND STUCKOPEN SAFETY REUEF VALVE CARRYOVER NUREG/CR4954. LONG TERM PERFORMANCE OF SPENT FUEL TESTS MB-2 Steam Generator Trenaient Response Test Program. . WASTE FORMS 2 NUREG/CR4955 LONG TERM PERFORMANCE OF CONTAINER MA. Mg gNG,m,w, TERLALS FOR HIGH-LEVEL WASTE NUREG/CR4829 V01: SHtPP1NG CONTAINER RESPONSE TO SEVERE HIGHWAY AND RAILWAY ACCOENT CONDITONS.Mac MCCREERYAE. NUREG/CR4824: EVALUATION OF INTEGRAL CONTINUING EXPERI- NUR CR4829 V02: SHIPPtNG CONTAINER RESPONSE TO MENTAL OAPABILITY JCEC) CONCEPTS FOR LIGHT WATER REAC- HIGHWAY RAILWAY SEVERE AND ACCIDENT TOR RESEARCH . PWR SCAUNG CONCEPTS. CONDITONS Ws MCELAOY,W.N NUREG/CR4685: SEISMIC HAZARD CHARACTERIZATCN OF THE f NUREG/CR-3319 R01: LWR PRESSURE VESSEL SURVEILLANCE 00 EASTERN UNITED STATES Comparatrve Evaluabon Of The LLNL And SIMETRY IMPROVEMENT PROGRAM LWR Power Reactor Surved. EPRI Studes. lance Phytacs-Doswne NUREG/GR-3320 V03, bData Base Compendium. R PRESSURE VESSEL SURVEILLANCE 00- MERKLEJ.G. SIMETRY IMPROVEMENT PROGRAM PSc Physes-Dosabetry Pro- NUREG/CR-4760 TEST OF 6-IN, THICK PRES $URE VESSELS Seres

m. 3 Intermediate Test Vessel V 8A.Teanng Behavior Of Low Upper-Shelf f N REG /CR-3320 V04- LWR PRESSURE VESSEL SURVEILLANCE 00 Matenat S: METRY IMPROVEMENT PROGRAM PSF Metanurgy Prooram NUREG/CR-4930 CRACK ARREST BEHAVIOR IN SEN WOE PLATES NUREG/CR4307 VC3 LWR PRESSURE VESSEL SURVEILLANCE DO. OF QUENCHED AND TEMPERED A S33 GRADE B STEEL TESTED S; METRY IMPROVEMENT PROGRAM 1986 Annual Report.0ctoter UNDER NONISOTHERMAL CONDITIONS.

MERWIN.S E. MC F ADDE N,K.M. NUREG/CR-4938 OCCUPATIONAL RADIATON EXPOSURES ASSOCl-NUREG/CR-4976 PLANT RHI20$PHERE PROCESSES INFLUENCING ATED WITH ALTERNATfvE METHOOS OF LOW LEVEL WASTE DIS- - RADCNUCLCE MOBP 'TY IN SOIL POSAL l MCGUtRE.M.V. MEWHINNEY,J.A. NUREG/CR 3968 STUDY OF OPERATING PROCEDURES IN NUCLE- NUREG/CR4986. RADIATON DOSE ESilMATES AND HA2ARD EVAL. AR POWER PLANTS Pract<es And Problems- UATONS FOR INHALED AIRBORNE RADONUCLOES Final Report. MC K E NNA,T* l MEYER.M.A. NUREG/CR4722. SOURCE TERM ESTIMATCN USING MENU TACT. NUREG/CR-4814: SOURCES OF CORRELATCN BETWEEN EXPERTS Empincal Results From Two Extremes. MCKENNA.T.J. NUREG-1210 V01: PtLOT PROGRAM NRC SEVERE REACTOR ACCb "I E .O DENT NT RESPONSE TRAIN!NG MANUALOvervew And Sum- g NUREG 1210 V02: PtLOT PROGRAM NRC SEVERE REACTOR ACCI. AND IMPACTS OF UPGRADED EMERGENCY OPERATING PROCE- i NCl T RESPONSE TRAINING MANUAL $evere Reactor Ac. E,$ NVALG 1210 V03 PtLOT PROGRAM NRC SEVERE REACTOR ACCp BABCOCK AND WILCOX FLANTS Volume 1. Results Overvew. DENT INCOENT RESPONSE TRAINING MANUAL Response Of U-NL$RE 121 1O NNRC SEVERE REACTOR ACCI. NUREG/dR 4708 V01 N1: PROGRESS IN EVALUATION OF RADONU. DENT INCOENT RESPONSE TRAIN 1NG MANUAL Pubhc Protectrve CLOE GEOCHEMICAL INFORMATON DEVELOPED BY DOE HIGH-Actions . Preceterrmned Cntena And trwtml Actions LEVEL NUCLEAR WASTE REPOStTORY SITE NUREG-1210 vo5 PILOT PROGRAM NPC SEVERE REACTOR ACCb PROJECTS Semennual Report For October 1985. Maren 1966-DENT INCOENT RESPONSE TRAINING MANUAL U S. Nuclear Rego. NUREG/CR-4865: THE SOLUBlUTY OF ELECTRODEPOSITED TC(IV) Latory Commisson Response. OxOES. MCNAMARA.N. WILLER C.W. NUREG-0837 V07 Not: NRC TLD DIRECT RADIATCN MONITORING NUREG t210 VQ1: PILOT PROGRAM NRC SEVERE REACTOR ACCl-NETWOAK Progress Report. January March 1987 DENT INCOENT RESPONSE ' RAINING MANUAL Overvew And Sum-NUREG4837 V07 NO2. NRC TLD D RECT RADIATON MONITORING ma/y Of Map:ir Points. [ NETWORK Progress Report. Aprd-June 1987. NUREG 1210 V02 PILOT PROGRAM NRC SEVERE REACTOR ACCb ' NUREG4637 V07 NO3 NRC TLD DIRECT RADIATON MONITORING DENT INCOENT RESPONSE TRAINING MANUAL. Severe Reactor Ac-NETWORK Progress Report. Ju ry-September 1987. cident Overvem NUREG 1210 V03 PILOT PROGRAM NRC SEVERE REACTOR ACCL

                                                                                                           ^ "                   "'

NUR /CR4616 ROOT CAUSES OF COMPONENT FAILURES con eAd ie NURE / -4 7 01 N N FAILURE SURVEY OF LCHT

• WATER REACTOR SAFETY SYSTEMS AND COMPONENTS Act ons . Predeterrmned Cntena And Irvtal Actons ME ANS.J L NUREG 1210 V05. PILOT PROGRAM NRC SEVERE REACTOR ACCb NUREG/CR 4795 LONG TERM PE RFORM ANCE OF HIGH-LEVEL DENT tNCOENT RESPONSE TRAINING MANUAL U S Nuclear Regu.

GLASS W ASTE FORMS tatory Comrmston Response NUREGICR-454 LONG-TERM PERFOAMANCE OF SPENT FUEL RE'G CR-4781 DRFT STUDY OF SEVERE ACCOENT MITIGATON MEGAHED.M M. SYSTEMS. NUREG/CR4799 RELAPS/ MOD 2 ASSESSMENT S'MULATION OF SE-M: SCALE MOD 2C TEST S-NH 3 MILLE R.N.E. l NUREG/CR-4795 LONG TERM PERFORMANCE Or H GH4 EVEL L MEININGER.R D. GLASS W ASTE FORMS NUREG/CR 5008 DEVELOPMENT OF A TESTING AND ANALY$15 METHOOOLOGY TO DETERM.NE THE FUNCTCNAL CONDITCN OF MILLER.R.W. SOLENOC OPERATED VALVEJ NUREG/CR-4866 AN ASSESSMENT OF HYDROGEN GENERATON [ FOR THE P8F SEVERE FUEL DAMAGE SCOPING AND 11 TESTS ' ME tSTE R,H-NUREG/CR 4719 COOLABfUTY OF STRATIFIED UO2 DEBRIS IN MILSTE AD.W. SODtUM WITH DOWNW ARD HE AT REMOVALThe D13 Expenment NUREG4933 S06 A PRORIT12ATON OF GENERIC SAFETY ISSUES

94 Personal Author index MINAROKAW. MULLEN M.F. ' NUREG/CR4674 V03- PRECURSORS TO POTENTIAL SEVERE ODRE NUREG/CR 4958 IMPACT OF PROPOSED FINANCIAL ASSURANCE DAMAGE ACQDENTS.1964,A STATUS REPORT.Mac Report Ard AP- REQUIREMENTS ON NUCLEAR MATERIALS LCENSEES. pendaos A And 8 NUREG/CR4674 V04: PRECURSORS TO POTENTLAL SEVERE CORE MUteNO.CA DAMAGE ACODENTS.1964.A STATUS REPORT.Apperdues C,0 And NUREG/CR4843 V01: UNIVER$1TY OF MARYLAND AT COLLEGE E- PARK (VMCP) 2X4 LOOP TEST FAOLITY.Armuel Report Fw 1985 I MtTCHELL.G.W. MUNNO,FA NUREG/CR-4719. COOLABluTY OF STRATIFIED 002 DEBRIS IN NUREG/CR4843 V01: UNIVERSITY OF WARYLN4D AT COLLEGE i SOOlUM WITH DOWPMARD HEAT REMOVALThe D13 Espenment PARK (UMCP) 2X4 LOOP TEST FACluTY. Annual Report For 1965 MITCHELL.JA MUNRO.P.8, hENT.M R Dr F NUREG/CR-4753 V02: CANADIAN SEISMC AGREEMENT. Annual Report MOELLER,M.P. NUREG/CR-4445 V02 THE IMPACT OF FUEL CLADDNG FAILURE MFIN.W.S. EVENTS ON OCCUPATIONA( RADATION EXPOSURES AT NUCLE. NUREG/CR-4551 V1 DRF: EVALUATION OF SEVERE ACODENT

'                                                                            RISKS AND THE POTENTIAL FOR RISK REDUCTON SURRY AR POWER PLANTS. Case $lu:yPWR Dunng An outage.

POWER STATON. UNIT 1. Draft For Comment MOFFETT,DL NUREG/CR-4551 V2 DRF: EVALUATION OF SEVERE ACCOENT NUREG/CR-2478 V03. A STUDY OF TRENCH COVERS TO M; nim 12E RISKS AND THE POTENTIAL FOR RISK REDUCTON SEQUOYAH INFILTRATION AT WASTE DSPOSAL SITES Feel Rept POWTR STATION. UNIT 1 Dra't For Comment NUREG/CR4700 V1 DRF: CONTAINMENT EVENT ANALYSIS FOR MOHR.CL POSTULATED SEVERE ACCCENTS: SURRY POWER STATION. UNIT NUREG/CR-5059: VOID FRACTON MEASUREMENT LIOutD LEVEL 1.Drafl For Comment DETECTON CONCEPT ASSESSVENT AND DEVELOPMENT. NUREG/CR4700 V2 DRF: CONTAINMENT EVENT ANALYSIS FOR , POSTULATED SEVERE ACCOENTS. SEQUOYAH POWER CR-4550 V05: ANALYST $ OF CORE DAMAGE FREQUENCY FROM INTERNAL EVENTS SEQUOYAH. UNIT 1 MURPHY,L NUREG/CR4826 V02: SEISMC MARGIN REVIEW OF THE MAINE NUREG/CR4912- DATING GROUND WATER AND THE EVALUATION i YANKEE ATOMC POWER STATCH Volume 2 Systems Anaysis. OF REPOSITOR!ES FOR RADOACTIVE WASTE. WOORLS1 gggpgy,gA NUREG/CR4943 PREPARATON OF DESIGN SPEOFICATIONS AND NUREG/CR4692. OPERATING EXPERIENCE REVIEW OF FAILURES DES 1GN REPORTS FOR PUMPS. VALVES. PIPING.AND PnPtNG SUP. OF POWER OPERATED REUEF VALVES AND BLOCK VALVES IN PORTS USED IN SAFETY RELATED PORTIONS OF NUCLEAR NUCLEAR POWER Pt. ANTS  ! i POWER PLANTS t MORGENSTERN M. U'HTMA NUREG/CR 3968 STUDY OF OPERATING PROCEDURES IN NUCLE, NUREG 1150 DAF V1 FC: REACTOR RISK REFERENCE l DOCUMENT. Man Report Draft For Comment AR POWER PLANTS Pracbces Ard ProNoms MOR LE Y,5.M. MURPHY,VA NUREG/CR4950 V01: THE SHOREUNE ENVIRONMENT ATMOS. NUREG/CR-4957; SURVEY OF GEOPHYSCAL TECHNOVES FOR PHERC DISPERSON EXPERIMENT (SEADEX)Expenment Desenp. SITE CHARACTERt2ATION IN BASALT,$ ALT AND TUFF, 1 bon. 4 NUREG/CR-4D50 V02 THE SHORELINE ENVtRONMENT ATMOS. MURRAY,R.C. PHERC DSPERSON EXPERIMENT (SEADEX) Meteorological And NUREG/CP-0087.

SUMMARY

REPORT OF THE SYMPOSIUM ON SEIS-Gas Tracer Data MC AND GEOLOGC SITING CRITERIA FOR NUCLEAR POWTR PLANTS. MORRIS.B.M. NUREG/CR-4826 V01: SEISMC MARGIN REYlEW OF THE MAINE NUREG-1150 DRF V1 IC: REACTOR RISK REFERENCE YANKEE ATOMC POWER STATON Volume 1 Summary Report DOCUMENT. Man ReportDra't For Comment. MUSTONE N,P, MORROW.P.E NUREG/lA4004 THERMAL MtXING TESTS IN A SEMLANNULAR NUREG/CR-4951: NEPHROTOXCITY OF UR ANYL FLUORCE AND RE- DOWNCOMER WITH INTERACTING FLOWS FROM COLD LEGS l VERStBluTY OF RENAL IPOURY IN THE RAT, NAJAFLB. MOSE S.M.J. NUREG/CR-4550 V04. ANALYSi$ OF CORE DAMAGE FREOVENCY ,1 NUREG/CR-4974. INTRAPLATE SE!SMCITY IN THE EASTERN FROM INTERNAL EVENTS PEACH BOTTOM UNIT 2 i UNtTED STATES. NA K AGAKI,M. MOSLEH.A NUREG/CR4082 V05. DEGRADED PIPING PROGRAM PHASE NURE G/UA-4962: METHODS FOR THE ELOITATON AND USE OF la Serrmannual Report Apnt September 1986. EXPERT OPINON IN RISK ASSESSMENT. Phase i . A Cnbcal Evalua-con And Drectons For Future Researett NANSTAD,RA MOUNT,M.E. NUREG/CR-4760 TEST OF 64N THCK PRESSURE VESSELS Senes NUREG/CR4829 YO1: SHioPtNG CONTAINER RESPONSE TO 3 nntermedate Test vessel V-8ATeanng Behacor Of Low Upper-Shelf Ma SEVERE HIGHW AY AND RAILWAY ACCOENT CONDITIONS Man gR NUR CR4829 V02- SHIPPING CONTAINER RESPONSE TO OF QUENCHED AND TEMPERED A 533 GRADE B STEEL TESTED l SEVERE HIGHWAY AND RAlLWAY ACCCENT UNDER NONISOTHERMAL CONDTICM

                                       **                                NAPlf R,5A MUELLE R,G L                                                           NUREG/CR-3620 $02. INTRUDER DOSE PATHA AY ANALYSIS FOR

, NUREG/CR-4689 THERMAL-HYDRAULIC AND CHARACTERLSTC THE ONSITE DISPOSAL OF RADOACTIVE W ASTES The ONSITE/ MODELS FOR PACF.ED DEBRIS BEDS MAXI 1 Computer Program. i MULLE R G. NARSUT,P.P. NUREG/CR-4922 STEAM SEPARATOR MODELING FOR VAROUS NUREG-1269 LOSS OF RESOUAL HEAT REMOVAL SYSTEM Datso NUCLEAR REACTOR TRANSIENTS Canyon Urvt 2. Aprd 10,1967.

                  - - - . . - - -          -                                                                       => -'   -
                                                                                                                                -'~'

Personal Author Index 95 L t NAT9tAVASA NOROE N.K. NUREG/CR-4F76: RESPONSE OF SOSMO CATEGORY I TANKS TO NUREG/CR-2907 V05: RADOACTIVE MATERIALS RELEASED FROM a EARTHOVAKE EXCITATION. NUCLEAR POWER PLANTS. Arruel Report 1964. ' NAUS.DJ. NOWLENAP. NUREG/CR471t REGULATORY ANALYSIS OF REGULATORY GUOE NUREG/CR4679: OUANTITATIVE DATA ON THE FIRE BEHAVIOR OF 1.35 (REVISION 3. DRAFT 21 IN-SERVOE INSPECTION OF UN. COMBUST 18LE MATERIALS FOUND IN NUCLEAR POWER ! GROUTED TENDONS IN PRESTRESSED CONCRETE CONTAW- PLANTS.A LMerature Renew. MENTS. NUREG/CR4681: ENCLOSURE ENVIRONMENT CHARACTER!2ATION NUREG/CR4931 CRACK. ARREST BEHAVOR IN SEN W10E PLATES TESTING FOR THE BASE UNE VALOATION OF COMPUTER FIRE OF QUENCHED AND TEMPERED A 633 GRADE 8 STEEL TESTED G:MULATION CODES. UNDER NONISOTHERMAL CONDTONS. O'DONNELLL NEITIEL.DA NUREG/CR-4918 VO1: CONTROL OF WATER INFILTRATON INTO NUREG/CR4626 V02 iMPROV1NG THE REUABluTV OF OPEN- NEAR SURFACE LLW DISPOSAL UNITS Arvbal Report. October 1965 a CYCLE WATER SYSTEMS. Appncaton Of Bdouhng Survestance And . September 1966. i Cor*ol Technges To Sodment And Corrosaon Fodng At Nuclear i Power P4nts. O'KELLEY.Q.D. NUREG/CR-4706 V01 N1: PROGRESS IN EVALUATON OF RADONU-NELSON.J.D. CUDE GEOCHEMICAL INFORMATION DEVELOPED BY DOE HIGH-NUREGICR4651: DEVELOPMENT OF R)PRAP DESGN CRITERIA BY LEVEL NUCLEAR WASTE REPOSITORY SITE RIPRAP TESTING IN FLUMES. Phase L PROJECTS Sermannual Report For October 1985. March 1986. NELSON.T.A. O'REILLY.P.D. NUREG/CR-3966. METHODS FOR IMPACT ANALYSIS OF SHIPPING NUREG 1275. OPERATING EXPERIENCE FEEDBACK REPORT - NEW CONTAINERS. PLANTS. Comrnercial Power Reactors. NELSON.W.R. 0007.M.T. NUREG/CR4696: CONTAJNMENT VENTWG ANALYSIS FOR THE NUREG/CR-4972 TWO-PHASE FLOW REGtME TRANSITON CRiTE. PEACH BOTTOM ATOMC POWER STATON RfA IN POST.DRYOUT REGION BASED ON FLOW VISUAUZATION NUREG/CR.4966 V01: EVALUATON OF OPERATONAL SAFETY AT EXPER:MENTS BABCOCK AND WILCOX PLANTS Voeume t . Results Overv6ew OKAILY,A A. NEtef77,J#, NUREG/CR-4952 EXPERIMENTAL STUDY OF FILLET WELD UNDER. NUREG/CR4590 V01: AGWG OF NUCLEAR STATON DESEL CUT EFFECTS ON WELDED TUBING STRUCTURES UNDER CEN. , GENERATORS Evaluaton Of Opersung And Expert Exponence Phase TRIC AND ECCENhc CYCUC LOADNGS. 1 OUVER.M.S. 1 NEUDER.S.M. NUREG/CR4871: RESULTS FROM THE DO41 EXPERIMENT. J NUREG.1101 Vot ONSITE DISPOSAL OF RADCACTIVE WASTE Methodo6ogy For The Re<boiogical Assessment Of Dsposal By ONESTOAT. Subeurface Bunal NUREG/CR4859; SEISMC FRAG!UTY TEST OF A 6-INCH DAMETER NUREG/CR.3620 $01 INTRUDER DOSE PATHWAY ANALYSIS FOR PIPE SYSTEM. THE ONSITE DSPOSAL OF RADIOACTIVE WASTESThe ONSITE/ MAX 11 Computer Program. OPELKAJ.H. NUREG/CR4964 UPDATE OF TABLE $ 3 NONRADIOLOGICAL ENVL NEWTON.QJ. RONVENTAL PARAMETERS FOR A REFERENCE UGHT-WATER NUREG/CR-6025. EXPERIMENTAL STUDES OF THE EARLY EFFECTS REACTOR Uraruum Mrwng.MAng And Ennchment OF INHALED BETA-EMITTING RADONUCUDES FOR NUCLEAR AC. COENT RISK ASSESSMENT. Phase 11 Report ORNSTEIN.HL 1' NUREG.1275 V02: OPERATING EXPERIENCE FEEDBACK REPORT . NEYMOTIN.LY. AIR SYSTEMS PROBLEMS. Commerc.at Power Reactors NUREG/CR4739. RAMONA.30 CALCULATONS FOR BROWNS i FERRY ATWS STUDY. ORTI2.N R. q NUREG/CR-2452 RISK UETHOOOLOGY FOR GEOLOGIC DSPOSAL MICHOLLSAK. OF RADOACTIVE WASTE. Frsal Report NUREG/CR4958. IMPACT OF PROPOSED FWANCIAL ASSURANCE REOUIREMENTS ON NUCLEAR MATER 41ALS UCENSEES OSETE K.DJ. NUREGICR4866 AN ASSESSMENT OF HYDROGEN GENERATON MICOLETTE.VI. FOR THE PBF SEVERE FUEL DAMAGE SCOPING AND 11 TESTS. NUREG/CR4941 EQUIPMENT OPERABluTY DURING STATON BLACKOUT EVENTS. OSTMEYER.R.M. NUREG/CR4825. A PREUM NARY EVALUATION OF THE ECONOMC NICOLO$t.S.L. RISK FOR CLEANUP OF NUCLEAR MATERIAL LICENSEE CONTAMi-NUREG/CR-4954 SYSTEM PERFORMANCE OF HIGH-LEVEL W ASTE NATON INCOENTS PACKAGE COMPONENTS. OTIS.M.D. NIEMC2YK.SJ. NUREG/CR-4701 Vol SAFETY ASSESSMENT OF ALTERNATIVES TO NUREG/CP/J078. PROCEEDINGS OF THE SYMPOSIUM ON CHEMI- SHALLOW. LAND BURIAL OF LOW. LEVEL RADCACTIVE CAL PHENOMENA ASSOCLATED W11H RADOACTIVITY RELEASES W ASTE volume 2 Ermronmental Cordtnes Affectng Rehatality Of En-DURING SEVERE NUCLEAR PLANT ACCIDENTS gmeered Barners NIGHTINGALE,T. OTTINGER.C.A. NUREG/CR.5040 RADONUCUDE MiGRATON AROUND URANIUM NUREG/CR4719. COOLABluTY OF STRATIFIED 002 DEBRIS tN ORE BOEMES . ANALOGUE OF RADIOACTIVE WASTE SODeUM WITH DOWNWARD HEAT REMOVALThe D13 Emervnert REPOSJTORIES Anrual Report For 1964 1985. 00ELLETTEAL NITZ KA NUREG/CR-4963 BORON CARBOE STE AM REACTONS WITH NUREG/CR.4950 V01: THE SHOREUNE ENVIRONMENT ATMOS- CiSiUM HYDROXOE AND WITH CESIUM IODOE AT 1270K IN AN PHERC DSPERSON EXPER;UENT (SEADEX)Expenment Descro- INCONEL 600 $YSTEM tort NUREG/CR4950 V02 THE SHOREUNE ENVIRONMENT ATMOS. PAIK.C Y. PHERC DSFTRSON EXPER: MENT (SEADEX) Meteorcycal And Gas NUREG /CR-4922 STEAu SEPARATOR MODELING FOR VAROUS Tracer Data NUCLEAR REACTOR TRANSJENTS , c

r I l M Personal Author Index  ; i PAMGOURN,G.C. PHtUPPACOPOULO  !

    - NUREG 1300' ENVIRONMENTAL STANDARD REVIEW PLAN FOR THE                                  NUREG/CP 0054 PROCEEDNGS OF THE WORKSHOP ON SOIL-REVIEW OF A LCENSE APPUCATCN FOR A LOW-LEVEL RADC-                                      STRUCTURE INTERACTCN.                                            [

ACTfvE WASTE OtSPOSAL FAOUTY.  ! PICIULO P.L 2 PANNE R.B.J. NUREGICA-3444 V04. THE IMPACT OF LWR DECONTAMiNATIONS f NVREGiCR-4H1: NEPHROTONCTY OF URANYL FLVORCE AND RE- ON SOUDFICATON WASTE DSPOSAL.AND ASSOCLATED OCCU-VER&BUTf OF RENAL INJURY tN THE RAT. PATCNAL EXPOSURE. Annual Report Fesce Year 1936 , NUREG4CR-4730: EVALUA) ON OF POTENTtAL MaED WASTES CON-PAPASPYPOPC%OS TAJNtNG LEAD, CHROMIUM /.' SED DL.OR ORGANC 0000$.  ! NUREGICR4062 V05: DEGRADED PtPtNG PROGRAM . PHASE ILSearrW Report, Apni September 1986. HLCH,W. g NUREG/CR48T1: RESULTS FROM THE EQ41 EXPERIMENT, PARKJ1 [ NUREG/CR4667 V03 ENVIRONMENTALLY ASSSTED CRACKJNG IN PITTIGUO.C.L

UGHT WATER REACTORS. Semnannual ReportApr& September 1966 NUREG-1274

REVIEW PROCESS FOR LOW LEVEL RADCACTNE t

WASTE DSPOSAL UCENSE APPUCATION UNDER LOW-LEVEL RA. PARKERF- DCACTIVE WASTE POLCY AMENDMENTS AC1. [ NUREG/CR-4766: MxS CROSS SECTION PREPROCESSOR USER'S NUREG 1293 DRFT FC OUAUTY ASSURANCE GUCANCE FOR LOW- , S MANUAL LEVEL RADOACTIVE WASTE DSPOSAL FAOUTY. Draft Fcr Com- j q PARKINS,R N. l NUREGiCR-3861- STRESS CORROSCN CRACKING OF LOW- PITTMANJ. STRENGTH CARBON STEELS IN CANDDATE HIGH-LEVEL WASTE NVREG4933 $06: A PRCRITl2ATON OF GENERC SAFETY ISSUES. REPOS! TORY ENVIRONVENTS. PLOTT.C. PASUPATHLV, NUREG 1258 EVALUATON PROCEDURE FOR SMULATION FAOU. I NUREG/CR4082 V05 DEGRADED PPING PROGRAM . PHASE TIES CERTIFIED L rPOER 10 CFR 55 Frial Report M.Somrsnnual Report, # sed-September 1M6- NUREG 1258 DAFT. EVALUATCN PROCEDUME FOR SMVtATCN i PATENAUDE.CJ.  ! NUREG/CR-4800: SIGPI A USErt$ MANUAL FOR FAST COUpVTA' POLLACK RN.  ! TON OF THE PROBA31USTC PERFORMANCE OF COMPLEX SYS* NUREG/CR-3145 V05 GEOFHYSCAL INVESTGATONS OF THE  ! i TEMS- WESTERN CHC.lNDAN A REGION Frial Report.Oetober 1981. Sep. l PAULSEN,GA ' NUREG/CR-4098. SEtSMC.FRAGIUTY TESTS OF NEW AND ACCEL- POL 2ER,W.L + ERATED' AGED CLASS 15 BATTERY CELLS NUREG/CR4737: INTERPRETATNE ANALYSIS OF DATA FOR 4 $OLUTE TRANSPORT IN THE UNSATUR ATED 20NE E S ^

)

N E CR 4942: EOViPMENT OPERABruTY DUR:NG STATCN OF FATE TRACE S NT TS U

;       BLACKOUT EVENTS'                                                                        1N THE UNSATURATED ZONE                                          i PAYNE T                                                                                   NUREG/CA-4M1: EFFECTS FROM INFLUENT BOUNDARY COND.

l NUREd/CR 5040 RADONUCLCE MiGRATON AROUND URANfUM TONS ON TRACER M GRATION AND SPATLAL VARIABluTY FEA- ( ORE BOOIES . ANALOGUE OF RADtOACTNE W ASTE TURES LN INTERMEDATE-SCALE EXPER:MENTS. j REPOSITORIES Anrual Report For 1984-1985' POMER0Y,P.W. I NUREG/CR4822; BROAD BAND SEISMC DATA ANALYSS September PELOOUIN.RA NUREG/CR-2850 V05. POPULATON DOSE COMMITMENTS DUE TO 1984. September 1966

!       RADOACTIVE RELEASES FROM NUCLEAR POWER PLANT STES                                   POPLE.R N         CA-3620 $02 INTRUDER DOSE PATHW AY ANALYS!S FOR                               NVREG/CR4862 Vot: COGNITNE ENVIRONMENT $lMULATION AN ARTIFCLAL INTELLGENCE SYSTEM FOR HUMAN PERFORMANCE               t j        THE ONSITE DSPOSAL OF RADCACTIVE WASTESThe ONSTE/

ASSESSMENT Votume 1

• And Overvee

MA* W8' N8*- NUREG/CR4862 YO2. CCG ENVIRONMENT SMULATION AN PERKINS.K. ARTIFCAL INTELUGENCE SYSTEM FOR HUMAN PERFORMANCE  ;

NUREG 1210 V05: PILOT PROGRAb ARC SEVERE REACTOR ACCI. ASSESSMENT. volume 2 Modeling Human intenton Formulatort ,

7) DENT INCICENT RESPONSE TRAINING MANUALU S Nuclear Reg +

POPPM' latory Commrssion Response NUREG/CR-4789' THE S4MULATION OF THERMOHYDRAULC PHE-4 pgggggg,g.g, NOMENA IN A PRESSURIZED WATER REACTOR PRIMARY LOOP. NUREG/CR-4982: SEVERE ACCIDENTS IN SPENT FUEL POOLS IN NUREG/CR4843 VQ1. UNIVERSITY OF MARYLAND AT COLLEGE PARK (UMCP) 2x4 LODP TEST F ACIUTY. Annual Report For 1985-SUPPORT OF GENERC SAFETY LSSUE 82 PE RTME R,0-PRASSINOS,P G. NUREG/CR-4843 V01: UNIVERSITY OF MARYLAND AT COLLEGE NUREG/Ch4826 V01 SEISMC M ARGIN REYlEW OF THE MAJNE ' PARK NMCP) 2x4 LOOP TEST F ACluTY Annual Report For 1985 YANKEE ATOMsC POWER STATON Volurne 1 Summary Resort PRATERJ.1, PETERSENJ.C. NUREG-1256 V01 INCENTIVE REGULATION OF NUCLEAR POWER NUREG/CR4889 ZlRCALOY4 OxCAh0N AT 1300 TO 2400 DE-PLANTS BY STATE PUBLC UTIUTY COMV:SSONS GREES C. NUREG/CR4890' HEAT OF REACTION OF MOr. TEN 21RCONfUM

,   PETERSEN K.M.                                                                               WITH UO2 NUHEG/CR 4928 OEGRADATION OF NUCLEAR PLANT TEMPERA-                                     NUREG/CR4991 PROPERTIES OF REACTOR FULL ROD MATERLALS I      TURE SENSORS AT HCH TEMPERATURES Final Sumtr.ary Report . Severo Core
)

Damage Property Tests Program. 4 PETERSON.SA PRATT,W.T. NUREG/CR4808 MrNTEO USER S MANUAL j NUREG/CR4552 A REVIEW OF THE SEABROOK STATCN PROBASI-1 PETTLDA USTC SAFETY ASSEUSMENT Ccednnent Fadure Modes And Rae j NUREG/CR4876 SILVER-tNDUMCADMiUM CONTROL ROO BEHAV- caogeW Source Terms OR AND AEROSOL FORMATON IN SEVERE REACTOR ACCl-DENTS PRENDERGAST K. i NUREG/CR-4925 FISSON PRODUCT BEHAVIOR QURiNG THE PBF NUREG-1269 LOSS OF RESIDUAL HE AT REMOVAL SYSTEM Dateo SEVERE FUEL DAMAGE TEST 11. Canyon Unrt 2, Apd 10,1967. 7 i I -_,y

                     - - . . - - - - , _ - . , ,.--- - , - - -          . - -     ,.- .- e_             ,- _ . _ . - _ .

Personal Author Index C7 PRUtte.K. MID.LD. NUREG/CR44C. TOUGH USER'S GUCE. NUREG/CR4583 YO2. DEVELOPMENT ANO VAUDAflON OF A REAL. TIME SAFT UT SYSTEM FOR THE INSPECTION OF UGHT WATER

                                                                                                                                                                                                                                                                  ^

CR421h V03 NL HEAVY SECTION STEEL TECHNOLOGY f985 PROGRAM.Se% annual ess Report For Apni-Septenter 1986 ' NUREG/CR4219 V04 N1; VY.SECTION STEEL TECHNOLOGY NUREG/CR 4583 V03 DEVELOPMFNT AND VALCATON OF A REAL. PROGRAM Sernannual Progress Report For October 1966 March TIME SAFT-UT SYSTEM FOR THE INSPECTION OF UGHT WATER REACTOR CGMPONENTS.A/nual Report.0ctoter 1985 . September NUREG/CR-4930 CRACK ARREST SEHAviOR IN SEN WOE PLATES " ' OF QUENCHED ANO TEMPERED A 533 GRADE B STEEL TESTED RENtERJ.A. > NURE /CR HEA ' STEEL TECHNOLOGY NUREG/CR-4758. A RETRAN MODEL OF THE CALVERT CUFFS.1 PROGRAM Fwe Year Pian FY 1966 1990. PRESSURIZED WATER REACTOR FOR ASSES $1NG THE SAFETY IMPUCATIONS OF CONTROL SYSTEMS. QUAYLLS.F. NUREG/CR4956. SYSTEM PEstFORMANCE OF HIGH-LEVEL WASTE RHEE,0.S, PACKAGE COMPONENTS, NUREG-1264: PROGRAM PLAN FOR CORRECTION OF U.S. INSTRU. MENT DEGRADATION OR FAILURE IN THE UPPER PLENUM TEST QUluCL4LD. FACIUTY (UPTF) W THE FEDERAL REPUSUC OF GERMANY. > NUREG/CR-4550 V03: ANALYSIS OF CORE DAMAGE FREQUENCY I FROM fNTERNAL EVENTS SURRY UNIT 1. RHODES,0.5. NUREG/CR-4826 V02 SEISMC MARGIN REVtEW OF THE MAINE NUREG/CR4821: REACTOR COOLANT PUMP SHAFT SEAL STABru. YANKEE ATOMC POWER STATION. Volume 2 Systems AnaWs. TY DURING STATON BLACKOUT. RASATIN,K. RICE 4E. NUREG4837 V06 NO3. NRC TLD DIRECT RADATION MONITOR:NG NUREGICR4957; SURVEY OF GEOPHYSCAL TECHNIQUES FOR NETWORK Progress Report. Jury September 1986-SITE CHARACTER 12ATION IN BASALT, SALT AND TUFF. AAM# ELE-UE Or OPERA 1 OCEDURES IN NUCLE. gq RICKER.R' NUREG/C R-4735 V02 EVALVATON AND COMP I NUREQ/CR4613. EVALUATON OF NUCLEAR POWTR PLANT OPER. WASTE PACKAGE TEST DATA. Biannual ReportAugust 1986 Janu-ATWG PROCEDURES CLASOFICATIONS AND 8'Y 1987* i q INTERFACES Protdems And Technques For emprovement RIDKY,R.W. RAasELU.A.R. NUREG/CR4918 V01: CONTROL OF WATER INFILTRATON INTO NUREG/CR4852. THE MEERS FAULT;TECTONC ACTIVITY IN NEAR SURFACE LLW DISPOSAL UNITS Annual Report. October 1965 1 SOUTHWTSTERN OKLAHOMA. September 1966. RAteEY.84ffTH A. RIGGS.R. NVREG 1214 R0t HISTORICAL DATA

SUMMARY

OF THE SYSTEMAT. NUREG4933 S06 A PRORIT12ATION OF GENERC SAFETY ISSUES O ASSES $ MENT OF UCENSEE PERFORMANCE. ! RIORDAN.B. RA4fSOELLJ.Y.  ! NUREG/CR-5036. COST ANALYSIS FOR IMPLEMENTATION OF PRO. NUREG/CR4801: CUMATOLOGY OF EXTREVE WINDS IN SOUTH- POSED CHANGES IN VITAL AREA REQUIREMENTS. ERN CAUFORNLA. RAS 40USSEN,T.C. RIVARD.J.B. i NUREG/CR-4655; UNSATURATED FLOW AND TRANSPORT NUREG/CR4320: THE RELATIONSHIP AND INFLUENCES OF FUEL THROUGH FRACTURED ROCK RELATED TO HIGH-LEVEL WASTE AND COOLANT SYSTEM PROCESSES DURiNG LWR SEVERE ACCl-REPOSITORtES Fr al Report Phase it DENTS ~ 1 gagg ROMRTS,F.P. NUREG/CR4626 V03 SEISMC MARGW REVIEW OF THE MAINE NUREG/CR-4773 DEDGN FEATURES TO FACIUTATE INTERNATON-YANKEE ATOMC POWER STATION. Volume 3 Freplity AnaWs AL SAFEGUARDS AT mixed.OICE CONVERSON FACiUTIES. I NUREG/CR 5003. DES 1GN OF A MATERLAL CONTROL MD AC. RAyasOND,R. COUNTING SYSTEM TO PROTECT AGAWST CONCEALMENT OF NUREG/CR4875: CHARACTERIZATON OF CRU$HED TUFF FOR THE OfvERSON BY FALSIFICATION AND COLLUSION EVALUAflON OF THE F ATE OF TRACERS IN TRANSPORT STUDES IN THE UNSATURATED ZONE. RO M RTS,Q.C. NUREG/CR4919 V01: AGING AND SERVICE WTAR OF SOLENotD. REE CE.W.D. OPERATED VALVES USED IN SAFETY SYSTEMS OF NUCLEAR NUREG/CR4418. DOSE CALCULATION FOR CONTAMWATON OF POWER PLANTS Volume 1 Operatry Exponence And Fadure 6dentifw THE SKW US4NG THE COMPUTER CODE VAR $KW cation. NUREG/CR4959 PERFORMANCE TESTING OF EXTREMITY DOSI-METERS. ROS6NSON,G C. NUREG/CR4760 TEST OF 6IN.THCK PRESSURE VESSELS Senes G/CR4719 COOLA81UTY QF STRATIFIED UO2 DEBRIS IN

                                                                                                                                                                                                                                                             '                    *'       ' "9                   

y ,n , SODUM WITH DOWWW ARD HEAT REMOVALThe 013 Expemnt NUREG/CR4930 CRACK ARREST BEHAvlOR tN SEN WCE PLATES REttesAN.A.L. OF QUENCHED AND TEMPERED A $33 GRADE B STEEL TESTED NUREG/CR-4936. AN INTEGRATED GEOLOGCALGEOPHYSCALAND UNM NONISOTHERMAL CONDTONS-GEOCHEMCAL INVESTIGATON OF THE MAJOR FRACTURES.ON RODA8AUGH.E.C. THE EAST SCE OF THE NEW MADRID EARTHOUAKE 20NE. NUREG/CR-4943 PREPARATION OF DESGN SPECIFCATONS AND I Rggygg,ag. DESIGN REPORTS FOR PUMPS. VALVES PIPING.AND PtPtNG SUP. NUREG/CR-3925 REY. SWIFT II SELF.TEACHWG PORTS USED IN SAFETY-RELATED PORTONS OF NUCLEAR CURRICULUM.hstra:Ne Prob 6 ems For The Sanea wasteanotebon POWER PLANTS Flow And Trenapart Mosel For Fractured Meda ROGN REICH.F.R. { NUREG/CR-4870 AN EVALUATON OF THE EFFECTS OF DESGN NUREG/CR 5059 VOC FRACTION MEASUREMENT UOut0 LEVEL DETAILS ON THE CAPACITY OF LWR STEEL CONTAINMENT DETECTION CONCEPT ASSESSMENT AND DEVELOPMENT. BUILDWC S i

t 98 Personal Author index  ; N00AAN,0. SALLACH.R A NUREG/CR 5040: RADONUCLIDE MCRATION AROUNO URANtOM NUREG/CR-4963 BORON CARBCE + STEAV REACTONS WITH r s ORE BOOIES . ANALOGUE OF RADCACTNE WASTE CEStVM HYDROXCE AND WITH CEStVM IOOCE AT 1270K IN AN i REPOSITORnES Anrual Report For 1984 1985 INCONEL 000 SYSTEM. 7 ROSA.EA SALLE TT,0.W. NUREG/CR4016 V02: APPLCATON OF SUM-MAUD A TEST OF AN NUREG/CR4443 V01: UNfVERSITY OF MARYLAND AT COLLEGE INTERACTIVE COMPUTER-BASED METHOO FOR ORGAN 12tNG PARK (UMCP) 2X4 LOOP TEST FACluTY. Annual Report For 1985. EXPERT ASSESSMENT OF HUMAN PERFORMANCE AND , REUABlUTY. Volume it Appereceit SAMANTA P. . NUREG/CR4410- EVALUATION OF DESEL UNAVAltABlVTY AND ROSS).W. RISK EFFECTNE SURVEILLANCE TEST LNTERVALS. NUREG/CR-3024: SUSTAINED CONCRETE ATTACK BY LOW- l SANDERS,GA , TEMPERATURE. FRAGMENTED CORE DEBRi$. NUREG/CR4871: RESULTS FROM THE DCH 1 EXPERIMENT, NUREG/CR4448. SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF A GENERAL ELECTRIC BWR3/ MARK l Case Study. , ROGS.PA NUREG/CR4458 SHUTDOWN DECAY HEAT REWVAL ANALY$$ OF NUREG4020 V10 N09- LCENSED OPERATING REACTORS STATUS A WESTINGHOUSE 2 LOOP PRESSURt2ED WATER REACTOR. Case SUOMARY REPORT. Data As of at 31.1986 (Gray Book i) Study NUREG4020 V10 N10' LCENSED RATING REACTORS STATUS NUREGICR-4710 SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF SUMMAR f REPORT Data As of September 30.1986 (Gray Book !) A COMBUSTON ENGINEER'NG PRESSURIZED WATER NUREG4020 V10 N11: LCENSED OPERATING REACTORS STATUS REACTOR Case Study.  !

SUMMARY

REPORT. Data As Of October 31.1986(Grey Book 1) NUREG/CR-4713 SHUTCOWN DECAY HEAT REMOVAL ANALYSIS OF i' NUREG4020 V10 N12: LCENSED OPERATING REACTORS STATUS A BABCOCK AND WILCOX PRESSURIZED WATER REACTOR Case

SUMMARY

REPORT. Data As Of November 30.1986(Gray Book I) Study , a NUREG-0020 V11 N01: LCENSED OPERATING REACTORS STATUS NUREG/CR4762. SHUTDOWN DECAY HEAT REMOVAL ANALYSS OF

SUMMARY

REPORT. Data As Of December 31.1986.(Gray Book !) A WESTINGHOUSE 3400P PRES $URIZED WATER REACTOR Case , ROTH.E.M. NUR /CR-4767: SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF NUREG/CR-4862 V01: COGNITIVE ENVIRONMENT SMULATON AN A GENERAL ELECTRC BWR4/ MARK LCase Study. ARTIFCIAL INTELUGENCE SYSTEM FOR HUMAN PERFORMANCE SASTRE,C. ASSESSMENT. Volume 1 Summary And Qvennes NUREG/CR4862 V02 COGNfTIVE ENVIRONMENT SMULATION-AN NUREG/CR4981: A SAFETY ASSESSMENT OF THE USE OF GRAPH. 1 ARTIFICIAL INTELUGENCE SYSTEM FOR HUMAN PERFORMANCE ITE IN NUCLEAR REACTORS LCENSED BY THE U S. NRC. l ASSESSMENT. Volume 2 MMeling Human intenton Formulatert i SATTERWHITE.D.  ! n NUREG/CR4862 V03. COGNITIVE ENYtRONMENT SMULATON AN l' ARTIFICIAL INTELUGENCE SYSTEM FOR HUMAN PERFORMANCE NUREG/CR4616: ROOT CAUSES OF COMPONENT FAtLURES , ASSESSMENT. Volume 3 Cogrvtree Reliebety Ana'yms Technque NU E / -4 47 V01 AN fNG ALLURE SURVEY OF UGHT I puppg.p, WATER REACTOR SAFETY SYSTEMS AND COMPONENTS. NUREG/CR4651: DEVELOPMENT OF RIPRAP DESGN CRITEM BY SATTISON,M B RIPRAP TESTING IN FLUMES Phase L NUREG/CRd644 DRFT. INTEGRATED REUABluTY AND RISK ANALY. , pygggg,yA SS SYSTEM ORRAS) USER'S GUOE VERSON 10 (DM NUREG/CR4623 IN-$1TU STRESS MEASUREMENTS IN THE EARTH'S CRUST IN THE EASTERN UNITED STATES gayyg. g, g,g/' CP 0087 SUMMAAY REPORT OF THE SYMPO$fuM ON SEls-RUNELE,GE. MC AND GEOLOGC SITING CRITERtA FOR NUCLEAR POWER , NUREG/CR4452. RISK METHOOOLOGY FOR GEOLOGC OtSPOSAL NUEk4661. DEVELOPMENT OF SITE SPECIFC RESPONSEl OF RADCACTIVE W ASTE. Final Rom SPECTRA pngpgg NUREGICR4685 SEISMC HAZARD CHARACTERIZATON OF THE , EASTERN UNITED STATES Comparatrre Evaluaton Of The LLNL And i NUREG/CR-4735 V02 EVALUATON AND COMPILATON OF DOE * 'j WASTE PACKAGE TEST DATA. Bannual ReportAugust 1986 Janu- , ary 1987. SAWY ER,W.D. I NUREG/CR.4995 EXPERIMENTAL ASSESSMENT OF THE SEAUNG  ! i RUSSELLAD. BN H E MS. NUREG/CR-4644 DRFT: INTEGRATED REUABluTY AND R!SK ANALY. j SIS SYSTEM ORRAS) USER'S GUIDE VERSON 10 (DRAFTK SCHAEFER,P. I NUREG/CR4763 ANALYSIS OF BALANCEOF. PLANT REGULATORY , i NURE -4667 V03 ENVIRONMENTALLY AS$STED CRACKING IN UGHT W ATER REACTORS Semennual ReportApni-September 1986 SCHA F F ER.A. NUREG/CR 4541: EXPER! MENT AL ASSESSMENT OF THE SEAUNG NJ C I4491: DEVELOPMENT OF MODELS FOR WARM PRES-i TRESSiNG. SCHERPEL2.R.L NUREG/CR4418. DOSE CALCULATON FOR CONTAM.NATON OF RE'G/CR-4739 RAMONA 3B CALCULATONS FOR BROWNS FERRY ATWS STUDY. SCHNEIDERA j NUREG/CP4085 MEETING WTH STATES ON THE LOW-LEVEL RA. I SAILOR V L DOACitvE WASTE POLCY AMENDMENTS ACT (LLRWPAA) OF NUREG/CR-4982 SEVERE ACCOENTS IN SPENT FUEL POOLS IN 1985 i SUPPORT OF GENERC SAFETY ISSUE 62 i SCHUL 2,R.K. j SAKEMAS,CA NUREG/CR4918 V01. CONTROL OF W ATER INFILTRATON INTO NUREG 1210 V03 PtLOT PROGRAM NRC SEVERE PEACTOR ACCI- NEAR SURFACE LLW DSPOSAl, UNITS Annual ReportOctober 1985 I DENT INCOENT RESPONSE TRAIN NG MANUAL Respor.ta Of L> . September 1986 j eensee And State And Local Othoa4 1 NUREG-1210 V05 P1 LOT PROGRAM NRC SEVERE RE ACTOR ACG- SCHWARTZ,L 1 DENT INCOENT RESPONSE TRAtNtNG MANUAL U S Nucioar Rep- NUREG4020 V11 NO2. LCENSED OPERATnNG REACTORS STATUS letory Commason Response

SUMMARY

REPORT Data As of January 31,1967 (Gray Br.ok i) l } l 1 _.

Personal Author index 99 a i NUREG4020 Vit NO3: UCENSED OPERATING REACTORS STATUS 9HAASAN H1

SUMMARY

REPORT.Deta As Of Fettuary 26.1987 (Gray Book 0 NUREG-1194: CONSTRUCTION APPRAISAL TEAM INSPECTION RE+

. NUREG4020 V11 N04: LCENSED OPERATING REACTORS STATUS                           SULTS ON WTLDNG AND NONOESTRUCTIVE EXAMtNATION AC.

$UMMARY REPORT.Deta As Of March 31,19874 Grey Book 0 TfVITIE S.

I NUREG4020 V11 N05: LCENSED OPERATING REACTORS STATUS

SUMMARY

REPORT.Deta As Of Apra 30,1987 (Gray Book 0 9 HACK,WJ.  ; NUREG4020 V11 Noe: UCENSED OPERATING REACTORS STATUS NUREG/CR4M7 V03 ENVIRONMENTALLY ASSASTED CRACMNG IN I

SUMMARY

REPORT.Deta As Of May 31,1967 (Gray Book 0 UGHT W ATER REACTORS Semiannual Report.Apre-September 1M6 NUREG4020 V11 N07; UCENSED OPERATING REACTORS STATUS

SUMMARY

REPORT.Deta As Of June 30,1987(Gray Book 0 gHAM,y.x, NUREG4020 V11 N06. UCENSED OPERATING REACTORS STATUS NUREG/CR 4731 V01. RESIOUAL UFE ASSESSMENT OF MAJOR  ! UGHT WATER REACTOR COMPONENTS . OVERV)EW Volume 1. NU 402 V N L D LA A ORS STATUS {

SUMMARY

REPORT.Deta As Of t 31,1M7.(Gray Book Q ggAigg,A, L NUREG-0020 Vit N10 UCENSED RATING REACTORS STATUS NUREG/CR4651: DEVELOPMENT OF RIPRAP DESIGN CRITERLA BY

SUMMARY

REPORT.Deta As of tomber 30,19671 Grey Book 0 RlPRAP TESTING LN FLUMES Phase L NUREG4020 VII N11: UCENSED RATING REACTORS STATUS

SUMMARY

REPORT.Deta As Of October 31,19674 Gray Book 0 SHAleNON,W.E. SCHWARTZ.S.V. NUREG/CR4753 V02- CANADAN SEtSMC AGREEMENT. Annual NUREG/CR 3145 V05: GEOPHYSICAL INVESilGATIONS OF THE R*PC't WESTERN OH104NDANA REGON Final Report,0ctober 1961. Sep- gpgg  ; i NUREG/CR-4550 V06PT1: ANALYSIS OF CORE DAMAGE FREQUEN-3CMWEITZER,0.Q. CY FROM INTERNAL EVENTS GRAND GULF. UNIT 1 Mac Report NUREG/CR-4981: A SAFETY ASSESSMENT OF THE USE OF GRAPH. NUREG/CR-4550 V06PT2. ANALYSIS OF CORE DAMAGE FREQUEN. CY FROM INTERNAL EVENTS GRAND GULF UNIT 1.Appen6ces. ITE LN NUCLEAR REACTORS LCENSED BY THE U S. NRC. SHARPE,R.W. SCHWEITZERA 'i NUREG/CR-4973. INTRAPLATE SEISMICITY OUTSOE OF THE NUREG-1210 Vol. PILOT PROGRAM NRC SEVERE REACTOR ACCI.  ; UNITED STATES. DENT INCIDENT RESPONSE TRAINfNG MANUALOvernew And Sum-mary Of Maior Poets

SCHWENM.E.9. NUREG-1210 YO2

PtLOT PROGRAM NRC SEVERE REACTOR ACCI-NUREG/CR-4850: STEAM GENERATOR GROUP PROJECT.Tesk 10 DENT INCIDENT RESPONSE TRAIN:NG MANUALSeve. Reacier Ac- [

Secondary Sde Esamrssten Final Report cadent Ovevew NUREG 1210 V03 PILOT PROGRAM NRC SEVERE REACTOR ACCI- , SC1ACCA.F. DENT INCOENT RESPONSE TRAIN:NG MANUAL Response Of U-NUREG/CR 5036: COST ANALYSl$ FOR IMPLEMENTATION OF PRO- consee And State And Local Of%als. POSED CHANGES IN Vff AL AREA REQU4REMENTS. NUREG 1210 V04 PILOT PROGRAM NRC SEVERE nEACTOR ACCI- i DENT INCOENT RESPONSE TRA!NH3 M ANUALPubic Protect've , SCOTT,9 A Actons . Predetermsned Crvtons And Irvtsaf Actons [ , NUREGICR-5025 EXPERIMENTAL STUDIES OF THE EARLY EFFECTS NUREG 1210 V05 PILOT PROGRAM NRC SEVERE REACTOR ACCI-OF INHALED SETA EMlTT4NG RADeCAUCUDES FOR NUCLEAR AC- DENT INCIDENT RESPONSE TRAINING MANUALU S. Nuclear Regu-COENT RISK ASSESSMENT. Phase 11 Report latory Commesson Response

  ; SCOTT MJ.                                                                   SHE PH ARD).E.

NUREG/CR4958 IMPAC' OF PROPOSED FINANCIAL ASSURANCE NUREC/CR4534. ANALYSIS OF DIFFUSON FLAME TESTS 3 REQUtREMENTS ON NUCLEAR MATERIALS LCENSEES. SHERM AN.M.P. N PROGRAM PHASE R .A E NT IN T BEL EF TE U nnual April NUREG/CR-4905 DETONABluTY OF H2. AIR DILUENT M3TURES. SCOTTA M. , NUREG/CR4872. EXPER' MENTAL AND ANALYTICAL ASSESSMENT SHutNM L OF CIRCUMFERENTIALLY SURFACE 4 RACKED PtPES UNDER NUAEG/CR-4726 EVALUATON OF PROTECTfVE ACTON RISKS BENDING NUREG/CR4877 ASSESSMENT OF DESIGN BASIS FOR LOAD. CAR SHIPW AY Q.0 RYING CAPACITY OF WELDCVERLAY REPAIRS NUREG/CR-4900 V01: COMPONENT F RAGIUTY RESEARCH , PROGRAM Phase i Demonstraton Tests Summary Report l SCOTT,W.B.

• NUREG/CR4900 V02- COMPONENT FRAGluTY RESEARCH NUREG/CR-4330 V03. REVIEW OF UGHT W ATER REACTOR REGU- PROGRAW Phase i Demonstrabon Tests Appendices t I LATORY REQUtREMENTS Assessment of Selected Re<Nia10ry Re.

l Qurements That May Have Margnal importance To Risk Postaccsdent gggy g Samphng System, Turtene M.ssdes.Combusttne Gas Control, Charcoal NUREG/CR4715. AN AGING ASSESSMENT OF RELAYS AND C1R. CULT BREAKERS AND SYSTEM INTERACTIONS. , SEE9ER L SHORTENCARIER NUREGICR4851: SEISMCITY 1886-89 IN THE SOUTHEASTERN NUREGICR 2452 RISK METHODOLOGY FOR GEOLOGIC DSPOSAL UNITED STATES.The Ahershock SecNonce Of The Chadeston Feuth OF RADCACTIVE WtSTE. Final Report i Caronne Earthquake 3ERGEANT,RL SHOTKIM. M. NUREG 1284 PROGRAM PLAN FOR CORRECTON OF U S. IN$TRU, NUREG/CR 4685 POST-PLOCE NE DSPLACEMENT ON FAULTS WITHtN THE KENTUCKY RfVER FAULT SYSTEM OF EAST-CEN. MENT DEGRADATION OR FAfLURE IN THE UPPER PLENUM TEST  ; TRAL KENTUCKY. FACIUTY (UPTF)IN THE FEDERAL REPUBUC OF GERMANY. SHULLR. t SETH EL ' NUREG/CR4953 CORRELATION OF RADIOODINE RESUSPENSION NUREG/CR4735 V01. EVALUATON AND COMFILATION OF DOE WASTE PACKAGE TES1 DAT A B. annual Repc4 December 1985 - WITH TEMPERATURE AT TWi-2 Juty 1986 SETH S. NUREG/C&l?35 V02 EV ALUAT ON AND COMPILATION OF DOE NUREG/CR-4783 ANALYSIS OF BALANCECF-PLANT REGULATORY W ASTE PACKAGE TEST DATA B. annual Report Aupst 1986. .lanu-ISSUES Final Report ary 1987 _m_ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ , _ _ .

100 Personal Author Index S4E GE L.B. NUREG/CR4551 V4 DAF: EVALUATON OF SEVERE ACCCENT NUREG 1231: SAFETY EVALUATION REPORT RELATED TO THE BAB- RISKS AND THE POTENTIAL FOR RtSK REDUCTON GRAND f l COCK AND WILCOX OWNERS GROUP PLANT REASSESSMENT GULF. UNIT 1 Draft For Comment SMITH,M.R 860ALLA.LA. NUREG/CR4921: ENGINEERING AND QUAUTY ASSURANCE COST NUREG/CR4418: DOSE CALCULATCH FOR CONTAM:NATCH OF FACTORS ASSOCIATED WITH NUCLEAR PLANT MOOtF#CATON THE SKIN USING THE COMPUTER COOE VARSKIN SMITH.O.L ' 88#@%Q-NUAEG/CR-5036. COST ANALYSIS FOR IMPLEMENTATION OF PRO. NUREG/CR47' J A RETRAN MODEL OF THE CALVERT CUFFS 1 POSED CHANGES IN VITAL AREA REQUIREMENTS PR'.SSURIZED WATER REACTOR FOR ASSES $tNG THE SAFETY IMPLCATONS OF CONTROL SYSTEMS. 84MMONS.C.E SMITH P R NUREG/CR-4817: LODINE PARTITCN COEFFICIENT MEASUREMENTS AT SIMULATED PWR STEAM GENERATOR CONoiTONS Interen NUREG/CR-4931: RESPONSE OF PENTR1 FUGAL AND AXI VANE

,                     Data Report,                                                             BLOWERS TO LARGE PRESSURE TRANS!ENTS g,gogg g,pA                                                            SMITH.SA
!                  NUREG/CR 3231: PIPE.TO PIPE IMPACT PROGRAM                             NUREG/CR4958 IMPACT OF PROPOSED FINANCIAL ASSURANCE
!                  NUREG/CR4469 V04. NONOESTRUCTIVE ExAMiNATON (NDE) REU.                      REQUIREMENTS ON NUCLEAR MATERIALS UCENSEES.

l AB:UTY FOR INSERVCE INSPECTON OF UGHT WATER RE ACTORS Sermannual Report October 1985. March 1986. SNCER.D.E NUREG/CR4469 VO$. NONDESTRUCTIVE EXAMINATION (NDE) REU. NUREG/CR4844 DAFT: INTEGRATED REUAB!UTY AND RISK ANALY. O ActuTY FOR INSERVCE INSPECTCN OF UGHT WATER SIS SYSTEM (IRRAS) USER'S GUCE VERSON 1.0 (DRAFT, RE ACTORS Sermannual Report. Apns-September 1966  ! NUREG/CR4469 V06 NONCESTRUCTIVE EXAM <NATON (NOE) REU- SNIPES.M.S. ) 2 ABluTY FOR INSERVICE INSPECTCN OF UGHT WATER NUREG/CR.5025. EXPER: MENTAL STUDIES OF THE EARLY EFFECTS 3 REACTORS Sermannual Report October 1986 IAtrch 1987. OF INHALED BETA-EMITTING RADONUCUDES FOR NUCLEAR AC-CIDENT RISK ASSESSMENT. Phase H Report NUREG/CR4623. IN SITU STRESS MEASUREMENTS IN THE SO9ERANO,F.T. EARTH'S CRUST IN THE EASTERN UNITED STATES. NUREG/CR 3956 IN SITU TESTING OF THE SHIPPINGPORT ATOMC SiSKIND.S.  ! NUREG/CR-4730: EVALUATION OF POTENTIAL MIXED WASTES CON- SOLD AT J.K-TA!NING LEAD, CHRoutVM.USED OIL.OR ORGANC LCUCS NUREG/CR4653 GASPAR li TECHNCAL REFERENCE AND USER SJOREEN.A. CE. NUREG/CR 4722: SOURCE TERM ESTIMATON USING MENU-TACT. SOZE R.A. NUREGICR4689 THERMAL HYDRAUUC AND CHARACTERISTC SKINNERN'4825 NUREG/CR A PRELIM NARY EVALUATCN OF MODELS THE ECONOMC FOR PACKED DEBRIS BEDS RISK FOR CLEANUP OF NUCLEAR MATERIAL LCENSEE CONTAMi-SPANNER.J C NATCN INCIDENTS NUREG/CR$4469 V04 NONDESTRUCTIVE EXAM:NATON (NDE) REU SKINNER L ABtVTY FOR INSERvCE INSPECTON OF UGHT WATER } NUREG/CR-4783 ANALYSIS OF BALANCE OF. PLANT REGULATORY REACTORS Sermannual Report. October 1985 Varch 1966 ISSUES Fnal Report NUREG/CR4469 V05 NONDESTRUCTIVE EXAM;NATON {NDE) RELI. j ABlUTY FOR INSERVICE INSPECTON OF UGHT WATER j SKR ABLE,lL W. RE ACTORS Semiannual Resort Apnl. September 1966 NUREG/CR4884 INTERPRETATON OF BCASSAY MEASUREMENTS NUREG/CR-4469 YM: NONDESTRUCTIVE EXAMINATON (NDE) REU. SLEWWONS.O.S. AB!UTY FOR LNSERVCE INSPECTON OF LGHT WATER RE ACTOR $ Sermannual Report October 1986 March 1987. NUREG/CR4852 THE MEERS F AULT TECTONC ACTIVITY IN ) SOUTHWESTERN OKLAHOMA SPETTE LLC.M. j NUREGICR4016 V02 APPUCATON OF SUM MAUD A TEST OF AN SLOVIK,0 C. i j NUREG/CA4739 RAMONA-38 CALCULATIONS FOR BROWNS INTERACTIVE COMPUTER-BASED METHOO FOR ORGANIZING FERRY ATWS STUOV. EXPERT ASSESSMENT OF HUMAN PERFORMANCE AND l REUABluTY. volume tt Appereces SMITKB.W. SPINOSAE D NUREG/CR4695 MATERIAL CONTROL AND ACCOUNTING (MCAA) i LOSS DETECTON DUR:NG TRANSITION PERCOS AND PROCESS NUREGICR4795. LONG-TERM PERFORMANCE OF HIGH-LEVEL UPSET CONOtTIONS Guss W ASTE FORMS NUREG/CR-5003 DESCN OF A MATER!AL CONTROL AND AC-COUNTING SYSTEM TO PROTECT AGAINST CONCEALMENT OF gppggg g,,$615 V02 MODEUNG STUDY OF SOLUTE TRANSPOR NUREG/CR-DivERSON BY FALSlFCATON AND COLLUSCN IN THE UNSATURATED ZONE Workshop Proceeengs SMITKC.M. NUREG/CR 4ict EFFECTS FROM INFLUENT BOUNDARY CONDI-NUREG/CR-4577. AUTOM ATED LONG TERM SURVEILLANCE OF A TONS ON TRACER M:GRATON AND SPATtAL VARLABluTY FEA-l COMMERCIAL NUCLEAR POWER PLANT. TURES IN INTERMEDIATE-SCALE EXPERIMENTS SMITKF.J. SPULAK.R G-NUREG/CR4134 R01. RE POSITOR Y ENVIRONMENTAL PARAM. NUREG/CR-3495 CALCULATCN OF FAILURE IMPORTANCE ME AS-ETERS AND MODELS RELEYANT TO ASSESSING THE PERFORM URES FOR BASC EVENTS AND PLANT SYSTEMS IN NUCLEAR j ANCE N lH-LEVEL WASTE PACKAGES (BASALT, TUFF AND POWER PLANTS ST AM ATE LATOS,M. i SMITRLN. NUREG/CR4646 HIGH-LEVEL W ASTE PRECLOSURE SYSTE MS j NUREG/CR4551 V3 PT1 EVALUATON OF SEVERE ACCCENT RISAS $AFETY ANALYS4$ Phase 2. Fnal Report. AND THE POTENTIAL FOR RISK REDUCTCN PE ACH I BOTTOM. UNIT 2 Maan Report Oran For Comm nt $fE ARNS.R.G. j NUREG/CR4551 v3 PT2 EVALUATON OF SEVERE ACCCENT RISKS NUREG/CR4936 AN INTEGRATED GEOLOGCALGEOPHYSCAL.AND

AND THE POTENTIAL FOR RISK REDUCTION PE ACH GEOCHEMCAL INVESTGATION OF THE MAJOR FRACTURES ON 1 BOTTOM. UNIT 2 4peroces Dra't For Commer't THE EAST SOE OF THE NEW MADRID E ARTHOUAKE 2ONE 1

4 1 1

Personal Author Index 101 STE E LE.R. SYKESAL NUREG/CR4734 SE8MC TESTWG OF TYPCAL CONT AINVENT NUREG'CR4820 COVPAR SON OF THE 1982 SEADEX DISPERSON P1 PING PENETRATCN SY$TEMS DATA WITH RESULTS FROM A NUVBER OF OtFFERENT MODELS STEIN 8RECHER D. TABATABAIAS. NUREG/CR4SO V01 N1 GENERC CC#VUNCATCNS NUREG/CR 4330 V03 REviCW OF OGHT W ATER REACTOR REGU-INDEX Listrgs Of Communn.atons (1971 1986) LATORY REQUtREMENTS Assessment Of Se+cted ReWatory Re. NUREG/CR-4690 V02 GENERC COVVUNCA1CNS INDEx User's osements That May Have Margeal importaxe To Rin Postacodent Marwal Sampung System, Turtane M< sues.Comtn,-stee Gas ControLCrescoaf Fsters STENHOUSE.MJ NURE GICR4954 LONG.TE RM PERFORMANCE OF SPENT FUEL T AR B E LL,W.W. WASTE FORMS. NUREG/CR 3024 $USTAiNED CONCRETE ATTACK SY LOW-TEMPFRATURE FRAGMENTED CORE DEBR:S STEVERSONJA NUREG/CR4671 RESULTS FROM THE OCH.1 EXPER: MENT. i I NUREGICR4407. PIPE BREAK FREQUENCY ESTiMATON FOR NU. TAYLOR G C, CLEAR POWER PLANTS NURE G /CR-4 79L LONG TERM PERFORMANCE OF HIGH4EVEL ST E W A R T.R D, GLASS WASTE FORVS NUREG/CR4844 DRFT; INTEGRATED REUABtUTY AND R:SK ANALY- NUREG/CR-4954 LONG TERM PERFORMANCE OF SPENT FUEL S:S SYSTEM (IRRAS) USER S GUCE VERSON 10 (DRAFT) W ASTE FORMS STOETZEL,O A TAYLORJH. NUREG/CR4330 V03 REVIEW OF UGHT W ATER REACTOR REGU- NUREG/CR4985 INDIAN POINT 2 PEACTOR COCUNT PUVA SEAL LATORY REOutREMENTS Assessment Of Se4cted Repatory Re- EVALUATONS Que ements Teat May Have Margnal impo tance To Risk Postaccdent Samphng System. Tu@ne hAwes.CombustMe Gas Controt Charcoal TA YLOR.T.T. Fdterg NUREG/CR4469 V04 NONDESTRUCTIVE DAM NATK'N (NDE) RELi-AB:UTY FOR INSE RVCE INSPECTION OF UGHT W A TER STOHR,CJ RE ACTORS Semennuai Reciort Octotier 1985 Varch 1986 NUREG/CR-2476 V03 A STUDY OF TRENCH COVERS TO M.N M ZE NUREG/CR4469 V05 NONDESTRUCTIVE ExAMAATON (NDE) REU-INrlLTRATION AT WASTE DISPOSAL SITES Finat Rept. AB!UTY FOR INSERVCE INSPECTON Oc UGHT WATER RE ACTORS Semenual Remrt. Aprd Sectenter 1996 STONESIFERAS. NUREG'CA4469 V06 NONDESTRUCTIVE EXAM:NATON (NDE) REU-NUREG/CR4491. DEVELOPVENT OF MODELS FOR W ARM PRES- ABlUTY FOR INSERVCE :NSPECTON OF UGHT WATER TRESDNG PEACTORS Se%annuat Recort. October 1963 Varch 1987. STREITAE., T EICHM A NN,T. NUREG/CR4793 RESULTS OF SEMACALE MOD 2C SVALL.BRE AK NUREG/CR4405 PROB A81USTC R SK ASSESSVENT (PRA) IN. LOSS-OF COOLANT ACCtDENT WITHOUT HPl (S NH) ErPER VENT StGHTS SER'E S T H E OF A NOUS,T.G. STRENGE DL NUREGiCR 4978 THE COOLDOWN ASPECTS OF THE TMi-2 ACCI-NUREG/CR46$3 GASPAR 41. TECHNICAL REFERENCE AND USER DENT. GUCE THOMASAT. STRUCKMEYER,R. NUR E G 'CR.4 7 53 V02 CANADtAN SEISV C AGREEVENT Annual NUREG4837 V07 NO3 NRC TLD D* RECT RADIATON MONITOR;NG Reccet NETWORK Progress Report July September i967. THOMPSON.N G. SUSUDHi,M. NUREG/CR 3861 STRE SS-CORROSION CRACMNG OF LOW NUREG/CR4965 INotAN PO:NT 2 REACTOR COOLANT PUVP SE AL STRENG1H CARBON STEELS 1N CANDCATE HiGH-LEVEL W ASTE EVALUATCNS RE POstTORY ENYiRONVENTS NUREG/CR 4955 LONG. TERM PERrORM ANCE OF CONTANER MA. SULUV A N.R. TER ALS FOR HIGH LEVEL A ASTE NUREG/CR-4783 #AALYSIS OF BALANCE OF-PLANT REGULATORY ISSUE $ Feel Reput THOW SONJF. NUREG<CR 4?04 V02 RELATIVE BOLOGCAL EFFECTIVENESS (RBE) i l SULUV AN,T. OF FISSION NEUTRONS AND GAMV A RAYS AT OCCUPATIONAL NUREG/CR4837. LOW 4 EVE L WASTE SOURCE TERM EXPOSURE LEVELS Voesme il St4*s On The EMects Of 60 Ewar EVALU ATON Reven et PutAshe Mcdehng And E mpenmental Cnce Weevy Essesses To Fiss.on Neutrons And Gamma Par s On Wort.And Presentaton Of Loe Level Waste 5.Nrce Term Mcdein9 kmal Of M<e Frame *0rk And Preimrery MMee Devetopment. TICHLERJ SUO ANTTILAA NUREG'CR 2907 V05 RADCACTIVE M ATERtALS RELE ASED FROM NUREG/CR4727 SWSS SUSTAINED HEATED METALLC MELT, CON NUCLE AR POWER PLANTS Annual Report 1994 CRETE INTER ACTCNS WITH OVERLYWG A ATER POOLS Tif SZE N,5 R. SURSOCKJP. NUREG /CR445 DETONAFUTY OF H2 A!R-DtLUENT MIXTURES NUREG-1163 COORDWATION OF SAFETY RESEARCH FOR THE BABCOCK AND WILCOX l' EGRAL SvSTEM TEST PROGRAM TILLSJL NUREG/CR-4996 CONT AINVE NT LOADS DUE TO DtNECT CON 1 A;N-SUTTE R,S L VENT HE AT:NG AND ASSOCIATED HYDRDGEN BEHAVIOR Ana$yses NUREG/CR4779 NEW DATA FOR AEROSOLS GENERATED By RE- AN Cawatens with The CONTAIN Code LEASES OF PRESSUR' ZED POWDER $ AND SOLUTONS IN STATC AtR TING.P. NUREG-1270 V01 INTERNATONAL CODE ASSF SSMENT AND APPU-SUTTOstG.M- CATONS PW)GA AM Annua? Retori NUREG'CR4822 BROAD BAND SEISV C DAT A ANALYS S September NUREG 1271 GuiDEUNES AND PROCEDURES FOR THE INTE RNA. 1964. Septemtr,r 1986 iONAL CODE ASSES $ VENT AND APPUCATONS PROGRAM SWAINAD. TKACHYKJ K NURE G/CR 4772 ACCIDENT SEQUENCE EVALUATON PROGRAM f*1 REG /CR 4766 TRANSFORT BE MAVOR OF OE=NE IN E F FLUE NT HUM AN RE UABtUTY ANALY5JS PROCE DURE RADOACTMTY MON TOR.NG SYSTE US

4' .  ; 4 i 102 Personal Author index TCetAS.M L VA80KulKENJ.C. t NUREG/CR-4794 IRON OXCE AEROSOL EXPERIMENTS IN STEAM. NUREG/CR4012 V02; REPLACEMENT ENERGY COSTS FOR NUCEE. 8 AIR ATMOSPHERES NSPP TESTS 501505 AND $11,OATA RECORD i AR ELECTRCITY-GENERATING UNITS IN THE UNITED i ? I N E CR 5017: DMESTONE CONCRETE AEROSOL EXPERIMENTS  ! IN STEAM-AIR ATMOSPHERES NSPP Tests 621,522,And 531,Deta VAUSLJ.W. l Record Report NUREG/CR-4590 V01: AG NG OF NUCLEAR STATION DIESEL  ; GENERATORS EvaMeton Ot Operateg And Expert Exponence Phase TONGATA j j NUREG/CR-4161 Vol CRITCAL PARAMET!RS FOR A HGH4EVEL 1 WASTE REPOSTORY, Volume FTuM. NUft%CR-4590 V02. AGANG OF NUCLEAR STATION OtESEL I GENERATOPS Evaluaton Of Operateg And Esport  ! 7048AN,GJ. Exponence Woritshce ( l NUREG/CR-4715. AN AGING ASSESSMNT OF RELAYS ANO CtR. NUR C 9 VO A RV E WEAR OF SOLENOID. E 4616; ROOT CAUSES OF COMPONENT FAILURES 2 OPERATED VALVES USED IN SAFEFY SYSTEMS OF NUCLEAR PROGRAM Metods And A@hcabons.  ; j POWER PtANTSYolume 1.Operatog Exponence And Faaure idenW, NURE G/CR-4769: RISK EVALUATIONS OF AGJNG PHENOMENAthe , cators Lnear Agng Reliebslrty Model And its Extensons. 1 i NUREG/CR4410' EVALUATION OF DESEL UNAVA'LA81UTY AND TOMKINS.J L RISK EH ECTIVE SURVEILLANCE TEST INTERVALS. NUREG/CR4909: MELPROG-PWR/MOOO:A MECHANtSTC CODE FOR i ANALYSIS OF REACTOR CORE MELT PROGRES$CN AND VESSEL YlRGiUO EJ. , 4 ATTACK UNDER SEVERE ACCIDENT CONDITIONS. NUREG 1285. NRC ST AFF FVALVATION OF THE GENERAL ELECTRC COMPANY NUCLE AR REACTOR STUDY ("REED REPORT"). TRAMMELLC M. [

!                                                                                          NUREG-1269 LOSS OF Rest 0 VAL HEAT REMOVAL SYSTEM O@o                                                             YO.T.V.                                                                                                    .

Canyon Urvt 2. 4rd 10.1967. NUREG/CR4330 V03 REVIEW OF UGHT WATER REACTOR REGO. LATORY REOUIREMENTS. Assessment Of Selected Regulatory Re.

• TRAUS,RJ. Ourements That May Have Marginal importance To RisitPostaccsdent NUREG/CR4410. DOSE CALCULATION FOR CONTAMWATION OF Samphng System, Turtune IAss4es.Corrcusttee Gas Control,Oureoal THE SKIN USNG THE COMPUTER CODE VARSKIN. Feters NUREG/CR-5006: PRA APPLCATION PROGRAM FOR IN$PECTION EG 2903 V01: SELECTION OF EARTHOUAKE RESISTANT AT MEE UN41 4 DESGN CRITERIA FOR NUCLEAR POWER PLANTS . METHODOLO- yonA,J.p, 1 GY AND TECHN8 CAL CASES. Drect Empncal Sea Of Respons* '

NUREG 1144 RO1: NUCLEAR PLANT AGWG RESEARCH (NPAR) PRO-j NU /CR 2 SELEY OF A AKE NANT NN DESGN CRITERIA FOR NUCLEAR PC%TR PLANTS . METHODOLO- yUutg . GY AND TECHNICAL CASES Methods For introducten Of Geo6oycal NUREG/CR4663. SURFACE SPE';TROSCOPY OF PRESSURE Data into Charactenraton Of Actrve FauRs And Seesmerty And-VESSEL STEEL FATIGUE FRACTURE SURFACE FILMS FORMED IN ! PWR ENV*0NMENTS. TSAO.L r ! NUREG/CR4161 Vot CRITCAL PARAMETERS FOR A HIGH-LEVEL

• NEG/ VO C IC PA AMETERS FOR A HGH-LEVEL WACHTEU'50 NUREG-12 EVALUATION PROCEDURE FOR SIMULATI WASTE REPOSITORY, Volume 3 Seit TIES CERTIFIED UNDER 10 CFR 55 Fnal Report 1

d NUREG-1258 DRFT: EVALVATICW PROCEDURE FOR $WULATION . TUfTE.P. FACILITIES CERTIFIED UNDER 10 CFR 65 Drei Report  ! I NUREG/CR-4968 EVALUATION CF UNCERTAINTIES tN tRRADLATED - l HARDWARE CHARACTER 12ATION. WAONER.K L 1 NUREGICR4844 DRFT; INTEGRATED REUA81UTY AND RISK ARALY. l 1 TUOMISTO.M. Sis SYSTEM PRRAS) USER'S GutOE . VERSaON 10 (DRAFT). ! NUREG/iA 0004. THERMAL M:XING TESTS IN A SEWLANNULAR i DOWNCOMER WITH INTERACTING FLOWS FROM COLD LEGS. W AGONE R S.R. I 4 NUREG/CR-4165 SEVERE ACODENT SEOVENCE ANALYSIS PRCL i i USHERJ L GRAM . ANTICIPATED TRANSlENT WITHOUT SCRAM SMULA. ' d NUREG/CR 5037. F6AE ENVIRONMENT DETERW: NATION IN THE LA* TIONS FOR BROWNS FERRY NUCLEAR Pt. ANT UNIT 1. ] SALLE NUCLEAR POWER PLANT CONTROL ROOM ! W AMSLEY,R E , UTHLLE NUREG/CR 5041 V01: RECOMMENOATION3 10 THE NRC FOR t NUR[G/CR4950 Vot: THE SHOREUNE ENVIRONMENT ATMOS' PHERIC DSPERSON EXPERIMENT (SEADEX)tspenment Descnp- REVIEW CRITERtA FOR ALTERNATNE METHODS DF LOW 1EVEL ton MADIOACTIVE WASTE DSPOSAL Tassi f a Beow4round VaJts i NUREG/CR4950 V02 THE SHOREUNE ENVIRONMENT ATMOS.

• wgggyy, PHERIC DISPERSON EXPERIMENT (SEADEX) Meteoroigcol And Gas NUREG/CR4843 V01: UNfyERSITY OF lAAR(LAND AT COLLEGE j Trecer Dam PARK (UMCP) 214 LOOP TEST FAQUTY Annual Resort For 1965-i UAN FLEET.LO.

W AMD.D.S. NUREGICR4469 V04 NONDESTRUCTNE EXAMINATION (NDE) REU-

                                                                                                                                                                                            ^                  NUREGICR 3325            REV     ShnFT          9                 SELF TEACHtNG ACTOR Sema                                                  et t 5 . March 9e                          CURRICULUM inustrative Protnems For The Sarda Waste-Isosahon NUREG/CR4469 VOS-                                                       f RUCT!VE EXAMINATION (NOE) REU.                 Flow And Transport ledet For Fractured Meda ABluTY FOR INSERYlCE INSPE CTION OF LGHT WATER                                                           WASHINGTON,K.L i'

E CR 4 NONDE fR T I ON (NDE) REU. NUREG/CR48a?. POSTCON A POSTPROCESSOR ANO UNIT CON-AB UTY FOR INSERVICE INSPECTION OF LIGHT WATER VERSION PROGRAM FOR THE CONTAtN COMPu t ER CODE I REACTORS Semannual Report. Oc1cht 1966 . March 1987 W ATE RMAN.D K. VANARSDALER S. NUREG.1214 Rot HISTOR8 CAL DATA

SUMMARY

OF THE SYSTEMAT. j NURE G/CR46e5 FOST.PUCCENE DtSPtACEMENT ON FAULTS IC ASSESSMENT OF LICENSEE PERFORuANCE i WITHN THE KENTUCKY RIVER FAULT SYSTEM OF E ASTCEN-2 TRAL KENTUCKY. W AT KINS).C. ! NUREG/CR480? AN EVALUADON OF TRAC #F1/ MOO 1 COMPUTER i UANDERMOLE N,H. CODE PERFORMANCE DURENG POSTTEST SMUtATIONS OF SF. ) NUREG4iG3 S06 A PRIORitt2ATION OF GENERC SAFETY ISSUES MISCAtt MOO 2C FEEDWAftR UNE BREAK TRANSIENTS L

                                                                                                               - , - ~ ~, . . , - _ . - , . , , - . , -- - - ,-                                - - - - - , -                .-    mym,--,-.-nm     -n----n      , - - - - - , , - -     n.-   - , . - , - - - - - - - -

Personal Author inder 103 t CATKINS. Ret WHE ATLE Y.P.O. l

NUREG 1210 V01

PtLOT PRCORAW NRC SEVERE REACTOR ACC8- NUREG/CR-4165; SEVERE ACCICENT SEQUENCE ANALY$tS PRO- ,

DENT INOOENT RESPONSE TRAINWG MANUALOromes A/4 Sum- GRAW ANTIOPATED TRANStENT WtTHOUT SCRAW SaVULA. j d mary Of Wa#cr Posnts TONS FOR BROWNS FERRY NUCLE AR PLANT UNIT 1.  ; NUREG-1210 V02 pitot PROGRAW NRC SEVERE REACTOR ACC8- NUREG/CR 4966 YO2. [ VALUATION OF OPERATION 4 SAFETY AT .

 ;                                                                                                              BABCCrK AND WRCOX PLANTS Volume 2. ThermeLHy*eA Re-                                        i OENT WCIDENT RESPONSE TRAWWG WANUALSevero Reactor Ac-cdont Owemee.                                                                                            eurts                                                                                      !

NUREG-1210 V03 PILOT PROGRAW NRC SEVERE REACTOR ACCL DENT INCOENT RESPONSE TRANWG MANUALRespore, of Lk WHEELER.TA j eensee And State And Local C#oeit NUREG/CR-3495; CALCULATION OF FAILURE IMPORTANCE WEAS- i

NUREG 1210 V04 PILOT PROGRAW NRC SEVERE REACTOR ACCb URES FOR BASC EVENTS AND PLANT SYSTEWS IN NUCLEAR DENT WCOENT RESPONSE TRAINWG MANUALPMC Protecirve POWTR PLANTS 3 r

i Actone . Predetermned Cntena Ar4 inmal Actes NUREG/CR4550 YO6PT1: ANALYSIS OF OORE DAMAGE FREQUEN-

!    NUREG.1210 VOS PILOT PROGRAW NRC SEVERE REACTOR ACCI.                                                      CY FROW INTERNAL EVENTS GRAND GULF. UNIT 1 h Report                                       l DENT INCIDENT RESPONSE TRAtNWG MANUALU S. Nucieer Re9J-                                       NUREG/CR4550 V06 Pit ANALY$l$ OF CORE DAWAGE FREOVEN-                                                i a       tatory Cormuseon Response.                                                                               CY FROM INTERNAL EVENTS GRAND GUtF. UNIT 1.Aspeneces                                      ;

CATLINJTON.S. WHEELER,WA NUREG/CR 5036. COST ANALYSIS FOR IMPLEMENTATION OF PRO- NVREG/CR-3M4 STUDY OF OPERATING PROCEDURES IN NUCLE. POSED CHANGES IN VITAL AREA REQUIREWENTS AR POWER PLANTS. Practices And Pr@lems , CATSON.E.C. WHITEJ.R. I NUREG/CR4856 FEA$rBlVTY STUDY ON A DATA BASED SYSTEW NUREG/CR44tl. DEMONSTRATON TESTWG OF A SURVirLLANCE l FOR DECtS10NS REGARDING OCCUPATIONAL RADATON PRO- ROBOT AT BROWNS FERRY NUCLEAR PLANT.Ana4sts Of Costs I t TECTION WEASURES_ A/4 Benehts WEATHERGYJA WHITEHEAD.D.W. NUREG/CR4969 AXISYWWETRC ANALY$r$ OF 14-SCALE REtN. NUREG/CR-4834 V01: RECOVERY ACTIONS IN PRA FOR THE RISK .{ FORCED CONCRETE CONTAINWENT SUtLDWG USNG A DSTRIB- WETHODS INTEGRATON AND EVALUATION PROGRAW

;      UTED CRACKWG WOOEL FOR THE CONCRETE-                                                                       (RWtEP). Volume 1. Development Of The Data Based Method WE etR.C.F.                                                                            wigggg,gw

NUREGICR4610 EFFECTS OF LATERAL SEPARATON OF OKOIC NUREG/Cd3232 DETAILED STUDES OF SELECTED.WELL EXPOSED l'

!      AND WETALLIC COAE DEBRIS ON THE BWR WK 1 CONTAWWENT                                                        rRACTURE ZONES IN THE ADRONDACK MOUNTAWS DOWE.NEW DAYWELL FLOOR.                                                                                            yong,                                                                                    ;

i t WEEKSJ.R WILSURN.M P NUREG/CR-4981 SEVERE ACCOEllTS IN SPENT FUEL POOLS 6N NUREG/CR4640. HANDOOCE OF SOFTWARE QUAUTY ASSURANCE SUPPONT OF GENERIC SAFETY ISSUE 62. TECHNIQUES APPLICABLE TO THE NUCLEAR INDUSTRY. I ' WEIA.TJ NUREG/CR.5006 DEVELOPWENT OF A TESTING AND ANALYSJS ##"0AE' NUREGICR4 976. PLANT RH120$PHERE PROCESSES INFLUEN WETHODOLOGY TO DETERWINE THE FUNCTIONAL CONDTON OF RADONUCLOE WOBW W SOL SOLENOC OPERATED VALVES. I WILKOWSKI.G. wggggy I NUREG/CP.0062 VQ1; PROCEEDNGS OF THE FOURTEENTH W ATER NUREG/CR4870 ANALYSIS OF EXPERtWENTS ON STAWLESS j STEEL FLUK WELDS Topical Report < REACTOR SAFETY INFORWATON WEETNG NUREG/CP4062 V02 PROCEEDNGS OF THE FOURTEENTH WATER mLKOWSKI.GR REACTOR SAFETY INFORW ATION WEETtNG N9AEG/CR-4052 V05 DEGRADED PIPtNG PROGRAW - PHASE NUREG/CP4062 V03. PROCEEDNGS OF THE FOURTEENTH W ATER h Semennual Report, Apnt-Septemt,or 1986. , RE ACTCA SAFETY INFORW ATON WEETWG I NUREG/CP4062 V04 PROCEEDNGS OF THE FOURTEENTH W ATER WILUAVS.D.C. l RE ACTOR SAFETY tNFORWATION WEETNG NUREG/CP4062 V05 PROCEEDNGS OF THE FOURTEENTH W ATER NURE G/CR4551 V1 DRF. EVALUATION OF SEVE.RE ACCIDENT r 1 RISKS AND THE POTENTIAL FOR RISK REDUCTION SURRY r ] RE ACTOR SAFETY INFORWATON WEETNG 1 i NUREG/CP4062 YO6. PROCEEDNGS OF THE FOURTEENTH W ATER POWER STATION UNIT 10 ram For Comment RE ACTOR SAF ETY INFORW ATON WEETING NUREG/CR4551 V2 DRF: EVALUATON OF SEVERE ACCOENT ( RISKS AND THE POTENTIAL FOR RISK REDUCTON SEQUOYAH NUREG/CP4094 TRANSACTONS OF THE F6FTEENTH WATER RE. ' ACTOR SAFETY INFORWATON WEETNG POWER STATION UNIT 1 Dram For Comment NUREG/CR4551 V4 DAF: EVALUATION OF SEVERE ACODENT I NUREG/CR-2331 VQ6 N2- SAFETY RESEARCH PROGRAMS SFON. SORED BY OFFICE OF NUCLEAR REGULATORY RtSKS AND THE POTENTIAL FOR RISK REDUCTON GRAND RESE ARCH Cberterly Progress Report ApnLJune 1966 GULF. UNIT 1 Dram For Comment . NUREG/CR-2331 V06 N3 SAFETY RESEARCH PROGRAWS SPON- NUREGICR 4896 CONTAINWENT LOADS DUE TO DRECT CONTAW- . SORED BY OFFICE OF NUCLEAR REGULATORY WENT HEATWG AND ASSOCtATED HYDROGEN BEMAYOR.A/*4ses ' RESE ARCH Qaartery Progrest Report JuPy-Sepienter 1986 And Calculabons With The CONTAIN Code NUREG/CR 2331 V06 N4 SAFETY RESEARCH PROGRAWS SPON-SORED BY OFFICE OF NUCLEAR REGULATORY WILUAWSJA RESEARCH Charisety Progress Report Octoter December 1986 NUREG/CR-4963 THE SEALING PERFORMANCE OF BENTONITE / L NUREG/CR 2331 V07 N1: SAFETY RESE ARCH PROGRAMS SPON- CRUSHED BASALT BOREHOLE PLUGS I SORED BY OF FICE OF NUCLEAR AEGULATORY RESEARCH Omer$y Progress Resort. Anuary March 1987. WTTTE.M C. t NUREG/CR-4s?9 V01. SHIPPtNG CONTAWER RESPONSE TO WENSE LR.G. SEVERE HGHWAY AND RAILW AY ACCOENT CONDTONS h [ NUREG/CR4621; REACTOR COOLANT PUMP SHAFT SEAL STAStu- R TV DURNJ STATON BLACs OUT. NUR CR 4629 V02 SHIPPING CONTAINE R RE SPONSE TO r SEVERE HIGHW AY AND RAILWAY ACCOENT WE STON.L M. CONDTIONS Appen&ces NUREG/CR4834 V01. RECOVERY ACTIONS IN PRA FOR THE RISK WETHOOS INTEGRATION AND EVALUATON PROGRAW WITTLE R.R. J. t (RW:EPhyolume 1 Devotopment Of The Deta-Based WethA1 NUREG/CR 4651. DEVf LOPWENT OF RIPRAP DEAN CRITERIA 9f l RIPRAP TESTWG IN FLUVES Ftee I  ! WETMILLE RM. NUREG/CR4753 V02 CANADAN SEISWiC AGREEMENT Annual MTZXLW.F. r Report NUREG/CR4726 EVALUATION OF PROTECTliE ACTON R;Se $

                                                                                                                                                                                                           ?

r

104 Personal Author Index WOLLEN8 ERG.H A. NUAEG/CR4530 V02 U $ iFRENCH JO;NT RESEARCH PAOGRAM NUREGICA-4161 V02 CAITCAL PARAVETERS FOR A HIGH4EVEL REG AADiNG THE DEHAVCA OF POOVER B ASE MATERIALS SUB-W ASTE REPOSITORf. Volume 2 Tug JECTED TD BETA RAuATCN Volume 2 Phase 2a screen.ng Tests NUREG/CA4161 V03 CRiTCAL PARAVETERS FOR A H GH4EVEL W ASTE REPOSITOAY. Volume 3 Sait YlHU A.X. gggq NUAEG/CA4684 INTERPRETATCN OF BCASSAY ME ASUREVENTS NVAEG/CA 4753 V02 CANAD4AN SEISMC AGREEVENT. Annual ygygg NUREG/CR 4550 V03 ANALi$is OF COAE DAMAGE FAEQUENCY WOOD.A.S. FROM INTERNAL E%ENTS SURRY UNIT 1. NURE G-0327 Rod OWNERS OF NUCLEAA POWER NVAEG/CR4826 OS SEISVtC M ARG N REVIEvv OF THE VAINE PLANTS Percentage Ow<wrsNp Of Commerce! Nuc4ar Fower Plants YANKEE ATOV t nER STATCN Volume 2 $rstems AnaWs YOUNO.J.K. WOODS.D.D. NUREG/CR4695 MATERsAL CONTROL AND ACCOUNT;NG (MCAA) NUREG/CR-4862 V01: COGN1TrVE ENViAONVENT S:MULATCN AN LOSS DETECTON OUR.NG TR ANSITCN PERODS AND PROCESS ARTIFCAL INTELLCENCE SYSTEM FOR >"JMAN PERFORMANCE UPSET CONDITIONS. ASSESSMENT Volume 1 Summa 7 And Chervea NUREG/CR-48*2 V02 COGNtTIVE ENylRONMENT S MULATON AN yoygqu p, ARTiFCAL IMELLCENCE SYSTEM FOR HUMAN PERFOAMANCE ASSES $ VENT Voivme 2 MooSeq Human intente Formulaton NUREG/CA490^ MELPADG PWR/MOOO A VECHAN STIC COOE FOR NUREG/CR464 VON COGNITIVL ENVIRONMENT S.VULATON AN ANALYSIS C+ HE ACTOA CORE VELT PROGRESSON AND VESSEL ARTIFCAL INTM UGENCE SYSTEM FOR HUM AN PERFORMANCE ATTACK UNDER SEVERE ACCCENT CCNDITONS ASSESSVENT.Vwne 3 CorutNe Rekatakty Anaws Tecw yoyyg,y,w, WR E ATHALL.J. NV A E G-1163 COOAD:NATCN OF S AF E TY RESEARCH FOR THE NURE G-1150 DAF V2 FC REACTOR R:SK REFERENCE BABCOCK AND W1LCOx INTEGRAL SYSTEM TEST PROGRAM DOCUMENT Appe%ces A-l Drsi For Cowent WRIGHT,A.E. NUAEG/CA-4752 CO NC DENT STE AM GENERATOA TUBE RUPTUAE NUREGrCR4407 PIPE BREAK FREQUENCY ESTIMATCN FOR NU- AND STUCKOPEN SAFETY RE L'E F VALVE CAARYOVE9 CLEAR POWER PLANTS TESTS VB 2 Steam Generator Trans+nt Response Test Propas d WU,P C-YU ANN R. NUREG-1194 CONSTRUCTCN APPRAISAL TEAM INSPECTON RE-SUt.TS ON WELDi4G AND NONDESTRUCTIVE EXAMJNATCN AC- NUAEG/CA 5010 AELAP5' MOD 2 ASSESSVENT US:NG SEU: SCALE T'VITIE S ExPER.MENTS S-NH-1 AND S.LH-2 WU.S. ZlEGLER,E.J. NUREG/CA-3950 V03 FUEL PERFOAV ANCE ANNUAL REPORT FOR NUREG/CA 4921 ENGiNEE A'N3 AND OJALITY ASSURANCE COST iM5 F ACTORS ASSOC 4 ATED wtTH NUCLE AR PLANT MODiF CATON WY A NT.F.J. ZUROFF,W.F. NUREG/CA 4301. STATUS REPOAT ON EOutPMENT OVALIFCATCN NUREG/CA-4437 PrPE BAE AK FREQUENCY EST;MATON FOR NU-ISSUES RESE ARCH AND RESOLUTCN CLEAR POWE A PLANTS I i

t i Subject Index This index was developed from keywords and word strings in titles and abstracts. During this development period, there will be some redundancy, which will be removed later when a rea-sonable thesaurus has been developed through experience. Suggestions for improvements are welcome. 1/14 teele NUREG/CR-4739 RAMONA-38 CALCULATIONS FOR BROWNS NUREG/CR4907; $;MULATED SEISMC TESTS ON 1/42. AND 1/14- FERRY ATWS STUDY. SCALE CATEGORY 1, AUUUARY BUtLDING. Abnormal Occurrence 1M488I8 NUREG4090 V09 NO2. REPORT TO CONGRESS ON ABNORMAL NUREG/CR4947. SIMULATED SELSMC TESTS ON 1/42 AND 1/14 OCCURRENCES ApnbJune 1966. SCALE CATEGORY i, AUXIUARY BUtLD NG. NUREG-0090 V09 NO3 REPORT TO CONGRESS ON ABNORMAL OCCURRENCES JuPrSeptember 1986 WR 64 N " AESS ON ABNORMAL NUREG-1254 EVALUATON PROCEDURE FOR SIMULATON FAClu- N Oct 9 FOR S:MULAtcN NUREG-0090 V10 N01. REPORT TO CONGRESS ON ABNORMAL N EG.25 F ALVA CCEDU T F ACIUTIES CERYlFIED UNDER 10 CFR SS Dram RW NU V 7R OCCURRENCES Aprd June 1947. RT CONGRESS ON ABNORMAL 10 CPR Porte to And 65 NUREG-1262 ANSWERS TO OVESTONS AT PUBUC MEETINGS RE- Abstract GARDING IMPLEMENTATION OF TITLE 10. CODE OF FEDERAL ' NUREG4304 V11 N04 REGULATOAY AND TECHNCAL REPORTS REGULATIONS.PART 55 0N OPERATORS' LCENSES_ ' (ABSTRACT INDEX JOURNAL). Annual ComNaton For 1966 1$4eele NUREG-0304 V12 N01' REGULATORY AND TECHNICAL REPORTS NUREG/CR-4913 ROUNDROBIN PRETEST ANALYSES OF A 16 (ABSTRACT INDEX JOURNALL Compdaton For Frst Ova 1er SCAtt REINFORCED CONCRETE CONTAINMENT MODEL SUBJECT 1987.Janua*y-Ma ch 1 TO STATC INTERNAL PRESSURIZATON NUREG 0304 V12 402 REGULATORf AND TECHNCAL REPORTS a NUREG/CR 4969 AxlSYUMETRC ANALYST $ OF t o SCALE REIN- (ABSTRACT INDEA JOURNAL) Cornpnaton For Second Quarter FORCED CONCRETE CONTAINMENT BUILDING USING A OtSTRIB- 1987.Aprd June UTED CRACKING MODEL FOR THE CONCRETE. NUREG 0304 V12 NO3 REGULATORY AND TECHNCAL REPORTS (ABSTRACT INDE X JOURNAL) Cornpuaton For Thre Ouater G/CR4218. EXPERIMENTAL RESULTS FOR A 14-$CALE STEEL j MODEL NUCLEAR POWER PLANT CONTA!NVENT PRES $UR:2ED Accident i TO F AILURE- NUREG-1250 REPORT ON THE ACCCENT AI THE CHERNOBYL NU-CLE AR POWTR ST ATON

            /CR 64 V01. UNfyERSITY OF MARYLAND AT COLLEGE RGM              EW ON NE ATOEM AT NE CMEMn PARK (UMCP) 2x4 LOOP TEST F ACIUTY, Annual Report For 1985          NURk 251             FC      CATcNS OF THE ACCCENT AT CHER.

NO8YL FOR SAFETY REGULATON C# COMMERCIAL NUCLE AR A106 94ee4 POW 1R PLANTS IN THE UNITED STATES Erth For Comment NUREGICA 4416 TRANSITON RANGE DROP TOWER J-R CURVE i NUREG/CR 4485 V02 THE tMPACT OF FUEL CLADOtNG F AILUHE ( TESTING OF At06 STEEL. EVENTS ON OCCUPATIONAL RADIATON EXPOSURES AT NUCLE-ACR0 Reporte AR POWER PLANTS Case Stay PWR Dunng An Outage NUREG-1125 Voe A COMPILATON OF REPORTS OF THE ADYiSORY NUREG /CA4689 THE RM AL-HYDR AULC AND CHAR ACTE R;STC OOMulTTEE ON REACTOR SAFEGUARDS,1996 MODELS FOR PACKED DEBR:SBEDS NURE G/CR-4963 BORON CARBCE STE AM RE ACTONS WITH A800 CESIUM HYDROxOE AND WITH CESIUM COCE AT 1270A IN AN k NUREG.1272 REPORT TO THE U S NUCLEAR REGULATORY COM- INCONEL 600 SYSTE M MISSON ON ANALYSi$ AND EVALUATCN OF OPE RATON AL NUREG/CR-4978 THE COOLDOWN ASPECTS OF THE Tul-2 ACCL DAT A .1964 DENT. NUREG/CR-532$ EXPER' MENTAL STUDIES OF THE E ARLY EFFECTS EG/CR4469 V03 OCCUPATCNAL DOSE REDUCTON AT NU- NT S ASSE S P CcEAR POWtR PLANTS Annotated Behogaphy Of Se*ected Reas- , m98 in R***1on Prot *C*on A/d ALARA Accident Anarysie ' NURE G/CR-4765 Ux5 CROSS SECTON PREPROCESSOR USE R S gpggg MANUAL NUREGICR4689 THERMAL-HYORAUUC AND CHARACTERISTC MODELS FOR PACmED DEBRIS BEDS Accident Aueument NUREG-1210 V01 PtLOT PROGRAM NRC SCvf RE RE ACTOR ACCL M Cees DENT tNCCENT RESPONSE TRAIN.NG MANJAL Overve And Sum-NUREG/CR4859 SEISMC FRAGIUTV TEST OF A 6-INCH DlAMETER PtPE SYSTEM ma9 01 Marr Por ts NUREGICA-4943 PREPARATON OF DEssGN SPECWICATONS AND NVREG 1210 VC2 PILOT PROGRAM NRC SEVERE RE ACTOR ACCL DESaGN REPORTS FOR PUVPS. VALVES,PtPtNG AND PtPWG SUP. DENT INCCENT RESPONSE TRAANG MANUAL Seve<e Reactor Ac-PORTS USED IN SAFETV RELATED PORTONS OF NUCLEAR cdont Overve* POWER PLANT.e, NUREG 1210 V03 PtLOT PROGRAM NRC SEVERE RE ACTOR ACCb DENT INCOENT RESPONSE TRAANO MANUAL Respcese Of b ATWB conses And State And Local O*c+s l NUREG/CR4165 SENTRE ACCIDENT SEQUENCE ANALYSd5 PRO- NUREG 1210 V04 P1 LOT PROGRAM NRC SEVERE RE ACTOR ACCb GRAM ANTCiPATED TRANSENT wiTHOUT SCR AM S'MULA. DEN 7 INCOENT RESPONSE TRAINNG MANUAL Putec Pree trve TIONS FOR BROWNS FERRY NUCLE AR PLANT UNIT 1 Actons Predeterfruned Cntena And irrt41 Actens 105  !

                   - -.             - . . _ _ _             --             -                                                       .      .-_ -- I

106 Subject Index NUREG 1210 VOS PILOT PROGRAM NRC SEVERE REACTOR ACCs. NUREG/CR4976 SILVER-INDIUM 4ADM1UM CCNTROL RW BEHAV-DENT 14C4 DENT RESDONSE TRAIN NG MANUALU S N4 ear Rep IOR AND AEROSOL FORMATION W SEVERF REACTOR ACCI-4 tory Commess.on Respyse DENTE Accident CondNa NUREGiCR-4%6 RAD!ATON DOSE ESTIMATES AND HAZARD EVAL UATONS FOR WHALED ALR00RNE RADONUCUDES Fnal Report NVREG/CR 4405 V01 REACTOR SAFETY RESEARCH SEM: ANNUAL NUREG/CR 5017. LIMESTONE CONCRE1E AEROSOL ERPER:WENTS REPORT January 4une iM6 NUREG/CR 4829 Vol SN'PPING CONT AWE R RESPONSE TO W STEAM A1R ATMOSPHERES NSPP Tests $21.52 Land $31. Data RecorJ Report SEVERE H6GHW AY AND RAILW AY ACCOENT CONDITIONS Mac Recort Aftershock Sequence NURE G/CR4629 V02 SKPPWG CONTAtNE R RESPONSE TO SEVERE H:GHWAY AND RAILWAY ACCOENT NUREG/CR-4851. SEiSMcTY 166649 IN THE SOUTHEASTERN CONDITONS AccenAes UNITED STATESine Ahershock Seosent.e CW The Charteston South Carcena Eanhouake Accident Scenario Aged Cells NUREG/CR 4003 THE POSS'B'UTY OF LOCAL DE TON A TONS DURWG DEGRADED 40RE ACCTENTS IN THE BELLEFONTE NU- NUREG/CR4096. SEISMCFRAGluTY V? CJ NEW AND ACCEb CLE AR POWER PLANT ERATED AGED CLASS 1E BATTERY CELLS. NUREG/CR4641. FRACTURE EVALUATION Os SURFACE CRACKS g ging EMBEDOED IN REACTOR VESSEL CLADOWG untradW Bend Scecamen Ressts NUREG 1144 R01 NUCLEAR PLANT AG NG RESEARCH (NPAR) PRO-gqgy ptgy NUREG/CR 4457. AG:NG OF CLASS 1E BATTER ES IN SAFETY SYS-UE 432 THE RELATONSHiP AND INFLUENCES CF FUEL VgS, N LE AR PO A E PLA S y g g NUCL. EAR STATION DtESEL AND COOLANT SYSTEM PROCESSES DUR NG LAR SEVERE ACCI-DENTS G EWORS baw 0 Operatng AN Erm Wenence % NUREG/CR4550 V03 ANALYSIS OF CORE DAMAGE FREQUENCY I SW FROM INTERNAL EVENTS SURRY UNti i NURE G/CA 4590 V02 AGWG OF NUCLEAR STATION DtE SFL NUREG/CR4550 VO4 ANALYS!S OF CORE DAMAGE FREQUENCY GENERATORS Evaivaton Of Operetng And Expert FROM INTERNAL EVENTS PE ACH BOTTOM UNIT 2 Egerence Worsshcc NUREG/CR-4550 VOS ANALYSIS OF CORE DAM AGE FREQUENCY NUREG/CR4715 AN AGWG AS-SESSMENT OF RELAYS AND CIR-FROM WTERNAL EVENTS SEOVOYAH.UNrT 1 CUlf BREAKERS AND SYSTEM INTERACTONS NUREG/CR-4550 VC4PT1 ANALYSIS OF CORE DAMAGE FREQUEN. NU AE G /CR -4731 V01 RESOUAL UFE ASSESSVENT OF MAJOR CY FROM tNTERNAL FVENTS GRAND GULF UN:T 1 Mac Accort UGHT WATER RE ACTOR COUPONENTS OVERV'EW Voisme 1. NUREG/CR-4550 Vo6PT2 AN ALYSis OF CORE DAMAGE FREQUEN- NUREG /CA 4 747 V01. AN AG1NG FAILURE SURVEY OF UGHT CY FROM INTERNAL EVFNTS GRAND GULF UNIT 1 Appen*** W ATER RE ACTOR SAFETY SYSTEUS AND COMPONENTS NUREG/CR4674 V03 PRECURSORS TO POTENTIAL SEVERE CORE NUREG/CR-47e9 RISK EVALUATONS OF AGWG PHENOVENA.The DAMAGE ACCOENT$ 1964 A STATUS REPORT Va!n Repor1 And Ap- Unes' A perdses A And B NUAEG/C;png RelaWy MOded And its Estems.ons R 4819 V01 AS'NG AND SERVICE WEAR OF SOLENOO-NUREG/CR4674 VD4 PRECURSORS TO POTENTIAL SEVEPE CORE OcER ATED VALVES USED IN SAFETY SYSTEUS OF NUCLEAR DAMAGF ACCOENTS 1984.A STATUS REPORT AppeMaes C D And POWER PtANTS Vedume 1 Operst.ng E ngerence A 4 FaNro k$enth N REG /CR4742 WELPROG-PWR/h4DD1 ANALYSTS OF A TULB' AC. COENT SEQUENCE Air Cleaneng NUREGrCR 4772 ACCOENT SEQUENCE EVALUATON PROGRAV HOM AN REUABluTY ANAL 4 5;5 PROCEDURE NUREGrCPOM6 V01 PROCEEDWGS OF THE 19TH DOE /NRC NU. CLE AR A1R CLE ANWG CONF E RE NCE Held M Accident-Generated Water Seame WasNnge Ap 18R1M6 NUREG-Of 83 502 PROGR A VM ATC E NWRONVE NT AL tVPACT NUREG'CPOO66 V02 PROCEEDWGS OF THE 197H DOE /NRC NU. STATEVENT RELATED TO DECONT AU,N ATON AND DISPOSAL OF C(FAR A1R CLE AN NG CONFERENCE Heu in RADCACTIVE A ASTES RESULTWG FROM M ARM 2819?9 ACCI. Seame Washngton.A+st is 21,1M6 DEN *' AT THREE M.LE tSLAND NUCLE AR STATON uvf 2 Feat 43, g ,,,,, Wment DeaW wtm 0%posat 04 NUREG 1?S V02 OPERATWO E APER-tNCE FEEDBACK REPORT - Accidental Release AR SYSTEMS PRO (3LD/S Commercal Fower Reactors NUREG/CR 4825 A PREL V NARY EVALUATON OF THE ECONOUC R:SK FOR CLE ANUP OF NUCLE AR M ATER AL UCE NSEE CONTAV, no ResonocWe NATON WCOENTS NUREG'CR4M6 RADtATON DOSE ESilMATES AND HAZARD EVAL-NURE G / CR-4956 IMPACT OF PROPOSED FWANCI AL ASSURAME UATONS FOR INHALED AIRBORNE RADIONUCDDES Fr.at Rm j REQUtREMENTS CW NUCLE AR M AT ERt At S UCENSEE S Airt>orne Release ) Acoustic EmisskorVFlaw Relat6onsNp NURE G / CR -4 7M CC#9USTON AEROSOLS FORVED DUA W3 NUREG/CR4E0 V03 N2 ACOUSTC E M SSON/ FLAW RELATON. BURN NG Cf RADtOACTNELY CONTAV NATED MATERIALS . EL SH ' P FOR INSERVICE MOr+TORNG C# NUCLE AR PRESSURE PER UENTAL RESULTS VESSELS Pwess Ref4 Acrs Seemre' 1M6 NUREG'C4 4779 NE W DATA FOR AEROSOLS GENER ATED By RE. NUREG/CR4Kh VO4 N1 ACOUSTC E V SSON 'F LA W R E LAT ON. LEASES OF PRESSURt2ED POWDERS AND SOLUTIONS IN STATIC SHIP FOR IN SERVCE MON TORNG OF NUCLE AR PHESSURE AtR VESSELS Prcytts Regort Octater 1M6. Math 1H7 Ampthest.on Factor Adapttve-FTe&cttve Controne NUREG CR SQ14 PARAVETRC STUDY OF PIPE WH:P ANALY$t$ NUREG'CR 5011 APPLICAT ON OF THE AOAPTrvt P%~DiCTNE CONTHOLLERS TO PLANT SAFET f SURbEiLANCE UT4UZ NG 04 A^*'7*'s And Evaluat>on Of Operational Data LINE PLANT ANALY2ER NVRE G 1272 RE POR f TO THE U S NtRLE AR REGULATOR Y COM. V SS'ON ON ANALYLS AND EVALUATION O' OPERATIOPA Adkondach Wouruama DATA 1M6 NUREG/CA3232 CiTA: LED STUD 4ES OF SELECTED WELL EaPOSED FRACTURf ZONES W THE ADiRONDACK MDUNT ANS DOVE AE W Aremals YORv NJRE G/CR 4M6 RADiATON DCSE E STIMATE S AND HA2ARD E V AL. BATONS FOR INH ALE D A,RBORNE RADONUCLOES Fnal Report NURE G /CR 47M COUSuSTON AE ROSOts FORME D DUR-NG Armal Report BURN NG C# R ADCACTN ELY CONT AU NATED M ATER4ALS ER. NURE SWS VOS COVALATON OF CONTRACT RESEAROM FOR PER.VENTAL RESULTS THE WATER ALS E*R A NCH. DNIS ON C# E NGWE E RWG NUREG'CR4779 NE W CATA FCA AEROSOLS GENE R ATE D Bf RE- SM E T Y Annw Ag1 F ce F Y I M6 LE ASES OF PRESSURilED POWDERS AND SOLUTONS W ST ATIC NURE G 19 45 VM U S NUCLE AR FE GULATORY CC4M.SSON 126 AR ANNUAL RE PORT

i Subject index 107 Anmelpeted Trenelent illmhout herem ANCE OF HiGH. LEVEL W ASTE PACKAGES (BASALT. TUFF AND NUREG/CR4165 SEVERE ACCIDENT SEOUENCE ANALYSJS PRO. SALT 1 2 GRAM ANTCIPATED TRANSENT W1THC4JT $ CRAM $lWVLA. NUREG/CR4657 SURVEY OF GEOPHYSICAL TECHNIOUES FOR # TIONS FOR SROWh3 FERRY NUCLEAR PLANT C**T 1, SJTE CHARACTER (IATON IN BASALT. SALT AND TUFF. ) 4 NVREG/CR4943 THE SEAUNG PERFORMANCE OF BENTOMTE/ 1 AMissielInteingenee CRUSHED SASALT BOREHOLE PLUGS MREGICR4062 V01: COGNITfVE ENYtRONMENT SMVLATON AN MtTFOtAL 1NTELUGENCE SYSTEM FOR HUMAN PERFORWANCE tenense ASSESSMENT Voeume i Summerr AM Ov*Y** NVREG/CR44th AOtNG OF CLASS 1E BATTERIES IN SAFETY SY3-  ! j NUREG/CR4462 V02. COGNITIVE ENytRONu(NT SMULATiON AN TEWS OF NVCLEAR POW 1R PLANTS r 4 ARTIFICIAL INTELUGENCE SYSTEM FOR HUMAN PERFORMANCE ' ASSESSWENT Vohene 2 Modeema Hur%n latenton Formulato Senery Cet l NUREG/CR4462 VC3 COGNilrW ENYtRONMENT S!MutAT"ION NUREQ/CR4M6 ANSEISMC-FRAGIUTY TESTS Or NEW AND ACCEL. f ] ARTFICAL INTELUGENCE SYSTEW FOR HUMAN PERFORMANCE ERATENGED CMSS 1E BATTERY CEdi  ; 1 ASSESSMENTNotume 3 Cogr:1rve RohetMy Anayses Techruque i sei .or und veum  ! i NUREG/CR SO41 VOI: RECOMVENDATONS TO THE NRC FC44 P CR COMPARCON OF THE 1942 SEADEX DSP(RSJON REytEW CRITERW FOR ALTERNATIVE WETHODS OF LOWtEYtt DATA WfiH RESULTS FROM A NUWBER DiFFERENT WOOEL RADIOACTIVE W ASTE DISPOSAL. Test 2a BelowGrwnd Vaults [ NVREG/CR4750 VOI: THE SHOREONE NYtRONMENTA1MOh ERO DISPERSON EXPERMENT (SEADEX)EW Descre l NVREG/CR4472 EXPER= MENTAL ANO ANALYTCAL ASSESSMENT g

 !    NURE'G/CR4950 V02- THE SHOREUNE ENVIRONMENT ATMOS.                   OF CIRCUMF ERENTALLY SVRFACECRACKED PlPES UNDER PHERC DISPERSON EXPER! MENT (SEADEX)Meteorologcet And                                                                          l BE NDING.

j Gas Tracer Date Auselery Duedang Sentenfte NUREG/CR4919 FIELD TESTtNG OF BENTONtTE AND CEMENT i*

NUREG/CR-496 P: SVVLATED SEtSVC TESTS ON 1/42. AND 1/14 SCALE CATEGORY t, AUXtuARY BUILDNG BOREHOLE PLUGS IN GRANITE.

I NUREG/CR4663 THE SEAUNG PERFORMANCC QF BENTONittf AskVane Blo**' CRUSHED BASALT BOREHOLE PLUGS NVREG/CR4931: RESPONSE OF CENTRIFUGAL AND AXLVANE NUREG/CR4NS: EXPER MENTAL ASSESSMENT OF THE SEAUNG I J

 !      BLOWtRS TO LARGE PRESSURE TRAN$ TENTS-                              PERFORVANCE OF BENTONTE BOREHOLE PLOGS                     [
                                     "         L MI/Nu[C NTONOWAUR                   MPORANC[y                     JR    CR 4530 V02 V $ / FRENCH DNT RESEARCH PROGRAM REGARONG THE BEHAVOR O' POLYVER BASE M ATER!ALS SUS-      l URES FOR BASC EVENTS AND PLANT SYSTEMS IN NVCLEAR                  JECTED TO BETA RADATON Volume P Phase fa Screenng Tests.

1 PCwER PLANTS j NUREG/CR4446 SHUTDOWN DECAY HE&T REMOVAL AN4YS15 OF WEmMng Reeenuchee f 1 A GENERAL ELECTRC BWR3/M ARK 1 Case Stadv NUREG/CR S025 EXPER! MENTAL STUDIES OF THE EARLY EFFECTS f NUREG/CR4551 V3 PT1: EYALUATON OF SEVERE ACCOENT RISKS ) AND THE POTENTAL FOR RtSK REDUCTON PEACH Of INHALED BETA EulTTtNG RADONUCLOES FOR NUCLEAR AC. 1 BOTTOM.UNT 2 Use ReportDram For Comment COENT RISK ASSESSMENT Phase il Rowt i NUREG/CR-4551 V3 PT2 tyALVATON OF SEVERE ACCIDENT RtSAS } 1 I I AND THE POTENTtAL FOR RtSK REDUCTION PEACH SteeprePhy I BOTTOM.UMT 2 Agoneces DreM For Comment NUREG/CR 3469 V03 OCCUPATONAL DOSE REDUCTON AT NU-NUREG/CR4551 V4 DRE EV ALVATION OF SEVERE ACCIDENT CLEAR POWER PONTS Annotood Betoyaphy Of 5ewted Reas- l i RISKS AND THE POTENTAL FOR RtSK REDUCTON GRAND mgs M Re$4 bon ProWton And 4 ARA [ GULF.VVT 1 Dram For Comment WREG/CR4610 EFFECTS OF LATERAL SEPARATON OF OxotC 3.eeeeey neeeurement AND METALLC CORE DEBR;S ON THE BWR VK t CONTAINVENT NUREG/CR4464 INTERPRETATION OF BOASSAY ME ASUREVENTS fr ! DRYWELL FLOOR [ NUREG/CH4689 THERM 4 HYDRAUUC AND CHARACTER:STIC M eubng l EG W ON M NSW & N f ' NU / 4 A T VENTING ANALYSS FOR TH6 E W ATER SYSW Waw 0 MW Mew w PEACH BOTTOM ATOUC POWER STATION Control Toom To S6w W Cmoson Fou4ng At Nac4ar } l NUREG/CR-4700 V4 DAF CONT AINVENT EVENT ANALYSTS FOR Power Plants. j I POSTULATED SEVERE ACCOENTS GRAND GULF NUCLEAR i j STATlON UMT 1. Dram For Comment 8'*** V 8 NUREGICR 4739 RAMONA 38 CALCULAtlONS FOR BROW %S NUREG/CR4697 OPERATINu ErPER4ENCE REVIEW OF F ArLURES FERRY ATWS STUDY OF POWER OPERATED RELtEF WALVES AND BLOCK VALVES IN NUREG/CR-4767. SHUTDOWN DECAY HEAT REMOVAL AN4YSS OF NUCLEAR POWIR PLANTS A GENERAL ELECTRC BWR4iMARK lCase StLoy i NUREG/CA-4860: FLAW DENSITY EKAMiNATONS OF A CLAD BOii. Soiling water Reector l ING W ATER REACTOR PRESSURE VESSEL SEGMENT. I NUREG-1291 BWR AND PWR OFF NORMAL EVENT DESCR PTONS NVREG/CR-3495 CALCULATON OF F A&URE #PORTANCE ME AS- t Sebcock And W5ces NUREG 1231 SAFETf EVALUATON REPORT RELATED TO THE BAB- URES FOR BASC EVENTS AND PLANT SYSTEVS IN NUCLE AR l COCK AND WLCON 0%hERS GROUP PLANT RE ASSESSMENT PowtR PLANTS I PROGRAW NUREG/CR4448 SHUTDOWN DECAY HE AT REMOV4 AN4YS45 OF L NUREG/CR4713 SHUTDOWN DECAY HEAT REMOVAL A44YSS OF A GENERAL ELECTRC BWR3 WARK tCase StacN NUREG/CR 4551 V3 Pit EVALUATON OF SEVERE ACCOENT Rtsa$  ! A BABCOCK AND WILCOK PRESSUR12ED WATER REACTOR Case N /CR4966 V01 EVALUATON OF OPERATIONAL SAFETY AT TTOM T A r NUREG/CR4551 V3 Pit EVAtuATiON OF SEdRE ACCOENT RLSaiS N G 4 b AL AT OF C BABCOCK AND W1LCOs P(ANTSvoune 2 ThermeLHy$ewhc Re, ETV AT AND THE POTENTIAL FOR RISK REDUCTON PE ACH BOTTOM.UMT # Appeneces Dram For Comtrent

• NUREG/CR4551 V4 DRF Ev4UATON OF SEVE RE ACCOE NT RISn$ AND THE POTE NTAL FOR RlSK REDUCTION GRAND gegene,.oe pgne GULF.UNT 1 Dram Fce Comment NUREG/CA4783 AN4YS S OF BALANCEOF PLANT REGULATORY NUREG/GR4410 EFFECTS OF LATERAL SEPARATON OF OXOC BSSUE S Final Rwort AND WETALLC CORE DEBRIS CN THE BAR W l CONT AINVENT >

I DRrWELL FLOOR Deeeft NvREG/CR4 t >4 ROI REPO$aTORY E NVIRONME NT AL PARAW- NUREG/CR 4689 THERMAL HYDRALAC AND CMARACT E R:STIC MODELS FOR PACS.ED DE BRIS BLDS ETERS AND WODELS RELEV ANT TO ASSES $N3 THE PERFC'RM-i

                                                                                                                                      )

i

i r I 4 100 Subject index t NUREG/CR4696 CONTAWVENT VENTWG ANALY$l$ FOR THE Carm Steed PEACH BOTTOW ATOUC POWER STAtlCW , i NUREG/CR4700 V4 DRF; CVNTAWVENT EVENT ANALY$ $ FOR NUREG/CR 3641: $7RE$$.CDRRO$ON CRACKING OF LOW. i j POSTULATED SEVERE ACCCENTS. GRANO GVLF NUCLEAR STRENGTH CARBON STEELS IN CANDOATE HIGM-LEVEL WASTE i

;          $T ATION UNIT 10ra't ror Commet                                   REPOSTORY ENVIRONVENTS                                                                                            !

i NURE G/CR-4739 RAMONA-38 CALCULATIONS FOR BROWNS NUREG/CR4472: E APER # ENTAL AND ANALYTICAL AS$ES$WENT  ; FERRY ATWS $TUOY OF ggggg CIRCUVFERENTIALLY $URFACECRACKED PIPES UNDER  ! i t NUREG/CR-4767: $dVTOOWN DECAY HEAT REMOVAL ANALY$JS OF NUREC/CR-$007; PREDICTCN AND MrTIGATION OF ERO$lVE COR. [ NVR 4 F W NS E AT C5 A CLAD BOfL. ROSNE WEAR W SMOARY PWNG SYSTEWS OF NVCLEAR LNG WATER RE ACTOR PRES $URE YES$EL SEGVENT. POWER PLANTS.  !' j go,, pen pewg t Cast Steinisee Steed t ( NUREG/CR4919 FrELO TE$ttNG Or t[NTONtTE AND CEMENT NUREGICR4744 V01 N1' LONG-TERM EptR:TTLEWENT OF CAST BOREHOLE PLUG $ 1N GRAN:TE.  ! -i NUAEG/CR4943 THE SEALWG PERFORMANCE OF BENTON:TE/ DUPLEE STAWLES$ STEEL $ LN tWM SYSTEu$ $emwwwel Report,0ctoter 1965. March 1944 'I 1 CRU$HED BAULT f4REHOLE PttGS j NUREG/CR-4744 V01 Nt LONG. TERM EW6RITTLEWENT OF CAST NUREG/CR4995. EXPER# ENTAL ASSES $ VENT OF THE $[AllNG i PERFORMANCE OF BENTONITE BOREHOLE PLUGS- OUPLEX STAWLESS STEELS IN LWR SYSTEu$.Sermennwel  ; Report.Apre-$eptemte 1966. 3 NUREG/CR4744 V02 N1: LONG TERM EMSRITTLEWENT OF CAST L NUREG 4953 BORON CAR 8CE . STEAM REACTIONS WITH 8 R . Marc - CESUV HYDROx!OE AND WITH CESIUM OOCE AT 1270K IN AN '  ! tNCONEL 600 SYSTEM. l Coment  ! 3 gg gg,, NURIGsCR4919 FIELD TESTWG OF BENTONITE ANO CEWFT , NUREG/CR4793 RESULTS OF SEM $CALE MOCL2C SMALL BREAK BOREHOLE PLUG $ IN GRANITE. , COOLANT ACCOENT MTHOUT hP1 ($-NH) EXPER#ENT $ CWMhw

• j tvekung NUREGICR4831 RESPONSE OF CENTR *UGAL AND AXLVANE >

BLOWER $ TO LARGE PRES $URE TRAN5;ENTS. l NUREGICR4892 A STUDY OF THE EFFECTS OF PENETRATCN FRAM<NG ON STEEL CONTAWutNT BUCnWG CAPAcTV Centrtfuge#y Coot NUREG/CR-4904 INVESTGATsON OF STEEL CONTAINMENT SUCK. NUREGICR 4970 STAWLE$$ $ TEEL ROUNO RO9W i } LING FROM DYNAMC LOADS TEST.Centnfugany Cast Stewess Steel $crosng Phase.  ! Dveget Certmcate Of Comonence I j NN $ ELNNENMA5N'aS 'YeIMs1989 NVREG4343 V01 R10 DRECTORY OF CERT # CATES OF COWPU. [ ANCE FOR RADCACTfvE tt4TERIALS PACKAGES $wmmary Report i Durted Weste Of NRC Approved Packens j l NUREG/CR4918 V01: CONTROL OF W ATER INFILTRATCN 6NTO NUREG0383 V02 RIO: DRECTORY OF CERTWICATES OF COMPLL  ; NE AR $URFACE LLW DISPOSAL UN:TS Anrust Report,0ctober 1965 ANCE FOR RADCACTIVE MATERIALS PACKAGES Cer%cetoe Of

          . Sepumter 1986                                                  Corrcmance                                                                                                          r i

j DurWng NUREG4343 YO3 R07. DRECTORY OF CERTFICATES OF COMPLk [ ANCE 80R RADeOACTIVE MATERIAL $ PACKAGES Summary Report i NUREG/CR4679 OUANTITAtiVE DATA ON THE F6RE BEHAvlOR OF Of NRC Approved Ouawy Aesurance Program 6 For Reeoecove Wesen- > COUBU$ttBLE MATER:ALS FOUND IN N@ LEAR POAER alPeckages PLANTS A Lnerature Revee NUREG/CR 4 736 COMBU$ TON AE ROSOLS FORMED DURWG Chem 6 cal Ptenemone BURN:NG OF RADOACTtvELY CONTAMWATED MATERIAt$ . Ex- { i PER MENT AL RE50.TS NUREG/CP 0078 PROCEEDNGS OF TNE SWPOS8UM ON CHEWi. ' NUREG/CR-49st A SAFETY A$$ES$ VENT OF THE USE OF GRAPH- CAL PHENOVENA AS$0CtATED W1TH RADOACTIVITY RELEASES r 5' ITE IN NUCLEAR MACTOR$ LCENSED BY THE U $ NEC. DURWG SEVERE NUCLEAR PLANT ACCOENTS I 4 I N EG $0 SAFETV EVALUATCN REPORT RELATED TO THE G 1250 REPORT ON THE ACCIDENT AT THE CHERNOGYL NU-1 FWAL DESGN OF THE STANDARD NUCLEAR $ TEAM $UPPLY CLEAR POWEP STATON 2 REFERENCE $YSTEM CESSAR Setem 63 Docket No $0470(Com- NUREG-1250 RCc REPORT ON THE ACCCENT AT THE CHERNOGYL J N'# IN O'" NUCLEAR POWER $TATCN NUREG 1251 DAFT FC LMPLCATONS OF THE ACCOENT AT CHER-CFITsu NO6YL FOh fMFETY REGULATION OF COWWERCIAL NUCLEAR NUREG/CR4737. INTE RPRET ATIVE ANALY$l$ OF DATA FOR PGAER PLANI $ IN THE UNITED $T ATES Dre't For Comment SOLUTE TRANSPORT IN THE UNSATURATED ZONE i 4 CoelTAl*6 j NUREG/CR-4647. POSTCON A POSTPROCESSOR ANO UNfT CCW-NUFtEG/CR-3956 IN SITU TESTING OF THE $HIPPWGPORT ATOWIC POWER STATON ELECTRCAL CIRCylTS )

• VER$cN PROGRAM FOR THE CONT AW CQUAUTER CGE NUREGrCR-4896 CONTAWWENT LOAO$ DUC TO DRECT CONTAW- C6rewrt Breeter l UENT HEATWG AND ASSOCLATED HYDROGEN MMAVCR Ana'ysrs NUREG/CR4715 AN AGWG ASSE$$WENT OF RELAYS AND CIR-i And Cm4atens we TM CONT AW Coo
• 4 Cutt BREAAER$ AND Sv$ TEM INTERACTONS

;   CeWaet Fire Test Cleoeng NUREG/CR4527 V01 AN EXPERWENT AL INVE?TGATON OF IN.

TERNALLY GNT8ED FIRES IN NUCLE AR POWER PLANT CONTROL NUREG/CR 4641 FRACTURE EVALUATON OF SURTACE CR?CKS j CAB %ET$ Part 1 Catunet EPects Tes4 EMBE000,0 W RUCTOR VESSEL CuDOWG Wwd SW i Canneer $e.amec Agreement i NUREGrCA.4753 YO2 CANADAN SEISUC AGREEUENT Aw Cloes 1E p% NUREG'CR4094 SEISMC FRAGILITY TE$T$ OF NEW AND ACCEL-

  '                                                                       ERATED- AGED CLA$$ IE BATTERY CELLS Cepecety NUREG/CR4457. AG:% OF CLAS$ 1E BATTERIES IN $AFETY $Y$.

NUREGICR4870 AN EV ALUAflON OF TME EFFECTS OF DE$GN TEUS OF NUCLE AR POWER PLANTS DE TAILS ON THE CAPACITY OF LAM $ TEEL CONT AWVENT NUREGICR 4747 V01 AN AGWG F Alt,URE $URVEY OF UGHT

         $U6LDNGS                                                         W ATER N ACTOR SAFETV $YSTEMS AND COV.mNENTS i

j u I

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

Subject Index 109 Cleanup Cost NUR E GIC.44 731 vol. RE S'DU AL UFs~ ASSESSMENT OF MAJOR NUREGICR4425 A PREUV. NARY EV ALUATON OF THE ECONNC LGHT W ATER RE ACTOR COMPONENTS OYERV EW Volume 1 NUREG/CR 4900 V01 COVPC6ENT F RAG!UT Y RE SE A RCH R:SK FOR CLEANUP OF NUCLEAR VATEntAL UCENSEE CONTAVa PRC41AM Puse i Demonst abon Tests Spireary Report NATON LNCIDENTS NUHE G /CR4900 V02 COVPONENT F R AGIUTY RESEARCH Cemetono9Y PROGR AM Phase i Deestaston tests Ame%ces PJUREG/CR4801. CUVATOLOGY OF EXTREME WWDS tN SOUTH- NUREGcCR 474 $16?EV PERFORMANCE OF HiGH LENEL W ASTE ERN CALIFORNtA PACAAGE C0 VPONENTS Clooeout Component Freg*ty NUREG/CR4524 CLOSEOUT OF IE BULLETIN 80-24 PREVENTON NUREGICA 499* COMPC%ENT F RAGtLITY RESEAACN OF DAMAGE DUE TO W ATER LE An. AGE INS DE CONT A;NVE NT PROGRAM Pt au l Comconent Prorwabon NU(OCTOBER 17.160 lNDtAN PcxNT 2 EiENT) REG /CR46% CompuutW MW CLOSEOUT OF IE BULLETIN 8341 F ALLUR OR TR REAAERS MESTINGHOUSE 08 50) TO OPEN ON NUREG/CR4855 DEVELOPVENT AND APPUCATON OF A COVPUT. ER MODEL FOA LARGE-SCALE FLAME ACCE.ERATON ER.PE RI. NUREGICR4664' CtOSEOUT OF lE OVLLEttN 8344 F A! LURE OF M IS THE UNDERv0(TAGE TRP FUNCTION OF REACTOR TR4P BRE AK. ERS Computer NUREG/CR+M2 UETHOCS FOR THE ELCTATON AND USE OF Coal Fuel Cycle EXPERT OP'NON IN R:5K ASSESSMENT Phase I . A Crmc41 Evava-NURF.G4332: POTENTIAL HEALTH AND ENv;RONVENTAL IVPACTS ton And Drestoes For Future Research. ATMUTABLE TO THE NUCLE AR AND COAL FUEL CYCLES Final Concrete NURE GICA-3024 SUST A!NE D CONCRETE ATTACK BY LOW-Code Asussment TEVPERATUREJRAGMENTED CORE DEBR:S NUPEG-1270 YO1 INTERNATIONAL CODE ASSESSVENT AND APPU. NUALG/CR4610 EFFECTS OF LATERAL SEPARATION OF OzcC CATIONS PROGRAM Anwi ReFort. AND METALUC CO9E DE3RIS ON THE B AR V( l CONTAtNVENT NUREG-1271: GUOEUNES ANO PROCEDURES FOA THE INTERNA OR 'WELL FLCOR TIONAL CODE ASSESSVENT AND APPUCATIONS PROGRAM NUREG/CR 4913 ACr.lNSPOB:N PRETEST ANALYSES OF A 16-Cogtme Enytronment $6mulation SCALE REINFORCED CONCRETE CCNTA:NVENT WODEL SUBJECT TO ST AT C INTERNAL PRES $UR!2AT,DN NUHEGICR4862 vol. COGNITIVE ENWONVENT S VULATON AN ARTIFCAL INTELUGENCE SYSTEM FOR HUVAN PERFOrV ANCE NUREG/CR 4M9 sx51VVETRC ANALYS!S OF 16-SCALE REIN. ASSES $ VENT Volume 1 Sammary And Overv** FORCED CONCRET E CONTAlNVENT BUILDING US,NG A D:STR'8-NUREG/CR4862 V02 COGN)TIVE ENv6RONVENT S MULATON AN UTED CRACKING MODEL FCA THE CO4 CRETE ARTFCAL INTELUGENCE $% TEM FOR HUMAN (ERFCAV ANM NURE G/CR 'M7 UMESTONE CONCRETE AE AOSOL E3PER'UENTS ASSE:NNT Volume 2 M30ehrig Human Intention Formuta% IN STE AM AIR ATMOSPHERES N$PP Tests $21.522.Ard $31, Data NUREG/CR4862 YO3 COGNiffu ENVIRONVENT SiUULAT"C*d g p ,g AN ARTIFCAL INTELUGENCE SYSTEM FCM HUVAN PERFCAM ANCE ASSESSMENT Voivme 3 Cogevtwo RehabMy A.naWe Techn4e Construct 4n Appraisal Team NUREG 1194 CONSTRUCTION APPRA: SAL TE AM INSPECTON RE-CWnRehm NVmEG/CR4862 V03 COGNlTIVE ENytRONVENT S MUL ATON AN SULTS ON WELD NG AND NONDESTRUCTIVE E AAV NATON AC-WMS ARTLFCAL INTELUGENCE SYSTEM FOR HUMAN PERFORMANCE ASSESSMENT Volume 3 Cogavtive Rekatory Anaws Techen,e CpwMM NVAEG/CR-4955 LONG-TERM PERFOAVANCE OF CONT AINER M A-ggy (,9, TERIALS FOR H GH4EVEL f ASTE NUREG/LA4004 THE RM AL MaiNG TESTS IN A SE Ui ANNULAR DOWNCOMER WITH INTERACTING FLOWS FROM COLD LEGS g NUREG/CR4216 EWER VENTAL RESULTS FOR A 16-SCALE STEEL Cc6uson MODEL NUCLEAR FOWER PLANT CONTAINVENT PRES $URi2ED NUREG/CR-5003 DES GN OF A M ATERiAL CONTROL AND AC. TO F AILURE COUNTING SYSTEM TO PROTECT AGAiNST CONCE ALVENT OF NUA E G/CR 4524 CLOSEOUT OF IE BUtLETIN 6}24 PREVENTON DrvERSON BY F ALS1FICATON AND COLLUSON OF DAM AGE DUE TO W ATER LE AFAGE INSOE CONT AfNVENT (OCToef R 17.,90 INDtAN PO.NT 2 eve NT) Combustitdo Gas Control NUREG/CR4330 V03 REVIEW OF UGHT W ATER REACTOR REGU- NUREG/CR4870 AN EV ALU ATON OF THE E FFECTS OF DESGN LATORY REQUIRE AENTS Assess /nent Of Sewed Req >atyy Re- DET AILS ON THE CAPACITY OF LAR STEEL CONT AINVE NT osoments that May Have Magnal importance To R sA Posta:ccent BUILOiNGS Samphng Systeen. Turt,r,e u.ssaes Combustoe Gas ContraiCharcoal NURE G/CR4e 32 A STUDY OF THE EFFECT$ OF PE NETR ATON FR AM N3 ON STEEt CONTAiNuE NT BUC* LING CAPACITY. Ffters NUREG/CRaiO4 INVEST 6GATON OF STEEL CONTA!NVENT BUCK. Combustible Material UNG FRoy D3gayc (OADS NUREG/CR4679 OVAPTIT AffVE DATA ON THE FIRE BEHAVOR OF NURE G 'CR 4313 ROUND-ROB.N PAETEST ANALYSES OF A 16-COMBUSTIBLE MATERIALS FOUND IN NUCLE A A POWER SCALE REINFORCED CONCRETE CONT AINVENT UDOEL SUBJECT PLANTS A Laerature Rev'e* TO ST ATC INTERNAL PRESSUR12ATION NUREG/CR4926 AN ASSES $UENT OF LOSSOFCONTA!NVENT pow L 8EC USE OF *NUCKLE BUC nUNG FOR - 1 STEEL COh G CR $464 HYDROGEN AIR STE AM F LAUV AB:UTY UV TS A E H DS NW GiCR 4M9 arf'1MMETRC ANALY sis OF 16-SCALE REIN-NU E G A D U FLAME TE FCACED CO*A' RETE CCNT AiNMENT BUILDING U$h3 A D6TRtB NUREG/CR 4 7% COM8UST ON AEROSOLS FORVED DUA NG UTED CR AC*!NG MODE L FOR THE CJNCRETE BURN #3 OF RADCACTivtLY CONT AM NATED MATER'.ALS E x. PER: MENTAL RESULTS Cesnment Ennt Anatyeis NWEG'CR 47tYJ v1 DAF CONT A'NVENT EVENT AN ALYS;S FOR Compaction POSTULATED SEVERE ACCtDENTS SURRY POWER ST ATON UNIT NUREG/CR 4767 CONFERENCE OF R AD A T ON CCHTROL PRO 10'an For Comment GRAM DIRECTORS' tNrORMATON FOR UCENS NG LOW LEvf L NURE G 'CR4 700 Y2 DAF CONT A.NMENT ENENT ANALYN$ FOR RAOCACTfVE W ASTE INONERATORS AND COMP ACTOpS ACDDE NT S SE QUC f AH POWER POSTULAT E D SEVE RE ST ATON LNT 1 Dra*t Repvt Fce Comment Component NVAEG/CR 47D0 V4 DM CONT ArNUE NT E VE NT AN A(T S;S FOR NUREG/CR1226 V05 STRUCTURAL INTE GNTY OF W ATE R RE AC- POSTMATE D SE VE RE ACCDE NT S GAAND gut F VXLEAR TOR PRESSURE BCUNDAR Y CC# PONE NTS Arvu R yrt F cr ST AT ON UNT 1 Dra9 Fcv Comment 1986

110 Subject Index Containment Failure NUREG/CA-4550 V06PT2: ANALYSIS OF CORE DAMAGE FREQUEN-NUREG/CR-4552: A REVEW OF THE SEABROOK STATION PROBABI- CY SROM INTERNAL EVENTS 9 RAND GULF, UNIT 1.Appendees. LISTIC SAFETY ASSESTAENT.Cowt FaAse Modes And Rad. obgical Source Terrr.a NUREG/CR4674 V03: PRECURSORS TO POTENTIAL SEVERE CORE DAMAGE ACCIDENTS.1984 A STATUS REPORT. Main Report And Ap-Containment integrttY pendues A And B NUREG 1264: CONTAINMENT INTEGRITY RESEARCH DROGRAM NUREG/CR-4674 V04: PRECURSORS TO POTENTIAL SEVERE CORE PLAN DAMAGE ACCIDENTS:1984.A STATUS REPORT.Appendres C,0 And NUREG/CR-3412 V02: E CONTAINMENT LNTEGR(TY PROGRAM. Progress Report.Apni 1983 December 1964. yy[EG/CR-4741: FEEDWATER TRANSIENT AND SMALL BREAK LOSS OF COOLANT ACCOENT ANALYSES FOR THE BELLFFONTE Containment Load NUCLEAR PLANT. NUREG/CR4' s96: CONTAINMENT LOADS DOE TO DIRECT CONTAIN. NUREG/CR4834 V01: RECOVERY ACTONS IN PRA FOR THE RISK MENT HEATING AND ASSOCIATED HYDROGEN BEHAVIOR. Analysts METHODS INTEGRATION AND EVALUATON . PROGRAM And Calculations With The CONTAIN Code. WEP) Volume 1.Devebiment Of The Data-Based Method. Containment Penetration NUREG/CR-4891: PROPERTIES OF REACTOR FUEL ROD MATERIALS AT HIGH TEMPERATURESFinal Summary Report - Severe Core NUREG/CR-4944: CONTAINMENT PENETRATON ELASTOMER SEAL Damage Property Tests Program. LEAK RATE TESTS. NUREG/CR-5042: EVALUATON OF EXTERNAL HAZARDS TO NUCLE-Ce*ttainment Penetration System AR POWER PLANTS IN THE UNITED STA TES. NUREG/CR-4734: SEISMC TESTING OF TYPCAL CONTAINMENT Core Debria PIPING PENETRATON SYSTEMS. NUREG/CR-3024: SUSTAINED CONCRETE ATTACK BY LOW. Containment Performance Design Otdoctfve TEMPERATURE. FRAGMENTED CORE DEBRIS. NUREG/CP0084. PROCEEDINGS OF THE WORKSHOP ON A CON- NUREG/CR4610 EFFECTS OF LATERAL SEPARATON OF OXIOC TAINMENT PERFORMANCE DESIGN OBJECTNE.MAY 12- AND METALLC CORE DEBRIS ON THE BWR MK 1 CONTAINMENT 13.1966. HARPERS FERRY, WEST VIRGINIA- DAYWELL FLOOR. NUREG/CR-4871: RESULTS FROM THE DCH 1 EXPER: MENT. g gg NUREG/CR-5028. ON THE MELTING AND REFREEZlNG OF POROUS NUREG-0800 06.5 2 R2: STANDARD REVIEW PLAN FOR ThE REVIEW OF SAFETY ANALYSIS REPORTS FOR NUCLEAR POWER Core MMt PLANTS LWR Estion. Proposed Revson 2 To Section 6.5.2, "Contair-ment Spray As A Frasion Product Cleanup System." For CommenL NUREG-1250: REPORT ON THE ACCOENT AT THE CHERNOBYL NU-CLEAR POWER STA?ON. Containment Venting NUREG 1250 R01: REPORT ON THE ACCIDENT AT THE CHERNOBYL NUREG/CR-4696: CONTAINMENT VENTING ANALYSIS FOR THE NUCLEAR POWER STATION. PEACH BOTTOM ATOMIC POWER STATION. NUREG/CR-3495: CALCULATON OF FAILURE IMPORTANCE MEAS-Contamination URES FOR BASC EVENT 3 AND PLANT SYSTEMS IN NUCLEAR POWER PLANTS. NUREG 1243. GROUN0' WATER PROTECTON ACTIVITIES OF THE NUREG/CR-4552 A REVIEW OF THE SEABROOK STATION PROBABI-U.S. NUCLEAR REGULATORY COMMISSON LISTC SAFETY ASSESSMENT.Contanment Fadure Modes And Red-ological Source Terms. C(Ataminetton Incident NUREG/CR4825: A PREUMINARY EVALUATON OF THE ECONOMC NUREG/CR-4909: MELPROG-PWR/ MODO.A MECMANISTC CODE FOR RISK FOR CLEANUP OF NUCLEAR MATERIAL LICENSEE CONTAMi- ANALYSIS OF REACTOR CORE MELT PROGRESSON AND VESSEL NATION INCIDENTS. ATTACK UNDER SEVERE ACCIDENT CONDfilONS. Control Rod Behertor Core Mettdown NUREG/CR4876: SILVER iNDIUMCADMfUM CONTROL ROD BEHAV* NUREG-1150 DRF V1 FC- REACTOR RISK REFERENCE DOCUMENT Mac heportDraft For CommenL LOR AND AEROSOL FORMATION IN SEVERE REACTOR ACCl-DENTS. NUREG-1150 DAF V2 FC: REACTOR RISK REFERENCE DOCUMEN' 'Opendices A-1 Draft For Comment Control Room NUREC 1150 DRF V3 FC: REACTOR RISK REFERENCE NUREG/CR-5037: FIRE ENVIRONMENT DETERMINATON IN THE LA. DOCUMENT.Appendces J-O Draft For CommenL SALLE NUCLEAR POWER PLANT CONTROL ROOM NUREG/CR-4742. MELPROG-PWR/ MOD 1 ANALYSIS OF A TMLB' AC-CIDENT SEQUENCE. Control System NUREG/CR-4758: A RETRAN MODEL OF THE CALVERT CLIFFS-1 Oore-concrete interaction PRESSURIZED WATER REACTOR FOR ASSESSING Ti:E SAFETY NUREG/CR 3024. SUSTAINED CONCRETE ATTACK BY LOW-IMPLICATIONS OF CONTROL SYSTEMS. WNPERATURE.FRAGMENTFD CORE DEBRIS. Coosent inventory MorWtor System Corporate Nuclear Performance Plan NUREG/CR 5059: VOID FRACDON MEASUREMENT LIQUlO LEVEL NUREG-1232 V01: SAFETY EVALUATON REPORT ON TENNESSEE DETECTON CONCEPT ASSESSMENT AND DEVELOPMENT, VALLEY AUTHORITY, Revised Corporate Nuclear P:,riormance Plan. Cooient System Process Correlation Services NUREG/CR4320 THE RELATONSHIP AND INFLUENCES OF FUEL AND COOLANT SYSTEM PROCESSES DUR!NG LWR SEVERE ACCI-NUREG/CR4814: SOURCES OF CORRELATON BETWEEN EXPERTS Empincal Resutts From Two Extremes. DENTS. Cooldow" Corrosion NUREG/CR 4978: THE COOLDOWN ASPECTS OF THE TM12 ACCl- NUREG/CR4626 V02: IMPROVING THE RELIABILITY OF OPEN-DENT. CYCLE WATER SYSTEMS. App 6cabon Of Befouling Surveistance And Control Technques To Sediment And Corrosson Fouhng Al Nuclear Power Plants. RE 4550 V01: ANALYSIS OF CORE DAMAGE FREQUENCY NUREG/CR4863: SURFACE SPECTROSCOPY OF PRESSURE FROM INTERNAL EVENTS: METHODOLOGY GU DELINES VESSEL STEEL FATIGUE FRACTURE SURFACE FILMS FORMED IN NUREG/CR4550 V03: ANALYSIS OF CORE DAMAGE FREQUENCY PWR ENVIRONMENTS. FROM INTERNAL EVENTS.SURRY UNIT 1. NUREG/CR4955. LONG TERM PERFORMANCE OF CONTAINER MA-NUREG/CR-4550 V04: ANALYSIS OF CORE DAMAGE FREQUENCY TERIALS FOR HIGH LEVEL WASTE. FROM INTERNAL EVENTS PEACH BOTTOM UNIT 2. NUREG/CR 4550 V05: ANALYSIS OF CORE DAMAGE FREQUENCY Cost ' FROM INTERNAL EVENTS: SEOVOYAH. UNIT 1, NUREG/CR4815. DEMONSTRATON TESTING OF A SURVEILLANCE NUREG/CR4550 V06PTI: ANALYSIS OF CORE DAMAGE FREQUEN. ROBOT AT BROWNS FERRY NUCLEAR PLANT.Analysrs Of Costs CY FROM INTERNAL EVENTS. GRAND GULF, UNIT 1.Mac Report And Benefits.

Subject index 111 Coot Analyste NUREG/CR4710 SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF NUREG/CR-5038: COST ANALYSIS FOR IMPLEMENTATION OF PRO. A COMBUSTON ENGINEERING PRESSURIZED WATER POSED CH/ NGES IN VITAL AREA REQUIREMENTS. REACTOR Case Study. NUREG/CR4713: SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF Coot Factore A BABCOCK AND WILCOX PRESSURIZED WATER REACTOR. Case NUREG/CR-4921: ENGINEERING AND OVAUTY ASSURANCE COST Study. FACTORS ASSOGATED WITH NUCLEAR PLANT MODIFICATION. NUREG/CR-4762; SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF A WESTINGHOUSE 3-LOOP PRESSURt2ED WATER REACTOR. Case Crack Gath Study NUREd/CR-4667 V03: ENVIRONMENTALLY ASSISTED CRACKING IN NUREG'/CR 4767: SHUTDOWN DECAY Pi AT REMOVAL ANALYSIS OF UGHT WATER REACTORS. Semiannual Report. April-September 1986- A uENERAL ELECTRO BWR4/ MARK i. Case Study. Crack M D NUREG/CR-4930 CRAC& ARREST BEHAVIOR IN SEN WIDE PLATES OF QUENCHED AND TEMPERED A 533 GRADE B STEEL TESTED h ' S01: DRAFT SUPPLEMENT TO THE FINAL ENVIRON-MENTAL STATEMENT RELATED TO THE DE00MMISSIONING OF UNDER NONISOTHERMAL CONDITIONS. THE RARE EARTHS FACluTY, WEST CHtCAGO,fLUNOIS Docket No. < 40 20614 Ken McGee) Crmed P1pe NUREG-1166: FINAL ENVIRONMENTAL STATEMENT FOR DECOM-NUREG/CR-4082 V05: DEGRADED PIPlNG PROGRAM - PHASE MISSONING HUMBOLDT BAY POWER PLANT, UNIT 3. Docket No. Itsemnnual Report. Aori-September 1966. 50-133 (Pac #fic Gas An1 Electne Company) NUREG/CR-4853: APPRoxlMATE METHOOS FOR FRACTURE ANALY. SES OF THROUGH-WALL CRACKED PIPES. Decontamination NUREG/CR4872: EXPERIMENTAL AND ANALYTICAL ASSESSMENT OF CIRCUMFERENTIALLY SURFACE. CRACKED PtPES UNDER NUREG-0683 SO2- PROGRAMMATIC ENVIRONMENTAL IMPACT STATEMENT RELATED TO DECONTAMINATION AND DISPOSAL OF BENDING. RADOACTIVE WASTES RESULTING FROM MARCH 28.1979 ACCI-Cr1tical Safety Function DENT AT THREE MILE ISLAND NUCLEAR STATON. UNIT 2. Final NUREG/CR-4797: PROGRESS REVIEWS OF Six SAFETY PARAME- Supplement Deahng With Disposa! Of.--. TER DISPLAY SYSTEMS. NUREG/CR 3444 V04: THE IMPACT OF LWR DECONTAMiNATONS ON SOUDIFICATION. WASTE DISPOSAL.AND ASSOCIATED OCCU-E 952 EXPERIMENTAL STUDY OF FILLET WELD UNDER. CUT EFFECTS ON WELDED TUBING STRUCTURES UNDER CEN- Degredation TRO AND ECCENTRO CYCLO LOADINGS. NUREG 1284; PROGRAM PLAN FOR CORRECTON OF U S. loSTRd-MENT DEGRADATION OR F AILURE IN THE UPN'R PLENUM TEST DCH 1 Expertment FACIUTY (UPTF) IN THE FEDERAL REPUBUC OF GERMANY. NUREG/CR-4871: RESULTS FROM THE DCH-1 EXPERIMENT. NUREG/CR-4590 V01: AGING OF NUCLEAR STATON DESEL GENERATORS Evaluaten Of Operatng And Expert Expenence. Phase DEGRi$

                                                     "                                                 ^       "^ ^

NURE CR-4590 V02- AGING OF NUCLEAR STATON DIESEt g HACKED S GENERATORS Ev8vation Of Operating And Expert Exponence Workshop. DOE NUREG/CR-4735 V01: EVALUATION AND COMPILATON OF DOE NUREG/CR-4701 V02: SAFETY ASSESSMENT OF ALTERNATIVES TO WASTE PACKAGE TEST DATA N.nnual Report. December 1985 SHALLOW. LAND BURIAL OF LOW-LEVEL RADCACTIVE WASTE. Volume 2 Envronmental Conditions Attacting Rebatzlity Of En-July 1986. NUREG/CR-4735 V02 EVALUATON AND COMPILATION OF DOE gmeered Barrers. WASTE PACKAGE TEST DATA. B4 annual ReportAugust 1986 Janu. NUREG/CR 4731 V01: RESIDUAL UFE ASSESSMENT OF MMOR ary 1987. UGHT WATER REACTOR COMPONENTS OVERVIEW. Volume 1. NUREG/CR-4819 V01: AGING AND SERVICE WEAR OF SOLENOO-DOE / RECON OPERATED VALVES USED IN SAFETY SYSTEMS OF NUCLEAR NUREG/CR-3469 V03. OCCUPATIONAL DOSE REDUCTION AT NU- POWER PLANTS. Volume 1.Operstmg Exponence And Fa4ure identifi-CLEAR POWER PLANTS. Annotated Beliography 01 Selected Read- cation. Ings in Radiation Protection And ALARA. NUREG/CR-4928. DEGRADATON OF NUCLEAR PLANT TEMPERA-TURE SENSORS. Data Sese NUREG/CR4955: LONG-TERM PERFORMANCE OF Cor;TAINER MA-NUREG/CR-4409 V02: DATA RASE ON NUCLEAH POWER PLANT TERtALS FOR HIGH-LEVEL WASTE-DOSE REDUCTION RESEARCH PROJECTS. Degraded Core Accider.1 Data Reienon Mode NUREG/CR-4803- THE POS$lBluTY OF LOCAL DETONATIONS NUREG/CR4531: AN INVESTIGATON OF INTEGRAL FACluTY SCAL

• DURING DEGRADED 40RE ACODENTS IN THE BELLEFONTE NU-ING AND DATA RELATON METHODS (INTEGRAL SYSTEM TEST CLEAR POWER PLANT, PROGRAM).

Degraded Piping

                                                                                                                                                                                                                                                                        ^

R -48 FEASIBluTY STUDY ON A DATA-8ASED SYSTEM "$ ApntS ' FOR DEOSONS REGARDING OCCUPATONAL RADIATION PRO-

                                                                . ECTION MEASURES-                                                                                                                         Department of Energy NUREG/CR4735 V01: EVALUATION AND COMPILATON OF DOE WASTE PACKAGE TEST DATA. Benrual Report. December 1985 -

E CR-4C89: THERMAL-PYDRAUUC AND CHARACTERISTIC M 1986. MODELS FOR PACKED DEBRIS BEDS. Design Det 4 Coolamty N.,HEG/CR-4719- COOLABfUTY OF STRATIFIED UC2 DEBRIS IN NUREG/CR-4870 AN EVALUATION OF THE EFFECTS OF DESIGN SODIUM WITH DOWNWARD HEAT REMOVALThe 013 Expennent DETAILS ON THE CAPAC(TY OF LYvR SSL CONTAINMENT BUILDNGS Decay Heat Removal NUREG/CR4943: PREPARATION OF DESIGN SPECIFICATIONS AND NUREG 1269 LOSS OF RESIDUAL HEAT REMOVAL SYSTEMDiablo DESON REPORTS FOR PUMPS. VALVES.P1 PING.AND PIPING SUP. Canyon urut 2. Apn110,1937. PORTS l! SED IN SAFETY.RELATED PORTONS OF NUCLEAR NUREG/CR4448. SHtJTDOWN DECAY HEAT REMOVAL ANALYSIS OF POWER PLANTS. A GENERAL ELECTRO BWR3/ MARK 1. Case Study. NUREG/CR4458: SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF DeWgn BasJe A WESTINGHOUSE 2-LOOP PRESSURIZED WATER REACTOR Case NUREG/CR4877: ASSESSMENT OF DESGN BASTS FOR LOAD-CAR-Study. RrtNG CAPACITY OF WELD-OVERLAY REPAIRS.

112 Subject Index Detonat6on Du. meter NUREG/CR4803: THE POSSIBILITY OF LOCAL DETONATONS NUREG/CR-4959: PERFORMANCE TESTING OF EXTREMITY DOSI-DURING DEGRADED CORE ACCOENTS IN THE BELLEFONTE NU- METERS. CLEAR POWER PLANT. Doolmetry Detonation Cel' NUREG/CR-4905: DETONABILITY OF H2 AIR-DILVENT MIXTURES- NUREG/CR 3320 V03: LWR PRESSURE VESSEL SURVEILLANCE DO. SIMETRY IMPROVEMENT PROGRAM PSF rhysses-Dosametry Pro-p,g oram. NUREG/CR4810- EVALUATON O" D'ESEL UNAVAILABILITY AND NUREd/CR-3320 V04: LWR PRESSURE VESSEL SURVEILLANCE DO-RISK EFFECTIVE SURVEILLANCE TEST INTERVALS. SIMETRY IMPROVEMENT PROGRAM PSF Metallurgy Program. NUREG/CR4418: DOSE CALCULATON FOR CONTAMlNATON OF Diesel Genuantor THE SKIN USING THE COMPUTER CODE VARSKIN. NUREG/CR-4590 V01: AGING OF NUCLEAR STATON . DIESEL NUREG/CR4886: ANALYSIS OF THE NESDIP2 AND NESOiP3 RADIAL GENERATORS Evaluation Of Opera ng And Expert Expenence. Phase SHIELD AND CAVITY EXPERIMENTS. N E CR 4590 V02. AGING OF NJCLEAR STATON DidSEL Drop Tower GENERATORS. Evaluation Cf Operating And Expert NURFL CR4818: TRANSITON RANGE DROP TOWER J-R CURVE Exponence Workshop. TESilNG OF A106 STEEL , Nffusion Flame Dyersburg Line NUREG/CR4534. ANALYSIS OF DIFFUSON FLAME TESTS. NUREG/CR4936: AN INTEGRATED GE3LOGCAL,GFOPHYSICAL,AND GEOCHEMCAL INVESTIGATON OF THE WJOR FRACTURES ON U EG4386 004 R04: UNITED STATES NUCLEAR REGULATORY b ' COMMISSION STAFF PRACTICE AND PROCEDU9E DIGESTJuly Dynamic Load NU 4 ROS: UNITED STATED NUCLEAR REGULATORY COMMISSON STAFF PRACTICE AND PROCEDURE DIGESTJuly p y 8f g-NU G 8 00 System 06 UNITED STATES NUCLEAR REGULATORY COMMISSON STAFF PRACTCE AND PROCEDURE DIGEST. July .dVREG/CR-3956: IN SITU TESTING OF THE SHlPPINGPORT ATOMC 1972. De N POWER STATON ELECTRICAL CIRCUITS. D6 rect containment Heating ECCS NUAEG/CR 4871: RESULTS FROM THE DCH-1 EXPERIMENT. NUREG 1230 DAFT FC: COMPENDIUM OF ECCS RESEARCH FOR RE-NUREG/CR4894 CONTAINMENT LOADS DUE TO DIRECT CONTAIN. ALISTIC LOCA ANALYSIS. Draft Report For Comrnent MENT HEATING AND ASSOCIATED HYDDOGEN EEHAVOR.AnaPysas And Cak:ulations With The CONTAIN Code. EVNT E D6epero6on POSTULATED SEVERE ACCOENTS. GURRY POWER STATON. UNIT NUREG/CR-4820: COMPARISON OF THE 1982 SEADEX DISPERSON 1 Draft For Cornment.

      '1ATA WITH RESULTS FROM A NUMBER Or DiFFERENT MODELS.                 NUREG/CR4700 Y2 DAF; CONTAINMENT EVENT ANALYSIS FOR NUREG/CR4950 VOI: THE SHORELING                . 'RONMENT ATMOS.

PHERC DISPERSION EXPERIMENT ; 9 Expenment Desenp-POSTULATED SEVERE ACCIDENTS: SEQUOYAH POWER STATION. UNIT 1. Draft Report For Comment tio% NUREG/CR-4700 V4 DAF: CONTAINMENT EVENT ANALYSIS FOR POSTULATED SEVERE ACCOENTS. GRAND GULF NUCLEAR H E 4J85: POST PLIOCENE C4SPLACEMENT ON FAULTS S aN Comnw WITHIN THE KENTUCKY RIVER FAULT SYSTEM OF EAST CEN. Earthquake TRAL KENTUCKY-NUREG/CR-3145 V05: GEOPHYSICAL INVESTIGATIONS OF THE g p,  ; WESTERN OHIO INDIANA REGION Final Report,0ctober 1981 - Sep-HAR RE CHARACTERI T . R 53 V02: CANADIAN SEISMC AGREEMENT. Annual Report. D6eposal Of Radioactive Weste NUREG/CR4776: HCSPONSE OF SEISM C CATEGORY I TANKS TO NUREG4683 S02: PAOGRAMMATIC ENVIRONMENTAL IVPACT EARTHOUAKE EXCITATON STATEMENT RELATED TO DECONTAMINATON AND DISPOSAL OF NUREG/CR4851: SEISMCITY 1886 O IN THE SOUTHEASTERN RADCACTIVE WASTES RESULTING FROM MARCH 28.1979 ACCI. UNITED STATES The Aftershock S69uence Of The Charleston. South ] DENT AT THREE MILE ISLAND NUCLEAR STATION.UNfT 2 Fmal Carohna Earthquake. I Supplement Deahng Wdh Dsposal Of- NUREG/CR4852. THE MEERS FAULT;TECTONC ACTIVITY IN SOUTHWESTERN OKLAHOMA Disposal System NUREG/CR4861: DEVELOPMENT OF SITE SPECIFIC RESPONSE NUREG 1245 V01: RADCACTIVE WASTE MANAGEMENT RESEAC 4 SPECTRA PROGRAV PLAN FOR HGH-LEVEL WASTE 1987. NUREG/CR4903 V02: SELECTCN OF EARTHQUAKE RESJSTANT DissolutM DESIGN CRITERIA FOR NUCLEAR POWER PLANTS METHODOLO-GY AND TECHNCAL CASES. Methods For introduction Of Geological NUREG/CR4954: LONG TERM PERFORMANCE OF SPENT FUEL Data into Charactenzation Of Actrre Faults And Seismecify And.... WASTE FORMS NUREG/CR4910: RELAY CHATTER AND OPERATOR RESPONSE U**30" AFTER A LARGE EARTHOUAKE.An improved PRA Methodology With Case Studies NUREG/CR-5003 DESIGN OF A MATERIAL CONTROL AND AC-NUREG/CR4936 AN INTEGRATED GEOLOGCAL GEOPHYSICAL,AND COUNTING SYSTEM TO PROTECT AGAINST CONCEALMENT OF D(VERSON BY FALSIFICATON AND COLLUSON- GEOCHEMCAL INVESTGATON OF THE MAJOR FRACTURES ON THE EAST SCE OF THE NEW MADRID EARTHOUAKE ZONE. Dose Calculation NUREG/CR4974. INTRAPLATE SEISMCITY IN THE EASTERN NUREG/CR-4418. DOSE CALCULATON FOR CONTAMINATION OF UNITED STATES THE SKIN USING THE COVPUTER CODE VARSKW. NUREG/CR-5034 AN UPDATE OF M DCONTINENT TECTONISM. Does Rate Earthquake Engineering NUREG/CR-5035: DATA BASE OF SYSTEM AVERAGE DOSE RATES NUREG/CR4903 V01: SELECTON OF EARTHOUAkE RESISTANT AT NUCLEAR POWER PLANTS Frsal Report. DESIGN CRITERIA FOR NUCLEAR POWER PLANTS METHODOLO-GY AND TECHNCAL CASES Drect Emprical Scaling Of Response Doce Reduction Research Spectral Ampetudes From Vanous Sde And Earthouake Parameters. NUREG/CR-4409 V02: DATA BASE ON NUCLEAR POWER PLANT NUREG/CR4903 V03 SELECTON OF EARTHOUAkE RESISTANT DOSE REf)UCTON RESEARCH PROJECTS DESGN CRITERIA FOR NUCLEAR POWER PLANTS METHODOLO-

Subject Index 113 GY AND TECHNICAL CASES. Dislocaten Models Of Near Source NUREG/CR4726: EVALUATION OF PROTECTIVE ACTION RISKS. Earthquake Ground Moton. A Recew. Emergency Response Plan Economic Regulation NUREG 0654 S01 R01: CRITERIA FOR PREPARATON AND EVALUA. NUREG 1256 V01: INCENTIVE REGULATON Oc NUCLEAR POWER TION OF RADIOLOGICAL EMEAGENCY RESPONSE PLANS AND PLANTS BY STATE PUBUC UT UTY COMMISSIONS- PREPAREDNESS IN SUPPORT OF NUCLEAR POWER PLANTS.Cntena For Utmty Offsite Ptannog And Preparedness Draft E RM Report NUREG/CR-4825: A PREUMINARY EVALUATION OF THE ECONOMIC RISK FOR CLEANUP OF NUCLEAR MATERIAL UCENSEE CONTAMI- Enforcement Act'on NATON INCOENTS. NUREG-0940 VOS N04: ENFORCEMENT ACTONS.SIGNIFICANT AC. Effluent TONS RESOLVED.Ouarterty Progress Report. October-December NUREG/CR 2907 V05: RADCACTIVE MATERIALS RELEASED FROM 1986. NUCLEAR POWER PLANTS. Annual Report 1914. NUREG4940 V06 Not: ENFORCEMENT ACTONS SIGNIFICANT AC. NUREG/CR4786: TRANSPORT BEHAVIOR OF IOD4NE IN EFFLUENT TiONS RESOLVED.Ouarterty Progress ReportJanuary-March 1987. RADIOACTIVITY MONITORlNG SYSTEMS. NUREG4940 VO6 NO2: ENFORCEMENT ACTIONS.SIGNIFICANT AC-TONS RESOLVED.Ouarterty Progress ReportApnt June 1987. Electomer Seal NUREG-0940 V06 NO3: ENFORCEMENT ACTIONS SiGNIFICANT AC-NUREG/CR4944: CONTAINMENT PENETRATION ELASTOMER SEAL TIONS RESOLVED.Ouarterty Progress ReportJuly-September 1987. LEAK RATE TESTS. Engineered Barrier Electrical in Situ Teeung NUREG/CR-4701 V02: SAFETY ASSESSMENT OF ALTERNATIVES TO NUREG/CR 3956: IN SITU TESTING OF THE SHIPPINGPORT ATOMC SHALLOW-LAND BURIAL OF LOW LEVEL RADCACTW E POWER STATION ELECTRICAL ClRCUITS. WASTE Volume 2 Envronmental Condatons Affecteg Rehabildy Of En-geeered Bamers. Electr@Wt NURE 4865: THE SOLUBluTY OF ELECTRODEPOSITED TC(IV) Engineering Cost NUREG/CR4921: ENGINEERING AND QUALITY ASSURANCE COST Emtrittlement FACTORS ASSOCIATED WITH NUCLEAR PLANT MOOlFICATION. NUREG/CR-4744 V01 N1: LONG TERM EMBRITTLEMENT OF CAST DUPLEX STAINLESS STEELS IN LWR SYSTEMS.Serrmannual Environmental Assessment ReportOctobr.r 1985 March 1966 NUREG 123S. ENV1RONMENTAL ASSESSMENT FOR RENEWAL OF NUREG/CR-4744 V01 N2: LONG TERM EMBRITTLEMENT OF CAST SOURCE MATERIAL UCENSE NO. STB 401 Docket No. 446563 (Co. DUPLEX STAINLESS STEELS IN LWR SYSTEMS Semiannual lurrbum Tantalum Dmson.Malknekrodt.ine ) R ' September 1986 NUR G/ 4744 V02 N1; LONG TERM EMBRITTLEMENT OF CAST Enytronmental lmpact DUPLEX STAINLESS STEELS IN LWR SYSTEMS Semiannual NUREG 0332: POTENTIAL HEALTH AND ENVIRONMENTAL IMPACTS Report. October 1986 March 1987. ATTRIBUTABLE TO THE NUCLEAR AND COAL FUEL CYCLES Foal NUREG/CR 4955. LONG TERM PERFORMANCE OF CONTAINER MA* Report TERIALS FOR HIGH-LEVEL WASTE. Enytronmentel impact Statement NUREG-0683 SO2. PROGRAMMATC ENVIRONMENTAL IMPACT

             /CR-4722: SOURCE TERM ESTIMATION USING MENU TACT            STATEMENT RELATED TO DECONTAMINATION AND DISPOSAL OF NUREG/CR-4797: PROGRESS REVIEWS OF SIX 3AFETY PARAME-TER 04 SPLAY SYSTEMS,                                              RADIOACTIVE WASTES RESULTING FROM MARCH 28.1979 ACCI-DENT AT THREE MILE ISLAND NUCLEAR STATON, UNIT 2.Fnal Emergency Core Coonng System                                            Supplement Dealog Wdh Dispost! Of...

NUREG 1230 DRFT FC: COMPENDIUM OF ECCS RESEARCH FOR RE-AUGTIC LOCA ANALYS!S. Dratt Report For Comment Enyttonmental Parameters NUREG/CR4964. UPDATE OF TABLE S-3 NONRADOLOGCAL ENVI-Emergency Operating Procedures RONMENTAL PARAMETERS FOR A REFERENCE LIGHT WATER NUREG/CR-4617: ONSITE ASSESSMENTS OF THE EFFECTIVENESS REACTOR Uraruurn Mong Mung And Ennchment AND IMPACTS OF UPGRADED EMERGENCY OPERATING PROCE-DURES. Environmental Ouahfication NUREG/CR4819 V01: AGING AND SERVICE WEAR OF SOLENOO. Emergency Plan OPERATED VALVES USED IN SAFETY SYSTEMS OF NUCLEAR l NUREG4762 R1 DRF FC: STANDARD FORMAT AND CONTENT FOR POWER PLANTS. Volume 1.Operatog Expenence And Fake ident6 i EMERGENCY PLANS FOR FUEL CYCLE AND MATERIALS caton. FACluTIESPatt Report For Comment Environmental Standard Review Plan Emergency Preparednese NUREG-1300: ENVIRONMENTAL STANDARD REVIEW PLAN FOA THF NU9EG-0654 S01 ROI: CRITERIA FOR PREPARATION AND EVALUA. REVIEW OF A UCENSE APPUCATION FOR A LOW-l.EVEL RADIO-TON OF RADOLOGICAL EMERGENCY RESPONSE PLANS AND ACTIVE WASTE DISPOSAL FACIUTY' PREPAREDNESS IN SUPPORT OF NUCLEAR POWER PLANTS Cntena For Ut6ty Offsde P'arnng And Preparedness Dre't Enytronmental Statement Report NUREG 1300- ENVIRONMENTAL STANDARD REVIEW PLAN FOR THE Emergency Response REVIEW OF A UCENSE APPUCATON FOR A LOW-LEVEL RADIO. ACTIVE WASTE DISPOSAL FACILITY. NUREG 1210 V01: PILOT PROGRAM NRC SEVERE REACTOR ACCI. DENT INCOENT RESPONSE TRAINING MANUALOvennew And Sum- pment Operm mary Of Mapr Points NUREG 1210 V02: PILOT PROGRAM.NRC SEVERE REACTOR ACCI. NUREG/CR4942: EQUIPMENT OPERABluTY DURING STATON DENT INCOENT RESPONSE TRAINING MANUALSevere Reactor Ac. BLACKOUT EVENTS. cadent Overyw Equipment Queefication NUREG-1210 V03 PILOT PROGRAM.NRC SEVERE REACTOR ACCI. DENT INCOENT RESPONSE TRAINtNG MANUALResponse Of U- NUREG/CR *301: STATUS REPORT ON EOUtPMENT OVALIFICATON consee Ana State And Local Officials. ISSUES RESEARCH AND RESOLUTON. NUREG-1210 V04: PILOT PROGRAM NRC SEVERE REACTOR ACCl- NUREG/CR4734 SEISMC TESTING OF TYPICAL CONTAINMENT DENT INCOENT RESPONSE TRAINING MANUALPubhc Protectnre PINNG PENETRATON SYSTEMS. Actons Predetermired Cntena And Irvtsal Actons NUREG-1210 V05: PILOT PROGRAM NRC SEVERE REACTOR ACCl- EroWon DENT INCOENT RESPONSE TRAINING MANUALU S Nuclear Regu- NUREG/CR-4727; SWISS SUSTAINED HEA1ED METALLIC MELT / CON-letory Commisson Response. CRETE INTERACTONS WITH OVERLYING WATER POOLS

114 Subject Index EroelorbCorroelon Mechanism Feesitditty NUREG/CR4868: METALLURGICAL EVALUATON OF AN 18 INCH NUREG/CR4856: FEASIBiUTY STUDY ON A DATA BASED SYSTEM FEEDWATER UNE FA! LURE AT THE SURRY UNIT 2 POWER STA. FOR DECISIONS REGARDING OCCUPATONAL RADIATON PRO-TION. TECTON MEASURES. Eroelve-Corroelve Wear F,ed And B6eed Coonng NUREG'CR-5007; PREDICTON AND MITIGATON OF EROSNE40R-ROSlVE WEAR IN SECONDARY PIPING SYSTEMS OF NUCLEAR NUREG/CR4946: DAVIS-BESSE UNCERTAINTY STUDY. POWER Pt. ANTS. Foodwater une NUREG/CR4868: METALLURGICAL EVALUATON OF AN 18-tNCH N E 4726. EVALUATON OF PROTECTNE ACTON RISKS. b

• Evaluation Procedure NUREG 1258. EVALUATON PROCEDURE FOR SJMULATON FAClu- Feedwater une Broek TIES CERTIFIED UNDER 10 CFR 55 Frial Report NUREG/CR4802- AN EVALUATON OF TRAC-PF1/ MOD 1 COMPUTER i

NUREG-1258 DRFT: EVALUATION PROCEDURE FOR SIMULATON CODE PERFORMANCE DURING POSTTEST SIMULATONS OF SE. FACIUTIES CERTIFIED UNDER 10 CFR 55 Draft Report. MISCALE MOD 2C FEEDWATER UNE SREAK TRANSIENTS. Event Feedwater Transient NUREG-0525 R12: SAFEGUARDS

SUMMARY

EVENT UST (SSEL). NUREG/CR4741: FEEDWATER TRANSIENT AND SMALL BREAK NUREG4525 R13: SAFEGUARDS

SUMMARY

EVENT UST (SSEL). LOSS OF COOLANT ACCOENT ANALYSES FOR THE BELLEFONTE Expert NUCLEAR PLANT. NUhEG/CR4814: SOURCES OF CORRELATON BETWEEN Fillet Weld Undercut EXPERTS Empreal Results From Two Ertremes. NUREG/CR-a952: EXPERIMENTAL STUDY OF FtLLET WELD UNDER. Expert Opelon CUT EFFECTS ON WELDED TUBING STRUCTURES UNDER CEN-NUREG/CR-4962: METHODS FOR THE EUCITATON AND USE OF TRIC AND ECCENTRC CYCUC LOADINGS. EXPERT OPINION IN RISK ASSESSMENT. Phase 1 A Cntcal Evalua-ton And Dreebons For Future Research. IIIm N External Hazard RIA IN POST-DRYOUT REGON BASED ON FLOW VISUAUZATON NUREGICR-5042: EVALUATON OF EXTERNAL HAZARDS TO NUCLE- EXPERIMENTS. AR POWER PLANTS IN THE UNITED STATES. Final Design Approval Extreme Wind NUREG4852 S03: SAFETY EVALUATON REPOFsT RELATED TO THE NUREG/CR-4801: CUMATOLOGY OF EXTREME WINDS IN SOUTH-ERN CAUFORNIA- FINAL DESIGN OF THE STANDARD NUCLEAR STEAM SUPPLY REFERENCE SYSTEM.CESSAR System 80. Docket No. 50-470(Com-Extremity Dosimeter

• NUREG/CR4959 PERFORt!ANCE TEST!NG OF EXTREMITY DOSI. Final Environmental Statement METERS-NUREG 0904 S01: DRAFT SUPPLEMENT TO THE FINAL ENVIRON-FITS Vnd MENTAL STATEf 2NT RELATED TO THE DECOMMISSONih3 OF NUREG/CR-3468: HYDROGEN.A!R: STEAM FLAMMABluTY UMITS THE RARE EAR 14 FACluTY, WEST CHICAGO,lLUNOISDocket No.

AND COMBUSTON CHARACTERISTICS IN THE FITS VESSEL. NURE 11 NL NVIA'NMENTAL STATEMENT FOR DECOM-FRAPCON-2 MISSONING HUMBO E'T BAY POWER PLANT. UNIT 3. Docket No. NUREG/CR-4718 EXPERIMENTAL SUPPORT AND DEVELOPMENT OF $0133 (Pacrhc Gas And 9ectre Compariy) SINGLE. ROD FUEL CODES PROGRAM. Summary Report p Failure NUREG/CR4958. IMPACT OF PFOPCSED FINANCLAL ASSURANCE NUREG/CR4691 OPERATING EXPERIENCE REVIEW OF FAJLURES REQUIREMENTS ON NUCLEAR M.'.TERIALS LCENSEES. OF POWER OPERATED REllEF VALVES AND BLOCK VALVES IN NUCLEAR POWER PLANTS. Fire NUREG/CR-4747 V01: AN AGING FAILbRE SURVEY OF UGHT NUREG/CR-4527 V01: AN EXPERIMENTAL INVESTIGATON OF IN-WATER REACTOR SAFETY SYSTEMS AND COMPONENTS. TERNALLY IGNITIED FIRES IN NUCLEAR POWER PLANT CONTROL NUREG/CR-4919 V01: AGING AND SERVICE WEAR OF SOLENOID- CABINETS Part 1-Catset Effects Tests. OPERATED VALVES USED IN SAFETY SYSTEMS OF NUCLEAR NUREG/CR4679. QUANTITATIVE DATA ON THE FIRE BEHAVOR OF POWER PLANTS. Volume 1.Operaung Expenence And Fa. lure identif> cation. COMBUSTIBLE MATERIALS FOUND IN NUCLEAR POWER { PLANTS A Uterature Rewew. j NUREG/CR4681: ENCLOSURE ENVIRONMENT CHARACTERIZATON UREG -5003. DESJGN OF A MATERIAL CONTROL AND AC- yg g COUNTING SYSTEM TO PROTECT AGAINST CONCEALMENT OF OfVERSON BY FALSIFICATON AND COLLUSON NUREG/CR.5037: FIRE' ENVIRONMENT DETERMINATON IN THE LA. CALLE NUCLEAR POWER PLANT CONTROL ACOM. NUREG/CR-5042- EVALUATON OF EXTERNAL HAZARDS TO NUCLE. CR5 08 E C MENT OF A TESTING AND ANALYSIS AR POWER PLANTS IN THE UNITED STATES. METHODOLOGY TO DETERM NE THE FUNCTONAL CONDITON OF SOLENOlO OPERATED VALVES. Fiscal Year NUREG-1100 V03. BUDGET ESTIMATES. Fiscal Years 1988 1989 Fat 9ue NUREG-1100 V03 ADO: BUDGET ESTIMATES Fiscal Years 1J88-1989 NUREG/CR-4863: SURFACE SPECTROSCOPY OF PRESSURE Fission Neutron VESSEL STEEL FATIGUE FRACTURE SURFACE FILMS FORMED tN PWR EPMRONVENTS NUREG/CR-4704 V01: RELATIVE BOLOGICAL EFFECTIVENESS (RBE) OF FiSSON NEUTRONS AND GAMMA RAYS AT OCCUPATIONAL Fatigue Crack Growth Rate EXPOSURE LEVEL % Volume 1. Studies On The Genete Effects in NUREG/CR4724 FATIGUE CRACK GRCWTH RATES IN PRESSURE Mce Of 60 Equal Once-WeekY Exposures To Fisson Neutrons And VESSEL AND PtPING STEELS IN LWR ENVIRONMENTS Final Report. G Faults OF FISSON NEUTRONS AND GAMMA RAYS AT OCCUPATONAL NUREG/CR-4685: POST.PLOCENE DISPLACEMENT ON FAULTS EXPOSURE LEVELS.Vos u me ti StuGes On The Effects Of 60 Equal WITHIN THE KENTUCKY RIVER FAULT SYSTEM OF EAST 4EN. Once WeeUy Exposures To Fissaon Neutrons And Gamma Rays On TRAL KENTUCKY. S'reval Of Mce.

Subject index 115 Flesion Product NUREG/CR-4818: TRANSITION RANGE DROP TOWER J-R CURVE NUREG/CR4925: FIS110N PRODUCT BEHAVIOR DURING THE PBF TESTING OF A106 STEEL SEVERE FUEL DAMAGE TEST 1 1. Fracture Zone Fleelon Product Cloenup System NUREG/CR-3232: DETAILED STUDIES OF SELECTED.WELL EXPOSED NUREG4800 06.5.2 R2: STANDARD REVIEW PLAN FOR THE REVIEW FRACTURE ZONES IN THE ADIRONDACK MOUNTAINS DOME.NEW OF SAFETY ANALYSIS REPORTS FOR NUCLEAR POWER YORK. PLANTS LWR Edibon. Proposed Revieso12 To Sact on 6.5.2, "Contain-ment Spray As A Fission Product System." For Comment. Fractured Medle NUREG-0800 06.5.5 R0- STANDARD R EW PLAN FOR THE REVIEW NUREG/CR4925 REV: SwtFT ll SELF-TEACHING Of SAFETY ANALYSIS REPORTS FOR NUCLEAR POWER CURRICULUM.lliustratrve Problems For The Sandia Waste-Isolation PLANTS. LWR EditortProposed Revision 0 To New SRP Sechon 6.5.5. Flow And Transport Model For Fractured Med a.

                      "Preeeure Suppraseita Pools As Fission Product Dean Up Systems."

For Comment Fractured Rock NUREG/CR-4654: RADIONUCUDE TRANSPORT AS VAPOR Fieme Acceleretton THROUGH UNSATURATED FRACTURED ROCK. NUREG/CR-4855 DEVELOPMENT AND APPUCATION OF A COMPUT. NUREG/CR-4655: UNSATURATED FLOW AND TRANSPORT EA MODEL FOR LARGE-SCALE FLAME ACCELERATION EXPERl- THROUGH FRACTURED ROCK RELATED TO HIGH-LEVEL WASTE MENTS. REPOSITORIESFmal Report Phase 11. FlammabiNty umit Fractures NUREG/CR-3468: HYDROGENAIR: STEAM FtAMMABILITY UMITS NUREG/CR-4863: SURFACE SPECTROSCOPY OF PRESSURE AND COMBUSTION CHARACTERISTICS IN THE FITS VESSEL VESSEL STEEL FATIGUE FRACTURE SURFACE FILMS FORMED IN PWR ENVIRONMENTS. Flow Donelty NUREG/CR-4936: AN INTEGRATED GEOLOGICALGEOPHYSCAL.AND NUREG/CR-4860: FLAW DENSITY EXAMINATONS OF A CLAD BOIL- GEOCHEMICAL INVESTIGATION OF THE MAJOR FRACTURES ON ING WATER REACTOR PRESSURE VESSEL SEGMENT- THE EAST SOE OF THE NEW MADRID EARTHOUAKE ZONE. Flood Fregaty NUREG/CR 5942: EVALVATION OF EXTERNAL HAZARDS TO NUCLE

• NUREG/CR-4826 V01: SEISMIC MARGIN REVIEW OF THE MAINE AA POWER PLANTS IN THE UNITED STATES. YANKEE ATOMC POWER STATON Volume 1. Summary Report NUREG/CR4826 V02: SEISMIC MARGIN REVIEW OF THE MAINE

                                                                                                                                                                  ^"K                    ^ "                 v        '"

NUR CR TWO PHASE FLOW REGIME TRANSITION CRITE- yREG/CR48 VO E7S RG E AINE RtA IN POST DRYOUT REGON BASED ON FLOW VISUAUZATON YANKEE ATOMIC POWER STATON Volume 3.Fragihty Analysis. EXPERIMENTS. NUREG/CR4859: SEISMC FRAGluTY TEST OF A 6 INCH DIAMETEM PtPE SYSTFM. JREG/CR4651: DEVELOPMENT OF RIPRAP DESIGN CRITERIA BY ** I *E "" ** RIPRAP TESTING IN FLUMES Phase L France Flux Weided Pipe NUREG;CR-4530 V02 U.S3 FRENCH JOINT RESEARCH PROGRAM NUREG/CR-4878: ANALYSIS OF EXPERIMENTS ON STAINLESS REGARDING THE BEHAVOR OF POLYMER BASE MATERIALS SUB-STEEL FLUX WELDS. Topical 'W JECTED TO BETA RADLATON. Volume 2: Phase 2a Screerung Tests. Fracture Analysis

                                                                                                     ^

UAEG-1281: EVALUATION OF THE QUAUFICATION OF SPERT FUEL S T OUG AL CRAC E ES FOR USE IN NON-POWEN REACTORS. Fracture Grouting NUREG 1282- SAFETY EVALUATON REPORT ON HIGH. URANIUM CONTENT, LOW-ENRICHED URANFUM-ZlRCONIUM HYDROE NUREG/CR4541: EXPERIMENTAL ASSESSMENT OF THE SEALING EFFECTIVENESS OF ROCK FRACTURE GROUTING. FUELS FOR TRK1A REACTORS Docket No. 5016HGA Technolog.es. incorporated) NUREG/CR 4320; THE RELATONSHIP AND INFLUENCES OF FUEL Fracture Mechanico " NUREG/CR 3228 V05: STRUCTURAL INTEGRITY OF WATER REAC- AND COOLANT SYSTEM PROCESSES DURING LWR SEVERE ACO. TOR PRESSURE BOUNDARY COMPONENTSAnnual Report For DENTS. 1966. Fuel Cladrng NUREG/CR4082 V05: DEGRADED PIPtNG PROGRAM PHASE i liierrmannual R Apni-September 1986 NUREG/CR-4485 V0t TI'8i IMPACT OF FUEL CLADDtNG FAILURE NUREG/CR 4219 N2 HEAVY-SECTON STEEL TECHNOLOGY EVENTS ON OCCUPATIOiW. RADIATION EXPOSURES AT NUCLE-l PROGRAM. Semiannual Progress Report For Apni-Septemtw 1986. AR POWER PLANTS. Case Study-PWR Dunng An Outage. NUREG/CR-4219 YO4 N1: HEAVY SECTON STEEL TECHNOLOGY PROGRAM.Ser.6 annual Progress Report For October 1986 March Fuel Cycle 1987. NUREG 0332- POTENTIAL HEALTH AND ENVIRONMENTAL IMPACTS NUREG/CR-4760: TEST OF 6-IN, THICK PRESSURE VESSELS.Senes ATTRIBUTABLE TO THE NUC' EAR AND COAL FUEL CYCLESFinal 3 6ntermedate Test Vessel V 8A.Teanng Behavior Of Low Upper Srcf Report Matenal. NUREG/CR 4964: UPCMTE OF TABLE S4 NONRADOLOGICAL ENVI-NURGG/CR-4872: EXPERIMENTAL AND ANALYTICAL ASSESSMENT RONMENTAL PARAM7ERS FOR A REFERENCE UGHY WATER OF CIRCUMFERENTIALLY SURFACECRACKED PIPES UNDER REACTOR.Vranium Mong.Milting And Ennchment. BENDING. Fuel Cycle And Meterials Foc616ty NUREG/CR 4877: ASSESSMENT OF DESIGN BASIS FOR LOADCAR-RYING CAPACITY OF WELD-OVERLAY REPAIRS NUREG-0762 R1 DRF FC: STANDARD FORWT AND CONTENT FOR NUREG/CR-4878: ANALYSIS OF EXPERIMENTS ON STAINLESS EMERGENCY PLANS FOR FUEL-CYCLE AND MATERIALS STEEL FLUX WELDS Topical Report FActuTIES Draft Report For Comment. NUREG/CR-4894: A USER'S GUtDE TO THE NRC'S PIPING FRAC-TURE MECHANCS DATA BASE (P1 FRAC). Fuel Damage NUREG/CR-1930 CRACK ARREST BEHAVOR IN SEN WIDE PLATES NUREG/CR 4320 THE RELATONSHIP AND INFLUENCES CF FUEL OF OUENCHED AND TEMPERED A 533 GRADE B STEEL TESTED AND COOLANT SYSTEM PROCESSES DURING LWR SEVERE ACCI-UNDER NCNISOTHERMAL CONDITIONS. DENTS. NUREG/CR-4990- HEAVY-SECTION STEEL TECHNOLOGY NUREG/CR4866: AN ASSESSMENT OF HYDROGEN GENERATON PROGRAM F'rve Year Plan FY 1986-1990. FOR THE PBF SEVERE FUEL DAMAGE SCOPING AND 11 TESTS Fracture Toughnese Fuel Performance NUREG/CR-4491: DEVELOFMENT OF MODELS FOR WARM PRES- NUREG/CR 3950 V03 FUEL PERFOHMANCE ANNUAL 9EPORT FOR TRESSING 1985.

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

116 Subject indCx NUREG/CR-4718: EXPERIMENTAL SUPPORT AND DEVELOPMENT OF Geophysical Technique S!NGLE ROD FUEL CODES PROGRAM Summary Report NUREG/CR-4957: SURVEY OF GEOPHYSOAL TECHNIQUES FOR SITE CHARACTERIZATON IN BASALT, SALT AND TUFF. NUREG/CR4891: PROPERTIES OF REACTOR FUEL ROD MATERIALS Glasa AT HIGH TEMPERATURES Feal Summary Report Severe Core Damage Property Tests Program- NUREGICR-4795: LONG TERM PERFORMANCE OF HIGH-LEVEL GLASS WASTE FORMS. Functionality Granite NUREG/CR 5008: DEVELOPMENT OF A TESTING AND ANALYSIS METHODOLOGY TO DETERMINE THE FUNCTONAL CONDITION OF NUREG/CR-4919: FIELD TESTING OF BENTONITE AND CEMENT BOREHOLE PLUGS IN GRANITE. SOLENOC OPERATED VALVES. Grant Fundamental Nuclear Material Control NUREG-1280 STANDARD FORMAT AND CONTENT ACCEPTANCE NUREG/CR-5007: PREDCTION AND MITIGATION OF EROSfVE COR-CRITERIA FOR THE MATERIAL CONTROL AND ACCOUNTING ROSfVE WEAR IN SECONDARY PIPING SYSTEMS OF NUCLEAR POWER PLANTS. (MC&A) REFORM AMENDMENT.10 CFR Part 74 Subpart E. GASPARtl Graphite NUREG/CR-4653: GASPAR II - TECHNICAL REFERENCE AND USER NUREG/CR-4981: A SAFETY ASSESSMENT OF THE USE OF GRAPH-GUIDE- ITE IN NUCLEAR REACTORS LICENSED BY THE U.S. NRC. Gamma ray Grophete Fire NUREG/CR 4704 V01: RELATIVE BIOLOGCAL EFFECTIVENESS (RBE) NUREG 1250- REPORT ON THE ACCCENT AT THE CHERNOBYL NU-CLEAR POWER STATON. OF FlSSON NEUTRONS AND GAMMA RAYS AT OCCUPATONAL EXPOSURE LEVELSVolume 1. Studies On The Genetc Effects in NUREG-1250 ROI: REPORT ON THE ACCOENT AT THE CHERNOBYL Mce Of 60 Equal Once-Weeuy Exposures To Fesson Neutrons And NUCLEAR POWER STATION. Gamma Rays. Ground Motion NUREG/CR4704 V02- RELATIVE BIOLOGICAL EFFECTIVENESS (RBE) OF FISSON NEUTRONS AND GAMMA RAYS AT OCCUPATONAL NUREG/CR4903 V03: SELECTON OF EARTHOUAKE RESISTANT EXPOSURE LEVELS. volume 11. S'udies On The Effects Of 60 Equal DESIGN CRITERIA FOR NUCLEAR POWER PLANTS METHODOLO-Onc+Weeuy Exposures To Fessmon Neutrons And Gamina Rays On GY AND TECHNCAL CASES. Dislocation Models Of Near Source Earthquake Ground Motion. A Review SurwalOf Mce. Ground Water Dating Gas Tracer NUREG/CR-4950 V02: THE SHORELINE ENVIRONMENT ATM%- NUREG/CR-4912- DATING GROUND WATER AND THE EVALUATON PHERC DISPERSION EXPERIMENT (SEADEX)Meteorologeal And OF REPOSITORIES FOR RADOACTIVE WASTE. Gas Tracer Data. Ground Water Protection General Electric BWR3 NUREG-1241 GROUND WATER PROTECTON ACTIVITIES OF THE U S. NUCLEAR REG'AATORY COMMISSON. NUREG/CR-4448: SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF A GENERAL ELECTRIC BWR3/ MARK l. Case Study. Grout Testing General Electric BWR4 NUREG/CR-4541: EXPERIMENTAL ASSESSMENT OF THE SEALING EFFECTIVENESS OF ROCK FRACTURE GROUTING. NUREG/CR 4767: SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF A GENERAL ELECTRIC BWR4/ MARK l. Case Study. H(2) Air Mixture NUREG/CR-4905: DETONABILITY OF H2-AIR-DILUENT MIXTURES. NUREG/CR4690 V01 N1: GENERC COMMUNICATONS Haaardous Weste INDEX trstengs Of Communcatons (1971 1986) NUREG/CA-4730. EVALUATON OF POTENTIAL MfXED WASTES CON-NUREG/CR-4690 V02: GENERC COMMUNICATONS INDEX. User's TAINING LEAD, CHROMlUM,USED OIL.OR ORGANC LOUCS. Manual Generic Safety lasue Health Effects NUREG 0933 S06: A PRIORITl2ATON OF GENERC SAFETY ISSUES NUREG 0332: POTENTIAL HEALTH AND ENVIRONMENTAL IMPACTS NUREG/CR-4982: SEVERE ACCOENTS IN SPENT FUEL POOLS IN ATTRIBUTABLE TO THE NUCLEAR AND COAL FUEL CYCLES. Foal p, port SUPPORT OF GENERC SAFETY ISSUE 82 Genetic Effect Heat Decay NUREG/CR-4704 VOI: RELATIVE BOLOGCAL EFFECTIVENESS (RBE) NUREG/CR4719. COOLABluTY OF STRATIFIED UO2 DEBRIS IN 1 SODIUM WITH DOWNWARD HEAT REMOVALThe D13 Expenment. OF FISSON NEUTRONS AND GAMMA RAYS AT OCCUPATIONAL l EXPOSURE LEVELS. Volume 1. Studies On The Genetc Effects in Heat Of Reaction Mce Of 60 Equal Once Weeuy Exposures to Fisson Neutrons And Gamma Rays. NUREG/CR-4830 HEAT OF REACTON OF MOLTEN ZlRCONIUM WITH U02 Goochemica6 Behavior Heat Removal NUREGICR4708 V01 N1: PROGRESS IN EVALUATON OF RADIONU-NUREG/CR-4719- COULABILITY OF STRATIFIED 002 DEBRIS IN CLIDE GEOCHEMCAL INFORMATON DEVELOPED BY DOE HIGH-LEVEL NUCLEAR WASTE REPOslTORY SITE SODIUM WITH DOWNW tRD HEAT REMOYALThe D13 Extenment PROJECTS.Semawal Report M Octobre 1985 March 1986. Heat Transfer Geolo9:e Disposal NUREG/CA-4758: A RETRAN MODEL OC THE CALVERT CUFFS 1 ARESSURIZED WATER REACTOR FOR ASSFSSING THE SAFETY NUREG/CR-2452: RISK METHODOLOGY FOR GEOLOGIC DISPOSAL IMPLICaTONS OF CONTROL SYSTEMS. OF RADCACTIVE WASTE. Final Report NUREG/CR4830: MELCOH VALCATON AND VERIK:ATON 1986 Geological Deformation PAPERS. NUREG/CR4903 V02. SELECTON OF EARTHOUAKE RESISTANT Heated Detonation Tube DESGN CRITERIA FOR NUCLEAR POWER PLANTS METHODOLO- NUREG/CR-4905: DETONABILITY OF H2 AIR DILUENT MIXTURES. GY AND TECHNICAL CASES Methods For introducton Of Geologeal Data into Characten24 tion Of Actrve Faufts And Seesmcrty And..- Heavy Section Steel Technology NUREG/CR4219 V03 N2; HEAVY SECTION STEEL TECHNOLOGY Geophysicalinvestigation PROGRAM Semiannual Progress Report For Apni-September 1986 NUREG/CR-3145 V05: GEOPHYSCAL INVESTIGATIONS OF THE NUREG/CR4219 V04 N1; HEAWSECTON STEEL TECHNOLOGY WESTERN OHC-INDIANA REGON Final Report. October 1981 Sep- PROGRAM Sermannual Progress Report For October 1986 March tomber 1986 1987.

Subject index 117 NUREG/CR-4711: LOW UPPER-SHELF TOUGHNESS.HOH TRANSI- Human Factors TON TEMPERATURE TEST INSERT IN HSST PTSE 2 VESSEL AND NUREG/CR-3968: STUDf CF OPERATING PROCEDURES IN NUCLE-WOE PLATE TEST SPECIMENS F nal Report AR POWER PLANTS. Practices And Problems. NUREG/CR4990: HEAVY SECTON STEEL TECHNOLOGY Human Reflet 61 tty PROGRAM.Feve Year Plan.FY 1986 1990. NUREG/CR-4772: ACCIDENT SEQUENCE EVALUATON PROGRAM V EG CR4 E COOLDOWN ASPECTS OF THE TMid ACCI- NUREG CR 46 HGH WA R CLOSURE SYSTEMS SAFETY ANALYSIS Phase 2. Final Report. NU E IIA 4004. THERMAL MIXING TESTS IN A SEMIANNULAR NUREG/CR4862 V01: COGNITIVE ENYtRONMENT SIMULATON AN DOWNCOMER WITH INTERACTING FLOWS FROM COLD LEGS' ARTIFICIAL INTELLIGENCE SYSTEM FOR HUMAN PERFORMANCE ASSESSMENT. Volume 1: Summary And Overview. H6gh-Level Weste NUREG/CR4862 V02: COGNITIVE ENVIRONMENT SMULATONAN NUREG-1245 V01: RADIOACTIVE WASTE MANAGEMENT RESEARCH ARTIFOtAL INTELUGENCE SYSTEM FOR HUMAN PERFORMANCE PROGRAM PLAN FOR HIGH-LEVEL WASTE .1987. ASSESSMENT Volume 2.Modelng Human intention Formulation. NUREG/CR4134 ROI: REPOSITORY ENVIRONMENTAL PARAM- NUREG/CR4862 V03. COGNITIVE ENYlRONMENT SIMULATION AN ETERS AND MODELS RELEVANT TO ASSESSING THE PERFORM-ANCE OF HIGH-LEVEL WASTE PACKAGES (BASALT, TUFF AND ARTIFICIAL INTELUGENCE SYSTEM FOR HUMAN PERFORMANCE ASSESSMENT. Volume 3 Cognitive Rehabilty Analysis Technique SALT). NUREG/CR4735 V01: EVALUATON AND COMPILATON OF DOE Hydrogen WASTE PACKAGE TEST DATA. 8. annual ReportDecember 1985 Jufy 1986. NUREG/CR4534. ANALYSIS OF DIFFUSION FLAME TESTS. NUREG/CR-4735 V02- EVALUATON AND COMPILATION OF DOE WASTE PACKAGE TEST DATA. B. annual ReportAugust 1986 - Janu- Hydrogen Behavior ery 1987. NUREG/CR4896: CONTAINMENT LOADS DUE TO DIRECT CONTAIN-MENT HEATING AND ASSOCIATED HYDROGEN BEHAVOR.Analysss NUREG/CR 4795: LONG TERM PERFORMANCE OF HIGH LEVEL

                                                                                                                                                                                                                                            ##8                   ^I" NUR /C               G LEVEL WASTE PRECLOSURE SYSTEMS SAFETY ANALYSIS Phase 2. Final Re_po t                                                                                             Hydrogen Gener3 tion NUREG/CR-4954: LONG TERM PERFORMANCE OF SPENT FUEL                                                                                               NUREG/CR4866. AN ASSESSMENT OF HYDROGEN GENERATON FOR THE PSF SEVERE FUEL DAMAGE SCOPING AND 11 TESTS.

NU E / 9 5 LONG-TERM PERFORMANCE OF CONTAINER MA, TERIALS FOR HIGH-LEVEL WASTE. Hydrogen Air: Steam Mixture NUREG/CR4956: SYSTEM PERFORMANCE OF HIGH-LEVEL WASTE NUREG/CR 3468: HYDROGEN. AIR. STEAM FLAMMABILITY LIMITS PACKAGE COMPONENTS. AND COMBUSTION CHARACTERISTICS IN THE FITS VESSEL H6gh Level Weste Repoeltory ICAP NUREG/CR-3861: STRESS CORROSION CRACKING OF LOW- NUREG 1270 YO1:INTERNATONAL CODE ASSESSMENT AND APPU-STRENGTH CARBON STEELS IN CANDIDATE HIGH-LEVEL WASTE CATONS PROGRAM. Annual Report REPOSITORY ENVIRONMENTS. NUREG 1271: GUOEUNES AND PROCEDURES FOR THE INTERNA. NUREG/CR4161 V02: CRITCAL PARAMETERS FOR A HIGH-LEVEL TIONAL CODE ASSESSMENT AND APPLOATONS PROGRAM. WASTE REPOSITORY. Volume 2-Tu'1 NUREG/CR4161 V03: CRITICAL PARAMETERS FOR A HIGH LEVEL WASTE REPOSITORY Volume 3 Salt IE Bulleun NUREG/CR4654: RADIONUCLOE TRANSPORT AS VAPOR NUREG/CR4524: CLOSEOUT OF IE BULLETIN 80 24 PREVENTION THROUGH UNSATURATED FRACTURED ROCK- OF DAMAGE DUE TO WATER LEAKAGE INSOE CONTAINMENT NUREGICR4655: UNSATURATED FLOW AND TRANSPORT (OCTOBER 171980 INDIAN POINT 2 EVENT) THROUGH FRACTURED ROCK RELATED TO HIGH-LEVEL WASTE NUREG/CR466i CLOSEOUT OF IE BULLETIN' 83-01. FAILURE OF RE-E S I ' ACTOR TRIP BREAKERS (WESTINGHOUSE D8 50) TO OPEN ON NUR , N S tN EVALUATON OF RADIONU. CtOE GEOCHEMICAL INFORMATON DEVELOPED BY DOE HIGH- NURE / 46 CL SE OF IE BULLETIN 8344 FAILURE OF SWE THE UNDERVOLTAGE TRIP FUNCTION OF REACTOR TRIP BREAK-PROJECTS Semia For ober 1 5 Mar 986 ERS. NUREG/CR 5040. RADt DE MiGRATON AROUND URAN!UM ORE BODIES . ANALOGUE OF RADCACTivE WASTE IRRAS REPOSITORIES Annual Report For 1984-1985. NUREG/CR-4844 DRFT: INTEGRATED REUABluTY AND RISK ANALY. SIS SYSTEM (IRRAS) USER'S GUIDE VERSON 1.0 (DRAFT). High Temperature Oxidation NUREG/CR-4889. ZlRCALOY4 OXOATON AT 1300 TO 2400 DE- ISAP GREES C. NUREG 1185 V01 DAFT: INTEGRATED SAFETY ASSESSMENT NUREG/CR-4890- HEAT OF REACTON OF MOLTEN 2)RCONJUM REPORT. integrated Safety Assessment Program Haddam Neck WITH UO2. PlantDocket No. 50-213. (Connecteut Yankee Atomic Power Compa. Highway And RePway Accident Conditions ny) NUREGICR4429 V01: SHIPPING CONTAINER RESPONSE TO NUREG-1185 V02 DRFT: INTEGRATED SAFETY ASSESSMENT SEVERE HIGHWAY AND RAILWAY ACCOENT CONDITONSMan REPORT. integrated Safety Assessment ProgramHaddam Neck

                                                                                                                                                                                                                                                                ""*      * * * ^ *           **'

NUR CR-4829 V02: SHIPPING CONTAINER RESPONSE TO SEVERE HIGHWAY AND RA!LWAY ACCOENT CONDITlONS Appendices- Impact Analysie NUREG/CR 3966- METHOOS FOR IMPACT ANALYSIS OF SHIPPING H4W Deu Summry CONTAINERS. NUREG 1214 R07 HISTORICAL DAT A

SUMMARY

OF THE SYSTEMAT-IC ASSESSMENT OF UCENSEE PERFORMANCE. Wpiemenut)on NUREG 1213 RO1: PLANS AND SCHEDULES FOR IMPLEMENTATION H' story OF U S. NUCLEAR REGULATORY COMMISSON RESPONSIBruTIES NU;EG 1214 Ron HISTORCAL DATA

SUMMARY

OF THE SYSTEMAT. UNDER THE LOW LEVEL RADCACTIVE WASTE POUCY AMEND-C ASSUSMENT OF UCENSEE FERFORMANCE. MENTS ACT OF 1985 (P.L 99-240). Human Error Prot >obility in-Sttu Stress NUREG/CR-4016 V02: APPUCATION OF SUM.MAUD.A TEST OF AN NUREG/CR-4623. IN-SITU STRESS MEASUREMENTS IN THE INTERACTfvE COMPUTER-BASED METHOD FOR ORGANt21NG EARTH'S CRUST IN THE EASTERN UNITED STATES. EXPERT ASSESSMENT OF HUMAN PERFORMANCE AND REUABluTY. Volume if Appendices. incident Response NUREG/CR4777 ACCIDENT SEQUENCE EVALUATON PROGRAM NUREG-0728 R02: NRC (NCOENT RESPONSE PLAN HUMAN REUABlUTY ANALYSIS PROCEDURE.

118 Subject index NUREG 1210 V01: PILOT PROGRAMNRC SEVERE REACTOR ACCI- NUREG4040 V11 NO3: LCENSEE CONTRACTOR AND VENDOR IN-DENT INCIDENT RESPONSE TRAINING MANUAL Orennew And Sum. SPECTION STATUS REPORT. Quarterly Report, July-September mery Of Maior Points. 1987.(Wtute Book) NUREG 1210 V02: PILOT PROGRAM.NRC SEVERE REACTOR ACCI- NUREG-1194: CONSTRUCTION APPRAISAL TEAM INSPECTON RE-DENT INCIDENT RESPONSE TRAINING MANUAL. Severe Reactor Ac-cident Ovennew. SULTS ON WELDING AND NONDESTRUCTIVE EXAMINATION AC-TtVITIES. NUREG 1210 V03: PILOT PROGRAM NRC SEVERE REACTOR ACCI-DENT INCIDENT RESPONSE TRAINING MANUALResponse Of U- NUREG-1258: EVALUATION PROCEDURE FOR SIMULATION FAClu-TIES CERTIFIED UNDER 10 CFR 55. Final Report covce And State And Local Offx: als. NUREG-1210 V04. PILOT PROGRAM.NRC SEVERE REACTOR ACCI- NUREG-1258 DAFT: EVALUATION PROCEDURE FOR SlMULATON DENT INCOENT RESPONSE TRAINING MANUALPubhc Protectrve FACluTIES CERTIFIED UNDER 10 CFR 55. Draft Report NUREG/CR-4583 V02 DEVELOPMENT AND VAUDATON OF A REAL. NU 21 Vo T PROGRAM RC SE lE REACTOR ACCl. TIME SAFT UT SYSTEM FOR THE INSPECTION OF UGHT WATER DENT INCIDENT RESPOf 4SE TRAINING MANUALU.S. Nuclear Regu- REACTOR COMPONENTSAnnual Report, October 1984 September I**Y **E"**' NUREG/CR-4583 V03: DEVELOPMENT AND VAllDATION OF A REAL. Incineration TIME SAFT-UT SYSTEM FOR THE INSPECTION OF UGHT WATER NUREG/CR-4787: CONFERENCE OF RADIATION CONTROL PRO. REACTOR COMPONENTS Annual Report,0ctober 1985 September GRAM DlHECTORS' INFORMATION FOR LCENSNG LOW-LEVEL 1986. RADIOACTIVE WASTE INCINERATORS AND COMPACTORS. NUREG/CR-5006: PRA APPUCATION PROGRAM FOR INSPECTION AT OCONEE UNIT 3. Inconet 600 System NUREG/CR-4963: BORON CARBIDE STEAM REACTIONS WITH Instrument Tube Rupture CEStVM HYDROXIDE AND WITH CESIUM IODIDE AT 1270K IN AN NUREG/CR-4672: ANALYSIS OF INSTRUMENT TUBE RUPTURES IN INCONEL 600 SYSTEM. WESTINGHOUSE 4 LOOP PRESSURIZED WATER REACTORS. Indes instrumente NUREG0304 VII N04: REGULATORY AND TECHNICAL REPORTS NUREG-1284: PROGRAM PLAN FOR CORRECTION OF U.S. INSTRU. N RE b YECH C EPORTS MENT DEGRADATION OR FAILURE IN THE UPPER PLENUM TEST (ABSTRACT INDEX JOURNAL). Compdation For Frst Quarter FACIUTY (UPTF) IN THE FEDERAL REPUBUC OF GERMANY. NURE 304 2 NO2: REGULATORY AND TECHNICAL REPORTS '"'*9 F **'"'Y 88*33"9 (ABSTRACT INDEX JOURNAL). Comp 4ation For Second Quarte, NUREG/CR-4531: AN INVESTIGATION OF INTEGRAL FACILITY SCAL-1987Apni-June ING AND DATA RELATION METHOOS (INTEGRAL SYSTEM TEST NUREG-0304 V12 NO3. REGULATORY AND TECHNICAL REPORTS PBOGRAM). (ABSTRACT INDEX JOURNAL). Compilation For Thrd Quarter 1987, Jury-September. Integral System Test Prograrn NUREG-1163. COORDINATION OF SAFETY RESEARCH FOR THE Infutretion BABCOCK AND WILCOX INTEGRAL SYSTEM TEST PROGRAM. NUREG/CR 2478 V03: A STUDf OF TRENCH COVERS TO M. nim 12E NUREG/CR4531: AN INVESTIGATION OF INTEGRAL FACIUTY SCAL. INFILTRATION AT WASTE DISPOSAL SITES Final Rept. ING ANO DATA RELATION METHODS (INTEGRAL SYSTEM TEST Influent Boundary Conditions NUREG/CR4901: EFFECTS FROM INFLUENT BOUNDARY CONDI- Integrated Plant Safety Asseeement TlONS ON TRACER MIGRATION AND SPATIAL VARIABIUTY FEA- NUREG4825 S01: INTEGRATED Pt. ANT SAFETY TVRES IN INTERMEDIATE SCALE EXPERIMENTS. ASSESSMENT, SYSTEMATIC EVALUATION PROGRAM, YANKEE NU. Inhetet6on Exposure CLEAR POWER STATION. Docket No. 50-029 (Yankee Atorruc Electne NUREG/CR-4968: RADIATION DOSE ESilMATES AND HAZARO EVAL. Company) UATIONS FOR INHALED AIRBORNE RADIONUCUDES.Fanal Report Integrated Renobility inservice inspection NUREG/CR-4844 DRFT: INTEGRATED REUABluTY AND RISK ANALY-NUREG/CR-4469 V04. NONDESTRUCTIVE EXAMINATION (NDE) REU. SS SYSTEM (tRRAS) USER'S GUlOE VERSION 1.0 (DRAFT 1 ABiUTY FOR INSERVICE INSPECTON OF UGHT WATER REACTORS Semiannual ReportOctober 1985 March 1986 Integrated Safety Assessment NUREG/CR 4469 VOS. NONDESTRUCTIVE EXAMINATON (NDE) REU. NUREG-1184 ORFT: INTEGRATED SAFETY ASSESSMENT ABlWTY FOR INSERVCE INSPECTION OF UGHT WATER REPORT,1NTEGRATED SAFETY ASSESSMENT PROGRAM MILL. REACTORS.Semaannual Report Aprtseptemter 1966 STONE NUCLEAR POWER STATON. UNIT 1. Docket No. 50-NUREG/CR-4469 V06: NONDESTRUCTIVE EXAM.NATON (NDE) REU- 245.(Northeast Nuclear Energy Co) Draft Report ABluTY FOR INSERVCE INSPECTION OF UGHT WATER NUREG-1185 V01 DRFT: INTEGRATED SAFETY ASSESSMENT i REACTORS Semiannual Reoort. October 1986 March 1987. REPORT. integrated Safety Assessrnent Program.Haddam Neck NUREG/CR4712- REGULATDRV ANALYSIS OF REGULATORY GUOE Plant Docket No. 50 213. (Connecticut Yankee Atome Power Compa. l 1.35 (REVISON 3. DRAFT 2) . IN-SERVCE .NSPECTION OF UN- ny) GROUTED TENDONS IN PRESTRESSED CONCRETE CONTA!N- NOREG-1185 V02 DRFT: INTEGRATED SAFETY ASSESSMENT MENTS. REPORT.integraled Safety Assessment Program.Haddam Neck NUREG/CR-4731 V01: RESIOUAL LIFE ASSESSMENT OF MAJOR PlantDocket No. 50-213. (Connectacut Yankee Atomic Power Compa. UGHT WATER REACTOR COMPONENTS OVERVIEW Volume 1. ny) inservice Monitoring NUREG/CR-4300 V03 N2: ACOUSTIC EMISSON/ FLAW RELATION- Into Event SHIP FOR INSERVICE MONITORING OF NUCLEAR PRESSURE NUREG/CR-4$50 V01: ANALYSS OF CORE DAMAGE FREOVENCY VESSELS.Proaress Rept.Apni ' tomber 1986 FROM INTERNAL EVENTS: METHOOOLOGY GUIDELINES. NUREG/CR-430D V04 r41. A STC EMISSON/ FLAW RELATON. NUREG/CR-4550 V03: ANALYSS OF CORE DAMAGE FREQUENCY SHIP FOR IN-SERVCE MONITORING OF NUCLEAR PRESSURE FROM INTERNAL EVENTS.SURRY UNIT 1. VESSELS. Progress Report, October 1986 March 1987. NUREG/CA-4550 V04 ANALYSS OF CORE OAMAGE FREQUENCY FROM INTERNAL EVENTS. PEACH BOTTOM UNIT 2. Inspection NUREG/CR-4550 V05: ANALYSIS OF CORE DAMAGE FREQUENCY NUREG4040 V10 N04. LCENSEE CONTRACTOR AND VENDOR IN. FROM INTERNAL EVENTS: SEQUOYAH. UNIT 1. SPECTON STATUS REPORT. Quarterty Report. October-December NUREG/CR-4550 V06PT1: ANALYSS OF CORE DAMAGE FREQUEN. 1986 (Whte Book CY FROM INTERNAL EVENTS-GRAND GULF. UNIT 1. Main Report NUREG4040 V11 N)01: LCENSEE CONTRACTOR AND VENDOR IN. NUREG/CR-4550 V06PT2: ANALYSS OF CORE DAMAGE FREQUEN. SPECTION STATUS REPORT. Quartedy Report. January-March CY FROM INTERNAL EVENTS-GRAND GULF, UNIT 1 Apperdces. 1987.(Wivte Boolt) NUREG4040 VII NO2- LCENSEE CONTRACTOR AND VENDOR IN. International Code Assessment And Appucation SPECTION STATUS REPORT. Cbarierty Report.ApnhJune 1987.(Whte NUREG-1270 V01: INTERNATIONAL CODE ASSESSMENT AND APPU-Book) CATONS PROGRAM Annual Report a

Subject Index 119 NUREG 1271: GutDELINES AND PROCEDURES FOR THE INTERNA- NUREG/CR-2000 V06 N8: LCENSEE EVENT REPORT (LER) TIONAL CODE ASSESSMENT AND APPUCATONS PROGRAM. COMPILATON For Month Of A t 1987. NURE.3/CR 2000 V06 N9: NSEE EVENT REPORT (LER) Intreplete Seismicity COMPILATON For Month Of Septerr+;er 1987. NUREG/CR-4973: INTRAPLATE SEISMICITY OUTSOE OF THE NUREG/CR 2000 V06N10- UCENSEE EVENT REPORT (LER) UNITED STATES. COMPILATON For Month Of October 1987. NUREG/CR-4974: INTRAPLATE SEISMCITY IN THE EASTERN NUREG/CA-2000 V06N11: UCENSEE EVENT REPORT (LER) UNITED STATES. COMPILATION.For Month Of November 1987, intruder Does Pathway Analysis LLRWPAA NUREG/CR 3620 SO2: INTRUDER DOSE PATHWAY ANALYSIS FOR NUREG 1213 R01: PLANS AND SCHEDULES FOR IMPLEMENTATION THE ONSITE DISPOSAL OF RADCACTIVE WASTES.The ONSITE/ OF U.S. NUCLEAR REGULATORY COMMISSION RESPONSIBluTIES MAX 11 Computer Program. UNDER THE LOW-LEVEL RADCACTIVE WASTE POUCY AMEND-MENTS ACT OF 1985 (P.L 99 240). Innnt mfference mte NUREG/CP 0085: MEETING WITH STATES ON THE LOW LEVEL RA-NUR 0430 V07 Not: UCENSED FUEL FACluTY STATUS DCACT.".I WA5th HJLu AMENDMENTS ACT (LLRWPAA) OF REPORT. Inventory Dfference Data January June 1986 (Grev Book H) S 1985. NUREG4430 V07 NO2: UCENSED FUEL FACillTY STATU REPORT. Inventory Dfference DataJuly-December 1986.(Gray Book it) gyp,q fodine NUREG/CR4719 COOLABluTY OF STRATIFIED 002 DEBRIS IN SODIUM WITH DOWNWARD HEAT REMOVALThe 013 Expenment. NUREG/CR4786: TRANSPORT BEHAVOR OF ODINE IN EFFLUENT RADCACTIVITY MONITORING SYSTEMS. lodine Partitlen Coefficient NUREG-1230 DAFT FC: COMPENDfUM OF ECCS RESEARCH FOR RE-NUREG/CR4817: LODINE PARTITON COEFFICIENT MEASUREMENTS ALISTIC LOCA ANALYSIS. Draft Report For Comment AT SlMULATED PWR STEAM GENERATOR CONDITIONS.Intenm NUREG/CR4799: RELAP5/ MOD 2 ASSESSMENT SIMULATON OF SE-Data Report MISCALE MOD 2C TEST S-NH-3. NUREG/CR-4965: TRAC-PF1/ MODI US/ JAPANESE PWR CONSERVA-tron Oulde Aerosol TIVE LOCA PREDeCTON. NUREG/CR4798: IRON OXIDE AEROSOL EXPERIMENTS IN STEAM- NUREG/CR 5010. RELAPS/ MOD 2 ASSESSMENT USING SEM! SCALE AIR ATMOSPHERES.NSPP TESTS 501505 AND 511, DATA RECORD EXPERIMENTS S-NH 1 AND S-LH 2. REPORT. Irredleted Hardware NUREG-1230 DAFT FC: COMPENDfUM OF ECCS RESEARCH FOR RE. NUREG/CR4968: EVALUATION OF UNCERTAINTIES IN IRRADIATED AUSTIC LOCA ANALYSIS. Draft Report For Corynent. HARDWARE CHARAOTER12ATON. NUREG/CR 2907 V05: RADCACTIVE MATERIALS RELEASED FROM NUCLEAR POWER PLANTS. Annual Report 1984. lootop6c Migration NUREG/CR 3228 V05: STRUCTURAL INTEGRITY OF WATER REAC-NUREG/CR 5060: AN APPROACH TO THE MATHEMATICAL MODEL* TOR PRESSURE BOUNDARY COMPONENTS Annual Report For LING OF THE URANIUM SERIES REDISTRIBUTON WITHIN ORE 1986. BODIES. NUREG/CR-3319 R01: LWR PRESSURE VESSEL SURVEILLANCE DO-S: METRY IMPROVEMENT PROGRAM. LWR Power Reactor Surve4-NU E /CR-4853. APPROX: MATE METHODS FOR FRACTURE ANALY' NUR / b PRESSU EISURVEILLANCE DO-SES OF THROUGH WALL CRACKED PIPES. SIMETRY IMPROVEMENT PROGRAM PSF Physcs-Dostnetry Pro. N RE /CR 3320 VO4: LWR PRESSURE VESSEL SURVEILLANCE DO-NUR G/CR 4 8: TRANSITON RANGE DROP TOWER J-R CURVE SIMETRY IMPROVEMENT PROGRAM PSF Metallurgy Program. TESTING OF A106 STEEL NUREG/CR 3412 V02- CONTAINMENT INTEGRITY Kentucky River Fault System PROGRAM Progress Report Apnl 1983 December 1984. NUREG/CR-4685: POST-PUOCENE DISPLACEMENT ON FAULTS NUREG/CR 3444 V04: THE !MPACT OF LWR DECONTAMINATONS WITHIN THE KENTUCKY RIVER FAULT SYSTEM OF EAST-CEN. ON SOUDIFICATON. WASTE DISPOSALAND ASSOCIATED OCCU-PATONAL EXPOSURE Annual Report, Frscal Year 1986 TRAL KENTUCKY' NUREG/CR-4216: EXPERIMENTAL RESULTS FOR A 18-SCALE STEEL Kinetics MODEL NUCLEAR POWER PLANT CONTAINMENT PRESSURIZED NUREG/CR4758. A RETRAN MODEL OF THE CALVERT CUFFS-1 TO FAILURE. NUREG/CR-4307 YO3; LWR PRFSSURE VESSEL SURVEILLANCE DO- ! PRESSURt2ED WATER REACTOR FOR ASSESSING THE SAFETY SIMETRY IMPROVEMENT PROGRAM.1986 Annual Report. October IMPUCATONS OF CONTROL SYSTEMS. 1985 September 1986 Knowledges And Abilities Catalog NUREG/CR4320- THE RELATIONSHIP AND INFLUENCES OF FUEL NUREG 1122 S01: KNOWLEDGES AND ABlUTIES CATALOG FOR NU. AND COOLANT SYSTEM PROCESSES DURING LWR SEVERE ACCI-CLEAR POWER PLANT OPERATORS.Pressurued Water Reactors. DENTS NUREG/CR-4330 V03. REV1EW OF UGHT WATER REACTOR REGU. Knuckle Buckling LATORY REQUIREMENTS Assessment Of Selected Regulatory Re-NUREG/CR-4926: AN ASSESSMENT OF LOSS OF-CONTAINMENT PO- quvements That May Have Margmal irrportance To Risk.Postacc4ent TENTIAL BECAUSE OF KNUCKLE BUCKUNG FOR 4:1 STEEL CON- Samphng System, Turtune Missdes. Combust 6e Gas Control, Charcoal TAINMENT HEADS. Fdters. NUREG/CR4469 V04. NONDESTRUCTIVE EXAM:NATON (NDE) REU-LER ABluTY FOR INSERVICE INSPECTON OF UGHT WATER NUREG/CR 2000 V05N12. UCENSEE EVENT REPORT (LER) REACTORS.Serrmannual Report.0ctceer 1985 March 1988 COMPILATON For Month Of Decemoer 1986- NUREG/CR 4469 VOS: NONDESTRUCTIVE EXAM' NATION (NDE) REU-NUREG/CR-2000 V06 N1: UCENSEE EVENT REPORT (LER) ABluTY FOR INSERVICE INSPECTON OF UGHT WATER NUR / V06 2 UC SE EVENT REPORT (LER) NURE / VO6 N TR T ION (NDE) REll-

                                        $EE EVENT REPORT (LER)                ABluTY FOR INSERVICE INSPECTON OF LGHT WATER NU G                V06 3 L                                              REACTORS Serrmannual Report, October 1986 March 1987.

COMPfLATION For Month Of March 1987' NUREG/CR-4583 V02: DEVELOPMENT AND VAUDATON OF A REAL-NUREG/CR-2000 V06 N4: UCENSEE EVENT REPORT (LER) TIME SAFT-UT SYSTEM FOR THE INSPECTON OF UGHT WATER COMPILATON For Month Of Apnl 1987. REACTOR COMPONENTS. Annual Report, October 1984 September NUREG/CR-2000 V06 NS: UCENSEE EVENT REPORT (LER) COMPILATO'l For Month Of May 1987. 1985-NUREG/CR 2000 V06 N6: UCENSEE EVENT REPORT (LER) NUREG/CR-4583 V03 DEVELOPMENT AND VAUDATON OF A REAL-COuptLATON For Month Of June 1987. TIME SAFT UT SYSTEM FOR THE INSPECTION OF UGHT WATER NOREG/CR 2000 V06 N7: UCENSEE EVENT REPORT (LER) REACTOR COMPONENTS Annual Report, October 1985 September COMPitATION For Month Of JuPy 1987. 1986.

120 Subj:ct Ind3x NUREG/CR 4616: ROOT CAUSES OF COMPONENT FAILURES NUREG 0750 V25101: INDEXES TO NUCLEAR REGULATORY COM-PROGRAM Methods And Appicatons. MISSION ISSUANCES. January March 1987. NUREG/CR-4667 V03: ENVIRONMENTALLY ASSISTED CRACKING IN NUREG-0750 V25 N01: NUCLEAR REGULATORY COMMISSION IS-UGHT WATER REACTORS. Sernannual Report.Apn'i September 1%6. SUANCES FOR JANUARY 1987 Pages 162. NUREG/CR-4674 V03: PRECURSORS TO POTENTIAL ScVERE CORE NUREG-0750 V25 NO2: NJCLEAR REGULATORY COMMISSION IS-DAMAGE ACCIDENTS.1984,A STATUS REPORT.Mac Report And Ap- SUANCES FOR FEBRUARY 1987.Pages 63128. pen 6xes A And B. - NUREG-0750 Y25 NO3: NUCLEAR REGULATORY COMMISSION IS. NUREG/CR 4674 V04. PRECURSORS TO POTENTIAL SEVERE CORE SUANCES FOR MARCH 1981Paoes 129-266. DAMAGE ACCIDENTS.1984,A STATUS REPORT.Appenenes C D And NUREG4750 V25 N04. NUCLEAA REGULATORY COMMISSION IS. E. SUANCES FOR APRIL 1987.Pages 267416. NUREG/CR-4724: FATIGUE CRACK GROWTH RATES IN PRESSURE VESSEL AND PIPING STEELS IN LWR ENVIRONMENTS Final Report. Leglelation NUREG/CR4731 V01: RESIDUAL UFE ASSESSMENT OF MAJOR NUREG-0980 R03: NUCLEAR REGULATORY LEGISLATON. UGHT WATER REACTOR COMPONENTS OVERVIEW. Volume 1. NUREG/CR 4734; SElSMIC TESTING OF TYPICAL CONTAINMENT Ucense Appucation PfPING PENETRATION SYSTEMS. NUREG 1199: STANDARD FORMAT AND CONTENT OF A LICENSE NUREG/CR-4744 V01 N1: LONG TERM EMBRITTLEMENT OF CAST APPUCATION FOR A LOW-LEVEL RADCACTIVE WASTE DISPOSAL DUPLEX STAINLESS STEELS IN LWR SYSTEMS Semannual FACluTY. Report,0ctober 1985. March 1986 NUREG 1200- STANDARD REVIEW PLAN FOR THE REVIEW OF A L1-NUREG/CR-4744 V01 N2: LONG TERM EMBRITTLEMENT OF CAST CENSE APPUCATON FOR A LOW-LEVEL RADIOACTIVE WASTE DUPLEX STAINLESS STEELS IN LWR SYSTEMS.Sermannual DISPOSAL FACluTY, Report.Apni-September 1986. NUREG-1274: REVIEW PROCESS FOR LOW LEVEL RADIOACTIVE NUREG/CR-4744 V02 N1; LONG-TERM EMBRITTLEMENT OF CAST WASTE DISPOSAL UCENSE APPUCATON UNDER LOW-LEVEL RA-DUPLEX STAINLESS STEELS IN LWR SYSTEMS.Sernannual DIOACTIVE WASTE POUCY AMENDMENTS ACT. Re. port October 1986 March 1987. NUREG-1300 ENVIRONMENTAL STANDARD REVIEW PLAN FOR THE NUREG/CR-4747 V01: AN AGING FAILURE SURVEY OF UGHT REVIEW OF A UCENSE APPUCATION FOR A LOW LEVEL RADIO-WATER REACTOR SAFETY SYSTEMS AND COMPONENTS- ACTIVE WASTE DISPOSAL FAC1UTY, NUREG/CR-4769. RISK EVALUATONS OF AGING PHENOMENA.The LmearA Rehatukty Model And its Ertensons- Ucensed Fuel Facility NUREG/ -4 81 DAF n STUDY OF SEVERE ACCIDENT MITIGATION NUREG-0430 V37 N01: UCENSED FUEL FACluTY STATUS NU " "*'"

                                      -4813. ASSESSMENT OF LEAK DETECTON SYSTEMS               NURE         V              2. L   SED U             F Ct     A S NU EG/                                           AL f6    OF TEG AL CONTINUING EXPERi-         REPORT. inventory Ddference Data. July-Docember 1986(Gray Book 10 MENTAL CAPABluTY (CEC) CONCEPTS FOR UGHT WATER REAC-                                     Ucensed Operating Reactors TOR RESEARCH . PWR SCAUNG CONCEPTS NUREG/ Cit-4870 AN EVALUATION OF THE EFFECTS OF DESIGN                                        NUREG-0020 V10 N09: LCENSED OPERATING REACTORS STATUS

SUMMARY

REPORT Data As Of August 31,1986 (Gray Book 0 DETAILS ON THE CAPACITY OF LWR STEEL CONTAINMENT NUREG-0020 V10 NIO: UCENSED OPERATING "EACTORS STATUS NUR G 964: UPDATE OF TABLE S-3 NONRADIOLOGCAL ENVI. RONMENTAL PARAMETERS FOR A REFERENCE UGHT WATER NUREG 20 V 11 ICE 4S D ING AC OR T TUS

SUMMARY

REPORT Data As Of October 31,1986(Gray Book f) REACTOR Uratwum Mang.Milhng And Ennchment NUREG 0020 V10 N12 UCENSED OPERATING REACTORS STATUS Large Pressure Transient

SUMMARY

REPORT. Data As Of Novernber 30,1986(Gray Book 0 NUREG/CR-4931: RESPONSE OF CENTRIFUGAL AND AXI-VANE NUREG4020 V11 N01: LCENSED OPERATING REACTORS STATUS

SUMMARY

REPORT. Data As Of December 31,1986(Gray Book 0 BLOWERS TO LARGE PRESSURE TRANSIENTS NUREG 0020 V11 NO2: UCENSED OPERATING REACTORS STATUS Lateral Separation

SUMMARY

REPORT. Data As Of January 31,1987.(Gray Book 0 NUREG/CR4610 EFFECTS OF LATERAL SEPARATION OF OXIDIC NUREG-0020 V11 NO3. LCENSED OPERATING REACTORS STATUS AND ETALL CORE DEBRIS ON THE BWR MK 1 CONTAINMENT 6UMM R R Dat F 98 ) gg

SUMMARY

REPORT. Data As Of March 31.1987.(Gray Book n Leeching NUREG-0020 VII N05 LCENSED OPERATING REACTORS STATUS NUREG/CR4954. LONG TERM PERFORMANCE OF SPENT FUEL

SUMMARY

REPORT Data As Of Aptd 30,1987(Gray Book 0 WASTE FORMS, NUREG-0020 V11 N06: UCENSED OPERATING REACTORS STATUS

SUMMARY

REPORT Data As Of May 31,1987.(Gray Book 0 Leek Detection NUREG4020 V11 N07. LCENSED OPERATING REACTORS STATUS NUREG/CR4813. ASSESSMENT OF LEAK DETECTON SYSTEMS

SUMMARY

REPORT. Data As Of June 30,1987.(Gray Book f) FOR LWRs October 1985. Sevynber 1986 NUREG-0020 V11 N08. UCENSED OPERATING REACTORS STATUS

SUMMARY

REPORT Data As Of July 31,1987(Gray Book 0 ] Leek Rate NUREG4020 V11 N09. LCENSED OPERATING REACTORS STATUS NUREG/CR-4216. EXPERl MENTAL RESULTS FOR A 1.8-SCALE STEEL

SUMMARY

REPORT. Data As Of August 31,1987(Gray Book 0 MODEL NUCLEAR POWER PLANT CONTAINMENT PRESSURIZED NUREG4020 VII NIO: UCENSED OPERATING REACTORS STATUS TO FAILURE.

SUMMARY

REPORT. Data As Of Septernber 30,1987.(Gray Book Q NUREG-0020 V11 N11: LCENSED OPERATING REACTORS STATUS Leak Rate Test

SUMMARY

REPORT. Data As Of October 31,1987.(Gray Book n NUREG/CR4944 CONTAINMENT PENETRATON ELASTOMER SEAL LEAK RATE TESTS. Ucensee NUREG/CR4958. IMPACT OF PROPOSED FINANCIAL ASSURANCE Legal issuances REOUIREMENTS ON NUCLEAR MATERIALS LCENSEES. NUREG-0750 V24101. INDEXES TO NUCLEAR REGULATORY COM-MISSON ISSUANCES. JuYSectember 1986 Ucensee Event Report NUREG4750 V24102; INDEXES TO NUCLEAR REGULATORY COM. NUREG/CR-2000 V05N12. LCENSEE EVENT REPORT (LER) MISSON ISSUANCES. July-December 1986 COMPILATON For Month Of December 1986, NUREG-0750 V24 N01: NUCLEAR REGULATORY COMMISSON IS- NUREG/CR 2000 YO6 N1: UCENSEE EVENT REPORT (LER) SUANCES FOR JULY 1986 Pages 1 195 COMPUTON For Month Of January 1987. NUREG4750 V24 N02. NUCdAR REGULATORY COMMSSON IS- NUREG/CR-2000 V06 N2; UCENSEE EVENT REPORT (LER) SUANCES FOR AUGUST 1986 Pages 197 396 COMPtLATON For Month Of February 1987. NUMEG4750 V24 N01 NUCLEAR REGULATORY COMMISSON IS. NUREG/CR-2000 V06 N3 LCENSEE EVENT REPORT (LER) SUANCES FOR SEPTEMBER 1986 Pages 397-4B8 COMPILATON For Month Of March 1987. NUREG-0750 V24 N04: NUCLEAR REGULATORY COMMISSON 15 NUREG/CR-2000 V06 N4 LICENSEE EVENT REPORT (LER) SUANCES FOR OCTOBER 1986 Pages 489-679 COMPILATON For Month Of Apnl 1987. NUREG4750 Y24 NOS NUCLEAR REGULATORY COMMISSON 15 NUREG/CR-2000 V06 N5 LCENSEE EVENT REPORT (LER) SUANCES FOR NOVEMBER 1986 Pages 681,768 COMPILATON For Month Of May 1987. NUREG0750 V24 N06 NUCLEAR REGULATORY COMM!SSION IS- NUREG/CR 2000 V06 N6 ' LICENSEE EVENT REPORT (LER) SUANCES FOR DECEMBER 1986 Pages 769 930. COMPILATON For Month Of June 1987.

SubpctInd:x 121 NUREG/CR 2000 V06 N7: UCENSEE EVENT REPORT (LER) NUREG/CR-4724: FATIGUE CRACK GROWTH RATES IN PRESSURE COMPILATON For Month Of Juey 1987. VESSEL AND PtPING STEELS IN LWR ENVIRONMENTS Final Report NUREG/CR 2000 V06 N8: UCENSEE EVENT REPORT (LER) NUREG/CR-4731 V01: RESIDUAL LIFE ASSESSMENT OF MAJOR COMPILATON.For Month Of August 1997. UGHT WATER REACTOR COMPONENTS OVERVIEW Volume 1. NUREG/CR 2000 V06 N9: UCENSEE EVENT REPORT (LER) NUREG/CR4734: SEtSMsC TESTING OF TYPICAL CONTAINMENT COMPtLATON For Month Of September 1987. PIPtNG PENETRATON SYSTEMS. NUREGICA 2000 V06N10: LKJ.NSEE EVENT REPORT (LER) NUREG/CR 4744 V01 N): LONG TERM EMBRITTLEMENT OF CAST COMPILATON For Month of October 1987. DUPLEX STAINLESS STEELS IN LWR SYSTEMS Sermannual NUREG/CR 2000 V06N11: UCENSEE EVENT REPORT (LER) Report. October 1985 March 1986. COMPILATION.For Month Of November 1987. NUREG/CR4744 V01 N2; LONG-TERM EMBRITTLEMENT OF CAST pg , DUPLEX STAINLESS STEELS IN LWR SYSTEMS.Sernannual NUREG-1214 R02: HISTORICAL DATA

SUMMARY

OF THE SYSTEMAT- NURE C 7 Y N1: LONG TERM EMBRITTLEMENT OF CAST IC ASSESSMENT OF UCENSEE PERFORMANCE. DUPLEX STAINLESS STEELS IN LWR SYSTEMS Sermannual Report. October 1986 March 1987. Uooneing NUREG/CR-4787: CONFERENCE OF RADIATON CONTROL PRO. NUREG/CR-4747 V01: AN AGlNG FAILURE SURVEY OF UGHT WATER REACTOR SAFETY SYSTEMS AND COMPONENTS. GRAM DIRECTORS' INFORMATON FOR UCENSING LOW LEVEL NUREG/CR-4769: RISK EVALUATONS OF AGING PHENOMENA.The RADCACTIVE WASTE INCINERATORS AND COMPACTORS NUREG/CR4856: FEASIBluTY STUDY ON A DATA-BASED SYSTEM Unear Agang Rehautsty Model And its Ex1 ens ons NUREG/CR-4781 DRFT: STUDY OF SEVERE ACCOENT MITIGATION FOR DECISONS REGARDING OCCUPATONAL RADtATION PRO. NURE CR-4813: ASSESSMENT OF LEAK OETECTON SYSTEMS Ught Water Reactor FOR LWRs October 1985 - September 1986. NUREG 1230 DAFT FC: COMPENDIUM OF ECCS RESEARCH FOR RE- NUREG/CR-4824: EVALUATON OF INTEGRAL CONTINUING EXPERI-AUSTIC LOCA ANALYSIS. Draft Report For Com nent MENTAL CAPABluTY (CEC) CONCEPTS FOR UGHT WATER REAC-NUREG/CR-2907 V05: RADIOACTIVE MATERIALS RELEASED FROM TOR RESEARCH PWR SCALING CONCEPTS. NUCLEAR POWER PLANTS. Annual Report 1984. NUREG/CR 4870- AN EVALUATON OF THE EFFECTS OF DESIGN NUREG/CR 3228 V05: STRUCTURAL INTEGRITY OF WATER REAC- DETAILS ON THE CAPACITY OF LWR STEEL CONTAINMENT TOR PRESSURE BOUNDARY COMPONENTS. Annual Report For BUILDINGS. 1986. NUREG/CR4964 UPDATE OF TABLE S-3 NONRADIOLOGCAL ENYl-NUREG/CR-3319 Rot: LWR PRESSURE VESSEL SURVEILLANCE DO- RONMENTAL PARAMETERS FOR A REFERENCE UGHT WATER SIMETRY IMPROVEMENT PROGRAM. LWR Power Reactor Surved- REACTOR Uramum Minrng.MAng And EnnChment lance Physacs-Dosametry Data Base Comperoum. NUREG/GR-3320 V03: LWR PRESSURE VESSEL SURVEILLANCE DO- Umestone SIMETRY IMPROVEMENT PROGRAM. PSF Physacs-Dosanetry Pro- NUREG/CR-5017. UMESTONE CONCRETE AEROSOL EXPERIMENTS

                                                                                            ^

• N /CA 3320 V04: LWR PRESSURE VESSEL SURVEILLANCE DO- p o, p SIMETRY IMPROVEMENT PROGRAM PSF Metallurgy Program.

NUREG/CR 3412 V02: CONTAINMENT INTEGRIT Y Uquid Level Detection NUREGICA-5059 VOID FRACTON MEASUREMENT U000 LEVEL NU E / 34 :T IWA OF W E TAMINATON$ DETECON CONCEM ASSESSVEM AND DEVE@N ON SOUDIFCATON. WASTE DISPOSAL.AND ASSOCIATED OCCU-PATONAL EXPOSURE. Annual Report. Fiscal Year 1986- Uquid Metal Fast Breeder Reactor NUREG/CR4216; EXPERIMENTAL RESULTS FOR A 18-SCALE STEEL NUREG/CR4719 COOLABluTY OF STRATIFIED UO2 DEBRIS IN MODEL NUCLEAR POWER PLANT CONTAINMENT PRESSURIZED SODIUM WITH DOWNWARD HEAT REMOVALThe D13 Experrnent TO FAILURE. NUREG/CR4307 V03: LWR PRESSURE VESSEL ~ SURVEILLANCE DO-SJMETRY IMPROVEMENT PROGRAM 1986 Annual Repod. October

• h*g 8[g*y* SESSMENT OF DESIGN BASIS FOR LOAD-CAR.

RYING CAPACITY OF WELDOVERLAY REPAlRS. NUREG'/CR T ELATONSHIP AND INFLUENCES OF FUEL AND COOLANT SYSTEM PROCESSES DURING LWR SEVERE ACCH DENTS l'*d'"8

• NUREG/CR 3412 V02. CONTAINMENT INTEGRITY NUREG/CR4330 V03: REWEW OF LIGHT WATER REACTOR REGU. PROGRAM Progress Report.Apnl 1983 December 1934 LATORY REQUIREMENTS. Assessment Of Selected Regulatory Re.

Qurements That May Have Margmal importance To Risk Postaccdent ' Sampkng System. Turbane Missdes Combustele Gas Control. Charcoal ( REG R LONG-TERM PERFORMANCE OF HIGH-LEVE L GLASS WASTE FORMS. NU E /CR4469 V04: NONDESTRUCTIVE EXAMINATON (NDE) REU. NUREG/CR-4955; LONG TERM PERFORMANCE OF CONTAINER MA-A81UTY FOR INSERVCE INSPECTION OF UGHT WATER TERIALS FOR HIGH-LEVEL WASTE. REACTORS.Sernannual Report,0ctober 1985 March 1986 NUREG/CR4469 V05: NONDESTRUCTIVE EXAMINATON (NDE) REll-OR N VICE NSPECTON UGHT WATER R CR 4695: MATERIAL CONTROL AND ACCOUNTING (MC&A) EXAMINATION (NDE) REU. LOSS DETECTION DURING TRANSITON PERODS AND PROCESS NUREG/CR4469 V06: NONDESTR T ABluTY FOR INSERVICE INSPECTON OF UGHT WATER UPSET CONDITIONS REACTORS.Sernannual Report. October 1986 March 1987. Loss Of Feedwater NUREG/CR4583 V02- DEVELOPMENT AND VAltDATION OF A REAL. TIME SAFT UT SYSTEM FOR THE INSPECTION OF UGHT WATER NUREG 1286. SAFETY EVALUATON REPORT RELATED TO THE RC REACTOR COMPONENTS Annual Report. October 1984 September START OF RANCHO SECO NUCLEAR GENERATING STATION. UNIT g ggg, 1 FOLLOWING THE EVENT OF DECEMBER 26,1985 Docket No. 50-NUREG/CR4583 V03: DEVELOPMENT AND VAUDAT,0N OF A REAL- 312 (Sacramento Municipal UtMy Distnet) TIME SAFT UT SYSTEM FOR THE INSPECTON OF UGHT WATER n TOR COMPONENT $ Annual Report. October 1985 - September Loss f onta NUREG/CR4616: ROOT CAUSES OF COMPONENT FAILURES TENTIAL BECAUSE OF KNUCKLE BUCKUNG FOR 41 STEEL CON-PROGRAM Methods And Applecatons TAINMENT HEADS. NUREG/CR-4667 V03: ENVIRONMENTALLY ASS lSTED CRACKING IN UGHT WATER REACTORS. Semiannual Report.Apnt September 1986 Loss-Of Coolant Accident NUREG/CR4674 V03: PRECURSORS TO POTENTIAL SEVERE CORE NUREG 1230 DRFT FC COMPENDIUM OF ECCS RESEARCH FOR RE. DAMAGE ACCOENTS.1984 A STATUS REPORT Marn Report And AP- AUSTIC LOCA ANALYSIS Dram Report For Comment perdues A And B NUREG/CR-4799. RELAPS/ MOD 2 ASSESSMENT S:MULATION OF SE-NUREG/CR4674 V04: PRECURSORS TO POTENTIAL SEVERE CORE M. SCALE MOD-2C TEST S NH-3 DAMAGE ACCOENTS 1984.A STATUS REPORT Apperdues C.D And NUREG/CR-4965 TRAC-PF1/ MOD 1 US/ JAPANESE PWR CONSERVA. E. TIVE LOCA PREDOTON

122 Subject Ind:x NUREG/CR-5010. RELAP5/ MOD 2 ASSESSMENT USING SEM! SCALE MELPROG-PWR/MOOI EXPER!MENTS S-NH-1 AND S.LH-2. NUREG/CR 4742: MELPROG-PWR/ MOD 1 ANALYSIS OF A TMLB' AC-Lose-Of Feedwater Transient NUREG/CR 4946: DAVIS-BESSE UNCERTAINTY STUDY. MENU-TACT Low Temperature Toughness NUREG/CR-4722: SOURCE TERM ESilMATON USING MENU TACT. NUREG/CR-4491: DEVELOPMENT OF MODELS FOR WARM PRES-TRESSING. MINTEO NUREG/CR4808. M NTEO USER'S MANUAL Low Upper Sheif Toughness NUREG/CR4711: LOW UPPER-SHELF TOUGHNESS.HIGH-TRANSl- MXS Proprocessor TION TEMPERATURE TEST INSERT IN HSST PTSE 2 VESSEL AND NUREG/CR-4765: MXS CROSS-SECTON PREPROCESSOR USER'S WIDE PLATE TEST SPECIMENS. Final Report MANUAL NUREG/CR-4760 TEST OF 6-IN THCK PRESSURE VESSELS Senes 3 Intermediate Test Vessel V 8A.Teanng Behavior Of Low Upper Shelf Main Steam loolation Valve Matenal. NUREG/CR-4739: RAMONA39 CALCULATIONS FOR BROWNS FERRY ATWS STUDY. Low-Enriched Uranium Fuel NUREG-1282- SAFETY EVALUATION REPORT ON NIGH-URANIUM Mark l CONTENT, LOW-ENRCHED URAN!UM 21RCONIUM HYDRIDE NUREG/CR-4448: SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF FUELS FOR TRIGA REACTORS Docket No. 50163.(GA A GENERAL ELECTRIC BWR3/ MARK l. Case Study. Technologies. incorporated) NUREG/CR-4767: SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF A GENERAL ELECTRIC BWR4/ MARK LCase Study. Low-Level Radioactive Waste Policy Act NUREG 1213 ROI: PLANS AND SCHEDULES FOR IMPLEMENTATON Mark 111 OF U S. NUCLEAR REGULATORY COMMIS$10N RESPONSIBluTIES NUREG/CR-4700 V4 DAF: CONTAINMENT EVENT ANALYSIS FOR

     - UNDER THE LOW-LEVEL RADIOACTIVE WASTE POUCY AMEND-                          POSTULATED SEVERE ACCOENTS: GRAND GULF NUCLEAR MENTS ACT OF 1095 (P.L 99-240)                                              STATION. UNIT 1. Draft For Comment.

NUREG/CP-008'c WiTING WITH STATES ON THE LOW-LEVEL RA. DIOACTIVE WASTE POUCY AMENDMENTS ACT (LLRWPAA) OF Material Control And Accounting 1985. NUREG 1280- STANDARD FORMAT AND CONTENT ACCEPTANCE Low-Level Weste CRITERIA FOR THE MATERIAL CONTROL AND ACCOUNTING (MC&A) REFORM AMENDMENT.10 CFR Part 74 Subpar 1 E NUREG-1274: REVIEW PROCESS FOR LOW LEVEL RADOACTNE WASTE DSPOSAL LCENSE APPUCATON UNDER LOW LEVEL RA- NUREG/CA-4695: MATERIAL CONTROL AND ACCOUNTING (MC&A) DOACTIVE WASTE POLCY AMENDMENTS ACT. LOSS DETECTON DURING TRANSITION PERODS AND PROCESS NUREG/CR-4615 V02- MODEUNG STUDY OF SOLUTE TRANSPORT UPSET CONDaTONS NUREG/CA 5002: METHODS FOR RECURRING LOSS TESTS. N E /C -4 0 2 S FETY A S E T OF ERNATIVES TO NUREG/CR-5003 DESIGN OF A MATERIAL CONTROL AND AC-SHALLOW LAND BURIAL OF LOW LEVEL RADCACTIVE COUNTING SYSTEM TO PROTECT AGAINST CONCEALMENT OF WASTE. Volume 2Envronmental Conditons Affecting Rekatwhty Of En- OfVERSON BY FALSIFCATON AND COLLUSON N /R CONFERENCE OF RADIATON CONTROL PRO- aFauN GRAM DIRECTORS' INFORMATON FOR LCENSING LOW LEVEL NUREG/CR-4852: THE MEERS FAULT: TECTONIC ACTIVITY IN NU E -4 7 L EVEL AS CE TERM NU G/CR 4937 NVES OF THE MEERS FAULT IN SOUTH-EVALUATON. Review of Pubbshed Modehng And Expenmental WESTERN OKLAHOMA. Work.And Presentaten Of Low-LeveJ Waste Source Term Modehng Mett/ Concrete interaction NU E A ADIA EXPOSURES ASSOCl NUREG/CR-4727: SWISS. SUSTAINED HEATED METALUC MELT / CON. ATED WITH ALTERNATIVE METHODS OF LOW LEVEL WASTE DIS. CRETE INTERACTONS WITH OVERLYING WATER POOLS. POSAL NUREGICR-5041 V01: RECOMMENDATONS TO THE NRC FOR MI"9 REVIEW CRITERIA FOR ALTERNATIVE METHODS OF LOW LEVEL NUREG/CA 5028. ON THE MELTING AND REFREEZING OF POROUS RADOACTNF. WASTE DISPOSAL. Task 2a Below4round Vaults. MEDtA. Low-Levst Wasie Disposal Metallurgical Fadure Analysis NUREG/CR-4976 PLANT RH120 SPHERE PROCESSES INFLUENCtNG NUREG/CR-4868: METALLURGICAL EVALUATION OF AN 18-INCH RADONUCUDE MOBlWTY IN SOIL FEEDWATER UNE FAILURE AT THE SURRY UNIT 2 POWER STA-TON. I Low-Level Waste Disposal Facility l NUREG 1199 STANDARD FORMAT AND CONTENT OF A LICENSE Metamurgy APPUCATON FOR A LOW-LEVEL RADCACTIVE WASTE DISPOSAL NUREG/CR 3320 V04: LWR PRESSURE VESSEL SURVEILLANCE 00-NU E 1 . STANDARD REVIEW PLAN FOR THE REVIEW OF A U-CENSE APPUCATON FOR A LOW LEVEL RADOACTNE WASTE Meteorolog' cal CondJtions DISPOSAL FACluTY. NUREG 1293 DRFT FC. QUAUTY ASSURANCE GUIDANCE FOR LOW- NUREG/CR-4950 V02: THE SHOREUNE ENVIRONMENT ATMOS. PHERIC DISPERSON EXPERIMENT (SEADEX) Meteorological And LEVEL RADIOACTNE WASTE DISPOSAL FACILITY. Draft For Com' Gas Tracer Data. mont. NUREG-1300: ENV!AONMENTAL STANDARD REVIEW PLAN FOR THE Meteorological Measurement REVIEW OF A LICENSE APPUCATON FOR A LOW LEVEL RADIO-NUREG/CA 4950 V01: THE SHORELINE ENVIRONMENT ATMOS-NURE / -4918 1 TR WATER INFILTRATION INTO NEE MSM EWNEM (SEAM Eent Descm. NEAR SURFACE LLW DISPOSAL UNITS Annual Report October 1985 September 1966 gic, MELCOR NUREG/CR 4704 V01: RELATIVE BOLOGCAL EFFECTIVENESS tRBE) NUREG/CR-4830- MELCOR VAUDATON AND VERIFICATON 1986 OF FISSON NEUTRONS AND GAMMA RAYS AT OCCUPATIONAL PAPERS EXPOSURE LEVELS Voeume 1. Studies On The Genetsc Effects in Mce Of 60 Equal Once Weekly Exposures To Frsson Neutrons And i MELPROG-PWR/ MODO Gamma Rayt NUREG/CR-4909: MELPROG-PWR/ MODO A MECHANISTO CODE FOR NUREG/CA-4704 V02: RELATIVE BOLOGICAL EFFECTNENESS (RBE) ANALYSJS OF REACTOR CORE MELT PROGRESSON AND VESSEL OF FtSSON NEUTRONS AND GAMMA RAYS AT OCCUPATIONAL A* TACK UNDER SEVERE ACCOENT CONDITONS. EXPOSURE LEVELS. Volume 11. StuGes On The Effects Of 60 Equal 7 - __-- _, , _ . _ . . _ v _ ,

Subject index 123 Once Weeuy Exposures To Fission Neutrons And Gamma Rays On Nephrotoxicity Survival Of Mce. NUREG/CR4951: NEPHROTOXICITY OF URANYL FLOORCE AND RE. VERSIBluTY OF RENAL INJURY IN THE RAT. NUREG/CR-4781 DRFT: STUDY OF SEVERE ACCIDENT MITIGATION New Madrid SYSTEMS. NUREG/CR4936: AN INTEGRATED GEOLOGICALGEOPHYSOAL.AND NUREG/CR-5007: PREDCTON AND MITIGATION OF EROSIVE-COR* GEOCHEMOAL INVESTIGATION OF THE MAJOR FRACTURES ON ROSIVE WEAR IN SECONDARY PIPING SYSTEMS OF NUCLEAR THE EAST SOE OF THE NEW MADRID EARTHOUAKE ZONE. POWER PLANTS. Noise Detection NUREG/CR-4822: BROAD BAND SEISMO DATA ANALYSIS September R G/ -4730. EVALUATION OF POTENTIAL MIXED WASTES CON. 464 September 1986. TAINtNG LEAD, CHROMIUM,USED OIL,OR ORGANO UQUIDS. NondestrucM Exarninabon Mixed 4mide Conversion Faculties NUREG/CR-4773 DES GN FEATURES TO FACIUTATE INTERNATION. NUREG 1194: CONSTRUCTON APPRAISAL TEAM INSPECTON RE-AL SAFEGUARDS AT MIXED-OXIDE CONVERSON FACTUTIES. SULTS ON WELDING AND NONDESTRUCTIVE EXAMINATON AC. TMTIES. Model Evaluation NUREG/CR4469 V04: NONDESTRUCTIVE EXAMINATION (NDE) REU-NUREG/CR-4820: COMPARISON OF THE 1982 SEADEX DISPERSION A8tUTY FOR INSERVICE INSPECTON OF UGHT WATER DATA WITH RESULTS FROM A NUMBER OF DFFERENT MODELS. REACTORS Serniannual Report. October 1985. March 1986. NUREG/CR-4469 V05: NONDESTRUCTIVE EXAMINATION (NDE) REU-Monitoring ABluTY FOR INSERVICE INSPECTON OF UGHT WATER NUREG-1243: GROUND. WATER PROTECTION ACTMTIES OF THE REACTORS Semiannual Report ApnLSeptember 1988. U.S. NUCLEAR REGULATORY COMMISSON. NUREG/CR-4469 V06: NONDESTRUCTIVE EXAMINATON (NDE) REU-ABluTY FOR INSERVICE INSPECTON OF LIGHT WATER MulthAttribute Utility Decomposition REACTORS. Semiannual Report, October 1986 March 1987 NUREG/CR 4016 V02: APPUCATON OF SUM-MAUDA TEST OF AN NUREG/CR-4583 V02- DEVELOPMENT AND VAUDATON OF A REAL. INTERACTIVE COMPUTER-BASED METHOO FOR ORGANIZING TIME SAFT-UT SYSTEM FOR THE INSPECTION OF UGHT WATER EXPERT ASSESSMENT OF HUMAN PERFORMANCE AND REACTOR COMPONENTS Annual Report,0ctober 1984 September REUABluTY. Volume llAppendces- 1985. NUREG/CR4583 V03: DEVELOPMENT AND VAUDATON OF A REAL-NDE TIME SAFT-UT SYSTEM FOR THE INSPECTON OF LIGHT WATER NUREG-1194: CONSTRUCTION APPRAISAL TEAM INSPECTON RE- REACTOR COMPONENTSAnnual Report,0ctober 1985 September SULTS ON WELDING AND NONCESTRUCTIVE EXAMINATION AC- 1986. TMTIES. NDE Relisbuity Nuclear Fuel Cycle NOREG/CR4469 V04: NONDESTRUCTIVE EXAMINATON (NDE) REU. NUREG-0332: POTENTIAL HEALTH AND ENVIRONMENTAL IMPACTS ABluTY FOR INSERVICE INSPECTION OF UGHT WATER ATTRIBUTABLE TO THE NUCLEAR AND COAL FUEL CYCLES Foal REACTORS. Semiannual Repor10ciober 1985. March 1986. Report. NUREG/CR-4469 V05: NONDESTRUCTIVE EXAMINATION (NDE) REL1-A81UTY FOR INSERYlCE INSPECTON OF LIGHT WATER Nuclear Plant Modthcauon REACTORS. Semiannual Report, April Septenter 1986_ NUREG/CR4921: ENGINEERING AND OUALITY ASSURANCE COST NUREG/CR-4469 V06: NONDESTRUCTIVE EXAM NATON (NDE) REu. FACTORS ASSOCIATED WITH NUCLEAR PLANT MODIFICATION ABILITY FOR INSERVICE INSPECTION OF UGHT WATER Nuclea Re tor S REACTORS Semiannual Report, October 1986 March 1987. NEFTRAN COMPANY NUCLEAR REACTOR STUDY ("REED REPORT"). NUREGICR-4766: USER'S MANUAL FOR THE NEFTRAN COMPUTER CODE. Nuclear Regulatory Legislation NUREG 0980 R03. NUCLEAR REGULATORY LEGISLATION. NEORISK NUREG/CR-4903 V02: SELECTON OF EARTHOUAKE RESISTANT Nuclear Safety Pliot Plant DESIGN CRITERIA FOR NUCLEAR POWER PLANTS METHOOOLO. NUREG/CR-4798. IRON OXCE AEROSOL EXPERIMENTS IN STEAM. GY AND TECHNOAL CASES. Methods For introduction Of Geological AIR ATMOSPHERES NSPP TESTS 501505 AND $11. DATA RECORD Data into Charactenzation Of Actrve Faults And Sersmicity And REPORT. I NESDip Nuclear Waste Glass l NUREG/CR4886: ANALYSIS OF THE NESDiP2 AND NESOP3 RADtAL NUREG/CR4842: A STUDY OF NATURAL GLASS ANALOGUES AS SHIELD AND CAVITY EXPERIMENTS. APPUED TO ALTERATION OF NUCLEAR WASTE GLASS. NESTOR ONSITE/ MAX 11 NUREG/CR4886: ANALYSIS OF THE NESDP2 AND NESDP3 RADIAL NUREG/CR 3620 S02: INTRUDER DOSE PATHWAY ANALYSIS FOR SHIELD AND CAVITY EXPERIMENTS. THE ONSITE DISPOSAL OF RADCACTIVE WASTES The ONSITE/ NRCPIPE NUREG/CR4853: APPROX 1 MATE METHODS FOR FRACTURE ANALY* OccupaUonal Dose SES OF THROUGH WALL CRACKED PIPES- NUREG/CR-3469 V03: OCCUPATIONAL DOSE REDUCTON AT NU-CLEAR POWER PLANTS. Annotated Behography Of Selected Read-National Env6ronmental Policy Act s in Radiation Protection And ALARA. NUREG 1300- ENVIRONVENTAL STANDARD REVIEW PLAN FOR THE NUhEG/CR4409 V02: DATA BASE ON NUCLEAR POWER PLANT REVIEW OF A UCENSE APPUCATON FOR A LOW LEVEL RADC- DOSE REDUCTON RESEARCH PROJECTS. ACTIVE WASTE DISPOSAL FACILITY. Occupational Eaposure 2: MELPROG-PWR/ MOD 1 ANALYSIS OF A TMLB' AC. NUREG/CR 3444 V04. THE IMPACT OF LWR DECONTAMiNATONS RE ON SOUDFICATON. WASTE DISPOSAL,AND ASSOCIATLD OCCV-CIDENT SEOVENCE PATONAL EXPOSURE Annual Report Fiscal Year 1986 NUREG/CR4788: AN ' ANALYTICAL AND EXPERIMENTAL INVESTIGA. TlON OF NATURAL CIRCULATON TRANSIENTS IN A MODEL PRES. NUREG/CR-4704 V01: RELATIVE BOLOGICAL EFFECTIVENESS (RBE) SURt2ED WATER REACTOR. OF FISSON NEUTRONS AND GAMMA RAYS AT OCCUPATONAL NUREG/CR-4789. THE SIMULATON OF THERMOHYDRAUUC PHE. EXPOSURE LEVELS volume 1. Studies On The Genetic Effects in NOMENA IN A PRESSURIZED WATER REACTOR PRIMARY LOOP. M*ce Of 60 EcNal Once-Wee 4@ Exposures To Fasson Neutrons And Gamma Rays. Naluel Glate Analogues NUREG/CR-4704 V02. RELATlVE BOLOGICAL EFFECTIVENESS (ABE) NUREG/CR4842: A STUDY OF NATURAL GLASS ANALOGUES AS OF FISSON NEUTRONS AND GAMMA RAYS AT OCCUPATIONAL APPUED TO ALTERATON OF NUCLEAR WASTE GLASS. EXPOSURE LEVELS Volume 11. Studies On The Efiocts Of 60 Equal

124 Subject index Once Weepy Exposures To Fisson Neutrons And Gamma Rays On Operator Ucensing Eneminer Sundval Of Mee. NUREG-1021 Rod. OPERATOR UCENSING EXAMINER STANDAROS. NUREG/CR4938: OCCUPATONAL RADATON EXPOSURES ASSOCI-ATED WITH ALTERNATNE METHOOS OF LOW LEVEL WASTE DS. Ore Body POSAL NUREG/CR 5060: AN APPROACH TO THE MATHEMATICAL MODEL-NUREG/CR 5035: OATA BASE OF SYSTEM AVERAGE DOSE RATES UNG OF THE URANIUM SERIES REDtSTRIBUTON WITHIN ORE AT NUCLEAR POWER PLANTS. Final Report. BODES. Occupational Radletion Organization Chart NUREG/CR4485 V02 THE IMPACT OF FUEL CLADOING FAILURE EVENTS ON OCCUPATONAL RAOLATON EXPOSURES AT NUCLE

• NUREG-0325 R10 U S. NUCLEAR REGULATORY COMMISSON FUNC-AR POWER PLANTS Case StudyPWR Dun'ng An Outage. TIONAL ORGANtZATION CHARTS.

NUREG/CR-4856: FEASJBluTY STUOY ON A DATA-BASED SYSTEM Ownersh6p FOR DECISONS REGARD (NG OCCUPATONAL RADIATON PRO. NUREG-0327 R04: OWNERS OF NUCLEAR POWER N E CA 9 PATONAL RADATION EXPOSURES ASSOCl- PLANTS Percentage OwnersNp Of Commercial Nuclear Power Plants ATED WITH ALTERNATIVE METHOOS OF LOW LEVEL WASTE DIS- By UtAty Companes. POSAL Oxidation Off-Normal Event NUREG/CR4866. AN ASSESSMENT OF HYDROGEN GENERATON NUREG 1291: BWR AND PWR OFF NORMAL EVENT DESCRIPTONS. FOR THE P8F SEVERE FUEL DAMAGE SCOPING AND 11 TESTS. Offelte Emergency Plan Oxide NUREG 0654 Sol RO1: CRITERIA FOR PREPARATON AND EVALUA. NUREG/CR 4865: THE SOLU 81UTY OF ELECTRODEPOSITED TC(IV) TON OF RADIOLOGICAL EMERGENCY RESPONSE PLANS AND OXtDES. PREPAREDNESS IN SUPPORT OF NUCLEAR POWER PLANTS Cntena For UtAty Offsste Plannsng And Preparedness Draft NAG 5007: PREDICTON AND MITIGATON OF EROSfVE-COR-ROSlVE WEAR IN SECONDARY PIPING SYSTEMS OF NUCLEAR Oneate bleposal POWER PLANTS. NUREG 1101 V02: ONSITE DSPOSAL OF RADCACTIVE WASTE. Methodology For The Radiologcal Assessment Of Deposal By Othe Growth Rate Subsurface Bunal. NUREG/CR4889. ZlRCALOY4 OXtDATON AT 1300 TO 2400 DE. GREES C. Onette Radioactive Waste D6eposal NUREG/CR-4890- HEAT OF REACTON OF MOLTEN ZlRCONIUM NUREG/CR 3620 SO2. INTRUDER DOSE PATHWAY ANALYSIS FOR WITH UO2. THE ONSITE DISPOSAL OF RADOACTIVE WASTES.The ONSITE/ MAX 11 Computer Program. PlFRAC NUREG/CR4834: A USER'S GUlOE TO THE NRC'S PIPING FRAC-Oper@ycle Water System TURE MECHANICS DATA BASE (PtFRAC). NUREG/CR4626 V02: IMPROVING THE REUABILITY OF OPEN-CYCLE WATER SYSTEMS. Appheation Of Biofouhng Survedlance And PISC lli Control Technwes To Sediment And Corrosson Fouhng At Nuclear NUREG/CR-4970: STAINLESS STEEL ROUND ROBIN Power Plants. TEST.Contnfugally Cast Stainless Steet Screening Phase. Operating Emperience POSTCON NUREG-1272. REPORT TO THE U.S. NUCLEAR REGULATORY COM- NUREG/CR4887: POSTCON A POSTPROCESSOR AND UNIT CON-MISSON ON ANALYSIS AND EVALUATON OF OPERATONAL VERSON PROGRAM FOR THE CONTAIN COMPUTER CODE. DATA .1986 NUREG/CR4692 OPERATING EXFTRIENCE REVIEW OF FAILURES PRA OF POWER OPERATED RELIEF VALVES AND BLOCK VALVES IN NUREG/CR 3495: CALCULATION OF FAILURE IMPORTANCE MEAS-NUCLEAR POWER PLANTS. URES FOR BASIC EVENTS AND PLANT SYSTEMS IN NUCLEAR NUREG/CR4819 V01: AGtNG AND SERVICE WEAR OF SOLENOID- POWER PLANTS. OPERATED VALVES USED IN SAFETY SYSTEMS OF NUCLEAR NUREG/CR 4405. PROBABlUSTIC RISK ASSESSMENT (PRA) IN-POWER PLANTSVolume 1. Operating Exponence And Fadure identfi- SIGHTS catiort NUREG/CR-5006. PRA APPLICATON PROGRAM FOR INSPECTON Operating Expertence Feedback NUREG-1275: OPERATING EXPERIENCE FEEDBACK REPORT . NEW PWR PLANTS Commercial Power Reactors NUREG 1122 SO1: KNOWLEDGES ANO ABluTIES CATALOG FOR NU. NUREG-1275 YO2: OPERATING EXPER:ENCE FEED 8ACK REPORT - CLEAR POWER PtANT OPERATORS Pressunzed Water Reactors. AIR SYSTEMS PROBLEMS. Commercial Power Reactors-NUREG 1291: 8WR AND PWR OFF NORMAL EVENT DESCRIPTIONS. j OP*reting Procedures NUREG/CR 3231: PIPE.TO-PIPE IMPACT PROGRAM. i NUREG/CR 3495: CALCULATON OF FAILURE IMPORTANCE MEAS. NUREG/CR 3968. STUDY OF OPERATING PROCEDURES IN NUCLE-AR POWER PLANTS. Practices And Problems- URES FOR BASIC EVENTS AND PLANT SYSTEMS IN NUCLEAR POWER PLANTS NUREG/CR4613. EVALUATON OF NUCLEAR POWER PLANT OPER. NUREG/CR4458: SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF N FACES. s echnique or L E2 W N N m W R M C M u 3 Operational Event NUR /CR4485 V02: THE IMPACT OF FUEL CLADO 4NG FAILURE NUREG/CR4674 V03: PRECURSORS TO POTENTIAL SEVERE CORE EVENTS ON OCCUPATONAL RADIATON EXPOSURES AT NUCLE-DAMAGE ACCIDENTS:1984 A STATUS REPORT Man Report And Ap-

           "                                                         NURE C 55 VI                   DRY:     L  ION     SE E E ACCIDENT NU       /CR4     V04: PRECURSORS TO POTENTIAL SEVERE CORE             RISKS AND THE POTENTIAL FOR RISK REDUCTION SURRY DAMAGE ACCCENTS.1984,A STATUS REPORT.Appendues C.O And                   E,R S                 N 1 Dr     or g

RISKS AND THE POTENTIAL FOR RISK REDUCTION SEQUOYAH Operator Error POWER STATION. UNIT 1.DraN For CcmTent NUREG/CR4910 RELAY CHATTER AND OPERATOR RESPONSE NUREG/CR4672: ANALYSIS OF INSTRUMENT TUBE RUPTURES IN AFTER A LARGE EARTHOUAKE An improved PRA Methodology W4h WESTINGHOUSE 4 LOOP PRESSURIZEO WATER REACTORS. Caw Studies. NUREG/CR4700 V1 DRF: CONTAINMENT EVENT ANAliSIS FOR POSTULATED SEVERE ACCOENTS: SURRY POWER STATON UNIT Operator Ucense 1.DraN For Comment. NUREG-1262. ANSWERS TO OVEF NS AT PUBLIC MEETINGS RE- NUREG/CR4700 V2 DRF: CONTAINMENT EVENT ANALYSIS FOR GARDING IMPLEMENTA10N OF TITLE 10. CODE OF FEDERAL POSTULATED SEVERE ACCOENTS: SEQUOYAH POWER REGULATONS.PART $5 ON OPERATORS' UCENSES, STATION UNIT 1.DraN Reoort For Comment

Subject Index 125 NUREG/CR-4710: SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF P9ot Program A COMBUSTION ENGINEERING PRESSURIZED WATEA NUREG-1210 V01: PILOT PROGRAM.NRC SEVERE REACTOR ACCI-REACTOR Case Study DENT INCOENT RESPONSE TRAINING MANUALOvennew And Sum-NUREG/CR-4713: SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF mary Of Major Points. A BABCOCK AND W1LCOX PRESSURIZED WHER REACTOR. Case NUREG 1210 V02: PILOT PROGRAM NRC SEVERE REACTOR ACCl-NUR /CR.4752: COfNCOENT STEAM GENERATOR TUBE RUPTURE nt AND STUCK OPEf 4 SAFETY RELIEF VALVE CARRYOVER NUREG-1210 V03: PILOT PROGRAM.NRC SEVERE REACTOR ACO-

                                                                                                                        * *D ^**

N GCU A E ON ET FFS 1 e,n , h i PRESSURIZED WATER REACTOR FOR ASSESSING THE SAFETY NUREG-1210 V04: PILOT PROGRAM'NRC SEVERE REACTOR ACCl-DENT INCIDENT RESPONSE TRAINtNG MANUAL.P@lic Protective N CR4 6 H DOW OE Y AT REMOVAL ANALYSIS OF A WESTINGHOUSE 3 LOOP PRESSURIZED WATER REACTOR. Case NUR 21 5 T PROGRAM SEVEbE REACTOR ACO-NUR /CR-4788: AN ANALYTICAL ANO EXPERIMENTAL INVESTIGA- DENT INCIDENT RESPONSE TRAINING MANUALU.S. Nuclear Regu-latory Comrrussmon Response. TON OF NATURAL CIRCULATON TRANSlENTS IN A MODEL PRES-SURIZED WATER REACTOR. P6pe Break EN N PRESS I D TE EACTO R ARY L NUREG/CR4407: PIPE BREAK FREQUENCY ESTIMATON FOR NU-NUREG/CR4817: CDINE PARTITON COEFFICIENT MEASUREMENTS CLEAR POWER PLANTS. A 5 MULATED PWR STEAM GENERATOR CONDITIONS.Intenm NUREG/ 843 V01: UNfVERSITY OF MARYLAND AT COLLEGE NUREG/CR 3231: PIPE TO-PIPE IMPACT PROGRAM. PARK (UMCP) 2X4 LOOP TEST FACILITY. Annual Report For 1985. NUREG/CR 5014: PARAMETRC STUDY OF PIPE WHIP ANALYS1$. NUREG/CR4845: AN ANALYSIS OF THE SEMISCALE MOO-2C S-NH-3 Pipe To-Pipe impact TEST USING THE TRAC.PF1 COMPUTER PROGRAM. NUREG/CR4863: SURFACE SPECTROSCOPY OF PRESSURE NUREG/CR 3231: PIPE TO PIPE IMPACT PROGRAM. VESSEL STEEL FATIGUE FRACTURE SURFACE FILMS FORMED IN PWR ENVIRONMENTS. W NUREG/CR-4945:

SUMMARY

OF THE SEMISCALE PROGRAM (1965- NUREG/CR4724: FATGUE CRACK GROWTH RATES IN PRESSURE 1986). VESSEL AND PiPtNG STEELS IN LWR ENVIRONMENTS. Final Report. NUREG/CR4965: TRAC PF1/ MOO 1 US/ JAPANESE PWR CONSERVA- NUREG/CR4943: PREPARATION OF DESIGN SPECIFCATIONS AND TrVE LOCA PREDCTON DESIGN REPORTS FOR PUMPS. VALVES PIPING.AND PIPING SUP. NUREG/lA 0004: THERMAL MIXING TESTS IN A SEMIANNULAR PORTS USED IN SAFETY RELATED PORTIONS OF NUCLEAR DOWNCOMER WITH INTERACTING FLOWS FROM COLD LEGS. POWER PLANTS. Pettern Recognition Piping Frecture Mechardce Data Base NUREG/CR-4577: AUTOMATED LONG-TERM SURVEllt.ANCE OF A NUREG/CR4894. A USSR'S GUiOE TO THE NRC'S PIPtNG FRAC-COMMERCIAL NUCLEAR POWER PLANT. TURE MECHANICS DATA BASE (PIFRAC). Penetret6on Fremang Piping SuppM NUREG/CR4892- A STUOY OF THE EFFECTS OF PENETRATON NUREG/CR 4943. PREPARATION OF DESIGN SPECIFCATONS AND FRAMING ON STEEL CONTAJNVENT BUCKLNG CAPACITY. DESIGN REPORTS FOR PUMPS, VALVES, PIPING.AND PIPING SUP-Percentage Ownerstep PORTS USED IN SAFETY-RELATED PORTONS OF NI) CLEAR POWER PLANTE, NUREG4327 R04. OWNERS OF >

                                                  .OtEAR    POWER PLANTS Percentage Ownersrup Of Commercial Nuclear Power Ptants By M Companes.                                                         EG         4859 SEISMC FRAGILITY TEST OF A 6-INCH OtAMETER Performance History                                                     PIF2 SYSTEM.

NUREG 1214 R02 HISTORCAL DATA

SUMMARY

OF iHE SYSTEMAT. NUREG/CA 5007; PREDCTON AND MITCATON OF EROSIVE 40R-C ASSESSMENT OF LCENSEE PERFORMANCE. ROSlVE WEAR IN SECONDARY PIPING SYSTEMS OF NUCLEAR POWER PLANTS. Performance incentive NUREG-1256 V01: INCENTIVE REGULATON OF NUCLEAR POWER Plant Analyzer PLANTS BY STATE PUBLIC UTILITY COMMISSIONS. NUREG/CR 5011: APPLCATON OF THE ADAPTIVE-PREDICTIVE CONTROLLERS TO PLANT SAFETY SURVEILLANCE UTILIZING ON-Performance Modelin9 LINE PLANT ANALYZER. NUREG/CR4956: SYSTEM PERFORMANCE OF HIGH-LEVEL WASTE PACKAGE COMPONENTS. Plant RNzoophere Process NUREG/CR 4976: PLANT RH120 SPHERE PROCESSES INFLUENCING V CR-495 PERFORMANCE TESTING OF EXTREMlTY 00S3 METERS- Plastic Zone NUREG/CR-4491: DEVELOPMENT OF MODELS FOR WARM PRES-E'""' N TRESSING' NUREG/CR4541: EXPERIMENTAL ASSESSMENT OF THE SEALING EFFECTIVENESS OF ROCK FRACTURE GROUTING Poincy And Planning Guidance Petitione For Rulemaking NUREG4885106: U S. NUCLEAR REGULATORY COMMiSSON POLOY NUREG-0936 V05 NO3. NRC REGU:.ATORY AGENDA.Quarterty AND PLANNING GUlOANCE 1987. NUR YO N04 NRC REGULATORY AGENDAOuarterty Polymer Base Material Amocth Decemhr 1986 NUREG/CR-4530 V02: U.S1 FRENCH JOINT RESEARCH PROGRAM NUREG4936 YO6 NOI: NRC REGU ATORY AGENDA.Ovarterty REGARDING THE BEHAVIOR OF POLYMER BASE MATERIALS SUB-Report Je March 1987. JECTED TO BETA RADIATION. Volume 2. Phase 2a Screerung Tests. NUREG4936 NO2. NRC REGULATORY AGENDAOuarterty Report.Apn't June 1987. Population NUREG4936 V06 NO3. NRC REGULATORY AGENDA Ouartery NUREG/CR-2650 V05: POPULATION DOSE COMMITMENTS OUE TO Report.Jufy September 1987- RADCACTIVE RELEASES FROM NUCLEAR POWER PLANT SITES IN 1983. Phyelce-Doelmetry NUREG/CR 3319 RO1: LWR PRESSUAE VESSEL SURVEILLANCE DO- Porous Med6a SfMETRY IMPROVEMENT PROGRAM LWR Power Reactor Surve+ NUREG/CR 5028. ON THE MELTING AND REFREEZING OF POROUS lance Physics-Cowmetry Data Base Compendium MEDIA.

126 Subject index Poeteccident Sampling System NUREG/CR-4990: HEAVY SECTION STEEL TECHNOLOGY NUREG/CR-4330 V03: REVIEW OF LIGHT WATER REACTOR REGU- PROGRAM Five Year Plan.FY 1986 1990. LATORY REQUIREMENTS. Assessment Of Selected Regulatory Re-ourements That May Have Marginal importance To RisitPostaccident Presourtzed Containment Samphng System, Turtune Missdes, Combustible Gas Control, Charcoal NUREG/CR-4216: EXPERIMENTAL RESULTS FOR A 18-SCALE STEEL Fitters. MODEL NUCLEAR POWER PLANT CONTAINMENT PRESSURIZED TO FAILURE. Power Operated Reelef Vehre NUREG/CR-4692: OPERATING EXPERIENCE REVIEW OF FAILURES Presourtzed Release OF POWER OPERATED REUEF VALVES AND BLOCK VALVES IN NUREG/CR-4779: NEW DATA FOR AEROSOLS GENERATED BY RE-NUCLEAR POWER PLANTS. LEASES OF PRESSURl2ED POWDERS AND SOLUTIONS IN STATIC

                                                                                         ^

Practice And Procedure Digeet NUREG-0386 004 R04: UNITED STATES NUCLEAR REGULATORY Presourtmed Thermal Shock COMMISSON STAFF PRACTCE AND PROCEDURE D6GESTJuly NUREG/CR4491: DEVELOPMENT OF MODELS FOR WARM PRES-1972. June 1966. TRESSING NUREG 0386 004 R05: UNITED STATES NUCLEAR REGULATORY NUREG/CR-4711: LOW UPPER SHELF TOUGHNESS.HIGH-TRANS-COMMISSON STAFF PRACTCE AND PROCEDURE DIGESTJuPy TON TEMPERATURE TEST INSERT IN HSST PTSE 2 VESSEL AND WIDE. PLATE TEST SPECIMENS. Final Report NU 4386 UNITED STATES NUCLEAR REGULATORY NUREG/CR-4841: FRACTURE EVALUATION OF SURFACE CRACKS COMMISSON STAFF PRACTCE AND PROCEDURE DIGESTJuty EMBEDDED IN REACTOR VESSEL CLADDING.Untra$ated Bend 1972 Dec 1986. Spece Results. Precioeure System NUREG/lA4004: THERMAL MIXING TESTS IN A SEMIANNULAR NUREG/CR4846: HIGH-LEVEL WASTE PRECLOSURE SYSTEMS DOWNCOMER WITH INTERACTING FLOWS FROM COLD LEGS. SAFETY ANALYSIS Phase 2, Final RepM Pressurtzed Water Reactor Pressure NUREG 1122 S01: KNOWLEDGES AND ABluTIES CATALOG FOR NU. NUREG/CR-4913: ROUND-ROBIN PRETEST ANALYSES OF A 1.6 CLEAR POWER PLANT OPERATORS Pressunzed Water Reactors. SCALE REINFORCED CONCRETE CONTAINMENT MODEL SUBJECT NUREG 1291: BWR AND PWR OFF-NORMAL EVENT DESCRtPTONS. TO STATC INTERNAL PRESSURIZATION. NUREG/CR 3231: PIPE TC PtPE IMPACT PROGRAM. NUREG/CR-3495: CALCULATON OF FAILURE IMPORTANCE MEAS-Proeeure Boundary URES FOR BASIC EVENTS AND PLANT SYSTEMS IN NUCLEAR NUREG/CR-3228 V05: STRUCTURAL INTEGRITY OF WATER REAC- FOWER PLANTS. TOR PRESSURE BOUNDARY COMPONENTS. Annual Report For NUREG/CR-4458: SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF 1966. A WESTINGHOUSE 2-LOOP PRESSURIZED WATER REACTOR Case NUREG/CR4300 V03 N2- ACOUSTIC EMISSON/ FLAW RELATON. Study. SHIP FOR INSERVICE MON'TORING OF NUCLEAR PRESSURE NUREG/CR4485 V02- THE IMPACT OF FUEL CLADDING FAILURE VESSELS ess Rept, April Reptember 1986. EVENTS ON OCCUPATIONAL RADIATON EXPOSURES AT NUCLE-NUREG/CR-4 V04 N1: ACOJSTIC FMISSON/ FLAW RELATION. AR POWER PLANTS. Case Study PWR Dunng An Outage. SHIP FOR IN-SERVCE MONf'CRING OF NUCLEAR PRESSURE NUREG/CR-4551 V1 DRF; EVALUATON OF SEVERE ACCIDENT VESSELS Progress Report, October 1986 March 1967. RISKS AND THE POTENTIAL FOR RISK REDUCTON SURRY POWER STATON UNIT 1. Draft For Comment Presoure i, _ _ _ - . Pool NUREG/CR-4551 V2 DRF: EVALUATON OF SEVERE ACCIDENT NUREG4800 06 5 5 R0: STANDARD REVIEW PLAN FOR THE REVIEW RISKS AND THE POTENTIAL FOR RISK REDUCTON SEQUOYAH OF SAFETY ANALYSIS REPORTS FOR NUCLEAR POWER POWER STATON. UNIT 1 Draft For Comment PLANTS LWR Edtion. Proposed Revisaon 0 To New SRP Section 6.5 5 NUREG/CA-4672: ANALYSIS OF INSTRUMENT TUBE RUPTURES IN

• Pressure Suppressson Pools As Fission Product Oean-Up Systems." WESTINGHOUSE 4-LOOP PRESSURIZED WATER REACTORS.

For Comment. NUREG/CR4700 V1 DAF: CONTAINMENT EVENT ANALYSJS FOR POSTULATED SEVERE ACCIDENTS: SURRY POWER STATION. UNIT 1 Proseure V M 1. Draft For Comment NUREG/CR-3319 R01: LWR PRESSURE VESSEL SURVEILLANCE DO. NUREG/CR4700 V2 DRF: CONTAINMENT EVENT ANALYSS FOR SIMETRY IMPROVEMENT PROGRAM. LWR Power Reactor Surve4* POSTULATED SEVERE ACODENTS: SEQUOYAH POWER lance Physes Dosimetry Data Base Compendium. STATON. UNIT 1. Ora 9 Report For Comment. NUREG/m 3320 V03: LWR PRESSURE VESSEL SURVEILLANCE DO- NUREG/CR-4710. SHUTDOWN DECAY HEAT REMOVAL ANALYS(S OF SMETRY IMPROVEMENT PROGRAM. PSF Physacs-Dosametry Pro. A COMBUSTON ENGINEERING PRESSURIZED WATER N[P /CR 3320 V04: LWR PRESSURE VESSEL SURVEILLANCE 00- NURhCR DOWN DECAY HEAT REMOVAL ANALYSS OF

                                                                                         ^ ^                                                         ***

NUR C 2 V03 N EAVY CION T NOLOGY PROGRAM Semnannual Progress Report For Apnt-September 1986- NUR /CR-4752- COINCIDENT STEAM GENERATOR TUBE RUPTURE NOREG/CR-4219 V04 N1: HEAVY SECTON STEEL TECHNOLOGY AND STUCK OPEN SAFETY REUEF VALVE CARRYOVER PROGRAM Sermannual Progress Report For October 1966 Ma ch TESTS MB 2 Steam Generator Trans,ent Response Test Program. NUREG/CR4758. A RETRAN MODEL OF THE CALVERT CLIFFS 1 N G/CR4300 V04 N1: ACOUSTO EMISSON/ FLAW RELATON- PRESSURIZED WATER REACTOR FOR ASSESSING THE SAFETY SHIP FOR IN-SERVICE MONITORING OF NUCLEAR PRESSURE NU E 4 P ESSU VESSE EILLANCE DO-N' 6 SH D Y EAT REMOVAL ANALYSS OF SIMETRY IMPROVEMENT PROGRAM.1986 Annual Report,0ctobe, A WESTINGHOUSE 3-LOOP PRESSURIZED WATER REACTOR Case NUR /CR-4788- AN ANALYTICAL AND EXPERIMENTAL INVESTIGA-NURE /CR L UPPER-SHELF TOUGHNESS.HIGH-TRANSI-TION TEMPERATURE TEST INSERT IN HSST PTSE 2 VESSEL AND TON OF NATURAL CIRCULATON TRANSENTS IN A MODEL PRES-W10E-PLATE TEST SPECIMENS. Final Report SUR12ED WATER REACTOR. NUREG/CR-4724: FATIGUE CRACK GROWTH RATES IN PRESSURE NUREG/CR-4789 THE SMULATON OF THERMOHYDRAULC PHE. VESSEL AND PIPING STEELS IN LWR ENVIRONMENTS Final Report NOMENA IN A PRESSURIZED WATER REACTOR PR: MARY LOOP. NUREG/CR4760 TEST OF 6-IN,THCK PRESSURE VESSELS Senes NUREG/CR 4817; COtNE PARTITION COEFFCIENT MEASUREMENTS 3 Intermedate Test Vessel V 8A.Teanng Behavior Of Low Upper Shelf AT SMULATED PWR STEAM GENERATOR CONDITONSIntenm Matenal. Data Report NUREG/CR 4860 FLAW DENSITY EXAMINATONS OF A CLAD BO(L. NUREG/CR4843 V01: UNfVER$1TY OF MARYLAND AT COLLEGE ING WATER REACTOR PRESSURE VESSEL SEGMENT. PARK (UMCP) 2x4 LOOP TEST FACluTY Annual Report For 1985 NUREG/CR4863: SURFACE SPECTROSCOPY OF PRESSURE NUREG/CR-4845. AN ANALYSIS OF THE SEMISCALE MOOL2C S-NH-3 VESSEL STEEL FATIGUE FRACTURE SURFACE FILMS FORVED ;N TEST USING THE TRAC.PF1 COMPUTER PROGRAM PWR ENVIRONMENTS. NUREG/CR4863 SURFACE SPECTROSCOPY OF PRESSURE NUAEG/CR4886. ANALYSIS OF THE NESDiP2 AND NESDIP3 RADIAL VESSEL STEEL FATIGUE FRACTURE SURFACE FILMS FORMED IN SHIELD AND CAVITY EXPERIMENTS. PWR ENVIRONMENTS

Subject IndCx 127 NUREG/CR-4945:

SUMMARY

OF THE SEMISCALE PROGRAM (1965- Probabillotic Safety Aseeeement 1906). NUREG/CR-4552: A REVIEW OF THE SEABROOK STATION PROBABI-NUREG/CR 4965: TRAC-PF1/ MOO 1 US/JAPANESF PWR CONSERVA. USTC SAFETY ASSESSMENT.Contarvnent Fe4ure Modes And Radi-NI G 0004 R AL MIXING TESTS IN A SEMIANNULAR DOWNCOMER WITH INTERACTING FLOWS FROM COLD LEGS- Procedure Closelfication NUREGICR-4613: EVALUATION OF NUCLEAR POWER PLANT OPER. RE LA OF ANALYS!S OF REGULATORY GUIDE ATING PROCEDURES CLASSlFCATONS AND CR-4 1.35 (REVISION 3, DRAFT 2) IN SERVICE INSPECTON OF UN- INTERFACES. Problems And Tectnques For improvement. GROUTED TENDONS IN PRESTRESSED CONCRETE CONTAIN. Procedure inMece MENTS, NUREG/CR-4613: EVALUATON OF NUCLEAR POWER PLANT OPER-Prkrttination ATING PROCEDURES CLASSIFCATONS AND NUREG-0933 S06: A PRORITt2ATION OF GENERO SAFETY ISSUES. INTERFACES. Problems And Tectnques For Irmrovement Probabilletic Performance Procedures NUREG/CR-4600 SIGPt.A USER'S MANUAL FOR FAST COMPUTA- NUREG/CR-3968: STUDY OF OPERATING PROCEDURES IN NUCLE-TION OF THE PROBABluSTIC PERFORMANCE OF COMPLEX SYS. AR POWER PLANTS. Pracbces And Problems. TEMS-Profeselonel Opinion Probabinetic Riek Assosoment NUREG-1290 DeFFERING PROFESSIONAL OPtNONS.1987 Speoal NUREG/CR 3495: CALCULATION OF FAILURE IMPORTANCE MEAS- Revew Pane 4. URES FOR BASIC EVENTS AND PLANT SYSTEMS IN NUCLEAR POWER PLANTS. Project Description NUREG/CR-4405: PROBASILISTC RISK ASSESSMENT (PRA) IN- NUREG 1260 V01: A REPORT TO CONGRESS ON NUCLEAR REGULA-NU E /CR4448: SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF A GENERAL ELECTRC BWR3/ MARK ICase Study. Protective Action NUREG/CR-4458: SHUTDOWN DECAY HEAT REwVAL ANALYSIS OF NUREG 1210 V01: PILOT PROGRAM NRC SEVERE REACTOR ACCI. A WESTINGHOUSE 2 LOOP PRESSURIZED WATER REACTOR Case DENT INCIDENT RESPONSE TRAINING MANUALOvervew And Sum. NA /CR4710- SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF NU G 2 0 V02 L'OT PROGRAM NRC SEVERE REACTOR ACCI-A COMBUSTION ENGINEERING PRESSURIZED WATER DENT INCOENT RESPONSE TRAJNING MANUALSevers Reactor Ac. NURE /CR4 15 SH DOWN DECAY HEAT REMOVAL ANALYS!S OF NU A BABCOCK AND WILCOX PRESSURIZED WATER REACTOR Case IfVOi PtLOT PROGRAM.NRC SEVERE REACTOR ACCI-DENT INCOENT RESPONSE TRAINING MANUALResponse Of U-N1 A /CR-4762: SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF consee And State And Local Officia!s. A WESTINGHOUSE 3-LOOP PRESSURIZED WATER REACTOR Case NUREG 1210 V04: PILOT PROGRAM NRC SEVERE REACTOR ACCI-

   $4                                                                          DENT INCIDENT RESPONSE TRAINING MANUALPubhc Protectrve NUREG'/CR4767: SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF                         Actons Predetenmned Cntena And latial Actons.

A GENERAL ELECTRIC BWR4/ MARK I Case Study. NUREG 1210 V05: PILOT PROGRAM.NRC SEVERE REACTOR ACCI. NUREG/CR-4768 V01: METHOOOLOGY AND APPUCATON OF SUR. DENT INCOENT RESPONSE TRAINING MANUALU.S. Nuclear Regu-ROGATE PLANT PRA ANALYSIS TO THE RANCHO SECO POWER latory Commess on Response. PLANT. Task 1 Anahsis Of ANO 1 And Oconee PRAs. NUREG/CR-4768 V02: METHOOOLOGY AND APPUCATON OF SUR. PubHc Muting ROGATE PLANT PRA ANALYSIS TO THE RANCHO SECO POWER NUREG 1262: ANSWERS TO OVESTIONS AT PUBLC MEETINGS RE-PLANT Final Report. GARDING IMPLEMENTATON OF TITLE 10. CODE OF FEDERAL NUREG/CR4800: SGPt.A USER'S MANUAL FOR FAST COMPUTA. REGULATONS,PART 55 0N OPERATORS' UCENSES. TON OF THE PROBABluSTO PERFORMANCE OF COMPLEX SYS-TEMS. Pump NUREG/CR4810' EVALUATION OF DIESEL UNAVAILABiUTY ANO NUREG/CR-4943: PREPARATION OF DESIGN SPECIFICATIONS AND RISK EFFECTIVE SURVEILLANCE TEST INTERVALS DESIGN REPORTS FOR PUMPS, VALVES, PIPING.AND PIPING SUP-NUREG/CR-4524. EVALUATON OF INTEGRAL CONTINUING EXPERI- PORTS USED IN SAFETY-RELATED PORTIONS OF NUCLEAR MENTAL CAPABluTY (CEC) CONCEPTS FOR UGHT WATER REAC- POWER PLANTS. TOR RESEAACH PWR SCAUNG CONCEPTS NUREG/CR4834 V01: RECOVERY ACTIONS IN PRA FOR THE RtSK Ouality Assurence METHOOS INTEGRATION AND EVALUATON PROGRAM NUREG 1293 DAFT FC: OUAUTY ASSURANCE GUCANCE FOR LOW. N1 / 4 VO TN ENV N ET LATON.AN ARTIFICIAL INTELLIGENCE SYSTEM FOR HUMAN PERFORMANCE NUREG/CR-4962: METHODS FOR THE ELCITATON AND USE OF NUR /CR VlENV NT SIMULATONAN

                                                                                                 '                            '^                         '

F ear ARTIFICIAL INTELLOENCE SYSTEM FOR HUMAN PERFORMANCE ASSESSMENT. Volume 2 Modehno Human intenton Fcsmutabon. Quality Assurance Coet NUREG/CR-4862 V03. COGNITIVE ENYlRONMENT SIMULATON.AN NUREG/CR4921: ENGINEERING AND OVAUTY ASSURANCE COST ARTIFCIAL INTELUGENCE SYSTEM FOR HUMAN PERFORMANCE FACTORS ASSOCIATED WITH NUCLEAR PLANT MODIFICATION. NUR / 8 T F E' ARCH OueNty Assurance Program NUR C4 VO COMPONE FRAGtUTY RESEARCH NUREG4383 V01 Rio DIRECTORY OF CERTIFICATES OF COMPU-ANCE FOR RADOACTNE MATERIALS PACKAGES. Summary Report PROGRAM Phase l Demonstrabon Tests RW

"        #                                        ^            ^ "

R Pme T NU EG V$2R CTORY OF CERTIFICATES OF COMPLI-NUREG/CR-4910' RELAY CHATTER RATOR RESPONSE ANCE FOR RADOACTIVE MATERIALS F ACKAGES Certificates Of R LARGE EARTHOUAKE.An improved PRA Methodokyy Wfth NUREG/CR 4962: METHOOS FOR THE EUCITATON ANO USE OF ANCE FOR RADOACTNE MATERIALS PACKAGES Summary Report EXPERT OPINION IN RISK ASSESSVENT. Phase i A Cntical Evalua. Of NRC Approved Quakty Assurance Programs For Radcactrve Materv ton And Drectons For Future Research. al Pacirages. NUREG/CR-4966 V01: EVALVATON OF OPERATONAL SAFETY AT BABCOCK AND WILCOX PLANTS Volume 1 Results Overvie, Quanty Control NUREG/CR4966 V02. EVALUATON OF OPERATONAL SAFETY AT NUREG 1293 DAFT FC: QUAUTY ASSURANCE GUOANCE FOR LOW-BABCOCK AND WILCCX PLANTSVolume 2 Thermal-Hydrauke Re- LEVEL RADCACTNE WASTE DISPOSAL FACIUTY. Dram For Com-sufts ment

128 Subject Index RAMONA-38 NUREG/CH4856: FEASIBluTY STUDY CW A DATA BASED SYSTEM NUREG/CR-4739- RAMONA 38 CALCULATONS FOR BROWNS FOR DECISIONS REGARDING OCCUPA1.'ONAL RAD 4ATON PRO. FERRY ATWS STUDY. TECTION MEASURES. RELAP6/ MOO 2 Red 60ective Effluent NUREG/CR4672 ANALYSIS OF INSTRUMENT TUBE RUPTURES IN NUREG/CR-4653: GASPAR 11 TECHN! CAL REFEREDCE AND USER WESTINGHOUSE 4-LOOP PRESSURIZED WATER REACTORS. GUIDE. NUREG/CR-4799- RELAP5/ MOD 2 ASSESSMENT SIMULATION OF SE-MISCALE MOD 2C TEST S.NH-3. Radioactive Material NUREG/CR-4946: DAVIS BESSE UNCERTAINTY STUDY. NUREG/CR 2907 V05: RADIOACTNE MATERIALS RELEASED FROM NUREG/CR-5010 RELAPS/ MOO 2 ASSESSMENT USING SEMISCALE NUCLEAR POWER PLANTS. Annual Repcwt 1984. EXPERIMENTS S-NH 1 AND S-LH-2. NUREG/CR4736: COMBUSTON AERCGOLS FORMED DURING BURNING OF RADCACTNELY CONTAMINATED MATERIALS . EX-UR G/CR-4758. A RETRAN MODEL OF THE CALVERT CUFFS 1 b' PRESSURIZED WATER REACTOR FOR ASSESSING THE SAFETY Radioactive Material Package IMPUCATIOf:S OF CONTROL SYSTEMS. NUREG4383 V01 RIO: DIRECTORY OF CERTIFCATES OF COMPU.

                       ,,7, ,,,,,,3                                                                                                   ANCE FOR RADICACTNE MATERIALS PACKAGES Summary Report NUREG/CR-4758: A RETRAN MODEL OF THE CALVERT CUFFS-1 PRESSURIZED WATER REACTOR FOR ASSCSSING THE SAFETY NU EG 383 V03 R0        NCTORY OF CERTIFICATES OF COMPU.

ANCE FOR RADIOACTIVE MATERIALS PACKAGES Summary Report IMPUCATONS OF CONTROL SYSTEMS. Of NRC Approved Quality Assurance Programs For Ra6oactrve Materi. RMIEP al Packages. NUREG/CR-4834 VO1: RECOVERY ACTONS IN PRA FOR THE RISK METHODS INTEGRATION AND EVALUATION PROGRAM Redbacuve MonW Sym (RMIEP). Volume 1: Development Of The Data Based Method. NUREG/CR-4786. TRANSPORT BEHAVIOR OF IODINE IN EFFLUENT RADIOACTNITY MONITORING SYSTEMS. Radial SNeed NUREG/CR4888. ANALYSIS OF THE NESDiP2 AND NESOP3 RADIAL Redescove Reese SHIELD AND CAVITY EXPERIMENTS. NUREG 1150 DRF V1 FC: REACTOR RISK REFERENCE DOCUMENT. Main ReportDraft For Comment Red 6ation Does NUREG 1150 DRF V2 FC: REACTOR RISK REFERENCE NUREG/CR-2850 V05: POPULATON DOSE COMMITMENTS DUE TO DOCUMENT.Appeneces A-l Draft For Comment. RADCACTIVE RELEASES FROM NUCLEAR POWER PLANT SITES NUREG 1150 DAF V3 FC- REACTOR RISK REFERENCE IN 1983 DOCUMENT.Appendees JC Draft For Comment. NUREG/CR-4418: DOSE CALCULATON FOR CONTAM NATON OF NUREG 1250: REPORT ON THE ACCIDENT AT THE CHERNOBYL NU-THE SKIN USING THE COMPUTER CODE VARSKIN CLEAR POWER STATON. NUREG/CR-4653: GASPAR 11. TECHNCAL REFERENCE AND USER NUREG/CP4078 PROCEEDNGS OF THE SYMPOSIUM ON CHEMI-GUIDE. CAL PHENOMENA ASSOCIATED WITH RADIOACTIVITY RELEASES NUREG/CR4986: RADIATON DOSE ESTIMATES AND HAZARD EVAL. DURING SEVERE NUCLEAR PLANT ACCOENTS. UATONS FOR INHALED AIRBORNE RADONUCUDES Final RW NUREG/CR-2850 V05: POPULATON DOSE COMMITMENTS DUE TO NUREG/CR-5025: EXPERIMENTAL STUDES OF THE EARLY EFFECTS RADCACTIVE RELEASES FROM NUCLEAR POWER PLANT SITES OF INHALED BETA-EMITTING RADONUCLCES FOR NUCLEAR AC. IN 1983. CIDENT RISK ASSESSMENT. Phase il Report

                                                                                                                                  ,       g Radletion Effect                                                                                             NUREG4683 S02: PROGRAMMATIC ENVIRONMENTAL IMPACT NUREG/CR-4704 V02 RELATNE BOLOGICAL EFFECTNENESS (RBE)                                 STATEMENT RELATED TO DECONTAMiNATON AND DISPOSAL OF OF FISSON NEUTRONS AND GAMMA RAYS AT OCCUPATONAL                 RADCACTNE WASTES RESUt. TING FROM MARCH 28,1979 ACCI-EXPOSURE LEVELS.Voaume IL Stu6es On The Effects of 60 Equal     DENT AT THREE MILE ISLAND NUCLEAR STATON. UNIT 2 Final Once Weeur Expasures To Fisson Neutrons And Gamma Rays On        Supplement Deahng Wrth Dspc6al Of....

Surwval Of Mce. NUREG 1101 V02: ONSITE DSPOSAL OF RADCACTNE WASTE. Methodology For The Radologeal Assessment Of Dsposal By Redletion Exposure Subsurface Bunal. NUREG/CR4409 V02 DATA BASE ON NUCLEAR POWER PLANT NUREG 1245 vot: RADCACTIVE WASTE MANAGEMENT RESEARCH DOSE REDUCTON RESEARCH PROJECTS. PROGRAM PLAN FOR HIGH-LEVEL WASTE .1987. NUREG/CR4485 V02: THE IMPACT OF FUEL CL ADDING FAILURE NUREG/CR 2452: RISK METHOOOLOGY FOR GIOLOGIC OtSPOSAL EVENTS ON OCCUPATONAL RADLATION EXPOSURES AT NUCLE. OF RADICACTNE WASTE. Final Report AA POWER PLANTS Case StudyPWR Dunng An Outage NUREG/CR-4912: DATING GROUND WATER AND THE EVALUATION j NUREG/CR-4815: DEMONSTRATON TESTING OF A SURVOLLANCE OF REPOSITORIES FOR RADOACTIVE WASTE. ROBOT AT BROWNS FERRY NUCLEAR PtANT. Analysis Of Costs NUREG/CR-4918 V01: CONTROL OF WATER INFILTRATON INTO And Benefits. NEAR SURFACE LLW DSPOSAL UNITS. Annual Report, October 1985 NUREG/CR4884:INTERPRETATON OF BOASSAY MEASUREMENTS. . September 1986. NUREG/CR-4938: OCCUPATIONAL RADlATION EXPOSURES ASSOCt. NUREG/CR4968: EVALUATON OF UNCERTAINTIES IN IRRADIATED ATED WITH ALTERNATIVE METHOOS OF LOW-LEVEL WASTE DS- HARDWARE CHARACTERIZATON. POSAL NUREG/CR 5035: DATA BASE OF SYSTEM-AVERAGE DOSE RATES Radio 6odine Resuspension AT NUCLEAR POWER PLANTS Final Report NUREG/CR4953. CORRELATON OF RADOODtNE RESUSPENSON WITH TEMPERATURE AT TML2. Radletion Monitoring Network NUREG4837 V06 NO3: NRC TLD DIRECT RADATON MONITORING Radiological Assessment NETWORK. Progress Report, July September 1986. NUREG 1101 V02: ONSITE DSPOSAL OF RADCACTNE NUREG-0837 YO6 N04. NRC TLD DRECT RADATION MONITORING WASTE Methodology For The Radologeal Assessment Of Dsposal By NETWORK. Progress Report. October-December 1986. Subsurface Bunal. NUREG-0837 V07 N01: NRC TLD DRECT RADIATON MONITORING NETWORK. Progress Report. January. March 1987. Recological Release NUREG-0837 VO? NO2: NRC TLD ORECT RADATON MOhiTORING NUREG/CR-4552: A REVIEW OF THE SEABROOK STATON PROBABI-NETWORK. Progress Report. April-June 1987. USTIC SAFETY ASSESSMENT.Contamment Fa4ure Modes And Rad-NUREG-0837 V07 NO3: NRC TLD DIRECT RADATON MONITORING cWycal Source Terms. NETWORK. Progress Repcat, Jufy Septerrter 1987. Red 6onucede Radiation Protection NUREG/CR-4654. RADONUCUDE TRANSPORT AS VAPOR NUREG/CR-3469 V03. OCCUPATONAL DOSE REDUCTON AT NU- THROUGH UNSATURATED FRACTURED ROCK. CLEAR POWER PLANTS. Annotated Bibliography Of Selected Read- NUREG/CR-4708 V01 N1: PROGRESS IN EVALUATION OF RADONU. ings in Radaten Protecton And ALARA. CUDE GEOCHEMICAL INFORMATION DEVELOPED BY DOE HIGH-

Subject index 129 LEVEL NUCLEAR WASTE REPOSITORY SITE Reactor Vesset PROJECTS Semiannual Report For October 1985 - March 1986. NUREG/CR4841: FRACTURE EVALUATION OF SURFACE CRACKS Radionuclide Migration EMBEDDED IN REACTOR VESSEL CLADDtNG Urwrachated Bend Specirnen Results NUREG/CR-5040: RADIONUCLCE MIGRATION AROUND URANfUM NUREG/CR4896: CONTAINMENT LOADS DUE TO DIRECT CONTAIN-ORE BODIES - ANALOGUE OF RADIOACTIVE WASTE MENT HEATING AND ASSOCIATED HYDROGEN BEHAVIOR Analyses REFOSITORIES Annual Report For 1984 1985. And Calculatx)ns With The CONTAIN Code. Radionuc#de MobHMy NUREG/CR-4978: THE COOLDOWN ASPECTS OF THE TMI-2 ACCI-DENT' NUREG/CR49'S: PLANT RH120$PHERE PROCESSES INFLUENCING RADIONUCLCE MOBIUTY IN SOIL Readinese Review NUREG 1278: VOGTLE UMT 1 READINESS REVIEW. Assessment Of E CR 7 OW-LEVEL WASTE SOURCE TERM N D **

• EVALUATION. Review of Pubhshed Modeling And Expenmental Recovery Action Wort.And Presentation Of Low-Level Waste Source Term Modeln9 NUREG/CR-4834 V01: RFCOVERY ACTIONS IN PRA FOR THE RISK Framework And Prehminary Model Development METHODS INTEGRATON AND EVALUATION PROGRAM (RMrEP) Volume 1: Development Of The Data Based Method.

NUREG/CR-4951: NEPHROTDXICITY OF URANYL FLUORIDE AND RE* Recogerv Procedure VERS:BluTY OF RENAL INJURY IN THE RAT. NUREG/CR 5025: EXPERIMENTAL STUDIES OF THE EARLY EFFECTS NUREd/CR4793: RESULTS OF SEMISCALE MOD 2C SMALL-BREAK OF INHALED BETA-EMITTING RADIONUCLCES FOR NUCLEAR AC. LOSS OF COOLANT ACCOENT WITHOUT HPl (S NH) EXPER! MENT COENT RISK ASSESSMENT. Phase 11 Report. SERIES. Recurring Loss N RE / 2 EACTOR COOLANT PUMP SHAFT SEAL STABlu- NUREG/CR 5002: METHODS FOR RECURRING LOSS TESTS. TY DURING STATON BLACKOUT. Reed Report NUREG/CR-4985: INDIAN POINT 2 REACTOR COOLANT PUMP SEAL EVALUATIONS. NUREG 1285: NRC STAFF EVALUATON OF THE GENERAL ELECTRIC COMPANY NUCLEAR REACTOR STUDg"REED REPORT"). Reactor Coolant System Reflection Seismolog NUREG/CR-4320 THE RELATIONSHIP AND INFLUENCES OF FUEL SYSTEM PROCESSES DURING LWR SEVERE ACCl* NUREG/CR 4975: A REVIEW OF THE RESOLVING POWER OF RE-FLECTION SEISMOLOGY METHODS TO DETECT SUBSURFACE FAULTS AND/OR CHANGES IN LAYER THICKNESS. Reactor Operator NUREG 1122 S01: KNOWLEDGES AND ABIUTIES CATALOG FOR NO-CLEAR POWER PLANT OPERATORS.Pressunted Water Reactors. EG 80 TANDARD FORMAT AND CONTENT ACCEPTANCE CRITERIA FOR THE MATERIAL CONTROL AND ACCOUNTING Reactor Risk (MC&A) REFORM AMENDMENT.10 CFR Part 74 Subpart E. NUREG-1150 DAF VI FC: REACTOR RISK REFERENCE DOCUMENT. Man ReportDraft For Comment. Retreezing NUREG-1150 DAF V2 FC: REACTOR RISK REFERENCE NUREG/CR-5028. ON THE MELTING AND REFREEZING OF POROUS DOCUMENTAppendices A4 Draft For Comment M EDIA. NUREG 1150 DRF V3 FC: REACTOR RISK REFERENCE DOCUMENT.Arpereces J.O Draft For Comment. R Re.co, Sa,e,, uTON. 6 NUREG/CP4002 VOI: PROCEEDINGS OF THE FOURTEENTH WATER REL*: TOR SAFETY INFORMATON MEETING Regulatory Agenda NUREG/CP-0082 V02: PROCEEDINGS OF THE FOURTEENTH WATER NUREG 0936 V05 NO3. NRC REGULATORY AGENDA.Ouarterty REACTOR SAFETY INrORMATION MEETING Report. July September 1986. NUREG/CP-0082 V03: PROCEEDINGS OF THE FOURTEENTH WATER NUREG 0936 V05 N04: NRC REGULATORY AGENDA Ouarterty REACTOR SAFETY INFORMATON MEETING. Report. October-December 1986. NUREG/CP4082 V04. PROCEEDINGS OF THE FOURTEENTH WATER NUREG4936 V06 NOI: NRC REGULATORY AGENDA.Ouarter9 REACTOR SAFETY INFORMATON MEETING. Report. January-March 1987. l NUREG/CP-0082 V05: PROCEEDINGS OF THE FOURTEENTH WATER NUREG 0936 V06 NO2- NRC REGULATORY AGENDA.Ouartetty [ REACTOR SAFETY INFORMATON MEETING. Report.ApniJune 1987. NUREG/CP 0082 V06. PROCEEDINGS OF THE FOURTEENTH WATER HUREG4936 V06 NO3: NRC REGULATORY AGENDA Ouar'.orty REACTOR SAFETY INFORMATION MEETING. Report.Jufy September 1987. NUREG/CR-4803. THE POSSIBILITY OF LOCAL DETONATONS DURING DEGRADED-CORE ACCOENTS IN THE BELLEFONTE NU. Regulatory Analysis CLEAR POWER PLANT. NUREG 1211: REGULATORY ANALWS FOR RESOLUTON OF UNRE-NUREG/CR-4805 V01: REACTOR SAFETY REMARCH SEMtANNUAL SOLVED SAFETY ISSUE A46.SEISMC QUAUFICATON OF EQUIP. REPORT. January June 1986 MENT IN OPERATING PLANTS. NUREG/CR-4712: REGULATORY ANALYS1S OF REGULATORY GUCE Reactor Shutdown 1.35 (REVISON 3. DRAFT 2) - IN-SERVICE INSPECTION OF UN-NUREG/CR-4012 V02. REPLACEMENT ENERGY COSTS FOR NUCLE- GPOUTCD TENDONS IN PRESTRESSED CONCRETE CONTAIN-AR ELECTRICITY GENERATING UNITS IN THE UNITED MENTS. STATES:1987 1991. NUREG/CR 5036. COST ANALYSIS FOA IMPLEMENTATION OF PRO. POSED CHANGES IN VITAL AREA REQUIREMENTS. Reactor Technology NUREG/CP-0088. TRANSACTONS OF THE 9TH INTERNATONAL Regulatory And Technical Report CONFERENCE ON STRUCTUAAL MECHANOS IN REACTOR NUREG4304 V11 N04. REGULATORY AND TECHNCAL REPORTS TECHNOLOGY. Panel Sesson JK Structtral And Mecharacal Engneer. (ABSTRACT INDEX JOURNAL). Annual Comodation For 1986 ing Research At The U S Nuclear Regulatory Commesson. NUREG4304 V12 NO1: REGULATORY AND TECHNCAL REPORTS (ABSTRACT INDEX JOURNAL). Compdation For Frst Quarter Reactor Trip Brooker 1987 January-March. NUREG/CR4663: CLOSEOUT OF IE BULLETIN 8341 FAILURE OF RE- NUREG4304 V12 NO2. REGULATORY AND TECHNCAL REPORTS ACTOR TRIP BREAKERS (WESTINGHOUSE DB 50) TO OPEN ON (ABSTRACT INDEX JOURNAL). Compdabon For Second Quarter AUTOM ATC TR:P SIGNAL 1987.Apni-June NUREG/CR4644 CLOSEOUT OF IE BULLETIN 8344 FAILURE OF NUREG4304 V12 NO3 REGULATORY AND TECHN CAL REPORTS THE UNDERVOLTAGE TRIP FUNCTION OF REACTOR TRIP BREAK- (ABSTRACT INDEX JOURNAL) Cortptabon For TNrd Ovarter ERS 1987, July September

130 Subject Index Reguietcry Gu6de Resolving Power NUREG/CR-4712: REGULATORY ANALYSIS OF REGULATORY GUCE NUREG/CR4975: A REVIEW OF THE RESOLVING POWER OF RE-1.35 (REVIS4ON 3. DRAFT 2) . IN-SERVCE INSPECTON OF UN- FLECTION SEISMOLOGY METHODS TO DETECT SUBSURFACE GROUTED YENDONS IN PRESTR'.SSED CONCRETE CONTAIN- FAULTS AND/OR CHANGES IN LAYER THCKNESS. MENTS. Reeponse Spectre Reguietory leaves NUREG/CR-4903 V01: SELECTON OF EARTHOUAKE RESISTANT NUREG/CR-4783: ANALYSIS OF BALANCE OF-PLANT REGULATORY DESIGN CRITERIA FOR NUCLEAR POWER PLANTS METHOOOLO-ISSUESFinal Report GY AND TECHNICAL CASES. Drect Ernpreal Scahng Of Response Spectral Arnphtudes From Vanous $4te And Earthquake Pararneters. Reguietory RWu6romonte NUREG/CR 4330 V03: REVIEW OF UGHT WATER REACTOR 6EGU- Restert LATORY REQUIREMENTS. Assessment Of Selected Regulatory Re-curements That May Have Margmal importance To Risk.Postaccident NUREG 1286: SAFETY EVALUATON REPORT RELATED TO THE RE-START OF RANCHO SECO NUCLEAR GENERATING STATON.UNf7 Samphng System Turtune Missdes,Comtxistele Gas Control. Charcoal 1 FOLLOWING THE EVENT OF DECEMBER 26.1985. Docket No. 50-Fdters. 312.(Sacramento Muncipal Utky Distnet) Re6ettve B6ological Ettoctivenees NUREG/CR-4704 V01: RELATIVE BOLOGCAL EFFECTIVENESS (RBE) Riprep DeeJgri Crtteria OF FISSON NEUTRONS AND GAMMA RAYS AT OCCUPATONAL NUREG/CR4651: DEVELOPMENT OF RIPRAP DESIGN CRITERIA BY EXPOSURE LEVELS. volume 1. Studies On The Genetc Effects in RIPRAP TESTING IN FLUMES Phase L Mce Of 60 Equal Once Weekty Exposures To Fisson Neutrons And Gamma Rays. R6 prep Testing NUREG/CR4704 V02- RELATIVE BIOLOGCAL EFFECTIVENESS (RBE) NUREG/CR-4651: DEVELOPMENT OF RIPRAP DES 6GN CRITERIA BY OF FISSON NEUTRONS AND GAMMA RAYS AT OCCUPATONAL RIPRAP TESTING IN FLUMES Phase L EXPOSURE LEVELS Volume 11 Studies On The Effects Of 60 Equal Once. Weekly Exposu os To Fessson Neutrons And Gamma Rays On Risk Surwval Of Mce. NUREG/CR-2452. RISK METHODOLOGY FOR GEOLOGC DISPOSAL OF RADCACTIVE WASTE. Fnal Report Ratey NUREG/CR 3495 CALCULATON OF FAILURE IMPORTANCE MEAS-NUREG/CR-4715: AN AGING ASSESSMENT OF RELAYS AND CIR- URES FOR BASIC EVENTS AND PLANT SYSTEMS IN NUCLEAR CUT BREAKERS AND SYSTEM INTERACTIOr4S. POWER PLANTS. NvREG/CR4330 V03: REVIEW OF UGHT WATER REACTOR REGO-REMEMENTS. Assessment Q Seleded Regdam Re. NUR /CR4910: RELAY CHATTER AND OPERATOR RESPONSE e a oR a GE EARTHOUAKE An improv4 PRA Methodology With 'g f y ,, j Fdters. NUREG/CR-4696. CONTAINMENT VENTING ANALYSIS FOR THE Roastemty NUREG/CR 4626 V02; IMPROVING THE MEUABluTY OF OPEN. PEACH BOTTOM ATOMIC POWER STATON CYCLE WATER SYSTEMS Appheation Of B;olouhng Survedlance And NUREG/CR4726 EVALUATON OF PROTECTIVE ACTON RISKS C4ctrol Techniques To Sedenent And Cortcsson Fouhng At Nuclear NUREd/CR4768 V01: METHOOOLOGY AND APPLCATON OF SUR-ROGATE FLANT PRA ANALYSIS TO THE RANCHO SECO POVdR Power Plants NUREGICR4810 EVALUATON OF DESIL UNAVAILABluTY AND PLANT. Task 1. AnaYses Of ANO.1 And Oconee PRAs RISK EFFECTIVE SURVEILLANCE TEST INTE RVALS, NUREG/CR4768 V02: METHOOOLOGY AND APPUCATON OF SUR-ROGATE PLANT PRA ANALYSIS TO THE RANCHO SECO POWER PLANT Fnal Report Ronal trW NUREG/CR-4769. RISK EVALUATIONS OF AGING f*HENOMENA.The NUREG/GR4951: NEPHROTOXICITY OF URANYL FLUORCE AND RE. VERSIB1UTY OF RENAL INJURY IN THE RAT. Lnear Ayng Ret Model And its Ertenssons NUREG/GR-4772. DENT SEQUENCE EVALUATION PROGRAM Repiscoment Energy Coet HUMAN RELIABluTY ANALYSIS PROCEDURE. NUREG/CR4012 V02. REPLACEMENT ENERGY COSTS FOR NUCLE- NUREG/CR4810. EVALUATION OF DESEL UNAVAILABlUTY AND AR ELECTRCITY GENERATING UNITS IN THE UNITED RISK EFFECTIVE SURVEILLANCE TEST INTERVALS STATES 1987 1991. NUREG/CR4814: SOURCES OF CORRELATION BETWEEN EXPERTS Empncal Results From Two Extremes Report To Congrees NUREG/CR4844 DRFT: INTEGRATED REUABruTY ANO RISK ANALY. NUREG-0090 V09 NO2- REPORT TO CONGRESS ON ABNORMAL S4S SYSTEM (IRRAS) USER'S GUOE VERSION 10 (DRAFT) OCCURRENCES Apni June 1986 NUREG/CR4966 V01: EVALUATON OF OPERATONAL SAFETY AT NUREG4090 V09 N01 REPORT TO CONGRESS ON ABNORMAL BABCOCK ANO WRCOX PLANTS. Volume 1. Results overnew NUREG/CR 5006: PRA APPLICATON PROGRAM FOR INSPECTON NUR VO E T CONGRESS ON ABNORMAL NURE -52 EX ERIMENTAL STUDES OF THE EARLY EFFECTS NU POR CONGRESS ON ABNORMAL OF INHALED BETA EMITTING RADONUCUDES FOR NUCLEAR AC. OCCURRENCESJanuary-March 1987. COENT RISK ASSESSMENT Phase 11 Report NUREG 0090 V10 NO2: REPORT TO CONGRESS ON ABNORMAL OCCURRENCES Apns-Ane 1987. NUREG/CR-5042: EVALUATION OF EXTERNAL HAZARDS TO NUCLE-NUREG-1260 YO1: A REPORT TO CONGRESS ON NUCLEAR REGULA- AR POWER PLANTS IN THE UNITED STATES TORY RESEARCH Protect Desenptons For FY87. Repository NUREG/CR-4962: METHOOS FOR THE ELCITATION AND USE OF NUREG/CR4912: DATING GROUND WATER AND THE EVALUATON EXPERT OPtNON IN RLSK ASSESSMENT Phase I A Cntcal Evalua. OF REPOSITORIES FOR RADCACTIVE WASTE tion And Drrtions For Future Research. Reeeerch Risk Reduction NUREG-0975 V05: COMPILATON OF CONTRACT RESEARCH FOR NUREG/CR4551 V1 DAF: EVALUATON OF SEVERE ACCOENT THE MATERIALS BRANCH, DVISON OF ENGINEERING RISKS AND THE POTENTIAL FOR RISK REDUCTION SURRY R NU 260 1: A E b0 CONGRESS ON NUCLEAR REGULA. gg fCA F VALUA OF SEVERE ACCOENT TORY RESEARCM Prosect Descrpbons For FY87. RISKS AND THE POTENTLAL FOR RISK REDUCTON SEQUOYAH Reeldual Heat Removal System POWER STATON. UNIT 1 Draft Fi./ Comment NUREG/CR4551 V3 PT1: EVALVATICN OF SEVERE ACCOENT RISKS NUREG-1269: LOSS OF RESOUAL HEAT REMOVAL SYSTEM Dabio AND THE POTENTIAL FOR RISK REDUCTON PEACH Canyon Urvt 2, Aprt 10.1967. BOTTOM. UNIT 2 Mac Report Draft For Gynment. Reelstance Temperature Detector NUREG/CR4551 V3 PT2: EVALUATON OF 3EVERE ACCOENT RISKS NUREG/CR-4928 OEGRADATION OF NUCLEAR PLANT TEMPERA- AND THE POTENTIAL FOR RISK REDUCTION PEACH BOTTOMTNIT 2 Appendices Dran For Commem TURE SENSORS

Subject IndCx 131 NUREG/CR4551 V4 DAF: EVALUATON OF SEVERE ACCIDENT SIGP1 RISKS AND THE POTENTIAL FOR RISV REDUCTON GRAND NUREG/CR-4800 SGPIA USER'S MANUAL FOR FAST COMPUTA-GULF, UNIT 1. Draft For Comment TION OF THE PROBABlUSTC PERFORMANCE OF COMPLEX SYS-NUREG/CR4781 DAFT: STUDY OF SEVERE ACCIDENT MITIGATION TEMS. SYSTEMS. SIMMER-fl P4VREG/CR-4765: MXS CROSS-SECTION PREPROCESSOR USER'S R G/CR-4815: DEMONSTRATION TESTING OF A SURVEILLANCE ROSOT Al BROWNS FERRY NUCLEAR PLANTAnaYsts Cf Costs And Benehts- SUM-MAUD Re Fee Grouting NUREG/CR-4016 V02- APPUCATION OF SUM-MAUDA TEST OF AN NUREG/CR4541: EXPER: MENTAL ASSESSMENT OF THE SEAUNG INTERACTIVE COMPUTER-8ASED METHOD FOR ORGANIZING EFFECTIVENESS OF ROCK FRACTURE GROUTING. EXPERT ASSESSMENT OF HUMAN PERFORMANCE AND REUA81UTY. Volume !!Appendees. RootCause Analye6e NUREG/CR-4616: ROOT CAUSES OF COMPONENT FAILURES SPERT PROGRAM. Methods And Appicates. NUREG 1281: EVALUATON OF THE OVAUFCATON OF SPERT FUEL FOR USE IN NON-POWER REACTORS. RulemeMng NUREG/CR4958. IMPACT OF PROPOSED FINANCIAL ASSURANCE SRNY Station REQUIREMENTS ON NUCLEAR MATERIALS LCENSEES- NUREG/CR-4822 BROAD BAND SEISMC DATA ANALYSIS September 1984 September 1986. NUREG4936 V05 NO3. NRC REGULATORY AGENDA.Ouarterty SURBOT NRC REGULATORY AGENDA.Ouarterty NUREG/CR-4815: DEMONSTRATION TESTING OF A SURVEILLANCE NUR NC Repor@obw Decembw 1986 ROBOT AT BROWNS FERRY NUCLEAR PLANTAnahsrs Of Costs NUREG-0936 V06 N01: NRC REGULATORY AGENDA Ouartaty And Benehts NO2 NRC REGULATORY AGENDA.Ouarterty SWIFT 11 NUR -0936 ReportApni-June 1987. NUREG/CR.3925 REY; SWIFT 11 SELF TEACHING NUREG-0936 V06 NO3 NRC REGULATORY AGENDA.Ouartetty CURRCULUM.llivstratnre Problems For The Sanda Wast +lsolation Report.JuPy Septemeer 1987. Flow And Transport Model For Fractured Meda. Ru6es Of Practice SWISS NUREG4386 004 R04 UNITED STATES NUCLEAR REGULATORY NUREG/CR-4727; SWISS SUSTAINED HEATED METALLC MELT / CON-COMMISSON STAFF PRACTICE AND PROCEDURE DGESTJufy CRETE INTERACTIONS WITH OVERLYING WATER POOLS 1972 June 1986 NUREG4J86 D04 ROS: UNITED STATES NUCLEAR REGULATORY Safe Shutdown COMMISSON STAFF PRACTICE AND PROCEDURE DIGESTJuly NUREG/CR-4861: DEVELOPMENT OF SfTE SPECIFC RESPONSE 1972 September 1986- SPECTRA NUREG4386 004 R06 UNITED STATES NUCLEAR REGULATORY COMMISSON STAFF PRACTCE AND PROCEDURE DGESTJuly Sofeguards 1972 Dec 1986 NUREG/CA-4773: DESIGN FEATURES TO FACIUTATE INTERNATION. AL SAFEGUARDS AT MIXEDCXIDE CONVERSON FACluTIES S44H Test Series NUREG/CR4793. RESULTS OF SEMISCALE MOO 2C SMALL-8REAK COOLANT ACCIDENT WtTHOUT HPI (S-NH) EXPERIMENT I 45 SAFEGU DS

SUMMARY

EVENT UST (SSEL). NUh6G4525 R13. SAFEGUARDS

SUMMARY

EVENT UST (SSEL). r S-NH-1 Test Safety NUREG/CR-4845. AN ANALYSIS OF THE SEMISCALE MOD-2C S-Net-3 TEST US NG THE TRAC-PF1 COMPUTER PROGRAM. NUREG 1144 RO1: NUCLEAA PLANT AurNG RESEARCH (NPAR) PRO-4 GRAM PLA N

         $20 Se% ence                                                             NUREG/Ctr3228 V05. STRUCTURAL INTEGRITY OF WATER REAC-NUREG/CR-4741: FEEDWATER TRANSIENT AND SMALL BREAK                       TOR PRESSURE BOUNDARY COMPONENTSAnrwal Repcrt For l             LOSS OF COOLANT ACCCENT ANALYSES FOR THE BELLEFONTE                     1986 I

NUCLEAR PLANT. NUREG/CR4/47 V01: AN AGtNG FAILURE SURVEY OF LIGHT WATER REACTOR SAFETY SYSTEMS AND COMPONENTS. . SAFT UT NUREG/CR-4769. RJSK EVALUATIONS OF AGING PHENOMENA.The NUREG/CR 4583 V02. DEVELOPMENT AND VAUDATON OF A REAL- Unear Agng RehabMy Model And its Ertensionst TIME SAFT UT SYSTEM FOR THE INSPECTON OF UGHT WATER NUREG/CR.4805 V01: REACTOR SAFETY RESEARCH SEM! ANNUAL REACTOR COMPONENTS Annual ReportOctober 1984 September REPORTJanuary June 1986 'i 1985- NUREG/CR4846: H'GH-LEVR WASTE PRECLOSURE SYSTEMS NUREG/CR-4583 V03: DEVELOPMENT AND VAUDATION OF A REAL- SAFETY ANALYSIS Phase 2. Final Report TIME SAFT UT SYSTEM FOR THE INSPECTION OF UGHT WATER NUREG/CR-4945:

SUMMARY

OF THE SEMISCALE PROGRAM (1965-REACTOR COMPONENTS Annual ReportOctober 1985 SeptemL*' 1986). 1986- NUREG/CR4966 V01: EVALUATION OF OPERATONAL SAFETY AT BABCOCK AND WILCOX PLANTS. Volume 1 Results C%rvew. NUREG/CR-4966 V02: EVALUATON OF OPERATIONAL SAFETY AT REG 1214 R01: HISTORCAL DATA SUUVARY OF THE SYSTEMAT- ^ ' '# l C ASSESSMENT OF UCENSEE PERFORMANCE ses. NUREG 1214 R02: HISTORICAL DATA

SUMMARY

OF THE SYSTEMAT-IC ASSESSMENT OF LCENSEE PERFORMANCE. g ,,,ygn ,y,j, SEADEx NUREG-0800 06 52 R2. STANDARD REVIEW PLAN FOR THE REVIEW NUREG/CR4820: COMPARISON OF THE 1982 SEADEX DISPERSON OF SAFETY ANALYSIS REPORTS FOR NUCLEAR POWER PLANTS LWR E$ ton Propned Rensson 2 To Sectaon 6 5.2. "Contae-DATA WITH RESULTS FROM A NUMBER OF OtFFERENT MODELS. NUREG/CR4950 V01: THE SHOREUNE ENVIRONMENT ATMOS- ment Spray As A Frssion Product Cleanup System." For Comment PHERC DSPERSION EXPERJUENT (SEADEX)Expenment Desenp. NUREG4800 06 5 5 RO. STANDARD REVIEW PLAN FOR THE REVIEW bon OF SAFETY ANALYSIS REPORTS FOR NUCLEAR POWER NUREG/CR-4950 V02. THE SHOREUNE ENVIRONMENT ATMOS- PLANTS LWR E6taon. Proposed Rewsson 0 To New SRP Sect,on 6 $ $, PHERC DSPERSION DPER1 MENT (SEADEX)Meteorologscal And Pressure Suppresson Poofs As Frssson Product Clean-Up Systems." Gas Tracer Data For Comment

 -- a~w,~                              .- , - -           -            ,.v- ---                n ,,-----+e                   ,v.-           - - .        w w+n -,

132 Subject index Safety Aseeeement Safety Goal NUREG/CR-4701 V02: SAFETY ASSESSMENT OF ALTERNATIVES TO NUREG/CP4064: PROCEEDINGS OF THE WORKSHOP ON A CON. SHALLOW LAND BURIAL OF LOW LEVEL RADCACTIVE TAINMENT PERFORMANCE DESIGN OBJECTIVE.MAY 12-WASTE. Volume 2 Ermronmental Condtens Affectog Renatnt'ty Of Erw 13,1966. HARPERS FERRY, WEST VIRGINtA. jpneered Bemers. NUREG/CR-4961: A SAFETY ASSESSMENT OF THE USE OF GRAPH. Safety Parameter Display System ITE IN NUCLEAR Rf. ACTORS LCENSED BY THE U S. NRC. NUREG/CR-4797: PROGRESS REVIEWS OF SIX SAFETY PARAME-TER DISPLAY SYSTEMS. Sofety Evolustion Report NUREG-0781 S02: SAFETY EVALUATON REPORT RELATED TO THE Safety Program OPERATON OF SOUTH TEXAS PROJECT, UNITS 1 AND 2 Docket NUREG/CR-4616. ROOT CAUSES OF COMPONENT FAILURES Nos. 54496 And 50499 (Houston Ughung And Power Company PROGRAM. Methods And Appbcations. NUREG4781 S03: SAFETY EVALUATON REPORT RELATED w} THE OPERATION OF SOUTH TEXAS PROJECT, UNITS 1 AND 2. Docket Safety Regulation Nos. 50-496 And 50-499. (Houston U'ghting And Power Company) NUREG 1251 DAFT FC: IMPUCATIONS OF THE ACCOENT AT CHER-

   'fuREG4781 SO4: SAFETY EVALUATION REPORT RELATED TO THE                                                              NOBYL FOR SAFETY REGULATION OF COMMERCIAL NUCLEAR OPERATON OF SOUTH TEXAS PROJECT, UNITS 1 AND 2. Docket                                                            POWER PLANTS IN THE UNITED STATES Draft For Comment Nos. 50496 And 50 499. (Houston Ughtartg And Power Company)

NUREG-0652 S03: SAFETY EVALUATON REPORT RELATED TO THE Safety Research FINAL DESIGN OF THE STANDARD NUCLEAR STEAM SUPPLY NU9EG 1163: COORDtNATON OF SAFETY RESEARCH FOR THE REFERENCE SYSTEM CESSAR System 80. Docket No. 50-470.(Com. BABCOCK AND WILCOX INTEGRAL SYSTEM TEST PRO ^2 RAM bustion E . incorporated) NUREG-1266 VC1: NRC SAFETY RESEARCH IN SUPPORT OF REGU-NUREG46 S06: ETY EVALUATON REPORT RELATED TO THE LATON - 1986. OPERATON OF CUNTON POWER STATON. UNIT 1 Docket No 50- NUREG/CR-2331 V06 N2: SAFETY RESEARCH PROGRAMS SPON-461 (Ilhnoes Power Company.et 40 SORED BY OFFCE OF NUCLEAR REGULATORY NUREG 0857 S11: SAFETY EVALUATION REPORT RELATED TO THE RESEARCH Ouarterty Progress Report.Apnl June 1986. OPERATON OF PALO VERDE NUCLEAR GENERATING NUREG/CR 2331 V06 N3: SAFETY RESEARCH PROGRAMS SPON-STATION. UNITS 12 AND 3 Docut Nos 50-526,50 529 And 50 SORED BY OFFCE OF NUCLEAR REGJLATORY

      $30 (Aruona Pubhc Serwee Company.et e9                                                                            RESEARCH Ouarterty Progress Report. July September 1986.

NUREG4857 S12: SAFETY EVALUATON REPORT RELATED TO THE NUREG/CR 2331 V06 N4 SAFETY RESEARCH PROGRAM 3 SPON-OPERATON OF PALO VERDE NUCLEAR GENERATING SORED BY OFFCE OF NUCLEAR REGU'.ATORY STATON. UNITS 1.2 AND 3 Docket Nos. 50 528.50 529 And 50- RESEARCH Ouarterty Progress Report. October-December 1966. NU E 46 $06 AFET E EPORT RELATED TO THE Safety Research Program OPERATON OF BY90N STATION. UNITS 1 AND 2 Docket Nos. 50- NUREG/CR 2331 V07 N1: SAFETY RESEARCH PROGRAltS SPON-454 And 50-455-(ComacnweaPth Edison Compang SORED BY OFFCE OF NUCLEAR REGULATORY NUREG-0696 $07: SAFETY EVALUATON REPORT RELATED TO THE RESEARCH Quarterty Progress Report, January-March i987. OPERATON OF SEABROOK STATON, UNITS 1 AND 2. Docket Nos Safety Surveulence N 100 EV A YPOR ELA b'hH NUREG/CR 5011: APPLCATON OF THE ADAPTfVE-PREDCTIVE OPERATON OF BRACWOOD STATON. UNITS 1 AND 2 Docket Nos. CONTROLLERS TO PLANT SAFETY SURVEILLANCE UTlUZING ON. 50456 And 50 457.(Commonweatth Edson Company) UNE PLANT ANALYZER. 7 NUREG 1002 SOS. SAFETY EVALUATON REPORT RELATED TO THE OPERATION OF BRACWOOD STATION. UNITS 1 AND 2 Docket Nos. 50456 And 50-457(Commonwea'th Edson Compa UE/ 4457: AGING OF CLASS 1E BATTER!ES IN SAFETY SYS-g op NUREG 1047 S06: SAFETY EVALUATON REPORT)) ELATED TO THE NU EG/CR-48 V : G S RVICE WEAR OF SOLENOLD-OPERATION OF NINE M:LE POINT NUCLEAR STATON, UNIT OPERATED VALVES USED IN SAFETY SYSTEMS OF NUCLEAR NUR 105 SO4 b'AL T POR RE f TO THE POWER PLANTS Volume 1.Opershng Exponence And Fadure Identife ca m OPERATON OF BEAVER VALLEY POWER STATION, UNIT 2 Docket No 50-412 (Duquesne Lght Company et s') SWt NUREG 1057 SOS SAFETY EVALUATON REPORT RELATED TO THE OPERATON OF BEAVER VALLEY POWER STATON. UNIT 2 Docket NUREG/CR4134 R01: REPOSITORY ENVIRONMENTAL PARAM. ETERS AND MODELS RELEVANT TO ASSESSING THE PERFORM. NU EG 057 SA ET EV EPORT RELATED TO THE ANCE OF HIGH-LEVEL WASTE PACKAGES (BASALT, TUFF AND OPERATION OF BEAVER VALLEY POWER STATION. UNIT 2 Docket NUMCR-4161 V03 CRITICAL PARAMETERS FOR A HIG NU EG 137 S05 S E EV 8 EPORT RELATED TO THE OPERATION OF VOGTLE ELECTRC GENERATING PLANT, UNITS 1 NUREG/ Y G OPHYSCAL TECHNIQUES FOR AND 2 Docket Nos 50424 And 50425 (Georpa Power Company et a!) SITE CHARACTERIZATON IN BASALT. SALT AND TUFF. NUREG-1137 506: SAFETY EVALUATION REPORT RELATED TO THE ge.nng OPERATION OF VOOTLE ELECTRC GENERATING PLANT UNITS 1 NUREG/CR4531: AN INVESTIGATION OF LNTEGRAL FACILITY SCAL. NU EG-1 4 ETY VAL TION E RE TED NE RE PROG AM NEWAL OF THE OPERATING LCENSE FOR THE UNIVERS4TY OF NUREG/CR-4824: EVALUATON OF INTEGRAL CONTINUING EXPERI. NEW MEXCO RESEARCH REACTOR Docket No. 50 252 (Unrversity MENTAL CAPABluTY (CEC) CONCEPTS FOR UGHT WATER REAC-NU E ETY EVALUATON REPORT RELATED TO THE BAB. TOR RESEARCH - PWR SCAUNG CONCEPTS. COCK AND W'LCOX OWNERS GROUP PLANT REASSESSMENT Seal Performance NU E 23 vot: SAFETY EVALUATON REPORT ON TENNESSEE EVA T S VALLEY AUTHORITY. Revised Corporate Nuclear Performance Plan. NUREG-1282: SAFETY EVALUATON REPORT ON HIGH-URAN!UM Seanng CONTENT, LOW ENRCHED URAN!UM-Z1RCONfUM HYDRCE NUREG/CR-4983 THE SEAUNG PERFORMANCE OF BENTONITE / FUELS FOR TRPGA REACTORS Docket No. 50-163 (GA CRUSHED BASALT BOREHOLE PLUGS Tecmologes. Incorporated) NUREG-1284 PROGRAM PLAN FOR CORRECTON OF U S INSTRU- Seehng Effectiveness MENT DEGRADATON OR FAILURE IN THE UPPER PLENUM TEST NUREG/CR-4541: EXPERIMENTAL ASSES $UENT OF THE SEAUNG FACIUTY (UPTF) IN THE FEDERAL REPUBLC OF GE AMANY. EFFECTIVENESS OF ROCK FRACTURE GROUTING NUREG-1286: SAFETY EVALUATION REPORT RELATED TO THE RE. l ftART OF RANCHO SECO NUCLEAR GENERATING STATON. UNIT SeeAng Performance 1 FOLLOWING THE EVENT OF DECEMBER 26,1985 Docket No 50- NUREG/CR4995. EXPERIMENTAL ASSESSMENT OF THE SEAUNG j 312(Sacramento Muropal Utsty Dt/nct) PERFORMANCE OF BENTONtTE BOREHOLE PLUGS t

Subject Index 133 Security NUREG/CR4851: SEISMCTY 1886-81 IN THE SOUTHEASTERN NUREG/CR-5036: COST ANALYSIS FOR IMPLEMENTATION OF PRO. UNITED STATES The Aftershocit Sequence Of The Charleston,Sesth POSED CHANGES IN VITAL AREA REQUIREMENTS. Carolma Earthquake NUREG/CR-4973: INTRAPLATE SEISMCTY OUTSIDE OF THE Sed 6 ment UNITED STATES. NUREG/CR-4626 V02: IMPROVING THE REUABlUTY OF OPEN- NUREG/CR4974 INTRAPLATE SEISMCTY IN THE EASTERN CYCLE WATER SYSTEMS. Application Of Befoulmg Sunreillance And UNITED STATES. Control Techniques To Sediment And Corroson Fouhng At Nuclear NUREG/CR 5034:AN UPDATE OF MCCONTINENT TECTONISM. Power Plants. Setemo6ogy Setem6c And Geolog6c S4 ting NUREG/CR-4903 V01: SELECTON OF EARTHQUAKE RESISTAW NUREG/CP-0087:

SUMMARY

REPORT OF THE SYMPOSIUM ON SEIS- DESIGN CRITERIA FOR NUCLEAR POWER PLANTS METHODOLO. MC AND GEOLOGC SITING CRITERLA FOR NUCLEAR POWER GY AND TECHNICAL CASES. Drect Emprical Scaang Of Response PLANTS Spectral Ampktudes From Vanous Sete And Earthouake Parameters. Seismic Category 1 Tank NUREG/CR 49M V02. SELECTCN OF EARTHOUAKE RESISTANT NUREG/CR-4776: RESPONSE OF SEISMC CATEGORY l TANKS TO OESIGN CRITERLA FOR NUCLEAR POWER PLANTS . METHODOLO-GY AND TECHNCAL CASES. Methods For introducten Of Geological EARTHOUAKE EXCITATON. M into CharacWMon G W Fm And %e And _ gg,,, g NUREG/CA-4903 V03. SELECTCN OF EARTHOUAKE REStSTANT NUREG/CR 4822: BROAD BAND SElSMC OATA ANALYSIS Septembe, DESIGN CRITERIA FOR NUCLEAR POWER PLANTS . METHODOLC-1984 . September 1986. GY AND TECHNICAL CASES. Dislocaton Models Of Near Source Earthquake Ground Moton. A Revew Seismic Design NUREG/CR-4975: A REVIEW OF THE RESOLVING PMER OF RE. NUREG/CR-4859. SEISMC FRAGluTY TEST OF A 6-INCH DIAMETER FLECTION SEISMOLOGY METHOOS TO DETEC1 3 SURFACE PlPE SYSTEM. FAULTS ANCvOR CHANGES IN LAYER THICKNESS Setemic Event SeSTeaching Curriculum NUREG/CR-4672. ANALYSIS OF INSTRUMENT TUBE RUPTURES IN NUREG/CR 3925 REV: SWIFT 11 SELF TEACHING WESTINGHOUSE 4 LOOP PRESSURIZED WATER REACTORS- CURRICULUM Illustrative Problems For The Sandia Waste-isolaton Flow And Transport Model For Fractured Meda. NUREG/CR4776: RESPONSE OF SEtSMC CATEGORY l TANKS TO Semiannuler Downcomer EARTHOUAKE EXCITATCN NUREG/lA 0004- THERMAL mix 1NG TESTS IN A SEl5 ANNULAR S Fr W DOWNCOMER WITH INTERACTING FLOWS FROM COLCMS. NUREG/CR*900 V01: COMPONENT FRAGILITY RESEARCH Semlocale Mod-2C NURE / -4 Y C POP Li RESEARCH NUREG/CR-4733. RESULTS OF SEMiSCALE MOO 2C SMALL-BREAK PROGRAM Phase i Demonstraton Tests Appendices ~ RE Setemic Heaerd NUREG/CR-4799. RELAP5/ MOO 2 ASSESSMENT SIMULATCN OF SE. NUREG/CR4852: THE MEERS FAULT.TECTONC ACTivlTY IN MISCALE MOO-2U TEST S-NH-3 SOUTHWESTERN OKLAHOMA NUREG/CR-4802. AN EVALUA1CN OF TRAC-PF1/ MOOT COMPUTER NUREG/CR-4885. SEISMC HA2ARD CHARACTERIZATCN OF THE 'JODE PERFORMANCE DURING POSTTEST S:MULATCNS OF SE. EASTERN UNITED STATES Comparatrve Evaivaton Of The LLNL And M! SCALE MOO 2C VEDWATER UNE BREAK TRANSIENTS EPRI Studies NUREG/CR-4845. AN ANALYSIS OF THE SEMISCALE MOD 2C S-NH-3 TEST USING THE TRAC-PF1 COMPUTER PROGRAM Se6emic Margin NUREG/CR-5010. RELAPS/ MOO 2 ASSESSMENT USINC SEMISCALE NUREG/CR-4826 V01: SEtSMC MARGIN REVIEW OF THE MAINE EXPER4MENTS S-NH-1 AND S-LH-2 I YANKEE ATOMC POWER STATCN Volume 1 Summary Report ' NUREG/CR4826 V02. SEISMC MARGIN REYiEW OF THE MAINE Semiscele Program YANKEE ATOMC POWER STATCN Volume 2 Systems Ana'yses NUREG/CR ,945: SUMVARY OF THE SEin SCALE PROGRAM (1965-NUREG/CR4826 V03 SEISMC MARGIN REVIEW OF THE MAINE 1986L YANKEE ATOMIC POWER STATCN VoOme 3 Fragtty AnaWs. Serv 6ce West

 !             Se4em6c Quakftcauon Of Equipment NUREG 1144 RO1: NUCLEAR PLANT AGING RESEARCH (NPAR) PRO-NUREG-1030 SEISMC QUAUFICATION OF EQUIPMENT IN OPERAT-                                                                                                  GRAM PLAN ING NUCLEAR POWER PLANTS Unresolved Safe issue A 46                                                                                       NUHEG/CR4819 V01: AGING AND SERVCE WEAR OF SOLENOG NUREG-1211: REGULATORY ANALYSIS FOR RE                                                                                  UTtON OF UNRE.                  OPERATED VALVEf USE' IN SAFETY SYSTEMS OF NUCLEAR SOLVED SAFETY ISSUE A46.SEISMC OVAUFCATCN OF EQUIP.                                                                                                   POWER PLANTS VUene testing Exponence And Failure IdentA-MENT IN OPERATING PLANTS.                                                                                                                            catort e

Seismic Safety Research Severe Accident NUREG 1147 RO1: SEISMC SAFETY RESE ARCH PROGRAM PLAN NUREG 1150 ORF V1 FC: REACTOR RISK REFERENCE DOCUMENT Main Report Dra't For Comment. SMc TW NUREG/CR 4734- SEISMC TESTING OF TYPCAL CONTAINMENT NUREG 1150 ORF V2 FC: REACTOR R!Sk REFERENCE yng DOCUMENThpendices A4 Dra't For Comment. NURE CR-48 9 EISM F  ! ITY TEST OF A 6-INCH DIAMETER NUREG 1150 ORF V3 FC: REACTOR RISK REFEREPCE DOCUMENT.Appereces J-O Dram For Comment PtPE SYSTEM , NUREG/CR-4987: SIMULATED SEISMC TESTS ON 1/42. AND 1/14- NUREG-1210 V01: PILOT PROGRAM NAC SEVERE REACTOR ACCI-SCALE CATEGORY I, AUX 1UARY BUILDING DENT WEM RENSE MMNG MAL h And Sum-tury Of Major Posnts Setemoc-Fregety Response NUREG 1210 V02. PILOT PROGRAM NRC SEVERE REACTOR ACCI-NVAEGICR4098. SEISMC-FRAG!LITY TESTS OF NEW AND ACCEL. DENT INCCENT RESPONSE TRAIN:NG MANUAL Severe 9eactcr Ac-ERATED AGED CLASS 1E BATTERY CELLS cdent Ovemew NVAEG-1210 V03 PILOT PROGRAM NRC SEVERE REACTOR ACC3-Seismietty DENT INCCENT RESPONSE TRAIN NG MANUALResponse Of Lk NUREGICR 3145 VOS GEOPHYSCAL INVESTIGATCNS OF THE censee And State And Local 0%afs. WESTERN OHlo tNDIANA REGCN Frial Aeport,0ctocer 1981. Sec. NUREG 1210 V04 PfLOT PROGRAM NRC SEVERE REACTUR ACCI-tomber 1986 DENT INCCENT RESPONSE TRAINING MANUAL Putec Protective NURE G/CR 4623 IN SITU STRESS MEASUREMENTS IN THE Actons Predetermined Cntena And Irvttal Actons EARTH'S CRUST IN THE EASTERN UNITED STATES NUREG 1210 V05. PTLOT PROGRAM NRC SEVERE REACTOR ACCl-NUREG/CR 4753 V02 CANADIAN SEISMC AGREEMENT. Annual DENT INCCENT RESPONSE TRAIN!NG M ANUAL U $ Nuclear Regu-Report latory Commrst,on Response

134 Subject Index NUREG 1250 R01: REPORT ON THE ACODENT AT THE CHERNOBYL Shipping Container NUCLEAR POWER STATION- NUREG/CR-3966: METHODS FOR IMPACT ANALYSIS OF SHIPPING NUREG 1264: CONTA1NMENT INTEGRITY RESEARCH PROGRAM CONTAINERS. PLAN. NUREG/CR4829 V01: SHIPPING CONTAINER RESPONSE TO NUREG 1265: UNCERTAINTY PAPERS ON SEVERE ACODENT SEVERE HIGHWAY AND RAILWAY ACCIDENT CONDITONS Mast SOURCE TERMS. NUREG/CP-0078: PROCEEDINGS OF THE SYMPOSIUM ON CHEMI-CAL PHENOMENA ASSOCATED WITH RA060 ACTIVITY RELEASES NUREG/CR-4829 M S 6 NG CONTAWER RESPONSE TO OURING SEVERE NUCLEAR PLANT Amt)ENTS SEVERE HIGHWAY AND RAILWAY ACODENT NUREG/CR4165: SEVERE ACCOENT MJENCE ANALYSIS PRO- CONDITONS.Apperoces GRAM ANTCIPATED TRANSEN. THOUT SCRAM SMULA-TONS FOR BROWNS FERRY NUCLEAM PLANT UNIT 1. ohne Enhnent NUREG/CR-4216: EXPERIMENTAL RESULTS FOR A 1.8 SCALE STEEL NUREG/CR-49$0 V02: THE SHORELINE ENVIRONMENT ATMOS-MODEL NUCLEAR POWER PLANT CONTAINMENT PRESSURIZED PHERC DISPERSION EXPERIMENT (SEADEX)Meteorologeal And TO FAILURE. Gas Tracer Data. NUREG/CR4320 THE RELATIONSHIP AND INFLUENCES OF FUEL AND COOLANT SYSTEM PROCESSES DURING LWR SEVERE ACo. Shutdown DENTS. NUREG/CR-4448: SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF NUREG/CR-4551 V1 DAF: EVALUATON OF SEVERE ACODENT A GENERAL ELECTRC BWR3/ MARK t Case Study. RISKS AND THE POTENTIAL FOR RtSX REDUCTION SURRY NUREG/CR-4458: SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF POWER STATON. UNIT 1 Draft For Comment A WESTINGHOUSE 2-LOOP PRESSURIZED WATER REACTORCase t NUREG/CR-4551 V2 DAF: EVALUATON OF SEVERE ACCCENT Study. RISK $ AND THE POTENTIAL FOR RISK REDUCTON SEQUOYAH NUREG/CR-4710 SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF POWER STATON. UNIT 1. Dram For Comment. A COMBUSTION ENGINEERING PPESSURIZED WATER NUREG/CR-4551 V3 Pf1: EVALUATON OF SEVERE ACODENT RISKS REACTOR. Case Study. AND THE POTENTIAL FOR RfSK REDUCTON. PEACH NUREG/CR-4713. SHP ITDOWN DECAY HEAT REMOVAL ANALYSIS OF A BABCOCK AND WILCOx PRESSURIZED WATER REACTOR. Case NU E CR 1 2 AL AT OF RE ACODENT RISKS AND THE POTENTIAL FOR RISK REDUCTON, PEACH NUR /CR-4762: SHUTDOWN DECAY HEAT REMOVAL ANALYSS OF NU E CR 51 V E LUA$ON SEVERE ACODENT A WESTINGHOUSE 3-LOOP PRESSURIZED WATER PIACTOR. Case RISKS AN THE PO FOR RISK REDUCTION. GRAND NUR /CR4767: SHUTDOWN DECAY HEAT REMOVAL ANALYSS OF , NUREG/CR-4552 A REVIEW OF THE SEABROOK STATON PROBABl. A GENERAL ELECTRC BWR4/ MARK l. Case Study. LISTO SAFETY ASSESSMENT.Contanment FaAre Modes And Rads NU CR . ECTS OF LATERAL SEPARATON OF OxlCtC REG /CR4577: AUTOMATED LONG TERM SURVEILLANCE OF A AND METALLO CORE DEBRIS ON THE BWR MK I CONTAINMENT COMVERCIAL NUCLEAR POWTR PLANT. ORYWELL FLOOR. NUREG/CR4696: CONTAINMENT YENTING ANALYSIS FOR THE simuletion Fecepty PEACH BOTTOM ATOMC POWER STATON NUREG 1258. EVALUATON PROCEDURE FOR SMULATION FACILL NUREG/CR4700 V1 DRF: CONTAINMENT EVENT ANALYSIS FOR TIES CERTIFIED UNDER 10 CFR 55 Final Report POSTULATED SEVERE ACODENTS. SURRY POWER STATON. UNIT NUREG 1?58 DRFT: EVALUATON PROCEDURE FOR SMULATON 1 Dran For Comment FAOLfhES CERTIFIED UNCSR 10 CFR 55 Dram Report NUREG/CR-4700 V2 DRF: CONTAtNMENT EVENT ANALYSl$ FOR 4 POSTULATED SEVERE ACCCENTS: SEQUOYAH POWER Singeded Fuel Codes Program 1 STATNUNIT 1. Dram Report For Comment NUREG/CR 4718. EXPERIMENTAL SUPPORT ANC DEVELOPMENT OF NUREG/CA-4700 V4 DRF: CONTAINMENT EVENT ANALYSl3 FOR $3 ctg.gog , .lEL CODES PROGRAM Summary Report POSTULATED VVERE ACODENTS, GRAND GULF NUCLEAR ] STATON, UNIT 1Wt "or Commet. Sete Cherectortastion NUREG/CR4719: COOLABluTY OF STRAtlFIED UO2 DEBRIS IN NUREGICR4957; SURVEY OF GEOPHYSCAL TECHNOUES FOR 2 NU 41: ATE TR N D$A AK TE CHARACTERl2ATON IN BASALT SALT AND TUFF. LOSS OF COOLANT ACODENT ANALYSES FOR THE BELLEFONTE Sete Sm Reeponse Spectre [ NU / 4 FT. STUDY OF SEVERE ACODENT WITIGATON NUREG/CR4861: DEVELOPMENT OF SITE SPECIFO RESPONSE SYSTEMS. SPECTRA-i NURdG/CR4666. AN ASSESSMENT OF HYDROGEN GENERATON FOR THE PSF SEVERE FUEL DAMAGE SCOPING AND t 1 TESTS. SMn Contaminenon NUREG/CR-4870 AN EVALUATON OF THE EFFECTS OF DESGN NUREG/CR4418 DOSE CALCULATON FOR CONTAM NATON OF DETAILS ON THE CAFK/TY OF LWR STEEL CONTAINMENT THE SKrN USNG THC COMPUTER COOE VARSKIN BUILDINGS. j NUREG/CR4876: SLVER-INDIUMCAoMlUM CONTROL ROC BEHAV. Smas Broek LOCA IOR AND AEROSOL FORMATON IN SEVERE REACTOR ACCb NUREG/CR 4550 V05. ANALYSS OF CORE DAMAGE FREOUENCY DENTS. FROM INTERNAL EVENTS: SEQUOYAH, UNIT 1. NUREG/CR-4883. REVIEW OF RESEARCH ON UNCERTAANTIES IN NUREG/CR4 s11: LOW UPPER-SHELF TOUGHNESS.HIGH-TRANSb ESilMATES OF SOURCE TERMS FROM SEVERE ACODENTS IN TION TEMvERATURE TEST INSERT IN HSST PTSE 2 VESSEL AND NUCLEAR POWER PLANTS WIDE-PLATE TEST SPECMENS. Fnal Report NUREG/CR-am MELPROGPAR/MOOO A MECHANISTC CODE FOR NUREG/CR-4788 44 ANALYTCAL AND EXPER! MENTAL INVESilGA-ANALYSS OF REACTOR CORE MELT PROGRECON AND VESSEL TON OF NATURAL ORCULATON TRANSENTS IN A MOCEL PRES-ATTACK UNDER SEVERE ACODENT CONOTONS SUR12ED W ATEA REACTOR NUREG/CR4944 CONTAINUENT PENETRATION ELASTOMER SEAL NUREG/CR4789. THE S;MULATON OF THERMOHYDRAULC PHE-LEAX RATE TESTS. NOMENA IN A PRESSURIZED WATER REACTOR PRIMARY LOOP. NUREG/CRA962- SEVERE ACODENTS IN SPENT FUEL POOLS IN NUREG/44793. RESULTS OF SEMISCALE MOD 2C SMALL BREAK

                                                                                                            -COOLANT ACODLNT WITHOGY HPI (S-NH) EXPER.Mth.'

4 NUR CR 50 VAL A AR POWER PLANTS IN THE UNITED STATES. OF R AL HAZARDS TO NUCLE- [ ' Severe Fuel Demoge Software l NUREG/CR-4925: FISSION PRODUCT BEHAVOR DURING THE PBF NUREG/CR4640 HANDBOOK OF SOFTWARE QUAUTY ASS A ANCE SEVERE FUEL DAMAGE TEST 11. TECHNOVES APPLCABLE TO THE NUCLEAR INDUSTRY. l' Shaft Seal 808 NUREG/CR4421 RiEACTOR COOLANT PUMP SHAIT SEAL STABILL NUREG/CA-4976 PLANT RH120 SPHERE PROCESSES INFLUENONG TY DURtNG STATION BLACKOUT. RADONUCLOE MOBtLITY IN SOIL e-. - _ . - , - . , _ . . , , . - - - , - - . ,. -- , _ - , - , - _--_-__ . _ . . _ - -

Subject index 135 Soil-Structure Interact > Spent Fuel Weste Form NUREGfCP4054 PROCEEDINGS OF THE WORKSHOP ON SOfL- NUREG/CR4954 LONG TERM PERFORMANCE OF SPENT FUEL STRUCTURE INTERACTON. WASTE FORUS. Solenoid Operated Valve stainlese Steel NUREG/CR4819 VO1: AGING AND SERVICE WEAR OF SOLENOO* NUREG/CR 4727. SWISS SUSTAINED HEATED METALUC MELT / CON-OPERATED VALVES USED IN SAFETY SYSTEMS OF NUCLEAR CRETE INTERACTONS WITH OVERLYING WATER POOLS 00WER PLANTS volume 10peratog Experence And Failure identifF NUREG/CR4744 V02 N1; LONG-TERM EV8RITTLEMENT OF CAST catort DUPLEX STAINLESS STEELS IN LWR SYSTEMS Semiannual NUREG/CR-5008. DEVELOPMENT OF A TESTING AND ANALYSIS RepMOcth 1986 March 1987. METHODOLOGY TO DETERMINE THE FUNCTONAL CONDITON OF NUREG/CR4872: EXPERIMENTAL AND ANALYTCAL ASSESSMENT SOLENOID OPERATED VALVES- OF CIRCUMFERENTIALLY SURFACE CRACKED PIPES UNDER BENDING UAE / R 290 V05 RADOACTIVE MATERLALS RELEASED FROM afRep NUCtEAR POWER PLANTS. Annual Report 1984. E ELDS T NUREG/CR4970- STAINLESS STEEL ROUND ROBIN Sohdincate TEST Centnfugany Cast Stainless Steat Screerung PhasA NUREG/CR 3444 V04: THE IMPACT OF LWR DECC8PAMANATONS ON SOLOtFCATION, WASTE DISPOSAL,AND ASSOCIATED OCCU- 8" PATONAL EXPOSURE. Annual Repod, Fiscal Year 1986. NAG 6 1 DR F STANDARD FORMAT AND CONTENT FOR EVERGENCY PLANS FOR FUEL CYCLE AND MATERIALS Solutputy FACIUTIES Dra4 Report For Comment. NUREG/CR4665. THE SOLUBlufY OF ELECTRODEPOS4TED TC(IV) NUREG-1280: STANDARD FORMAT AND CONTENT ACCEPTANCE . OXOES CRITERIA FOR THE MATERIAL CONTROL AND ACCOUNTING (MC&A) REFORM AVENOMENT.10 CFR Part 74 Sutpart E. Solute Transport

,                                           NUREG/CR4615 V02: MODEUNG STUDY OF SOLUTE TRANSPORT                                                                                                                Standard Review Plan                                                                                                                    ;

. IN THE UNSATUPATED ZONE. Workshop Procee6ngs NUREG-0800 06.5 2 R2. STANDARD REVIEW PLAN FOR THE REVIEW NUREG/CR4655: UNSATURATED FLOW AND TRANSPORT OF SAFETY ANALYals REPORTS FOR NUCLEAR POWEH THROUGH FRACTUPED ROCK RELATED TO HIGH LEVEL WASTE PLANTS LWR E$ ton Proposed Revis.on 2 To Sectson 6 5.2 "Contan. REPOSITORIES Final Report . Phase il ment Spray As A Frssson Product Cleanup System." For Comment. NUREG/CR4737: INTERPRETATIVE ANALYSIS OF DATA FOR NUREG 0800 06 5.5 R0 STANDARD REVIEW PLAN FOR THE REVIEW SOLUTE TRANSPORT IN THE UNSATURATED ZONE OF SAFETY ANALYS1$ REPORTS FOR NUCLEAR POWER NUREGiCR4875: CHARACTERIZATON OF CRUSHED TUFF FOR THE PLANTS LWR E6 ton Proposed Revtson 0 To New SAP Secton 6 5 5. I EVALUATON OF THE FAT 6 OF TRACERS IN TRANSPORT STUDIES

                                                                                                                                                                                                                                       .. Pressure Suppresson Pools As Fessson Product CleaAUp Systems."

IN THE UNSATURATED ZONE- For Cr ent NUREG 1 AO, STANDAAD REVIEW PLAN FOR THE REVtEW OF A Lt.  ; NU EG 265: UNCERTAWTY PAPERS ON SEVERE ACCOENT CENSE APPLCATION FOR A LOW-LEVEL RADOACTfvE W ASTE ,' SOURCE TERMS DISPOSAL FACIUTY. t NUREG/CR4552 A REvrew OF THE SEABR00K STATION PROBAB,. NUREG 1300 ENVIRONMENTAL STANDARD REVIEW PLAN FOR THE  ; USTIC SAFETY ASSESSMENT. Containment Fadure Modes And Rai. REVIEW OF A LCENSE APPLCATON FOR A LOW-LEVEL RADIO- ! ological Source Terms ACTIVE WASTE DISPOSAL FACluTY. 1 NUREG/CR-4722 SOURCE TERM ESTIMATON US4NG UENU-TACT. NUREG/CR4883 RFVIEW OF RESE ARCH ON UNCERTAINTIES IN Startup t ESTIMATES OF SOURCE TERMS FROM SEVERE ACCOENTS IN NUREG 1275. OPERATING EXPERIENCE FEEDBACK REPORT . NEW  ; NUCLEAR POWER PLANTS PLANTS. Commercial Power Reactors NUREG/CR-4897. LOW-LFVEL WASTE SOURCE TEAM . i EVALUATON Reve* of Pubtshed Modenng And Expenmental State Pubhc Utsty Comtrusson + , Work.And Presentaten Of Low-Level waste Source Term Modehng NUREG 1256 VOI: LNCENTIVE REGULATON OF NUCLEAR POWER Framework And Preirrunary Modsi Development PLANTS BY STATE PUBUC UTIUTY COUV:SSONS Southern confornia States 1 4 NUREGmR 4801: CUMATOLOGY OF EXTREME WINDS IN SOUTH. NUREG/CP-0085 MEEl&G WITH STATES ON THE LOW-LEVEL RA- ) i ERN CAL @N4 DIOAC'!VE WASTE POUCY AMENDMENTS ACT (LLRWPAA) OF  ! ! 1985 f Spatial VariatWkty r NUREG/CR-4901: EF' ICTS FROM INFLUENT BOUNDARY CONDL Static Air  ! TONS ON TRACEF M;GRATION AND SPAttAL VARIABluTY FEA* NUREGICR 4779 NEW DATA FOR AEROSOLS GENERATED BY RE- i TURES IN INTERVEJtATE-SCALE EXPEReVENTS LEASES OF PRESSURIZED POWDERS AND SOLUTONS IN STATC f Spectroscopy NUREG/CR4861 SURFACE SPECTROSCOPY OF PRESSURE Station Blackout i VESSEL STEEL FATIGUE FRACTURE SURFACE FILMS FORMED IN NUREG/CR4550 V03 ANALYSIS OF CORE DAVAGE FREQUENCY > PWW ENYtRONMENTS FROM INTERN AL EVENTS SURRY UNIT 1. NUREG/CR4742 UELPROG PWR/ MOO 1 AN ALYSIS Oc A TULB' AC-R CR 3966 METHOOS FOR LMPACT ANALYSIS OF SH:PPING CONTAINERS. NAG 4 1 REACTOR COOLANT PUUP SHAFT SEAL STAB lU-TY DUA:NG STATION BLACKOUT. Spent Fuel Cask NUREG/CR4942 EQUiPVENT OPERAB!LITY DUR NG STATON l NUREG/CR4829 V01: SHIPPtNG CONTA:NER RESPONSE TO BLACKOUT EVENTS  ; SEVERE HIGHWAY AND RAILWAY ACCOENT CONOtTONS Mac gg,,, NUR CR4829 V02. SHiPPtNG CONTAINER RESPONSE TO NUREG/CR4963 BORON CARBOE STEAM REACTIONS WITH f SEVERF HIGHWAY AND RA!LWAY ACCIC;NT CEStVM HYDRO *CE AND WITH CF.S!UM COtDE At 1270K IN AN f CONDITONS Wes. INCONEL 600 SYSTEM [ Spent Fuel Pool Steam Air Environment NUREG/CR4982: SEVERE ACCOENTS IN SPENT FUEL POOLS IN NUREG/CR4796 IRCN OXIDE AEROSOL ExPER.MENTS IN STEAM-  ! SUPPORT OF GENERC SAFETY ISSUE 82. AIR ATMOSPHERES NSPP TESTS $01505 AND 511. DATA RECORD l; REPORT. Spent Fuel Shipment NUREG/CR-5017 UVESTONE CONCRETE AEROSOL EXPER! VENTS  ! NUREG/CR4847. CASE Hl$TOA:ES OF WEST VALLEY SPENT FUEL IN STE AM-AIR ATMOSPMERES NSPP Tests 521.522.And $31. Data  ! SHiPVE NTS Final Report Record Repod  ? i

136 Subject index Steam Generator Stuck Open Safety Reuef Valve NUREG/CR 4752: COINOCENT STEAM GENERATOR TUBE RUPTUAE NUAEG/CR-4752: COINCIDENT STEAM GENERATOR TUBE RUPTURE AND STUCK-OPEN SAFETY REUEF VALVE CARRYOVER AND STOCKOPEN SAFETY REUEF VALVE CARRYOVER TESTS US-2 Steam Generator Trans,ent Response Test Program TESTS MB 2 Steam Generator Transent Response Test Program. NUREG/CR-4817. IOD:NE PARTITCN COEFFCENT ME ASUREMENTS AT SiMULA1ED PWR STEAM GENERATOR CONDITONSIntenm Subsurface Surial 4 Data Report NUREG 1101 V02. ONSITE DISPOSAL OF RADC 4CTIVE NUREG/CR-4848 STEAM GENERATOR GROUP PROJECTAnnual WASTE Methodology For The Radiological Assessment Ci @sposal By Report 1985. Subsurf ace Bunal. NUAEG/CR4850. STEAM GENERATOR GROUP PROJECT. Task 10 - Secondary See Esammat on Final Report Success Like# hood inden Methodology

• NUAEG/CR4016 V02: APPLCATON OF SUM-MAUDA TEST OF AN Steam Separator Modehng INTERACTIVE COMPUTER-BASED METHOD FOR ORGANIZING NVAEG/CR4922: STEAM SEPARATOR MODEUNG FOR VAACUS EXPERT ASSESSMENT OF HUMAN PERFORMANCE AND NUCLEAR REACTOR TRANStENTS REUAB3UTY. Volume 11 Appendices Steam Supply Surface Crack NUAEG-0852 S03 SAFETY EVALUATON REPORT RELATED TO THE NUREG/CR4841: FRACTURE EVALUATON OF SURFACE CRACKS l FINAL DES;GN OF THE STANDARD NUCLEAR STEAM SUPPLY EVBEDDED IN REACTOR VESSEL CLADDING Urwradiated Bond '

REFEAENCE SYSTEM CESSAR System 80 Docket No 50-470(Com- Specmen Resuits, buston Er9neereg incorporated) Survettience Steel NUREG/CR4577: AUTOMATED LONG. TERM SURVEILLANCE OF A NUAEG/CR4216 EXPER:VENTAL RESULTS FOR A 18-SCALE STEEL COMMERCIAL NUCLEAR POWER PLANT. MODEL NUCLEAR POWER PLANT CONTAINVENT PRES $URt2ED TO FAILUAE. Surveillance Dosimetry impresement Program NUAEG/CR4219 V03 N2 HEAVY SECTION STEEL TECHNOLOGY NUAEG/CR4307 V03. LWR PRESSURE VESSEL SUAYEILLANCE 00-PAOGRAM Semiannual Progress Report For Aprd-Septereber 1986 SiMETRY IMPROVEMENT PROGRAM 1986 Annual Report, October NUAEG/CR4724 FATGUE CRACK GROWTH RATES IN PRESSURE 1985 September 1986. VESSEL AND PtPiNG STEELS IN LWR ENVIRONVENTS Feal Report NUAEG/CR4863. SURFACE SPECTROSCOPY OF PRESSURE Surveillance Robot VESSEL STEEL FATGUE FRACTURE SUAFACE FILUS FOAVED IN NUREG/CR4815: DEMONSTRATON TESTING OF A SURVEILLANCE  ! PWD ENViAONVENTS ROBOT AT BROWNS FERRY NUCLEAR PLANTAna'ysts Of Costs NUAEG/CR4870. AN EVALUAftON OF THE EFFECTS OF DESIGN And Benetits. I DETAILS ON THE CAPACITY OF LWR STfiL CONTAINMENT  ! Butt.DrNGS Surveillance Techniquee ' L , NUREG/CR4892. A STUDY OF THE EFFECTS OF PENETRATION NUREG/CR4626 V02 IMPROVING THE REUABlUTY OF OPEN. < FRAMM ON STEEL CONTAINVENT BUCKUNG CAPACITY CYCLE W ATER SYSTEMS. Appiscaton Of Bofouleg Surveillance And NUREGICR4904 INVESTGATON OF STEEL CONTAtNMENT BUCK- Control Techtvgues to Sediment And Corrosson Fouing At Nuclear UNG FROM DYN AMC LOADS Power Plants. NUREG/CR4926- AN ASSESSMENT OF LOSS-OF CONTAINVENT PO- , TENTIAL BECAUSE OF KNUCKLE BUCKUNG FOR 41 STEEL CON- System Analysis , TA:NVENT HEADS. NUREG/CR4458. SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF  ! NUREG/CR4930 CAACK ARAEST BEHAVCR tN SEN WCE PLATES A WESTINGHOUSE 2 LOOP PRESSURIZED WATER REACTOR Case OF OUENCHED AND TEMPERED A 533 GRADE B STEEL TESTED Study UNDER NONISOTHERMAL CONDITCNS NUREG/CR-4710' SHUTDOWN DECAY HEAT REMOVAL ANALYSJS OF 4 A COMBUSTON ENGINEEAiNG PAESSURIZED WATER Strategec Special Nuclear Material REACTOR Case Study ' NUREGrCA4695 MATER.AL CONTROL ANO ACCOUNTING (MCAA) NUREG/CR4713 SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF LOSS DETECTON DURiNG TRANSITION PERIODS AND PROCESS A BABCOCK AND WILCOX PRESSURIZED WATER REACTORCase UPSEi CONDITONS Study. l NUREG/CA 5002 VETHODS FOA RECUARtNG LOSS TESTS NUREGICR4762. SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF , NV9EGICR 5003 DESGN OF A MATEAtAL CONTROL AND AC- A WESTINGHOUSE 3-LOOP PRES $URIZED WATER REACTOR Case l 2 COUNTING SYSTEV TO PROTECT AGAINST CONCEALMENT OF Study. ' DIVERSON BY FALS;FCATON AND COLLUSCN t NUREG/CR4826 V01: SEISMC MARGIN REVIEW OF THE MAINE YANKEE ATOMC POWER STATION Volume 1. Report. l 1 Stress NUREG/CR4826 V02 SEISMC MARGIN REVIEW - THE MAINE NUAE G/CA 4910: RELAY CHATTER AND OPERATOR RESPONSE YANKEE ATOMC POWER STATCN Volume 2 Systems Ana'yss.

AFTER A LARGE EARTHOUAkE An improved PRA Methodology W4h NUAEG/CR4826 V03. SEISMC MARGIN AEVIEW OF THE MAINE Cese 5tudies YANEEE ATOMC POWER STATCN Volume 3 'tagety AnaWs.

4 Stress Corros+en Crack 6ng System interaction 1 NUAEG/CR 3061 STRESS-CORROSON CRACKING OF LCW- NUREG/CA4715 AN AGING ASSESSMENT OF RELAYS AND CIA-STRENGTH CAABON STEELS IN CAND'DATE HGH-LEVEL W ASTE CUTT BREAKERS AND SYSTEu tNTERACTIONS. REPOslTORY ENVAONVENTS NUAEG/CR4667 V03 ENViRONVENTALLY ASSISTED CRACKING IN Systematic Assessment Of Ucensee Pedormaxe UGHT W ATER RE ACTORS Sem annual Repcrt.Aprd-September 1986 NUREG-1214 R01: HISTORCAL DATA SUMM/ HY OF THE SYSTEMAT. IC ASSESSMENT OF UCENSEE PERFOAMANCE. Stress Weasurement NUAEG'CR 4623 IN-SIT U STRESS MEASUREMENTS IN THE SystematM: Assessment Of Ucensee Performance EARTH S CAUST IN THE EASTERN UNITED STATES NUREG 1214 R02: HISTORCAL DATA

SUMMARY

OF THE SYSTEMAT. C ASSES $ MENT OF LCENSEE PERFORMANCE. Structural Integrity NUREGICR 4219 V03 N2 HEAVY-SECTION STEEL TECHNOLOGY Systematic Evaluat>on Program PAOGRAM Sermannual Progress Report For AprSSeptember 19%6 NUA EG-0825 S01: INTEGRATED PLANT SAFETY NUREG/CR 4219 V04 N1 HEAVY SECTION STEEL TECHNOLOGY ASSESSMENT.SYSTEMATC EVALUATION PROGRAM, YANKEE to PROGRAM Semennual progress ReCort for October 19A6 March CLEAR POWER STATION Docket No 50-029. (Yankee Atome Electne 1987. Company) f Structurei Mechanacs TLD NUpEG/CP 0088 TRANSACTONS OF THE 9TH INTERNATIONAL NVAEG-0437 YC6 NO3 NAC TLD DIRECT RADIATION MONITORING CONFERENCE ON STRUCTURAL MECHANCS IN REACTOR NETWOAK Progress Report Juty September 1986 TECHNOLOGY Panel Sesson JK Structura! And Mechancal Er9neer. NUREG 0637 VO6 N04 NRC TLD DIRECT RADIAT80N MONITORING

rg Aena ch At The U S Nsciear Regulatory Corrmston NE TWORK Progress Aeport. Octoter-December 1986 r

i i

  . .-- - - ~ _ _ -                             _ _ _ _ _  _ . . - _ _ , _ _ _ ___--_-,m.                  _

l i Subject Index 137 l NUREG4837 V07 N01: NRC TLD DIRECT RAOtATON MONITORING NUREG/CR-4711: LOW UPPER SHELF TOUGHNESS.HIGH TRANSI-NETWORK Progress Report, January March 1987. TON TEMPERATURE TEST INSERT IN HSST PTSE 2 VESSEL AND [

                     ~ NUREG-0837 V07 NO2- NRC TLD OlRECT RADIATON MONITORING                                                     WCbPLATE TEST SPECMENS. Frial Report

• NETWORK Progress Report. Apr4-June 1987. NUREG/CR-4891: PROPERTIES OF REACTOR FUEL ROO MATERIALS NUREG4837 V07 NO3. NRC TLD OIRECT RADtATCN MONITORtNG AT HIGH TEMPERATURES Final Summary Report Severe Core NETWORK. Progress Report, Jufy-September 1987. Damage Property Tests Prograrn. i

                           ,                                                                                                    NUREG/CR4953. CORRELATCN OF RADtOCOINE RESUSPENSION REG /CR4711: LOW UPPER SHELF TOUGHNESS,HGH-TRANSI-                                                          '                                                      '

TON TEMPERATURE TEST INSERT IN HSST PTSE 2 VESSEL AND Temperature Sensor i NU / 42 EP - R/ LYSIS OF A TUL7/ AC. P N RS' CIDENT SEQUENCE-Test interval NUREG/CR4810 EVALUATON OF DIESEL V. AWL sB!UTY ANO

                      ' ' REG /CR-4645: TOUGH USER S GUCE' RISK EFFECTIVE SURVEILLANCE TEST INTEP AL S TEAC-PF1/ MOO 1 NUREG/CR4802: AN EVALUATION O" TRAC-PF1/ MODI COMPUTER                                                  Test S-LH-2                                                                                                                                                           i CODE PERFORMANCE DURING POSTTEST S;MULATIONS OF SE.                                                   NUREG/CR 5010. RELAP5/ MOO 2 ASSESSMt:NT USING SEMISCALE                                                                                                            l MrSCALE MOO-2C FEEOWATER UNE BREAK TRANSIENTS.                                                          EXPERIMENTS b NH-1 AND S-LH-2                                                                                                                                    j NUREG/CR4845: AN ANALYSIS OF THE SEMISCALE L C-2C S-NH-3                                                                                                                                                                                                                     i TEST U?tNG THE TRAC-PF1 COMPUTER PROGRAM                                                            Test S-NH 1                                                                                                                                                          [

NUREG/CR4965. TRAC-PF1/ MOO 1 US/ JAPANESE PWR CONSERVA- NUREG/CR 5010 PELAP5/ MOO 2 ASSESSMENT US:NG SEMSCALE  ; TfVE LOC', PREOCTON EXPERIMENTS S-NH-1 AND S-LH-2. l NUREG/CR4988 A TRAC-PFI/ MOO 1 ANALYSIS OF THE GtNNA TUBE-RUPTURE EVENT ON JANUARY 25.1982 Test S-NH-3 , NUREG/CR-4799 RELAP5/ MOO 2 ASSESSMENT S:MULATCN OF SE-

• TDGA Reactor MISCALE MOC'2C TEST S-NH-3. L 1 NUREG-1282. SAFETY EVALUATCN REPCRT ON H GH-URAN!UM '

CONTENT, LOW-ENRCHED URANIUM-ZlRCONtVM HYORCE Thermal Mistreg FUELS FOR TAGA REACTORS Oocket No. 50163 (G A NUREG/lA 0004 THERMAL MUUNG TEST 3 IN A SEM1 ANNULAR i Technolog es, incorporated) DOWNCOMER WITH INTEPACTING FLOWS FROM COLO LEGS. i

                                                                                                                                                                                                                                                                                                  )

Toering Behavior Therme4-Hydraulic Production cme 6 NUREG/CR4760: TEST OF 6-tN,TH CK PRESSURE VESSELS Senes NURFG/CR4758. A RETRAN MODEL OF THE CALVERT CLIFFS-1 31ntermediate Test Vessel V-8A.Tearng Behamr Of Low Upper Sheff r AtSSURIZED WATEP REACTOR FOR ASSESSING THE SAFETY Matenal- IMPUCATONS OF CONTROL SYSTEMS,

.l                                                                                                                                                                                                                                                                                                ,

TochtWest Specificat>on Thermel-Hydraulice NUREG-1235: TECHNCAL SPECIFICATONS FOR CUNTON POWER NUREG 1244. PLAN FOR INTEGRATING TECHNCAL ACTIVITIES

• ^

NU 23 E C F O F YOG LECTRC [R HY R S l GENERATING PLANT. UNIT 10ocket No W424(Georgia Power NUREG/CR-4789 THE S:MULATION CF THERMOHYORAULC PHE. i N NU 17 0: TECHNCAL SPECIFICATONS FOR SHEARON HARRISNUREG/ 2 EVA AT O T GRAL TN P G EXP NUCLEAR POWER PLANT. UNIT 1 Docket No 50-400 (Carolma Poner MENTAL CAPABlWTY (CEC) CCNCEPTS FOR LIGHT WATER REAC-  ; TOR RESEARCH PWR SCALING CONCEPTS. l NURE 1 E NICAL SPEOFICATCNS FOR VOGTLE ELECTRC NUREG/CR4845 AN ANALYSIS OF THE SEMiSCALE MOO-2C S-NH-3 i GENERATING PLANT,0 NIT 1 Docket ho 50424(Geor@a Power TEST USING THE TRAC PF1 COMPUTER PROGAAM NUREG/CR-4966 V02- EVALUATON OF OPERATIONAL SAFETY AT , NU 1748 TECHNCAL SPEGFCATONS FOR PALO VERDE NU. CLEAR GENERATING STATION. UNIT 3 00cket No. W530(Antona BABM W MW MTS VM 2 - hmaWah Re. . l Public Semco Company  ! NUREG 1253 TECHNCA)L SPECFICATIONS FOR NINE MILE I POINT Y ' NUCLEAR STATON. UNIT 2 Docket No W410(N.agara Mohann l f 330- MELCOR VAUDATCN AND VERIFICATCN 1986 FM PAPERS j i NU 1 L SFEOFCATIONS FOR SOUTH TEXAS PROJECTMNIT 1. Doc 6et No 50498 fHouston Ughteg and Power Thermolummescent Oosimeter l ! NV 1 9 TECHNCAL SPEOFCATCNS FOR SEAVER VALLEY NUREG-0837 V06 NO3 NRC TLD DIRECT RADtATCN MONITORING L POWER STATON. UNIT 2 Docket Po %412(Ouguesne Lght Com- R NURE 0837 H R TON MONITORING NU 1261. TECHNCAL SPECIFICATONS FOR BRAOWOOD NETWORK Progress Report, October December 1986 r NUREG-0837 V07 NO2 NRC TLD DIRECT RADIATION MONtTOR;NG l. STATON. UNITS 1 AND 2 Docket Nos %456 A-d 50-457 (Common- NETWORK Prorress Report, Apr4Wne 1987 Compa NU7E 12 6 TECHN L SPECFCATONS FOR BRAIDWOOO NUREG 0837 V07 NO3 NRC TLD OIRECT RADIATON MONITORING NETWORK. Progress Report, Jury-September 1987. GTATON UNITS 1 AND 2 Dociet Nos 50 456 And 50457(Common-ThrougWan Crocked hpe NURE 12 9 T L SPEOFCATIONS FOR BEAVER VALLEY NUREG/CR 489 APPROX; MATE METHOOS FOR FRACTURE ANALY. POWER STATCPt UNIT 2 Doct et No W412 (Duquesne Lght , SES C# THROUGH-W ALL CRACAEO PIPES > NU tI8Y TECHN CAL SPECFICATONS FOR PALO VERDE NU-EAR GEN RA STATON, UNIT 3 Docket No W530(An cca UE 0540 V08 N10: TITLE LIST OF DOCVMENTS MADE PUBLCLY , AV AILABL E. October 1 31.1986 L Tectonic Activity NUREG 0540 V04 N11: TITLE UST OF DOCUMENTS MADE PUBLICLY r NUREG /CR4852 THE MEERS Faut,T TECTONC ACTIVITY IN AVAILABLE. Novernber 1 30.1986 i SOUTHWESTE RN O* LAHOMA NUREG 0540 V08 N12 TlTLE UST OF DOCUMENTS MADE PUBUCLY , AVAtLABLE Decerber 1 31,1986 Tectorwsm NUREG.0540 Vos Nat TsTLE UST OF DOCUVENTS MADE PUBUCLY NUREG/CR.5034 AN UPDATE - M OCONTiNENT TECTONtSM AVAILABLE. Arcary 1 11.1987 NUREG-0540 V09 NO2 hTLE UST OF DOCUMENTS MADE PUBUCLY Temperature AVAILABLE February 1 28.1987 NUREG/CR 3024 SUST A'NE O CONCRETE ATTACK BY LOW- NUREG4540 V09 N01. TITLE LIS1 OF DOCU./ENTS MADE PUBLCLY , TEMDERATUAEf RAGVENTED CORE DEBR!S AVAILABLE. March 1 31.1987  ; 4 t

   ,__.-,.,-r.----.                        .          ,        , _ - - . , , . . . _ . _ _                _._..._.,,_,___,._m                         , - . - . - -                                                                           _ - , , - - ~ . . . - - - - - . - . - - - - . -

138 Subject Index NUREG-0540 V09 N04. TITLE UST OF DOCUMENTS MADE PUBUCLY NUREG438.3 V02 R10: DIRECTORY OF CERTIFICATES OF COMPU. AVAILABLE. aped i 301997. ANCE FOR RADCACTIVE MATERIALS PACKAGES CertAcates Of NUREG 0540 V09 N05 IITLE UST OF DOCUVENTS MADE PUBLCLY Compece-AV AILABLE, May 1 31,1987. NUREG-0383 V03 R07: DIRECTORY OF CERTIFICATES OF COMPU. NUREG 0540 V09 N06. TITLE UST OF DOCUMENTS MADE PUSUCLY ANCE FOR RADOACTIVE MATERIALS PACKAGES Summay Report Of NRC Approved Ovakty Assurance Programs For Radioactere Materb NURE V N T E UST OF DOCUMENTS MADE PUBLCLY AVAILABLE My 1 31,1987 #*9" NUREG4540 V09 NOS- TITLE LOT OF DOCUMENTS MADE PUBLICLY AVA1ABLE August 1 31 1987 U '"" # 8 " " A** * "I NUREG4640 V09 N09 TITLE UST OF DOCUVENTS MADE PUBUCLY NUREG/CR 5042. EVALVATON OF EXTERNAL HAZARDS TO NUCLE. AVAILABLE September 1 30,1997. AR POWER PLANTS IN THE UNITED ST ATES NUREG-0540 V09 N10 TITLE UST OF DOCUMENTS MADE PUBLCLY AVA! LAME Cetccer 1 31,1987. Trench Cover NUREG/CR-2476 V03. A STUDY OF TRENCH COVERS TO McN.M12E Tornado INFILTRATON AT W ASTE OtSPOSAL SITES Fnal Rept NUREG/CR 5042. EVALUATON OF EXTERNAL HAZARDS TO NUCLE. AR POWER PLANTS (N THE UNITED STATES Tube Rupture NUREG/CR-4752 CO4NCOENT STEAM GENERATOR TUBE RUPTURE Tracer Mgation AND STUCK-OPEN SAFETY REL!EF VALVE CARRYOVER NURE G/ CR 4901. EFFECTS FRO.J INFLUENT GOUNDARY CONDI- TESTS MB 2 Steam Generator Transent Response Test PrcgrAm TiONS ON TRACER M!GRATON AND SPATIAL VAntAB'UTY FEA- NUREG/CR4988 A TR AC-PF1/MOOI ANALYSIS OF THE G:NNA TURES IN tNTERVEDIATE-SCALE E APERNENTS TUBE. RUPTURE EVENT ON JANUARY 25,1382. Tracers Tubing NUREG/CR-4875 CHARACTERIZATION OF CRU$HED TUFF FOP THE NUREGICR4952 EXPERNENTAL STUDY OF FILLET WELD UNDER-EVALUATON OF THE FATE Cf TRACERS IN TRANSPORT STUDIES CUT EFFECTS ON WELDED TUB.NG 2TRUCTUR;5 UNDER CEN-IN THE UNSATURATED 2ONt-TRC AND ECCENTR C CYCUP LOADINGS Traerung NUREG 1210 V01 PILOT PROGRAM NRC SEVERE REACTOR ACCI. Tuff DENT 'NCOENT RESPONSE TRA!N.NG MANUAL Overwew And Sum. NUREG/CR 4134 R01. REPOSITORY ENVIRONMENTAL F AM-mary Of Maor Pemts ETERS AND MODELS RELEVANT TO ASSESS:NG THE PERFORM-NUREG-1210 V02 PILOT PROGRAM NRC SEVERE REACTOR ACCl- ANCE OF HtGH-LEVEL W ASTE PACKAGES (BASALT, TUFF AND DENT INCOENT RESPONSE TRArNtNG MANUAL Severe Reactor Ac- SALT) cident Overvuw NUREG/CR-4161 VQ2 CRITCAL PARAMETERS FOR A HtGH-LEVEL NUREGPIO V03 PILOT PROGRAM NRC SEVERE REACTOR ACCl- W ASTE REPOSITORY. Vo6vme 2 Tuff DENT INCICENT RESPONSE TRA>N NG MANUAL Respnse Of b. NUREGICR-4875 CHARACTER 12ATON OF CRUSHED TUFF FOR THE ceosee And State And Loc 9 OH c+s EVALUATON OF THE FATE OF TRACERS IN TRANSPORT STUDtES NUREG 1210 V04 PILOT PROGR AM NRC SEVERE RE ACTOR ACCL- IN THE UNSATURATED 2ONE DENT INCOENT RESPONSE TRA!N!NG MANUAL Public Protective NUREGICR-4957. SURVEY OF GEOPHYSCAL TECHN'OUES FOR Actons . Preceterrruned Cotena And In$at Actions SITE CHARACTER 12AT60N IN BASALT,$ ALT AND TUFF. NbREG 1210 VOS PILOT PROGRAM NRC SEVERE REACTOR ACCI- ' DENT INCIDENT RESPONSE TRAINtNG MANUAL U $ Nuclear Regu- Turbine Missile latory Commission Pespor'se NUREGICR-4330 V03 REVIEvy OF UGHT A ATER RE ACTOR REGU-LATORY REOUiREMENTS Assessment Cf Selected Regulatcty Re-wmns at af Have aval Imp dane To R9 Postacc4W UE /CR-4768 AN ANALYTICAL AND EXPER' MENTAL INVESTIGA- TON OF NATURAL CIRCULATON TRANSIENTS IN A MODEL PRES. b* W b** "* ** * *

• O *
• C "" '

SURIZED W ATER REACTOA NUREGICR-4802 AN EVALU ATON OF TRAC-PFI/ MOO 1 COMPUTER " '#

• CODE PERFORM ANCE DUR;NG POSTTEST S MULATON5 OF SE-NUREG 1284 PROGRAM PLAN FOR CORRECTION OF V S INSTRU-M' SCALE MOD 2C FEEDW ATER UNE BRE AK TR ANStENTS NUR E G/ CR-4824 EVALUATION OF INTEGR AL CONTINUING EXPERI. MENT DEGRADATON OR FAILURE IN THE UPPER PLENUV TEST MENT AL CAPABiUTY (CEC) CONCEPTS FOR UGHT W ATER RE AC- FACluTY (UPTF) LN %E FEDERAL REPUBUC OF GERM ANY TOR RESEARCh PWR SCAUP+G CONCEPTS NURE G, CR -4 922 STEAM 3EPARATOR MODEUNG FOR VAROU$ UOIII NUCLEAR REACTOR TRANStENTS NUREG/CR-4890 HEAT OF REACTON OF MOLTEN ZiRCONtUM W'tiH UO2 Transient Response Test Program NUREGC% 5? CONDENT STE AM GENERATOR TUBE RUPTU TE U$i A 45 Att Stu LOPEN SAFETY RE L'E F V ALV E CARRYOVER NUREG/CR-4941- THE APPUCATON OF V ALUE :MMCT ANALYSIS TEJ w P ' beam Generator Transent Response Test Procyam TO Usi A-45 Summ7 Report Of UCLA Stu6es On vaive-Imput Anal ys,s in Retaton To USI A-45 Trar sn.c, Range NUREG/CR 4818 TRANSITON RANGE DAOP TOWER J R CURVE Ultrasonic Testmg TESTING OF A106 STEEL NUREG<CR a583 V02 DEVELOPMENT AND VAUDATON OF A REAL TNE SAFT UT SYSTEM FOR THE INSPECTION OF UGHT W ATER P UAE / 4 91 DEVELOPMENT OF MODELS FOR W ARM PRES- 95 I R E SSING NiiREG/CR 4583 V03 DEVELOPMENT AND VAUDATION OF A RE AL.

TNE SAFT UT SYSTEM FOR THE INSPECTION OF UGHT W ATER Tun W RE ACTOR COMPONENTS Annual RepytOctcter 1985 - Septemter NUR E G /CR-4654 R ADIONUCUDE TRANSPORT AS VAPOR 1986 THROUGH UNS ATUR ATED FR ACTURE D ROCK NURFG/^R 5060 AN APPROACH TO THE MATHEMATICA1 MODEL- U a y Ana ysis L ( THE UAAN t;M SER!ES REDISTR:BUTON WITHiN ORE Transport Behacor Undervottage Tnp Function NUREGICA 4766 TRANSPORT BEHAVOR OF ODiNE IN EFFLUENT NUR E G / CR-4664 CLOSEOUT OF tE BULLETIN 83-04 F AILURE OF RAD 60ACTMTY MONITORaNG SYSTEMS THE UNDERVOLTAGE T'tP rUNCTiON OF RE ACTOR TR:P BRE AK-ERS l Transportation NURE G 03&3 %01 R10 DIRECTORf OF CERTIFICATES OF COMPU. Ungrouted Tendon i ANCE FOR RADOACTIVE MATEFOAL S PACKAGES Summary Repori NUREG/CR 4712 REGULATORY ANALYSIS OF REGULATORY GudX. Of NRC Appecnred Paaages 135 (REVISION 3. DR AFT 2) - IN SERVN INSPECTION OF Uro l l l

Subject index 99 GROUTED TENDONS IN PRESTRESSED CONCRETE CONTAIN. Vegetation MENTS. NUREG/CR-4976 PLANT RHi20 SPHERE PROCESSES INFLUENONG RADONUCLIDE mobil'TY IN SOIL NUREG/CR4903 V02: SELECTCN OF EARTHOUAKE RESSTANT Ventdetion System DESCN CRITERLA FOR NUCLEAR POWER PLANTS METHOOOLO. NUREG/CR4931: RESPONSE OF CENTRIFUGAL AND AXIVANE GY AND TECHNCAL CASES Methods For introducten Of Geological BLOWERS TO LARGE PRESSURE TRANStENTS. Data into Charactenration Of Actrve Faults And Seesmoty And.- Vessel Attack N U" NUREG/CR-4909: MELPROG-PWR/MOOO.A MECHANISTC CODE FOR NUhEG/CR-4530 V02 U.S / FRENCH JOtNT RESEARCH PROGRAM ANALYSS OF REACTOR CORE WELT PROGRESSON ANO VESSEL REGARDNO THE BEHAVIOR OF POLYMER BASE MATERIALS $UB- ATTACK UNDER SEVERE ACCtDENT CONDITCNS JECTED TO BETA RADIATCN Volume 2: Phase-2a Screenng Tests. Unp6enned EM YII*I A'" A*9"I***I NUREG/CR-5036. COST ANALYSIS FOR IMPLEMENTATCN OF PRO-NUREG 1275: OPERATING EXPER!ENCE FEEDBACK REPORT NEW POSED CHANGES IN VITAL AREA REQUIREMENTS. PLANTS. Commercel Power Reactors. Unresol.ed Safety leave Vo6d Fraction NUREG/CR 5059 VO10 FRACTCN MEASUREMENT LOUID LEVEL NUREG 1030 SEISMC QUAUFICATION OF EOU1PMENT IN OPERAT. ING WCLEAR POWER PLANTS. Unresolved Safety issus A 46 DETECTION CONCEPT ASSESSMENT AND DEVELOPMENT. NUREG-1211: REGULATORY ANALYSIS FOR RESOLUTCN OF UNRE-SOLVED SAFETY ISSUE A-46.SELSMC QUAUFICATCN OF EOUip. Volume Reduction NUREG/CR4787; CONFERENCE OF RADATON CONTROL PRO-MENT IN OPERATING PLANTS. GRAM DIRECTORS' INFORMATCN FOR LCENSING LOW-LEVEL Unasturated Zone RADCACTIVE WASTE INCINERATORS AND COMPACTORS NUREG/CR-4615 V02 MODEUNG STUDY OF SOLUTE TRANSPORT IN THE UNSATURATED ZONE Workshop Proceedings Warm Prestressing NUREG/CR-4654. RAOCNUCLCE TRANSPORT AS VAPOR NUREG/CA4491: DEVELOPMENT OF HOOELS FOR WARM PRES-THROUGH UNSATURATED FRACTUREO ROCK. TRESSNG NUREG/CR4655 UNSATURATED FLOW AND TRANSPORT THROUGH FRACTURED ROCK RELATED TO HIGH-LEVEL WASTE Weste Desposal RE POSITORIES Feel Report . Phase it. NUREG 1274- REVIEW PROCESS FOR LOW-LEVEL RADIOACTIVE NUREG/CR4737; .NTERPRETATIVe ANALYSIS OF DATA FOR WASTE DSPOSAL LCENSE APPUCATON UNDER LOW-LEVEL RA. SOLUTE TRANSPORT IN THE UNSATURATED ZONE. DCACTIVE WASTE POUCY AMENOMENTS ACT. NUREG/CR4875. CHARACTERIZATCN OF CRUSHED TUFF FOR THE NUREG/CR-2452. FSSK METHOOOLOGY FOR GEOLOG'C DISPOSAL EVALUATCN OF THE FATE OF TRACERS IN TRANSPORT STUDIES OF RADIOACTIVE WASTE Foal Report IN THE UNSATURATED ZONE. NUREG/CR-2478 V03 A STUDY OF TRENCH COVERS TO M N:V!ZE INFIL*.RATON AT WASTE DISPOSAL STES F nel Rent.

                                                                                  #    ### # "        #        '*             #         O N       G/CR-5060 AN APPROACH TO THE MATHEMATICAL MODEL-               ON SONMMASTE MSALAND ASSOOATED m UNG OF THE UAAN'UM SERtES EDISTRIBUTCN WITHiN ORE                 PATON AL EXPOSURE. Annual Report, Fiscal Year 1986 BOD ES'                                                           NUREG/CR4615 V02-. MODEUNG STUOY OF SOLUTE TRANSPORT IN THE UNSATURATED ZONE. Workshop Proceedings Ure Ore BodW                                                            NUREG/CR 470t V02: SAFETY ASSESSMENT OF ALTERNATIVES TO NUREG/CR 5040: RADONUCUDE MiGRATON AROUNO URAN!UM                      SHALLO& LAND BURLAL OF            LOW-LEVEL RADIOACTIVE ORE BOOiES - ANALOGUE OF RADIOACT'VE WASTE                          W ASTE volume 2 Envronmental Condatens Affectsng Rai.atxiity Of En-REPOSITORIES Annual Repor1 For 19641965 pneered Bamers-Ureny1 Fluor 6de                                                       NUREG/CR4938 OCCUPATCNAL RADATON EXPOSURES ASSOCl-ATED WITH ALTERNATIVE METHOOS OF LOW-LEVEL W ASTE DIS-NUREG/CR4951: NEPHROTOXICITY OF URANYL FLUORCE AND RE.

POSAL VERS BlufY OF RENAL INJURY IN THE RAT. NUREG/r,R-5041 V01: RECOMMENDATIONS TO THE NRC FOR User's Manuel REVIEW CRITERIA FOR ALTERNATIVE ME'.HOOS OF LOW-LEVEL NUREGICR4690 V02. GENERC COMMUNCATCNS INDEX. User a RADCACTfvE WASTE DSPOSAL Task 2a Below-Gaund VaJts Manual NUREG/CR 4765 MXS CROSS-SECTCN PREPROCESSOR USER'S Weste Form MANUAL. NUREG/CR4795 LONG-TERM PERFORMANCE OF HIGH-LEVEL NUREG/CR-4766. USER'S MANUAL FOR THE NEFTRAN COMPUTER GLASS W ASTE FORMS CODE NUREG/CR4800: S1GPt A USER'S MANUAL FOR FAST COMPUTA- Weste Management TCN OF THE PRO 3ABluSTIC PERFORMANCE OF COMPLEX SYS- NUREG/CR-4318 V01; CONTROL OF WATER INFILTRATCN INTO TE MS. NEAR SURFACE LLW DtSPOSAL UNITS Annual Report,0ctober 1985 NUREG/CR-4808. M;NTEO USER'S MANUAL September 1966. VAPOR

• NOREG/CR4876' SILVSR INOtVUCADM:UM CONTROL ROD BEHAV- NUREG/CR4134 01: REPOSITORY ENVtRONMENTAL PARAM.

CR AND AEROSOL FORMA 1CN IN SEVERE REACTOR ACCl- ETERS AND MODELS RELEVANT TO AvSESSNG THE PERFCRM-DENTS. ANCE OF HIGH-LEVEL WASTE PACKAGES (BASALT, TUFF AND SALT) YARSKIN NUHEG/CR4735 V02- EVALUATCN AND COMPILATCN OF DOE NUREG/CR4418 OOSE CALCULATON FOR CONTAM;NATON OF W ASTE PACAAGE TEST DATA. B4nnual Repor1 August 1986 Janu-THE SKIN USING THE COMPUTER CODE VARSKIN ary 1987. Velve-impact Anotyees Weste Peckage Test Data NUREGICR4941: THE APPUCATION OF VALUE4MPACT ANALYSIS TO USI A45 Summary Report Of UCLA Stuses On Value impact Anal NUREG/CH4735 V01: EVALUATCN AND COMPILATCN OF DOE W ASTE PACKAGE TEST DATA Bennual ReportDecember 1985 - ysis in Relabon To USt A 45 July 1966. Yesv. NUREG/CR4343 PREPARATON OF DESGN SPECIFICATCNS AND Water letfWtration DESGN REPORTS FOR PUMPS VALVES. PIPING.ANO P1PtNu SUP- NUREG/CR4918 V01 CONTROL OF WATER INFILTRATION INTO PORTS USED IN SAFETY-RELATED PORTONS OF NUCLEAR NEAR SURFACE LLW DISPOSAL UNtTS Annual Report. October 1985 l POWER PLANTS September 1986

140 Subject Index Water Leakage Westoghouse 2 Loop NUREG/CR-4524 CLOSEOU.~ OF 4E BULLEllN BO-24 PREVENTON NUREG/CR-4458 SHUTDCAN DECAY HE AT RCMOVAL ANALYSIS OF OF DAMAGE DUE TO WATER LEAKAGE INSCE CONT A'NVENT A WEST.NGHOUSE 2 LOOP PRESSURf2ED WATER REACTOR Case (OC TOBE R 17,1960 INDtAN PO NT 2 EVENT) Stdy Water Quahty Westinghouse 3-Looo NUREG-1243 GROUND. WATER PROTECTION ACTivit;ES OF THE NUREG/CR-4762 SHUTDOWN DECAY HE AT REMOVAL ANALYSIS OF V S NUCLEAR REGULATORY COMMfSSON A WESTINGHOUSE 3-LOOP PRESSURIZED W ATER REACTOR Case Water Reactor Safety NUREG/CP4090. TRANSACTONS OF THE FIFTEENTH W ATER RE-ACTOR SAFETY INFORMATON VEETING WWho DW NUREG/CR-4%3 Ct.OSEOUT OF IE BULLETIN 83-01 FAILURE OF RE-Weld-Overlay Repair ACTOR TRtP OREAKERS CAESTINGHOUSE DB 50) TO OPEN ON NUREG/CR-4877. ASSESSMENT OF DESIGN BASIS FOR LOAD-CAR. AUTCMATC TR,P SIGNAL. RYtNG CAPACITY OF WELD-OVERLAY REPA:R$ Weide NUREG/CR-4330 CRACKJRAEST BEHAVOR IN SEN WCE PLATES NURIG-1 t S4 CONSTRUCTCN APPRAISAL TE AM :NSPECTON HE. OF OVENCHED AND TEMPERED A 533 GRADE B STEEL TESTED SULTS ON WELDING AND NONDESTRUCTIVE EXAM.NATON AC- UNDER NONtSOTHERVAL CONDiTONS TIylTIE S Work shop Welds NUREG/CP-0054 PROCEEDtNGS OF THE WORKSHOP ON Soil. NUREG/CR-4878 ANALYSIS OF EXPERIVENTS ON STA:NLESS STRUCTURE INTERACTON STEEL FLUX WELDS 1cocal Rewt NUREG /CP-0064 PROCEED,NGS OF THE WORKSHOP ON A UON-NUREG/CR-4352 EzPER MENTAL STUDY OF FILLET WELD UNDER. T AINVE NT PERFORVANCE CESIGN OBJECTIVE.M AY 12-CUT EFFECTS ON WELDED TUB.NG STRUCTURES UNDER OFN- 13.1986 HARPERS FERRY. WEST ViRG<NiA TRIC AND ECCENTRfC CYCL.C LOADfNGS West Valle # Y NUREG/CR 4647. CASE H STOR:ES OF WEST VALLEY SPENT rUEL NUR E G/CR-4B66 AN ASSESSMENT OF HYDROGEN GENERATON SH!PVE NTS Fr.al Report FOR THE PBF SEVERE FUEL DAVAGE SCOPING AND 11 TESTS Westmghouse Zircaloy 4 Omidation NUREG/CR-4672 ANALYSTS OF INSTRUVENT TUBE RUPTUAES IN NUREG/CR.4BB9 2:RCALOV 4 OACATON AT 1300 TO 2400 DE. WESTINGHOUSE 4-LOOP PRESSUR'2ED W ATER REACTORS GAEES C NUREGICA-4XS TRAC-PF1/VODI US/ JAPANESE PWR CONSER/A-TfvE LOCA PREDiCTON Drconsum NUAEG/CR-43B5 INDLAN PO"if 2 REACTOR COOLANT PUVP SEAL NUR E G / CR-4830 HEAT OF R E ACTION OF MOLT EN ZIRCON!UM EV A LU ATONS WITH UO2 5

NRC Originating Organization Index (Staff Reports) This index lists those NRC organizations that have published staff reports. The index is ar-ranged alphabetically by mgor NRC organizations (e.g., program offices) and then by sub-sections of these (e.g., divis ons, branches) where appropnate. Each entry is followed by a NUREG number and title of the report (s). If further informatien is needed, refer to the main citation by NUREG number. ADVISORY COMMITTEE (S) NUREG4090 V09 NO3. REPORT TO CONGRESS ON ABNCAMAL ACRS . ADY;SORY COMUTEE ON REACTOR SAFEGUARDS OCCURRENCES July September 1986. NUREG 1125 V08 A COMPILATON OF REPORTS OF THE ADYiSO- NUREGe090 V09 N04 REPORT TO CONGRESS ON ABNORMAL RY COMMITTEE ON REACTOR SAFEGUARDS.1986 OCCURRENCES October 4 ecember 1988 NURi 10090 V10 Not. RE' ORT TO CONGRESS ON ABNORMAL OFFICE OF EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) OCu)RRENCES AnuayMaren 1987. NU G 7 R TL DIRECT RADtATON MONITORING S J 987. NETWORK Progress Report. My Sectarter 1986. NUREG 0728 A02 NRC INCOENT RESPONSE PLAN NUREG-0837 V06 N04 NRC TLD DIRECT RADtATON MONtTOR;NG NUREG 1272 REPORT TO THE U.S NUCLEAR REGULATORY CCM-NURE 37 0 tN f E MONITORING 0N ANALYSIS AND EVALUATION OF OPERATONAL hST 98 NUREG 1275 OPERAT;NG ExDERiENCE FEEDBACK REPORT - NURE 37 0 02 N TLD E RA TON VONiTOR:NG NEW PLANTS Corr'rcial Power Reactors NUREG 0 0 N T RYC ATON VONITOR1NG NUr'EG-1275 V02- O iTING EXPERIENCE FEEDBACK REPORT . NETWORK Pr ess Report, Ju -Septemter 1997. AIR SYSTEMS PROBLEMS Cornmerc al Power Reactors NU G 12 9 LOS F E AL HEAT REMOVAL SYSTEM Diablo OFFICE OF INSPECTION & ENFORCEMENT (POST 12/11/80) OFC OF nNSPECTON & ENFORCEMENT. OIRECTOR (820201870413) OFC SFO VN t S 870413; NUREG4430 V07 N01. LICENSED FUEL FACILfiY STATUS NUREG-0940 VOC Not ENFORCEVENT ACTONS SIGN FICANT AC- REPORT Inventory D#erence Data JanuayJune 1986 (Gray Book 10 TONS RESOLVED OwtertProgress Report Jan uary-March 1997. NUREG-0940 V05 N04 ENFORCEMENT ACTONS 56GN:FICANT AC-NUREG-0940 V06 NO2 ENFORCEMENT ACTONS SIGN:FICANT AC. TIONS RE SOLVED Ouarterly Prog'ess Report.Octobee-Decemter TONS RESOLVED OuadeHy Progress Report Apr* June 1997. 1986 NUREG-0940 V06 NO3 ENFORCEMENT ACTONS SIGN:FICANT AC, OlV CF EMERGENCY PREPAREDV SS & ENGINEERING TIONS RESOLVED Cbaderty Progress Report.hy Septe'nber 1987. RESPONSE.lE(850212-870413) OFC OF SPEOIAL PROJECTS NUFsEG-1210 V01 PILOT PROGRAM NRC SEVERE REACTOR ACC:- NUREG-liJ2 V01. SAFETY EVALUATON REPORT ON TENNESSEE DENT INCOENT RESPONSE TRAIN:NG MANUALOverwen And VALLEY AUTHORITY Rev< sed Corporate Nxtear PerformaSce Pian Summary Of Mapr Poir ts NUREG 1210 V02 PILOT PROGRAM NPC SEVERE REACTOR ACC:- EDO . OFFICE OF ADMINISTRATION DENT INCOENT RESPONSE TRAINING MANUAL Severo Reactor OFFICE OF ADM;NISTRATON (PRE 870413) Accident Overce. NUREG C304 VII N04 REGULATORY AND TECHNCAL REPORTS NUREG 1210 V03 PILOT PROGRAM NRC SEVERE REACTOR ACCI-(ABSTR ACT INDEx JOURNAL) Annual Compdation For 19M DENT INCOENT RESPONSE TRAIN!NG MANUAL Response Of Le NUREG-0325 R10 US NUCLEAR REGULATORY COVMtSSON censee And State And Local Orficia's FU"CTONAL ORGANt2ATION CHARTS NUREG-1210 V04 PILOT PROGRAM NRC SEVERE REACTOR ACCl-NUREG4540 V08 N11 TITLE LIST OF DOCUCTS M ADE PUBLC DENT INCOENT RESPONSE TRA:N NG MANUAL Pubhc Protecwe j LY AVAILABLE Novemter 13019% get,on, , p,,o,,,,m,ned Criena And iret,al Actons i NUREG 0540 V08 N12 TITLE UST OF DOCUMENTS MADE PUBLIC- NUREG-1s 10 V05 PtLOT PROGRAM NRC SEVERE REACTOR ACC6-NUREG4 5 9 01 LE LtS DOCUMENTS MADE PUBLC b "' NUREG O SO 4 0 LEA REGULATORY COMV;SSON IS. NURE O 4 LCE SEE CONTRACTOR AND VENDOR IN-NUREG 24 2N E i E LATORY COVWSSON IS- SPECTON ST ATUS REPORT. Quadedy Report. October-December SUANCES FOR AUGUST 1986 Pages 197 396 NUREG 0750 V24 NO3 NUCLE AR HEGULATORY COVWSSON IS- g h9B6p ET PROGR AMS.tE (850212-8 704 t 3) OIY OF TE H L R ATO & UVENT CONTROL NUREG 1214 A00 HISTORCAL DATA SUVVARY OF THE SYSTEu-(PRE 870120) ATIC ASSESSVENT OF LICENSEE PERFORMANCE NUREG-0540 V08 N10 T:TLE UST OF DOCUVENTS MADE PUBLC OFFICE OF IVFOPWATION RESOURCES MANAGEMENT Divi O RUL E S EC RE 8704 t3) OFFICE OF AD%N:STRATtON & RESOURCES MANAGEMENT. Db NUREG4936 VOS NO3 NRC RE GULA TORY AGENDA Ouadeny NE gpEG 45 V03 US NUCLE AR REGULATORY COMESSON M'D"D*' # 1966 ANNUAL REPORT EDO . OFFICE OF STATE PROGA AMS DIVISON OF PUBUCATON SERVICES (POST 870413) ASSISTANT DaRECTOR FOR ST ATE AGREEWNTS PROGRAVS NUREG 0304 v12 NOI REGULATORY AND TECHN CAL REPORTS NUREG/CP-00e5 MEETING WITH STATES ON THE LOW-LEVEL RA. ( ABST R ACT INDEx JOURNAU Compnason for Fast Quader DOACTIVE W ASTE POLICY AVENDVENTS ACT (LLR APA A) OF 1987. January March 19 % NUREG 0304 V12 NO2 REGULATORY AND TECHNCAL REPORTS (ABSTRACT INDE x JOURNAL) Compaation For Secorxt Ouarter EDO . OFFICE FOR ANALYST $ & EVALUATON OF OPERATION AL 198 7.Apr* June OATA NUREG 0304 Vt2 NO3 REGULATORY AND TECHN' CAL REPOHTS OF F CE FOR ANALYS:S & EVALUA TON OF OPERATONAL DAT A. Di (ABSTRACT iNDE* JOURN AL) Carusteon For Trwd Quader RECTOR 198 7 Jur, Septemter NUREG 0030 V09 NO2 REPORT TO CONSRESS ON ABNORV AL NUREG 0540 V09 NO2 TITLE UST OF DOCUMENTS MADE PUBLC OCCURRENCES ApreJune 1966 LY AVAV ABL E Feorwary 1 28.1987 141

142 NRC Originating Organization index (Staff Reports) NUREG 0540 V09 NO3 TITLE LIST OF DOCUVENTS MADE PUBLtC- OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS LY AV AILABLE. March t 31.1987 OF F 6CE OF NUCLE AR VATER!AL SAFETY & NUREG 0540 vo9 N04 TITLE LIST OF DOCUVENTS MADE PUPL'9- SAFEGUARDS OtRECTOR LY AVAiABLE Apnl i-301967. NUREG-0430 V07 NO2- LICENSED FUEL FACillTY STATUS NUREG 0540 V09 N05 TITLE LIST OF DOCUVENTS MADE PUBLIC. REPORT. Inventory Doerence Data My December 1986(Gray Book i V AVAILABLE Mav 1 31.1987. 10 A uEG4540 V09 N06 TITLE LIST OF DOC /MENTS MADE PUBLtC. NUREG-1300; ENVIRONVENTAL STANDARD REVIEW PLAN FOR V AVAILABLE June 1-30.1987. THE REVIEW OF A LICENSE APPLICATION FOR A LOW-LEVEL

       %GC540 V09 N07. TITLE LIST 08 DOCUMENTS MAUE PUBLIC.            RADIOACTIVE WASTE DSPOSAL FACILITY.

Y AVAILABLE. My 1 31 1987 DlylSON OF SAFEGUARDS & TRANSPORTATION (POST 870413 aEG4540 V09 NOB TITLE LIST OF DOCUMENTS MADE PUBLIC. NUREG-0383 V01 RIO: DIRECTORY OF CERTIFlCATES OF COMPLI-

• AVAILABLE August 1 31.1987. ANCE FOR RADCACTIVE HATEHtALS PACKAGES Summary

  *. AEG4540 V09 N09 TITLE LIST OF DOCUVENTS MADE PUBLIC-              Report Of NRC Approved Packag- eS L r AVA;LABLE. Septemter 1 30.1987                             NUREG-03B3 V02 Rio. DIRECTOHY OF CERTIFICATES OF COMPLl-NUREG4540 V09 N10: TITLE LIST OF DOCUVENTS MADE PUBLIC-              ANC . FOR RADCACTIVE MATER lALS PACKAGES Certfacates Of LY AVAILABLE October 1 31,1987                                    W ance NUREG 0750 V24101. INDEXES TO NUCLEAR REGULATORf COM-             NUREG-0383 V03 RO7. DIRECTORY OF CERTIFICATES OF COMPLI.

MfSSCN ISSUANCES My-Septemter 1986 ANCE FOR RADIOACTIVE VATERIALS PACKAGES Summary NUREG 0750 V24102 INDEXES TO NUCLE AR REGUI ATORY COM- Report Of NRC Approved Quahty Assurance Programs For Radioac-V SSCN ISSUANCES July December 1986 trve Matenal Packages NUREG 0750 V24 N04 NUCLE AR REGULATORY COMMfS40N :S- NUREG4525 R13 SAFEGUAP.DS SUYVARY EVENT LIST ISSEL) SUANCES FOR OCTOBER 1986 Pages 489-679 OF INDUSTRIAL & MEDtCAL NUCLEAR SAFETY (POST 8 NUREG 0750 V24 N05 NUCLEAR REGULATORY COVV;SSCN IS-SUANCES F OR NOVEMBER 1986 Pages 681768 NUREG-0762 R1 DAF FC. STO4DARD 70RMAT AND CONTENT NUREG 0750 V24 N06. NUCLEAR REGULATORY COV%SSION iS- FOR EMERGENCY PLANS FOR FUEL CYCLE AND MATERIALS F ACILITIES Dra't Repor1 For Comment SUANCES FOR DECEMBER 1986 Pages 769-930 NUREG OTSO V25101 INDEXES TO NUCLEAR REGULATORY COM- DIVISION OF FUEL CYCLE MEDICAL. ACADE AC & COMVERCIAL M;SSON ISSL "'ES JarwaTMarch 1987- USE SAFETY 8704t NUREG 0750 V25 uct NUCLEAR REGULATORY COMV;SSCN IS. NUREG4904 S01: DRAFT SUPPLEVENT TO THt. FINAL ENVtRON-MENTAL STATEVENT RELATED TO THE DECOW:SSON;NG OF SUANCES FOR JANJARY 1987 Pages 1-62 NUREG-0750 V25 NO2. NUCLEAR REGULATORY COMV:SSON IS' THE RARE E ARTHS FACILITY. WEST CHICAGO'A LINOIS Docket SUANCES FOR FEBRUARY 1987 Pages 63128 No 40 2061 (Kerr-McGee) NUREG-0750 V25 NO3 NUCLEAR REGULATORY COVV;SSION IS- NUREG-1239. ENVIRONVENTAL ASSESSMENT FOR RLNEWAL OF SOURCE MATERIAL LICEFSE NO. S'B-401.Doch e; No 40-SUANCES FOR MARCH 1987 Pages 129-266 6563 (Columtnum-Ta9talum Dmsaon.Ma%ncuodt.inc ) NUREG-0750 V25 N04 NUCLEAR REGULATORY COMViSSION IS- OlV1 SON OF LOW LEVEL WASTE MAN AGEMENT & DECOMM:5SION-SUANCES FOR APRIL 1987 Pages 267-416 ING (POST 8704t36 DivlSCN OF RULES & RECORDS IPOST 870413) NUREG-1213 RO1: PLANS AND SCHEDULES FOR IMPLENENTA. NURE G49% V05 N04 NRC RE GULATORY AGENDA Ova ter'y TON OF U S. NUCLEAR REGULATORf COVM:SSION FiSPONSI-RepM Detober-Decemter 1966. gjLITIES UNDER THE LOW-LEVE6 RADIOACTIVE W AS' ' POLICY NUREG M36 V06 N01 NRC REGULATORY AGENDA Ouaderty AVENDVENTS ACT OF 1985 (P L 99 240) Report January March 1987-NUREG 1274 REVIEW PRi) CESS FOR LOW LEVEL RADUACTIVE NUREG-0936 V06 NO2 NRC REGULATORY AGE NnA Ovanerty W ASTE DISPOSAL LICENSE APPLC) TON UNDER LOW LEVEL Report Apr.1 June 1987 RADIOACTIVE W ASTE POLICY AMENOVENTS ACT. NUREG 0936 V06 NO3 NRC REGULATORY AGE NDA Oarterty NUPEG 1293 DRFT FC OVALITY ASSURANCE GU! DANCE FOR ReportJu ry September 1987 LOW LEVEL RADCACTIVE W ASTE OtSPOSAL FAGidTY D'a't For DIVIS*ON Or BUDGET & ANAL YS:S (POST 870413) Cor..mer.t NUREG 1100 V03 ADO BUDGET ESTIVATFS fescal Years 198tr OlVISION OF SAFEGUARDS (PRE 870413) 1989 NUREG-0525 R12 SAFEGUARDS SUMVARY EVENT LIST (SSEL) DMSCN Or COMPUTER & TE L ECCVM ACA TONS SERVICES NUR E G-1280 STANDARD FORMAT AND CONTENT A %cFTANCE [ POST 870413) CRtTERIA FOR THE M ATER!AL CONTROL AND ACCOUNitNG NUREG4020 V10 N11 LICENSED OPERATING RE ACTOR 5 STATUS (VC& A) REFORM AVENDVENT.10 CFR Pari 74 Subpart E SUVM ARY REPORT Data As Of 0:tober 31.1956 (Gray Book 1) OfVISION OF W ASTE MANAGEMENT (PRE 870413) NUREG4020 V10 N12 LCENSED OPERAT NG REACTORS STATUS

                                          ,                         NURE G-1101      V02. ONSITE    DIS) SAL OF RADCACTtVE SUVMARY REPORT Cata A Of November 30.1966 (Gray Book f)           W ASTE Methosogy For The Rabog<al Assessmena O! Disposal NUREG 0020 V11 N01 LCENSED OFER AT'NG REACTORS STATUS                By Subsurf ace Burial SUVV ARY REPORT Data As Of December 31.1966 (Gray Boce ll      NUAEG 1199 ST ANDARD FORMAT AND TNTENT OF A LICENSE NUREG-0020 V11 NO2 LtCENSED OPERADNG RE ACTORS STATUS                APPLICATON FOR A LOW-LEVL'        a sOACTIVE W ASTE DISPOS-SUVVARY REPORT Data As Of January 31.1987 (Gray Book 1)           AL FACILITY                                                                                       i NUREG4020 VII NO3 LICENSED OPERATING RE ACTORS STATUS             NUREG-1200 ST ANDARD REVIEW PLAN FOR THE REVtEW OF A SUVVARY REPORT Data As Of Februar: 28198 7 (Gray Bc ;A I)         LCENSE APPLCATON FOR A LCMEVEL RADIOACTIVE W ASTE NUREG4020 Vit Nod LCENSED OPER A 'NG RE ACTORS CT ATU$               OtSPOSAL FACILITY SUVV ARY REPORT Data As 09 March 't t '987 (Gray Boon l)       NUREG-1243 GROUND W ATER PROTETON ACTrylTIES OF THE NUREG 0020 VII N05 LICENSED OPERAT 'G AEACTORS STATUS               U S NUCLEAR REGULATORY COVM:Si N SUVV ARY REPORT Data As Of Aprd 30.10 7 IGrav Book f)       ggaggygggggy NUREG4020 V11 N06 LtCENSED OPERAT A AE ACTORS STATUS            COVYiSSIONE RS

SUMMARY

REPORT Data As Of Vay 31.198/ Gray Boc+ I) NUREG4885 10 3 US NUCLE AR REuULATORi COVM.SSION NUREG4020 V11 N07 LICENSED OPERATING JEACTOAS STATUS POLOY AND PLANN:NG GU'OAlCE 1987 SUVVARY REPORI Data As Of June 30.1987i ' -ay Book I) OrFICE OF THE GENERAL COUNSEL NUREG-0020 VII N08 LCENSED OPERATING R ACTORS STATUS NUREG 0386 D04 304 UNtTED ST ATES NUCLE AR REu .ATu.y SUVVARY REPORT Data As Of July 31.1987 (Gray Book f) COk.V.SSON STAFF PRACTCE AND PROCEDURE Dr2EST JJy NUREG 0020 VII N09 LCENSED OPERAT:NG RE ACTORS STAT,S 1972 June 1966 SUVVARY REPORT Data As Of August 311987 (Gray BMk 1) NUREG-0386 D04 A05 U*aTED STATES NUCLE AR REGULATORY NUREG4020 V 1 NIO LICENSED OPERATWG RE ACTORS STATUS COVU SSON STAFF PR ACTICE AND PROCEDURE OGEST Ju ry SUMM ARY r<EPORT Data As Of September 30.1987 tGray Book () 1972. September IM6 NuREG 0020 VII N1' LCENSED OPERATING RE ACTORS STATUS NVREG 0386 004 R06 UNITFD STATES NUCLE AR REGULATORY SUVVARY REPORT Data As Or October 311987 (Gray Book f) COVV'SSION STAU PRACTCE AND PROCEDUhE DIGEST Jey DMS40N OF COWJTER & TELECOUVUNCATONS SERV 1CES (PPE 1972 Dec 19A6 8704131 NUREG4980 R03 NUCLE AR REGULATOR y LEGISLATON NUREG 0020 vio NO9 LCENSED OPERATING RE ACTORS ST ATUS NRC ND DET ARED AFFILIAT.ON G%EN SUVV ARY REPORT Data As Of AWust 31 tW! (Gray Book i) NUREG4654 S01 ROI CRtTE R4A FOR PRE F AR AT)CN AND E V AL-NUREG OO20 V10 N10 L6 CENSED OPERAT NC RE ACTORS ST ATUS V A TCet OF RADC MXiCA, E VE RGE NCY RESPONSE PLANS SUVM ARi RE PORT Data A* Of Setember 30.1986 (Gray Boce t) AND PRE P ARE DNE SS IN SUPPORT C# NUCLE AR POAER

NRC Originating Organization Index (Staff Reports) 143 PLANTS Crderia For Utuy 09sete Piann,ng And Prepareoness Dratt OFFICE OF NUCLE AR RE ACTOR REGULATION (POST 4/28/80) Report OFFCE OF NUCLEAR RE ACTOR REGULATON. DIRECTOR (POST NUREG 1250 REPORT ON THE ACCOENT AT THE CHERNOBYL 870411) NUCLEAR POWEH STATON NURE G-0327 R04 OW NERS OF NUCLEAR POWER NUREG 1250 RO1 REPCRT ON THE ACCOENT AT THE CHERNO. PLANTS Percenta2e Oanersh*p Of Commercial NJear Power BYL NUCLEAR POWER STATON Plants By UtMy Compan.es NUREG-1251 DRFT FC IVPLCATONS OF THE ACCCENT AT NUREG 0332 POTENTI AL HEALTH AND ENVIRONVENTAL iM-CHERNOOTL FOR SAFETr REGULATON OF COVMERCIAL NU- PACTS ATTA BUTABLE TO THE NUCLE AR AND COAL FUEL CLEAR POWER PLANTS IN THE UNITED STATES Dram Fo* Corn- CYCLES Final Report rnent. NUREG-0800 06 5 2 R2 STANDARD REV:EW PLAN FOR THE NUREG 1290- DIFFERING PROFESSONAL OPiNONS 1987 Spece REVIEW OF SAFE 1Y AN ALY St$ REPORTS FOR NUCLEAR Revew Panel POWER PLANTS LW R Ed t>on Proposed Recson 2 To Sect,on NUREG/CR 3620 $02 INTRUDER DOSE PATHWAY ANALYS!S FOR 6 5 2. "Contament Spray As A F<sscn Product Cleanup System." THE ONSITE DISPOSAL OF RADIOACTIVE W ASTES The ONSITE/ For Comet MAX 11 Computer Prog'am NUREG-0600 06 5 5 R0 STANDARD REVIEW PLAN FOR THE NUREG/CR-3950 %03 FUEL PERFORVANCE ANNUAL REPORT REY;EW OF SAFETY AN ALY5is REPORTS FOR NUCL E AR FOR 1995 POWER PLANTS LWR Ed, ton ProFcsed Rewson 0 To New SRP OFFICE OF NUCLEAR REGULATORY RESEARCH (POST 4/05/81) C Up S s e For Com n OFFCE OF NUCLE AR REGULATORY RESEARCH. 02 RECTOR (POST NUREG-1122 S01 KNOWLEDGES AND AB UTIES CATALOG FOR

                                                                                                                   ^         **              #

N REG 150 DAF V1 FC: REACTOR RISK REFERENCE DOCUVENT Ma.n Report Draft For Com ment NkG 1164 DRFT INTE GR AT ED SAFE'Y ASSESSVENT NUREG-1150 DAF V2 FC REACTOR RISK REFERENCE F.EPORT.iNTEGR ATED SAFETY ASSESSVENT PROGRAV V'LL. STONE NUCLE AR POWER ST ATION UN:T t Docket No 50-N 1 F 3 C REA RtSK REFERENCE 245 (Northeast Nuc! ear Energy Cc) Drsit Report NUREG 1231 SAFETY EVALUATION REPORT REL a,TED TO THE N 24 PLAN F R T R T NICAL ACTIVITIES BABCOCK AND W!LCCA OWNERS GROUP FLANT RE ASSESS-WITHIN THE U S NRC AND ITS CONTRACTORS IN THE AREA OF NUREG 123 TE N' CAL SPECIFCATIONS FOR CUNTON POAER NURE VO A RE RT TO CONGRESS ON NUCLE AR REGU- STATON, UNIT 1. Docket No 50-4610:i4ros Poner Comr'aS)

        .ATORY RESEARCH Proyect Descr:ptons For Fv87 NUREG-1285 NRC STAFF EVALUATON OF THE GENERAL ELEC-NUREG-1265 UNCE RT A:NTY PAPERS ON SZvERE ACCOENT                         TRiC COMPANY NUCLE AR RE ACTOR STUDY [ REED REPORT")

SOURCE TERVS PROGRAM MANAGEMENT. POUCY DEVEL OPVE NT & ANALYSIS NUREG-1266 V01 NRC SAFETY RESEARCH IN SUPPORT OF REG. STAFF (POST 870411) ULATON .1986 NUREG 1256 V01 INCENT'VE REGULATION OF NUCLEAR POAER NUREG 1270 V01 INTERNATONAL CODE ASSESSVENT AND AP. PLCATIONS PROGRAM Annual Report PLANTS BY St ATE PUBUC UTIUTY COVV<SSIONS DmSION OF RE ACTOR PROJECTS till (POST 8704 t1) NUREG/CP 0082 V01. PROCE E D:NGS OF THE FOURTEENTH NURE G-0825 S01 INT E GR A TE D PLANT SAFETY W ATER REACTOR SAFETY INFORM ATON MEETING ASSESSVENT S f 5T EMATIC EV AL UATION PROGRAMM ANwEE NUREG /CP-0082 V02 PROCE E DINGS OF THE FOURTEENTH NUCLEAR POAER STATON De<6et No 50429 (Ya, hee Atom.c W ATER REACTOR SAFETY INFORMATION MEETING NUAEG /CP-0082 V03 PROCE EDINGS OF THE FOUR TE ENTH E4ctrc Comf ami W ATER RE ACTOR SAFETY INFORMATON MEETING NUREG 0896 S07 SAFETY EV ALU alton REPORT RELATED TO NURE C,NT VU PROCEEDINGS OF THE FOURTE ENTH THE OPERATON OF SEABROOK STATON. UNITS 1 AND 2 Dochet W ATER RE ACTO 4 SAFETY INFORY ATON MEETING Nos. 50-443 And 50 444 (Putt : Semce Co/nfaq Of New NURE G/CP4082 VOS PROCEEDINGS OF THE FOURTEENTH HampsNre et a0 W ATER REACTOR SAFETY INFORMATON MEETING NUREG 1047 506 SAFETY EVALUA .^N REPORT RELATED TO NURE G /CP-0082 V06- PROCE E DINGS OF THE FOUR TE E NTH THE OPER ATON OF MNE M:LE PO'NT C E AR ST ATION UN'T W ATER REACTOR SAFETY INFORMATON VEETING 2 Doc 6et No 54410 (N,agara Mohan Power Corw: ton et a') NUREG/CP 0090 TRANSACTONS OF THE FIFTEENTH WATER RE- NUREG-1057 SC5 SJE T f EVALUATON REPORT REL ATED TO ACTOR SAFETY INFORMATION VEETiNG THE OMRATO". CF EEAVER N ALLEY POWER ST ATON UN:T DIVISON OF ENGAEER:NG (POST 870413) 2 Docket No 50-412 (Dwasne Lght Corvary et al NUREG t t44 ROI NUCLE AR PLANT AGING RESEARCH (NP AR) NUHEG1057 506 SAFETY EVALUATION REPORT RELATED TO PROGRAM PLAN THE OPERATION OF BE AVER N ALLEY POAER STATCN UN 7 NUREG-1147 Ro1 SEISMC SAFETY RESE ARCH FROGRAM PLAN 2 Docket N 50 412 (Dwasne L9 th Carvan, et a.1 NUREG 1245 VOI. RADCACTIVE W ASTE MANAGEVENT RE- NUREG 1253 TECHN; CAL SPEC'FiCATONS FCR VNE V LE PO1NT SE ARCH PROGRAM PLAN FOR HIGH-LEVEL W ASTE .1987 NUCLEAR STATV ..UNG 2 Docket No 50-4)G Wya Voha*k NUREG-1264 CONTAINMENT INTEGRITY RESE ARCH PROGR AM pgy, CWatond 0 PLAN NUREG 1259 TECHN<C AL SPEC;FiCAT.ONS FOR SE AVER \ ALLE Y NUR E GICP-0088 TRANSACTONS OF THE 9TH INTERNATONAL POWER STATION. UNIT 2 Docker No 50-412 iDwuesne Lght Com. CONFERENCE ON STRUCTURAL MECHANbCS IN REACTOR p3n.g TECHNOLOGY Panet Session JK Structural And Mechanicar Ert NUREG 1279 TECHN CAL SPECIFICATOa5 F OR BEAVE R V ALLEY neerng Research At The U S Nuclear Regulatory Cornentsson POAER ST ATON UNIT 2 Doc = et N: 50 412 (Dwasne Lgtt DivtSON OF RE ACTOR & PLANT SYSTEMS (POST 870413) Cepe e' o NUREG 1230 ORFT FC COMPf NDIUV OF ECCS RESE ARCH FOR DMS ON OF RECTOR PROJECTS til N V & SPECIAL PROJECTS RE AUSTO LOCA ANALYS;S Dra't Report for Cornrnent (POST 8 % 1 NUREG 1271 GUIDELINES AND PROCEDURES FOR THE INTERN A- NUREGo?et 503 SAFETY Ei ALUATON REPORT RELATED TO TONAL CODE ASSESSMENT AND APPLOATONS PROGRAM THE OPE RATON CF SOUTH TE X AS PROJECT UN:15 1 MD NURE G- 1284 PROGRAM PLAN FGR CORRECTON C3 VS IN- 2 fv x set N3 50-G And 50 439 W ston Lghtmg Ano Fower STRUMENT DEGRADATON OR F AILURE IN THE UPPED PLENUM TEST F ACluTY (UPTF) IN THE F EDER AL REPUBLO OF GERVA. N 1 504 SAFETY EVALUATON "DORT RELA TE D TO DIV;S N O~ ENG;NEER NG SAFETY 1660720-6704131 NUAE10915 VOS COMPtLATON OF CONTRACT RESE ARCH FOR 2 d # A b0 U# L N ^' d , Pd THE MATERIALS BRANCH DfV:S ON OF E NG AEE RING q 2 SAF TV EVAMTm MPORT PMMD TO THE F A A' NSm & M SWA@ Md AR S4 AM DIVI A TC S STEM S FETY (W720 67041% SUPPLY REF ERENCE SY STEM CE SSAn E ntem 80 Dx6ct No n NUREG-tic COORDINATON OF SAFE TY RESE ARCH FOR THE 4 70 (Ccevon E Wenng Avraa' ell BABCOC+ AND W1LCOx INTEGR AL SYSTEu TE ST PROGRAM NUREG C+57 512 SVETY EVALUA TON RE POH T RE LATED TO EDO-HtSOURCE M ANAGZMENT THE OPE R ATON C PALO % E RDu NUCLE AR GE Nf R AT% DivisON OF BUDGET & ANALYSIS (PRE 670413) ST ATON UN'TS t.2 AND 3 Dx 6vt Nes 50 528 50 5W And 50 , NUNEG-1100 V03 BUDGET ESTIM ATES Fiscal Yea <s 198819N 530 ( Argona PutM Ser v ice Corva7 et ay

144 NRC Originating Organization Index (Staff Reports) NUREG 1002 503 SAFETY EVALUATON REPORT RELATED TO NUREG 1262 ANSAERS TO OVESTONS AT PUBLIC VEETINGS THE OPE RATON OF BRACWOOO STATION UNITS 1 AND REGARD *NG eMPLEMENTATON OF TITLE 10 CODE OF FEDERAL 2 Dochet Not W456 And 50-457 (Commcceea'th Ed4on Companyl REGULATONS PART 55 ON OPERATORS' LCENSES NUREG-1002 SO4 SAFETY EVALUATON REPORT RELATED TO NUREG 1278. VOGTLE UNIT 1 READ: NESS REYEW Assessment Of THE OPERATON OF BRA:DWOOD STATON UNITS 1 AND Georpa Power Company Readness Rece Pilot Pecqam 2 Dochet Nos 50 456 And W457 (Commonweanh Edison Company) NUR E } t 291. BWR AND PWR OFF-NORMAL EV ENT DESCRIP. NUREG 10^2 SOS SAFETY EVALVATON REPORT RELATED TO TiOUS THE OPERATON OF BRAOWOOD STATON UNITS 1 AND OPERATU' UCENS:NG BRANCH 2 Dochet Nos %4'4 And W457 (Commonwea1h Fd. son Company) NUREG 1P1 A04 OPERATOR UCENS.NG EX AM.NER STAND-NUREG 1166 FrNAL ENVIRONVENT AL STATEMENT FOR DECOM- ARDS M SSONNG HUMBOLDT BAY POWER PLANT UNIT 3 Doctet No DIVISION OF HUMAN FACTORS TECHNOLOGY (851125-870411)

        %133 (Pac 4 Gas And Electne Company)                              NUREG 1258 DRFT: EVALUATON PROCEDURE FOR SiMULATON NUREG-1185 V01 DAFT: INT EGR AT ED SAFETY ASSESSMENT                   FACiUT1ES CERTIFIED UNDER 10 CFR 55 Dra't Repcrt REPORT integr ated Safety Assessment Program Haddam Neck        OfVisiON OF PRESSURIZED W ATER REACTOR UCENS NG               A t Docket No %213 (Connecticut Yankee Atomic Power Com.            85 5 04 1 NURE61185 V02 DAFT- INTEGRATED SAFETY ASSESSMENT                       THE OPERATION OF SOUTH TEXAS PHOJECT. UNITS 1 AND REPORT 6ntegrated Sa'ety Assessment Program HaMam Neck               2 Docket Nos 50 498 And W493 (Houston Lghting And Power Piant Docket No W213 (Connect cat Yannee Atome Power Com.            Company) pan,)                                                             NLREG-0676 508 SAFETY EVALUATON REPOAT RELATED TO NUREG-1255 TECHN CAL SPECIFICATONS FOR SOUTH TERAS                     TME OPERATON OF BYRON STATON UN:TS 1 AND 2 Docket PROJECT. UNIT 1 Docket No D498 (Houston L9ntog and Pemer             Ncs 50 454 And %455 (Commonweath Ed< son Company)

Company) NUREG 1057 504 SAFETY EVALUATON REPORT RELATED TO NUREG 1261- TECHNCAL SPECirCATONS FOR BRA:DAOOD THE OPERATION OF BEAVER VALLEY PCAER STATION UNIT STATON,UNlTS 1 AND 2 Docket Nos %456 And 50-457 (Com. 2 Evacket No 50-412 (Duquesne Light Company et ay monwea'th Ed-son Compa y) NUREG 1137 SOS SAF E TY EVALUATON REPORT RELATED TO NUR E G-1276 TECHNCAL SPECFICATIONS FOR BAA'DAOOD THE OPER AT ON OF VOGTLE ELECTRC GENERATING STATON. UNITS 1 AND 2 Dochei Nos S456 And 50-45 7 (Com. PLANT.UN!TS 1 AND 2 Docket Nos 50-424 And W42A (Georg.a monwerth Ed. son Compa y) Po*er Company et al NUREG-1281 EV ALUATION OF THE QUAUFCATION OF SPEAT NUREG 1137 506 SAFETY EV ALUATON REPORT RELATED TO FUEL FOR USE IN NOt+ POWER RE ACTOAS THE OPE R A TON OF VOGTLE EL ECTRIC GENE R ATING NUREG 1282 SAFETY EVALUATON REPORT ON HtGH-UR AN1UV PLANT. UNITS 1 AND 2 Dochet Nos 50-424 And %425 (Georg a CC NTENT. LOW ENRICHED URAN UM ZIRCON?UM HYDR DE Po*er Company et a') FUELS FOR TRIGA REACTORS Dociet No W 163tGA NUREG 1237. TECHNCAL SPECtFCATONS FOR VOGTLE ELEC-Technologes encorpora'ed) TRC GENERATING PLANT, UNIT 1 Docket No 50-424 (Georg>a NUREG 1266 SAFETY EVALUATION REPORT RELATED TO THE Pc'*er Company) RESTART OF RANCHO SECO NUCLEAR GENER ATING NUREG 1240 T E CHN'CA L $5 ECiFCATONS FOR SHEARON STATON UN?T 1 FOLLOW NG THE EVENT OF DECEV3ER HARR:S NUCLEAh POWE R PL AN T.UN!T 1 Doctet No % 261985 Ebchet No 50-312 (Sacramento Usn.ccal Utuy E%tnct) 4XI(Carova Pm & L9nt Comcany) NUREG-1287 TECHNCAL SPECIFCATiONS FOR PALO VERDE NU- NUREG 124 7 TECHNCAL $P(ClFICATONS FOR YOGTLE ELEC-CLE Al GENER ATING STATON UNIT 3 Ebchet No %533 (Argona TRC UENERATING F %17.UN!T 1 Docket N3 50-424 (Georg.a NuOear Power Pro;ect) Power Compa y) TML2 CLE ANUP PROJECT OiRECTORATE DiviS!ON OF PRESSURC.) W ATER REACTOR LCE NS.NG B NUREG-0683 502 PROGR AVV AT C E NVIRONVE NT AL IUPACT (851125-8 70411l STATEVENT RELATED TO DECONT AV:N ATION AND DISPOSAL NUREG-0857 S11 SAFETi EVALUATION REPORT RELATED TO OF RADCACTIVE W ASTES RESULTING FROM VARCH 28 1979 THE OPERATON OF inLO VERDE NUCLEAR GENERATING ACCCENT AT THREE M1E ISLAND NUCLEAR STATON.UYT ST/ ION UNITS 12 ANC 3 Doctet Nos %528 50-529 And % 2 Feat Supplement Deaeg 4th D socsal Of 530 ( Ac2ana Pathe Serwce 'ompany et al OtVISON Or REACTOR iNSPECTiu & SAFEGUARDS (POST NUREG 1224 SAFETY EVAt JATON REPORT RELATED TO THE 870411) RENE A AL C' THE OPERA 'ING UrENSE FOR THE UN VERSITY NVREG-OG40 Vtt N01 UCENSEE CONTRACTOR AND VENDCA IN-OF NEW UE' CO RESEAR H REACTok 'schet No 50 252 (Urw I SPECTON STATUS REPORT Ova 1987 (W Me Boca)

                                             ,   ReportJanva y Varch NUREG Cc40 V11 NO2 UCENSEE CONTRACTOR AND VENDOR IN-SPECTON STATUS REPORT 1987 (WMe Book)

Ovader'y Repart. Apni Jur e vers % Of Nes Ve neci NURE412481 'CHNCAL SF CrFCATIONS FOR PALO VERDE NU-CLf AR GENER ATING STA' DN UN T 3 Ocche: No 50 530(Antona P>shc Semce Companyl DivtSON OF BOtuNG W ATEF 4E ACTOR (B AR) UCENS NG (851125-NUREG-0040 VII NO3 LICENSEE CONTR ACTOR AND VENDOR IN. e70411) SPECTON STATUS REPORT. Ovane", ReportJuYSeptember NU A t o-W SO8 SAFET, EVALUATIC-N REPORT RELATED TO 1987 MNe Boon THE OPtRA DON OF C. NTON PCA ER STATON UN!T I Dochet NUREG-11Sa CONSTRUCTON APPRA: SAL TE AM INSPECTON RE- No 50 461 Umnc*s Power L vaq et n') SULTS ON WELDING AND NONDESTRUCTIVE Ex AV:NATON AC. Olv'S'ON OF SAFETY REVIEW A Os e RS GHT (851125 870411) TiVIT 'E S NURE G m3 SG6 A PRtOR h2AT60N OF GENEHC SAFETY Ov510N OF LICENSEE PERFOAV ANCE & OVALITY EV ALU ATCN ISSUES i POST 870411) NUR E G- 10D SEiSU'C OUAUF ' A ' 'CN OF E QU$ VE NT IN OPE R. NUREG-1214 R02 HfSTOACAL CATA SUUVt RY OF THE SySTEV. ATING NLCLE AR POWER PL aTL UnrcsoNed Safe $ Ist.se A-46 ATC ASSE SSVENT OF LICE NSFE PE ArORV ANCE NURE G-1211 REGULATORY A 5 ALT 45 FOR PESOLUTiON OF UN-NURcG-1258 EVALUATON PROCE DURE F OR S VJLATON F AOu- RESOLV E D SAFETY ISSUE A 46 SEiSVC OV AL!FICATON OF T:ES CERTIF:ED UNDE R 10 CFR 55 Final Report EOUJ VEN' IN CPER ATiNG e a*..S

I 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 entry is followed by a NUREG number and title of the report (s), if further information is needed, refer to the main citation by NUREG number.

          'Sf'cE'o?hbE'f4R !$^u[f"JR< 5I^EE% s'ni'c!/A%ST                                                 ,

NUAEG A 0004 THERMAL MmNG TESTS IN A SEM ANNULAR DOWNCCVER WifH INTERACTING FLOWS FROM COLO LEGS e h i 145

NRC Contract Sponsor index (Contractor Reports) This index lists the NRC organizations that sponsored the contractor reports listed in this compilation. It is arranged alphabetically by major NRC organization (e.g., program office) and then by subsections of these (e.g., divisions) where appropriate. The sponsor organiza-tion is followed by the NUREG/CR number and title of the report (s) 3repared by that organi-zation. If further information is needed, refer to the main citation by tie NUREG/CR number. OFFICE OF EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) NUREG/CR4952. E APER; MENTAL STUOY OF hlLET WELD UN-PEGON 1. OFC OF THE D! RECTOR DERCUT EFFECTS ON WELDED TUB:NG STRUCTURES UNDER NUREG/CR-5006 PRA APPLOATION PROGRAM FOR INSPECTON CENTRIC AND ECCENTRC CYCLC LOADINGS. AT OCONEE UNIT 3 REGION 2. OFC OF THE OtRECTOR OFFICE OF INFORMATION RESOURCES MANAGEMENT NUREG/CR4868 MET AttVRGICAL EVALUATION OF AN 18-INCH OFFCE OF ADM.NISTHATON & RESOURCES MANAGEMENT. Db FEEDWATER LINE FAILURE AT THE SURRY UNIT 2 POWER STA- RECTOR (POST 870413) TON NUREG/CR-2907 V05 RADCACTIVE MATERIALS RELEASED FROM URANtUM RECOVERY FIELD OFC R4 NUCLEAR POWER PLANTS Annual Report 1984 NUREGICR4651 DEVELOPMENT OF RtPRAP DESIGN CRITERIA NUREG/CR-4921: ENG;NEERING AND QUAUTY ASSURANCE COST BY RiPR AP TE STING IN FLUMES Phase i FACTORS ASSOCIATED WITH NUCLEAR PLANT MOOtFCATION REGON 5. OFC OF THE DIRECTOR DMSON OF COMPUTER & TELECOMMUNCATONS SERVICES NUREG?CR 4768 V01: METHOOOLOGY AND APPUCATON OF SUR- (POST 870413) AOGATE PLANT PRA ANALYSIS TO THE RANCHO SECO POWER NUREG/CR 2850 VOS POPULATON DObG COMMITMENTS DUE TO PLANT Tash 1. Ana'ys,s Of ANC ? And Occ<ee PRAs RADCACTIVE RELEASES FROM NUCLEAR POWER PLANT SITES NbAEG/CR4768 YO2 METHODOW3Y AND APPLCATON OF SUR- IN 1983 ROGATE PLANT PRA ANALYSIS TO THE RANCHO SECO POWER PLANT Fanal Report OFFICE OF NUCLEAR M?TERIAL SAFETY & SAFEGUARDS OF FICE OF NUCLEAR MATERtAL SAFETY & ECO . OFFICE FOR ANALYSl$ & EVALUATION OF OPERATIONAL SAFEGUARDS. DIRECTOR i DATA NU7EG/CR-4515 V02 MODEUNG STUDY OF SOLUTE TRANSPORT OFFICE FOR ANALYSIS & EVALUATON OF OPERATONAL DATA. DI. IN THE UNSATURATED ZONE Workshop Proceedengs RECTOR NUREG/CR4(45 TOUGH USER S GUOE. N9P>EGeCR-2000 V0$N12- LICE NSE E EVENT REPORT (LER) NUREG/CA-4651 DEVELOPVENT OF RIPRAP DESIGN CRITERIA q COMPILATtON For Month Of December 1986 BY RIPRAP TESTING IN FLUMES Phase i

;          NUREGICR 2000 YO6 N1 LCE NSE E EVENT REPORT (LE R)                       NUREG/C44766 USER S MANUAL FOR THE NEFTRAN COMPUT.

COMPILATON For Month Of January 1987 ER CODE , NURE G/CR.2000 V06 N2 LCENSEE EVENT REPORT (LER) NUAEG/CR-4773 DESIGN FEATURES TO FACILITATE INTEPNA. t COMPILATON For Month Ot February 1987. TONAL SAFEGUARDS AT mixed-OXOE CONVERSON FACILL NUREC/CR 2000 V06 N3 LICENbEE ENENT REPORT (LE R) TtE S COMPIL ATON For Monm Of March 1987. NUREG/CR4808 M NTEO USER S MANUAL Nt MG/CA-2000 V06 N4 LCENSEE EVENT REPORT (LE R) NUREGICR4901- EFFECTS FROM INFLUENT BOUNDARY CONDI-COMPILATON For Month Of Apni 1987 TONS ON TRACCR MiGRATON AND SPATIAL VARIABillTY FEA-NURE G/CR-2000 V06 N5 LCENSEE EVENT REPORT .E R; TURES IN INTERVEDIATE SCALE EXPERIMENTS COMPILATION For Month Of Usy 1987 NUFGG/CR4957 $URVEY OF GEOPHYSICAL TECHNIOUES FOR NUREG/CR 2000 V06 N6 LCE NSE E EVENT REPORT (LER) ' SITE CHARACTERIZATON IN BASALT. SALT AND TUFF COMPILATON For Month Of June 1987. NUREG/CR4958 IMPACT OF PROPOSED FINANCIAL ASSURANCE NUREG/CR 2000 V06 N7 LCENSE E EVENT REPOaT (LER) REQUIREMENTS ON NUCLE AR MATERIALS LCENSEES COMPILAT:ON For Month Of JuPy 1987. NUREG/CR 5003 DESIGN OF A MATERIAL CONTROL AND AC-l COUNTING SYSTEM TO PROTECT AGAINST CONCEALMENT OF I NUREGICR 2000 V06 N8 LICE NSE E EVENT REPORT (LER) COMPILATON For Month 08 August 1987. OfvERSON BY FALStFICATON AND COLLUSON 7 NURE G/CR-2000 YO6 N9 LCENSE E EVENT REPORT (LER) DMSON OF SAFEGUARDS & TRANSPORTATON (POST 8?o413) COMPILATON For Month Of September 1987. NUREG/CR-3966 METHODS FOR IMPACT ANALYS4S OF SHIPPtNG l NURE G/CR-2000 V06N10 LICE NSEE EVENT REPORT (LERJ CONT AINE R S COMPILATON For Month Of October 1987. NUREG/CR-5002 MET"OOS FOR RECURRING LOSS TESTS NUREG/CR 2000 VO6N11. LCE NSE E EVENT REPORT (LE R) DIVISON OF FUEL CYCLE. MEDCAL. ACADEMO & COMMERCIAL COMPILATON For Month Of November 1987. USE SAFETY 87041 NUREGICR 4674 V03 PRECURSOPS TO POTENTIAL SEVERE NURE G t CR-4779 NEW DATA FOR AEROSOtS GENERATED Bf COPE DAMAGE ACCOENTS 1984 A STATUS REPORT Man RELEASES OF PRESSUR12ED POWDERS AND SOLUTONS IN Report And Appendses A And B STATC AIR NUREG/CR-4674 V04 PRECURSORS TO POTEN'IAL SEVERE OfVISON OF HIGH LEVEL W ASTE' MANAGEMENT (POST 870413) CORE DAMAGE ACCIDENTS 1984,A STATUS REPORT ApperWes NUAEG /CR4134 ROI RE POS4 TORY E NVIRONMENT AL PARAM-C.D And E ETERS AND MODELS RELEVANT TO ASSESSING THE PER. DIVISON OF OPERATIONAL ASSESSMENT (POST 870413) FORMANCE CF HIGH LEVEL W ASTE PACKAGES (BASALT,7UFF NUREG/CR 4722 SOURCE TERM ESTiMATON USING MENU-TACT AND SALT) NUREGICR4735 V02 EVALUATON AND COMPfLATION OF DOE OFFICE OF INSPECTION t ENFORCEMENT (POST 12/11/t9) W STE PACAAGE TEST DATA Bennual Report August 19As Jan-Ofy OF EMERGENCY PREPAREDNESS & E LG6NE E RING usi 198 7 RE SPONSE IEiB50212 -870413) LMVISON OF LOW LEVEL W AsTE MANAGEMENT & DECOMM;SSON NUREGICR 4524 CtOSf 0VT OF IE ELULLETIN 90 24 PREVENTON ING (POST 870413) OF DAMAGE Dur IO W ATER LEAKAGE INSOE CONTAINMENT NUR E G / CR-5041 V01 RECOVMFNDATONS TO THE NRC FOR (OCTOBE R 17,1960 INDtAN POINT 2 EVENT) REvtEW CRITE RI A FOR ALTERNATIVE METHODS OF LOW-NUREG/CA4663 CtOSEOUT OF IE BUU ETIN 83 01 F AILURE OF LEVEL RADCACTivE W ASTE DISPOSAL Task 2a Bew Gmund RE ACTOR TRIP BREAmERS (WESTINGHOUSE 08-50) TO OPEN Vau r ts ON AUTOM ATC TRIP SIGNAL DMSION OF FUEL CYCLE & MATERI AL SAFETY (PPE 87D413) NUREG/CR 4664 CLOSEOUT OF 'E BULLETIN 8304 F A1 LURE OF NUAEG/CR 4 736 COMBUSTON AEROSOLS FORMED DURANG THE UNDER /O(,T AGE T R tP F UNCTON OF REACTOR TR:P BUHNAG OF R ADiC ACTIVE LY CONTAM NATED M ATERIALS BRE A* E RS EtPER MENT AL RESULTS 147 L

F 144 NRC Contract Sponsor index  ! NOREG/CR4847: CASE HISTORIES OF WEST VALLEY SPENT NUREG/CR46et - ENCLOSURE ENV1RONVENT CHARACTERt2A-FUEL SHIPMENTS Feet Report TION TESTING FOR THE BASE LINE VALOATON OF COMPUTER i DiviSsON OF SAFEGUARDS (PRE 870413) FIRE S:MULATION CODES NUREG/CR4695. MATERIAL CONTROL AND ACCOUNTING (MC&A) NUREG/CR 4700 V4 DAF; CONTAINVENT EVENT ANALYSIS FOR LOSS DETECTION DURtNG TRANSITION PERODS AND PROC

• POSTULATED SEVERE ACCOENTS GRAND GULF NUCLEAR ESS UPSET CONDITIONS STATION UNIT 1 Draft For Comment C VERS TO MlN!M;2E NUREG/CR-4719: COOLA81UTY OF STRATIFIED UO2 DEBRIS IN +

tR /CR 78 0 S SODIUM WITH DOWNWARD HEAT REMOVALThe 013 Experrnent . N E /CR 3620 V D E H Y A ALY$l$ FOR FERRY STU Y THE ONSITE DISPOSAL OF RADOACTIVE WASTES.The ONSITE/ NUREG/CR4741: FEEDWATER TRANSIENT AND SMALL BREAK NURE /CR $ SWIFT la SELF TEACHING . CURRCUU,lM taustratrve Problems For The Sanaa Waste-isoittion LOSS OF COOLANT ACCOENT ANALYSES FOR THE BELLE 4~  ! NUR GI 5 A TRAN MODEL OF THE CALVERT CLIFFS-1 I NUR G CR 708 1N OGb N E UATON OF RADIO- PRESSURl2ED WATER REACTOR FOR ASSESSING THE SAFETY NUCLtDE GEOCHEMCAL INFORMATION DEVELOPED BY DOE EMS HIGH-LEVEL NUCLEAR WASTE REPOSITORY SITE N G A 6 x gagygt NURE 7 E VA ON F PC NT A ix W STES E R 77 N S N EVA UATON PROGRAM l g y CONTAW:NG LEAD, CHROMIUM.USED OIL,OR ORGANC LIO-NUREG/CR4802 AN EVALUATON OF TRAC-P'F1/ MODI COMPUT. , 1 NUR /CR4735 V01: EVALUATON AND COMPILATON OF DOE ER CODE PERNANCE DURING POSTTEST S:MULATONS OF bE E WASTE PACKAGE TEST DATA B4nnual ReportDecember 1985 - Nyg 48 TE BL Y L ET ATIONS NU G/CR-4737: INTERPRETATIVE ANALYSIS OF DATA FOR DURING DEGRADED-CORE ACCCENTS IN THE BELLEFONTE NUCLEAR POWER PLANT. SOLUTE TRANSPORT IN THE UNSATURATED ZONE NUREG/CR4805 V0t REACTOR SAFETY RESEARCH SEV;ANNU-NUREG/CR4825: A PRELIM; NARY EVALUATION OF THE ECONO,. AMINAT NCIO TS NUREG/CR48 CS OF CORRELATION BE' WEEN l EXPERTS Empercal Re*ults From Two Entremes i NUREG/CP 4875. CHARACTERIZATON OF CRUSHED TUFF FOR THE EVALVATON OF THE FATE OF TRAVERS IN TRANSPORT NUREG/CR-4819 V01: AGtNG AND SERVICE WEAR OF SOLENOO-OPERATED VALVES USED IN SAFETY SYSTEMS OF NUCLE AR , STUDIES !N THE UNSATURATED ZONE' POWER PLANTS Vo6ua ne 1 Operating Espenence And Fa41ure idente U S. NUCLEAR REGULATORY C048tilSS40N f'estion. 4 NRC . NO DETULED AFFILIATION GIVEN NUREG/CR4822: BROAD BAND SEISMC DATA NUREG/CR-4970: STAINLESS STEEL ROUND ROBIN ANALYS4$ September 1984 - September 1986. TEST Centrifugany Cast Stain 6ess Steet Screening Phase. NUREG/CR-4830 LELCOR VAllOATON AND VERIFICATON 1986 l PAPERS OFFICE OF NUCLE AR REGULATORY RESE ARCH (POST 4/08/80 NUREGICR4P45: AN ANALYS S OF THE SEMiSCALE MOD 2C S- L I

,                                                                        OFFCE OF NUCLEAR REGULATORY RESEARCH. OtRECTOR (POST                                                           NH 3 TEST USING THE TRAC PF1 COMPUTER PROGRAM 1

860720) NUREG/CR4848. STEAM GENERATOR GROUP PROJECT. Annual I 4 NUREG/CR-2331 V06 N2. SAFETY RESEARCH PROGRAMS SPON- Report .1985 [

SORED BY OFFICE OF NUCLEAR REGULATORY NUREG/CR4872- EXPER MENTAL AND ANALYTCAL ASSESSMENT i RESE ARCH Ouarterty Progress Report.Apr& June 1986 OF CIRCUMFERENTIALLY SURFACEORACAED P! PES UNDER  ;

4 NUREG/CR-2331 V06 N3 SAFETY RESEARCH PROGRAMS SPON- BENDING k SORED BY OFFCE OF NUCLEAR REGULATORY NUREG/CR4877. ASSESSMENT OF DESeGN basis FOR LOAD. RESEARCH Ouarterfy Progress Report July September 1986 CARRYING CAPACITY OF WELD OVERLAY REPAIRS , NUREG/CR 2331 YO6 N4. SAFETY RESEARCH PROGRAMS SPON. NUREG/CR4878: ANALYSIS OF EXPERIMENTS ON STAINLESS SORED BY OFFICE OF NUCLEAR REGULATORY STEEL FLUX WELDS Topcal Report RESEARCH Ouarterty Progress Report October December 1986 NUREG/CR4887: POSTCON A POSTPROCESSOR AND UNIT CON- r NUREG/CR-2331 V07 N1: SAFETY RESEARCH PROGRAMS SPON- VERSION PROGRAM FOR THE CONTAIN COMPUTER CODE i SORED BY OFFICE OF NUCLEAR REGutATORY NUREG/CR-4889 DRCALOY4 OxsDATON AT 1300 TO 2400 DE- l RESEARCH Ouarterty Prooress Report January March 1967 GREES C. ! NUREG/CR 3469 V03. OCCUPATONAL DOSE REDUCTON AT NU- NUREG/CR4897: LOW LEVEL WASTE SOURCE TERM , CLEAR POWER PLANTS. Annotated Behography Of Selected Read- EVALVATON Review of Pubhshed Modehng And Espenmental [ ings in Radiation Protecton And ALARA WortLAnd Presentation Of Low Level Waste Source term Modehng . NVHEG/CR 4062 VOS. DEGRADED PIPING PROGRAM + PHASE Frrnework And P 4mina y Model Deve6opment ' 11 Serrasnnual Report Apni September 1986 DIVISION OF ENG!NLJNG (POST 870413) i NUREG/CR4096. SEISMC-FRAGILITY TESTS OF NEW AND AC- NUREG/CR-2452 RISK METHOOOLOGY FOR GEOLOGC DISPOS-CELEAATED AGER CLASS 1E BATTERY CELLS AL OF RAv0 ACTIVE W ASTE. Final Report ] I NUREG/CR4216: EXPERIMENTAL RESULTS FOR A 18-SCALE NUREG/CR-3228 V05. STRUCTURAL INTEGRITY OF W ATER REAC- - STEEL MODEL NUCLEAR POWER PLANT CONTAJNMENT PRES- TOR PRESSUHE BOUNDARY COMPONENTS Annual Report For i SURIZED T7 F ALLURE. 1988 ] NUREG/CR4219 V0:1 N2 HEAVY SECTON STEEL TECHNOLOGY NUREG/CR 3231: PIPE TO PIPE IMPACT PROGRAM

!                                                                                          PROGRAM SUniennual Progress Report For Apr$ September 1986                       NUREG/CR-3319 400 LWR PRESSURE VESSEL SURVEtLLANCE j                                                                                  NUREG/CR-4301: STATUS FEPonT ON EOutPMENT OVAUFCA-                                                   DOSsMETRY IMPROVEMENT PROGRAM LWR Power Reactor Sur-4                                                                                           TON ISSUES RESEARCH AND RESOLUTON                                                           vediance Physcs-Dosametry Data Base Compensum j                                                                                  NUREG/CR4307 VQ3 LWR PRESSURE VESSEL SURVEILLANCE                                        NUREG/CR 3320 V03 LWR PRESSURE VESSEL SURVEILLANCE DOstMETRY            IVPROYEMENT             PROGRAM 1986        Annual                     DOSIMETRY IMPROVEMENT PROGRAM PSF Physics Dosanetry

' Reputoctober 1985 September 1966 Program { NUREG/CR-432& THE RELATONSHIP AND INFLUENCES OF FUEL NUREG/CR-3320 V04 LWR PRES $URE VESSEL SURVEILLANCE AND COOLANT SYSTEM PROCESSES DURING LWR SEVERE AC- DOSIMETRY IMPROVEMENT PROGRAM PSF MetaRurgy Program i COE NTS. NUREG/CA-3956 IN SITU TESTING OF THE SH PPINuPORT

NUREGICR4531

AN INVESTIGATON OF INTEGRAL FAC:UTY ATOMC POWER STATION ELECTRCAL CIRCUtTS 4 SCALING AND DATA RELATON METHOOS ONTEGRAL SYSTEM NUREG/CR-4161 V02 CRrTCAL PARAMETERS FOR A H GH LEVEL j TEST PROGRAM) W ASTE REP 7slTORY volume 2 Tutt NUREG/CR4617 ONSITE ASSESSMENTS OF THE EFFECTIVE- NUREG/CR-4161 V03 CRITCAL PARAMETERS FOR A HIGH-LkVEL d

NESS AND IMPACTS OF UPGRADED EMERGENCY OPERATING W ASTE REPOSITORY Volume 3 Evt PROCEDURES NUREGICR-4219 V04 N1 HEAVY-SECTON STEEL TECHNOLOGY 1 NUREG/CR4623 JN-SITU STRE3S MEASUREMENTb IN THE PROGRAM Semiannual Progress Heport For October 1986 March i EPRTH'S CRUST IN THE EASTERN UNITED STATES 1967

NUREG/CR4679 OUANTITATIVE DATA ON THE FIRE BEHAVOR NUREG/CR4300 V04 N1

ACOUSTC EM,SSION/ FLAW RELATION.

A OF COMBUSTIBLE MATERIALS FOUND IN NUCLEAR POWER SHIP FOR IN SERVCE MONITORING OF NUCLEAR PRESSURE j PLANTS A Laerature Recew VESSELS Progress Report. Octccer 1986 March 1987 4 I

NRC Contract Sponsor Index 149 NUREG/CR-4457; AGING OF CLASS 1E BATTERIES IN SAFETY NUREG/CR4863 SURFACE SPECT ROSCOPY OF PRESSURE SYSTEMS OF NUCLEAR POWER PLANTS VESSEL STEEL FATGUE FRACTURE SURFACE FILMS FORVED NUREG/CR4469 V05. NONDESTRUCTIVE EXAM,NATCN (NDE) RE- IN PNR ENViRONVENTS LIABluTY FOR INSERV1CE INSPECTCN OF LGHT WATER NUREG/CR4865. THE SOLU 8!UTY OF ELECTRODEPOSITED TCCV) RE ACTORS Semannual Report. Apnt-September 1986 Oxl DES NUREGICR4469 V06 NONDESTRUCTIVE EXAVAATON (NDE) RE- NUREG/CR4870- AN E\ ALUATON OF THE EFFECTS OF DESIGN LIABluTY FOR INSERV CE INSPECTON OF '.GH T W ATER DETAILS ON THE CAPACITY OF LWR STEEL CONTAINVENT RE ACTORS Semannual Report, October 1986 Va'ch 1987- BUILDINGS NUREG/CR-4527 V01: AN EXPERIMENTAL INVESTIGATCN OF IN- NUREG/CR 4886 ANALYSIS OF THE NE SDiP2 AND NESD'P3 TERNALLY GNITIED FIRES IN NUCLEAR POWER PLANT CON- RADIAL SHtELD AND CAVITY EXPER;MENTS TROL CAB: NETS Part 1 Catanet ENects Tests NUREG/CR4892 A STUDY OF THE EFFECTS OF PENETRATCN NUREG/CR-4S30 V02 U S / FRENCH JOtNT RESEARCH PROGRAM rRAM:NG ON STEEL CONTAINVENT BUCKLING CAPACITY. REGARDING THE BEHAVCR OF POLYVER BASE MATERIALS NUREG/CR 4894 A USER'S GUCE TO THE NRC'S PtPlNG FRAC-SUBJECTED TO BETA RADIATON Volume 2. Phase-ia Screening TURE MECHANCS DATA BASE (P: FRAC) Tests NUREG/CR-4S99 COMPONENT FRAGILITY RESEARCH NUREG/CR4534. ANALYSIS OF DiFFUSON FLAVE TESTS PROGR AM Pha M I Component Pnor*2atiort NUREG/CR-4577. AUTOMATED LONG-TERM SURVEILLANCE OF A NUREG/CR4900 V01 - COMPONENT FRAG 6LITY RESEARCH COMMERCIAL NUCLEAR POWER PLANT. PROGR AM PNsse i Demonstraton Tests Synrnary Report NUREG/CR4583 V02 DCVELOPMENT AND VALIDATON OF A NUREG/CR-4900 VC2- COVPONENT FRAGtLITY RESEARCH REAL TIVE SAFT UT SYSTEM FOR THE INWOON OF LIGHT PROGRAM Phase i Demonstraten Tests Append <es WATER REACTOR COMPONENTS. Annual Report,0ctoter 1984 - NUREG/CR 4903 VC1 STLECTON OF EARTHOUAF E RES;STANT September 1985 DES GN CRITERIA FOR NUCLEAR POWER PLANTS METHOO-NUREG/CR4583 V03. DEVELOPVENT AND VALIDATCN OF A OLOGY AND TECHNCAL CASES Dwect Empacal Scahng Of Re-REAL TIME SAFT UT SYSTEM FOR THE INSPECTCN OF LIGHT sponse Spectral Amphudes From Vanous Site And Earthquake Pa-WATER REACTOR COUPONENTS Anroal Report.Octoter 1985 - rameters September 1986. NUREGICR4903 V02 SELECTON OF EARTHOUAkE RES:STANT NUREG/CR4590 V01: AGING OF NUCLEAR STATON OtESEL DES:GN CRITERIA FOR NUCLEAR POWER PLANTS - METHOD-GENERATORS Evaluation Of Oper4 ting And Espect OLOGY AND TECHNCAL CASES Vethods For introducten Of Ge-Esponence Phase i Study olog<al Data into Cha a:tenzation Of Active Fa/ts And Se-smecify NUREG/CR 4590 V02. AGtNG OF NUCLE AR ST ATCN D!ESEL And. GENERATORS Evaluaton Of Operating And E xperi NUREG/CR-4903 V03 SELECTON OF EARTHOUAKE RES,$ TANT E rpenence Workshop DESIGN CRITERIA FOR NUCLEAR POWER PLANTS METHOD-NUREG/CR4654 RADeONUCLIDE TRANSPORT AS VAPOR OLOGY AND TECHNCAL CASES Desiocaton MMets Of Neaf. THROUGH UNSATURATED FR ACTURED ROCK Source tanhouake Ground Mcton A Recee NUREG/CR4655 UNSATURATED FLOW AND TRANSPORT NUR E G / CR-4904 INVESTGATON OF STEEL CONTAINVENT THROUGH FRACTURED FOJ RELATED TO HIGH-LEVEL W ASTE BUCKUNG FROM D)NAVC LOADS. REPOSJTORtES Feal Report Phase ll NUREG >CR 4912 DATING GROUND W ATER AND THE EVALUA-NUREG/CR 4667 V03 ENvlRONMENTALLY ASSISTED CRACKING TON OF REPOS; TOR'ES FOR RACCACTivE W ASTE IN LIGHT WATER REACTOAS Semiannual Repor1 Apni-Septence' NURE G /CR4 913 ROUND-ROD!N PRETEST AN ALYSES OF A 16-1980 SCALE REIN 50RCED CONCRETE CONT AINVENT MODEL SUS-NUREG/CR-4692. OPERATING EXPER:ENCE REY:EW OF FAILURES :ECT TO STATC INTERNAL PRESSURt2ATON OF POWER OPERATED RELIEF VALVES AND BLOCK VALVES IN NUREGICR4916 V01 CONTROL OF W ATER INrtLTRATCN INTO

                                                                        ^

NUR /CR 4 2 SAFETY ASSESSVENT OF ALTEF NATIVES 5 S e 96 TO SHALLOW LAND BURlAL OF LOW-LEvu RADCACTIVE NUREG/CR 4919 FIELD TESTtNG OF EENTONITE AND CEVENT W ASTE Volume 2 Envronmen'ai Conotions Affecting Rekat+ty Of BOREHOLE PLUGS IN GRAN TE Er9neered 8amers NURE G/CR-4926 AN ASSESSMENT OF LOSS-OF-CONT AiN VE NT NUREGeCR-4715 AN AGING ASSESSUENT OF RELAYS AND CIR- POTENTIAL BECAUSE OF KNUCKLE BUCKUNG FOR 41 STEEL CUIT BREAKERS AND SYSTEM .NTERACTONS CONTA% VENT HEADS NUREG/CR4731 V01. RESCUAL UFE ASSESSVENT OF MAJOR NUREG/CR-4928 DEGRADATION OF NUCLE AR PLANT TEVPERA-LIGHT W ATER REACTOR COMPONENTE OVERVIEW Volume 1 TURE SENSORS NUREG/CR 4744 V01 N2 LONG TERM EMBR;TTLEVENT OF CAST NUREG/CR-4930 CR ACK-AARE ST BE HAVCR IN SEN WT4 DUPLEX STAINLESS STEELS IN LAR SYSTEMS Semawal PuTES OF QUENCHED AND TEMPERED A 533 GRADE B STFEL NUR 74 i ONG TERM EMBalTTLEVENT OF CAST N E 43 6 A INTE G c ATE D DUPLE X ST AINLE SS STEELS IN LWR SYSTEMS Semiannua! ( GEOLOGCAL GEOPHv SCALAND GEOCHEV. CAL INVE ST GA-NUR GR 4 7 N FAILURE SURVEY OF LGHT WATER REACTOR SA N SYSTEMS AND COMPONENTS NUREG/CR 4 32 7 INVESTIG AT CN OF THE MEERS FAULT IN NUREG/CR4753 V02 NAD'AN SEISM C AGAEEMENT Annua' SOUTH AESTERN OnLA HOMA Nt RWCR470 TEST . r 6-IN THCK PRESSURE VESSELS Senes NUREG'CR 4443 PREP AR ATON OF DE SIGN SPE C>FICATONS AND DES GN REPORTS FOR PUVPS % ALVES PiPAG AND PIPING 3 Intermedate Test Vessel V BA Teanng Betacor Of Lem Upper. SUPPORTS USED IN SAFETY RELATED PORTONS Of NUCLEAR Sheff Matenal NTS NURE 4766 USER S MANUAL FOR THE NEFTRAN COMPUT. W[R NUREG/CR-4766 TPANSPORT BEHAVCR OF CO'NE IN EFFLU. SE AL LEAK RATE TESTS NUREC /CR-4 350 V01 THE SHOPEUNE ENvtRONVENT ATMDS-ENT RADCACTIVITY MON TORiNG SYSTEVS PHER C DGPERSON EXPER VENT ;SEACE*) Empereent Desenp-NUREG/CR4795 LONG TERM PERFORM ANCE OF H GH LEVEL GLASS WASTE FORMS ton NUREGICR4821 REACTOR COOuNT PUUP SHAFT SE AL STAB'L. NUREG/CR4950 V02 THE SHORELINE ENviRONVE NT ATMOS-ITY DUR:NG STATON BLACKOUT PHERC D SPERSON E* PER. VENT (SE ADE A) Veteorceg<at And NUREG/CR 4841: FRACTURE EVALUATON OF SURFACE CR ACKS Gas Tracer Data EMBEDOED 6N REACTOR VESSEL CLADOiNG unca$ated Bend NUHE G/CR4M 4 LONG-TERM PERFOHMANCE OF SPENT FUEL Specimen Results W ASTE FORMS NUREG/CR4846 HIGH-LEVEL WASTE PRECLOSURE SYSTEMS NUR E G /CR-4 955 LONG TE AM PE RF ORM ANCE OF CONT A'NE R SAFETY ANALYSIS Phase 2. Feat Report M ATE Ri ALS FOR H1C-H-LE v EL W ASTE NUREGICR4850 STEAM GENERATOR GROUP PROJECT Tash 10 - NURF G/CR-4356 SYSTEM PE RF ORM A NCE OF H-GH LE v E L Secondarr $de Enamenation Fear Report W ASTE FAN AGE COMA >Nt NTS NUREGICR-4851 SEISMCITY 1886 89 IN THE SOUTHEASTERN NuME G rCR4

• 8 E V ALU AT CN Of UNCE R T A!NTIE S IN tRR ADI AT -

UNITED STATES TM Aftershock Sequence Of T he ED HARDW ARE CHARACTERilATON Chaneston. South CaroMa Ear %uake NUHiG1CR 47% AUStVVE T4C ANALYSIS OF 16 SCALE PE!N NUR E G/CR-4860 FLA W DE NSIT Y EPU NATIONS OF A CLAD FORCED CONCRETE CONTAAVENT BUILDAG US!NG A D:S-BOtUNG W ATER REACTOR PRESSURE VE5SEL SEGVENT TRiBUTED CR ACWG VODEL FOR THE CONORETE

150 NRC Contract Sponsor index NUREG/CR 4973 tNTRAPLATE SEISMICITY OUTSOE OF THE NUREG/CR-4890 HE AT OF REACTON OF MOLTEN ZlRCONfUM UNITED ST ATES WITH 002. NUR E G/CR-4974 INTRAPLATE SElSM' CITY IN THE EASTERN NUR E G/ CR-4891: PROPERTIES OF REACTOR FUEL ROO MATERI-UNITED ST ATES ALS AT HGH TEMPERATURES Fnal Summary Report Severe NUREG/CR 4975 A REVIEW OF THE RESOLVtNG PCWER OF RE. Cue Dame Propery Tests Proys'n FLECTION SEISMOLOGY METHODS TO DETECT SUBSURFACE NUREG/CR 4896 CONTA:NVENT LOADS DUE TO OtRECT CON-F AULTS AND'OR CHANGES IN LAYER THiCKNE SS TAINVENT HEATING NUR EG/CR-4 376 PLANT RH!ZOSPHERE PROCESSES INFLUENC- AND ASSOCtATED HYDROGEN ING hAD+0NUCLCE MOSiUTY IN SOIL BEHAVIOR AnaWs And Caiculations With The CONTAIN Code NUREG/CR-4963 THE SEALING PERFORVANCE OF BENTONITE / NUREG/CR-4 SOS DETONABlUTY OF H2-AIR-DILUENT MIXTURES NUREG/CR-4909 MELPROG PWR/ MODO A MECHAN;STIC CODE NUREG/C 4 NT 2 ACTOR COOLANT PUVP p i ANALYSr5 OF REACTOR CORE MELT PROGRESSON AND SEAL EVALUATONS VESSEL ATTACK UNDER SEVERE ACCIDENT CONDtTONS. NUREG/CR-4987 S.VULATED SEISM;C TESTS ON 1/42 AND 1/14- NUREG/CR-4910 RELAY CHATTER AND OPERATOR RESPONSE SCALE CATEGORY L aux 1UARY BU4D!NG AFTER A LARGE E ARTHOUAKE An improved PRA Methodology NURE G / CR-4990 HEAVY SECTON STEEL TECHNOLOG Y W'tn Case Studes PROGRAM Free Year Plan FY 1986 1990 NUREG/CR-4925 FISSON PRODUCT BHAVIOR DURiNG THE PBF NUREG'CR-4995 E APER VENTAL ASSE SSMENT OF THE SEALING SEVERE FUEL DAMAGE TEST 11. PERFORMANCE OF BENTONITE BOREHOLE PLUGS NUR E G /CR-4953 CORRELATON OF RAD 40CDtNE RESUSPEN-NUREG/CR.5007 PREDCTON AND MittGATION OF EROSIVE. SON WITH TEMPERATURE AT TML2. CORROStVE WEAR IN SECONDARY PtPtNG SYSTEMS OF NU. NUREG/CR-4962 METHODS FOR THE EllCITATON AND USE OF CLEAR POWER PLANTS EXPERT OPtNON IN RSK ASSESSVENT Phase I A Crecal Eval-NUREG/CR 5008. DEVELOPMENT OF A TESTING AND ANALYMa uabon And Dwectons For Future Research METHODOLOGY TO DETERV,NE THE FUNCTONAL COND4 TON NUREG/CR 4963 BORON CARBCE STEAM REACTONS WITH OF sot E NO;D OPERATED VAL %ES CESIUM HYDROXOE AND WITH CES'UM ODOE AT 1270K IN AN NUR E G/CR-5014 PARAVETRIC STUDY OF PIPE WH'P AN ALY$;S INCONEL 600 SYSTE M NUREG/CR 5034 AN UPDATE OF M:DCONTINENT TECTON;SM NUREG/CR 5010- RELAPS/ MOD 2 ASSESSVENT USaNG SE M;S-NUREG/CR 5037. FIRE ENV!RONVENT DETERVlNATION iN THE CALE ExPER. VENTS S NH-1 AND S-LH-2 LASALLE NUCLE AR POAER PLANT CONTROL ROOM NUREG/CR-5040 RADIONUCUCE VORATION AROUND URANaVM NUREG/CR %17 UVE STONE CONCRETE AEROSOL E XPE RI. ORE BOOiES ANALOGUE OF RADIOACTIVE W ASTE VENTS IN STE AM air ATMOSPHERES NSPP Tests 521.522.And

                                                                      $31. Data Record Report NUAE / 5059 V           FR   I      EA V VENT L'OU)O LEVEL DETECTON CONCEPT ASSESSMENT AND DEVELOPVENT A $ DA NUREG/CR 5060 AN APPROACH TO THE MATHEMATICAL MODEL.             DMSiON OF REACTOR & PLANT SYSTEMS (POST 8704t3)

LING OF THE URANIUM SERtES REDtSTRlBUTON WITH,N ORE NUREG/CR-4407. P;PE BRE AK FREQUENCY ESTlMATON FOR NU-CLEAR POWER PLANTS DMS NUREGICR-4710 SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF RE SUST NUREG/CR-3024 ACTOR AiNEDACCOENT CONCRETE ATT ANAL'.S!S ACK BY L (POST OF A COMBUSTON E NGINE E R;NG PRE SSUR!2ED WATER 87013bW-TEM-PERATURE. FRAGVENTED CORE DEBRIS RE ACTOR Case Stwy NUREG/CR 4165 SEVERE ACCCENT SEOVENCE ANALYS:S PRO. NUREG/CR.4767 SHUTDOWN DECAY HEAT REMOVAL ANALYSIS GRAM . ANTICIPATED TRANSIENT WITHOUT SCRAM S MULA. OF A GENERAL ELECTRC BWR4/ MARK ICase Stay TIONS FOR BROWNS FERRY NUCLE AR PLANT UNIT 1 NUREG/CR 47Er9 RELAP5/ MOD 2 ASSESSVENT SIMULATON OF NUREG/CR-44SS VO2 THE IMFACT OF FUEL CLADDING FAILURE SEU: SCALE MOD-2C TEST S NH-3 EVENTS ON OCCUPATONAL RADIATION EXPOSURES AT NU- NUREG/CR 4810 EVALUATION OF D:ESEL UNAV AtLABrLITY AND CLE AR POWER PLANTS Case Sto FAR Dunng An Oua RISK EFFECTIVE SURVE!LLANCE TEST iNTEHvALS NUREG/CR-4534 ANALYS(S OF D USON F LAME TESTS NUR E G /CR.4817 COtNE PARTITON COEFFICiE NT MEASURE-NUREG/CR 4550 VOI ANALYSIS OF CORE DAMAGE FREQUENCY VENTS AT S.MULATED FAR ST E AM GENERATOR FROM INTERNAL EVENTS METHODOLOGY GUrDELINES CONDITONS interen Data Report NUREG/CR-4550 vo6PTt ANALYS!S OF CORE DAVAGE FRE- NUREG<CR 4934 V01 RECOVERY ACTONS IN PRA FOR THE RtSK OUENCY FROM INTERNAL EVENTS GA AND GULF UNIT I Van VETHODS INTE GR AT ON AND EVALUATON PROGRAM Report (RM'EP) Volume i Development Of The Data Based Methcd NURt.G CR 4550 V06PT2 ANALY sis OF CORE DAVAGE FRE- NUR E G /CR.4544 DRFT INT E GR A TE D RE LI ABtLIT Y AND RISK OVENCY FROM INTERNAL EV E NTS GRAND GULF.UNtf 1 Ame4 ANALYS S SYS'EM ORRAS) USER S GUCE VE RSiON 10 d<es (DRAFT) NUREG 'CR 4551 V3 PT1 EVALUATON OF SEVERE ACCCENT NUREG/CR-4862 VC1 COGNITIVE ENVIRONVENT S<MULATON AN R!SKS AND THE POT E NTI AL FOR RISK RE DUCTON PE ACH AR TIF C AL INTELUGENCE SYSTEM FOR HUM AN PERFORM-BOTTCM UNtT 2 Mac Aeport Dra't For Comment ANCE ASSESSVE NT vcaume 1 Summary And Over.ee NUREG/CR 4551 V3 PT2 E VALU ATON OF SEVERE ACCCENT NUREG'CR-4862 vo? COGN1TW E ENv1RONVENT 5:MUL ATON AN R:SkS AND THE POTENT!AL FOR R;SK REDUCTON FE ACH ARTircAL INThuGENCE SYSTEM FOR HUV AN PE RFORM-DOTTDM UN!T 2 Ameoces Dra't For Ccmment ANCE ASSESSVENT Vuume 2 MMeling Human intention Formula-NUREG/CR 4551 V4 DAF EVALUATON OF SEVERE ACCIDENT tion R'SKS AND THE POT E N TtAL FOR R;SK RE DUCTION GRAND WREG'CR 4862 V03 COGNITIVE E NVIRONME NT S-MULATON AN NU EG 72 EVA U TO[C F PROTECTNE ACTION ALSES " NUREG/CR 4727 SW:SS SUSTAINED HE A TED VE TALUC MELT / AN E ASSESSW Vm 3 Cogee Reawy Anaws h CONCAETE INTE R ACTONS WITH OvE RLviNG W ATER POOLS "** NUREG/CR-4769 RISK EVALUATONS OF AG'NG PHE NOVEN A The NJREG/CR r 22 s STE AM SEPARATOR MODEUNG FOR V ARCUS L ne ar A Renatuit MMet And its E ste%ons NUCLE AF RE ACTOR TRANSlE NTS NURE G/C 4 81 DRFY STUDY OF SE w ERE ACCtDE NT HTiG A. NUREGeCR 4H1 RESPONSE OF CE NTRiF UG AL AND Axi-V ANE TON SYSTEMS BLOWERS TO L ARGE PRESSURE TRANS ENTS NUREG/CR 400 SIGP1 A USER S VANU AL FOR F AST COVPUT A. NUREG!CR 4 341 THE APPUCATON OF VALUE-# PACT ANALYSIS TON OF THE PROB AB'USTIC PERFORVANCE OF COMPL E n TO USt A 45 %mmary Repon OI UCLA Studes On Value impact sySTE MS Anaws in Reision To list A 45 NURE G/CR-4855 DEVE LOPVENT AND APPuCATON OF A COM NUREG/CR 4942 E QuiFVE NT OPE R AB tut Y DUR NG ST A TON PUTER MODEL FOFt LARGE SCALE FLAVE ACCE LERATON E x. BL ACa OUT EVE NTS PE R VENTS NUR E G 'CR 4 94 5 SUUVARY OF THE SEM SCALE PROGRAM NUREG/CR 466G AN ASSE SSUENT OF HYDROGE N GE NER AT ON O M5 NO FOR THE PEF SE VE RE FUE L DAM AGE SCOPLNG AND 1-1 TE STS NJRE G/CR-4946 DAWS BE SSE UNCE RT A:NTY STUDY NURE G/CR 4e71 RE SUL TS F ROM THE DCH- 1 E nPE R VE NT MRE G/CR 4x5 fR AC PF1/MDDI US/J APANE SE PA R CONSE RV-NURE G'CR 4676 SiLVE R 1NDtLV CADUaM CON T ROL ROD BE. A Tr/E LOCA PREDICTON HAVOR AND AE ROSOL FORM ATON iN SE VE RE RE ACTOR AC- NURE G/CR 4M V01 E v ALUATON OF OPE RATONAL SAFE TY AT COENTS B ABCOO AND WILCOn PLANTS Volume 1. Resuits Owe NURE G 'CR 4% 3 RE v'E W OF RE SE ARCH ON UNCERT AtNT:E S tN NURE G CR 4 h V02 E V ALUATON OF OPE H ATONAL SAF ETY AT ESTiM ATES OF SOURCE TERMS FROM SE VERE ACCCE NTS IN B ABrock AND AtLCCx PLANTS Volume 2 . Thermat Hy&a.A; Re NUCL E AA POW E R K ANTS suns

NRC Contract Sponsor index 151 NUREG/CR-4972 TWO-PHASE FLOW REG.ME TRANSITON CRITE- NUR EG/CR-4712 REGULATORY ANALY SIS OF REGULATORY AlA IN POST-DRYOUT REGON BASED ON FLOW VISUAll2ATON GUOE 135 (REVISON 3. DRAFT 2) IN-SERVCE INSPECTION EXPf AtVENTS OF UNGROUTED TENDONS IN PRESTRESSED CONCRETE CON-NUREG/CR 4978 THE COOLDOWN ASPECTS OF THE TMI-2 ACCl- TAINVENTS DENT. NUREC/CR-4724 FATIGUE CRACK GROWTH RATES IN PRESSURE NUREG/CR 4982 SEVERE ACCCENTS IN SPENT FUEL POOLS IN VESSEL AND PIP'.NG STEELS IN LWR ENVIRONVENTS Foal SUPPORT OF GENERC SAFE 1(ISSUE 82 Report. NUREG /CA4988 A TRAC-PF1/ MOD 1 ANALYSTS OF THE GINNA NUREG/CR4734 SEISMC TESTING OF TYPICAL CONTAAMENT TUBE RUPTURE EVENT ON JANUARY 25,1982 PIPtNG PENETRATON SYSTEMS NUR E G / CR-5011. APPUCATON OF THE ADAPTIVE-PRED;CTIVE NUREG/CR-4744 V01 N1: LONG-TERM EMBRITTLEMENT OF CAST CONTROLLERS TO PLANT SAFETY SURVEILLANCE UTlu2iNG DUPLE X STAINLESS STEELS IN LWR SYST EMS Sewannuat ON UNE PLANT ANALYZER ReportOctober 1985 March 1986 NUREG/CR-5042 EVALUATON OF EXTERNAL HAZARDS TO NU' NUREGICR-4767; CONFERENCE OF RADIATON CONTROL PRO-CLEAR POWER PLANTS IN THE UNITED ST ATES GRAM OtRECTOR$' INFORMATON FOR LCENSING LOW LEVEL DIVISON OF REGULATORY APPtiCATONS (POST 870413) RADOACTIVE WASTE INCtNERATORS AND CCVPACTORS NUREGiCR 4330 V03 REVIEW OF LIGHT WATER REACTOR REGU- NUREG/CR-4813 ASSESSMENT OF LEAK DETECTON SYSTEMS LATORY REOUfREMENTS Assessment Of Setected RMutatory Re- FOR LWRs October 1985 September 1966 ouvements That May Have Magnal imponance To NUREG/CR4818 TRANSITION RANGE DROP TOWER 1R CURVE R sk Fcstaccedent Sampung Soters Turtune Missdes,Combustele TESTING OF A106 STEEL Gas ControlCvcoal Fate'$ NUREG/CR4820 COMPARISON OF THE 1982 SE ADEX DISPER. NUREG/CR 4416 DOSE CALCULATON FOR CONT AViNATON OF SiON DATA WITH RESULTS FROM A PUVSER OF D;FFERENT TFE SKIN US:NG THE CCMPUTER CODE VARSKIN MODELS NUREG/CR 4704 V01. RELATrVE BIOLOGICAL EFFECTIVENESS NUREG/CR-4826 V01: SEtSMtC M ARGlN REY:EW OF THE MAINE [RBE) OF FISSON NEUTRONS AND GAMMA RAYS AT OCCUPA. YANKEE ATOMC POWER STATON Volume 1 Summary Report TONAL EXPOSURE LEVELS Votume 1 Studes On The Genetic Ef- NUREG/CR 4826 V02 SEISM C MARG:N REV!EW OF THE MAINE fects in M<e Of 60 Equal Once-Weekly Esposures To Fsson Neu- YANKEE ATOJC POWER STATON Volume 2 Systems Ana'yus trons And Gamma Aays NUREG/CR4826 V03 SEISVC MARG lN REVIEW OF THE MA NE NUREG/CR4704 V02 RELATIVE BOLOGCAL EFFECTIVENESS YANKEE ATOMC POWER STATON Vcau m e 3 FragMy Ana'yts (RBE) Of FISSON NEUTRONS AND GAUMA RAYS AT OCCUPA- NUREG/CR4542 A STUDY OF NATURAL GLASS ANALOGUES AS TrONAL E)POSURE LEVELS Volume it Stud.es On The Etiects Of APPLIED TO ALTERATON OF NUCLEAR W ASTE GLASS 60 Eocal Once Weeoy Esposures To Fissson Neutrons And Gamma NUREG /CR4852 THE MEERS F AULT TECTONC ACTIVITY IN Rays On surnal Of Mce SOUTHWESTERN OKLAHOM A NUREG /CR 4884 INTE RPRET ATION OF BIOASSAY MEASUAE- NUREG/CR 4953 APPROLM ATE METHOOS FOR FRACTURE MENTS ANALYSES OF THROUGH-W ALL CRACnED PtPES NUREGICA 4938 OCCUPATONAL RADIATON EXPOSUAES ASSO- NUREG/CR4B59 SEtSM>C FRAG 1UTY TEST OF A 64NCH O! AVE-CIATED WITH ALTERNATIVE METHOOS OF LOW 4EVEL W ASTE TER PIPE SYSTEM NU R 4951 NEPHROTOXOTY OF URANYL FLUORCE AND SPEC RA REN ERStB'LITY OF RENAL INJURY IN THE RAT DIVISION OF REGULATORY APPLICATONS 6 60720-870413) NUREG/CR 4958 tVPACT OF PROPOSED FINANCIAL ASSURANCE NUREG/CR4479 VC2 DAT A BASE ON NUCLEAR POAER PLANT REOU!REVENTS ON NUCLEAR MATERIALS 6CENSEES DOSE REDUCTON RESEARCH PROJECTS NUAEG/CR4959 FERFORMANCE TESENG OF EXTREM;TY DOSI- NUREG/CR 4815 DE MONSTR ATION TESTING OF A SUR VE IL-0 #N' NURE CR 49B6 RADtATON DOCE ESilMATES AND HA2ARD g g EVALUATONS FOR INHALED A;ABORNE RADONUCLOES Fwsal NUREG/CR-4856 FEAStBtuTY STUDY ON A DAT A B ASED SYSTEM

                                                                                      $                           "L    ^      "

NR CR 5025 ExPER. MENTAL STUDIES OF THE E ARLY EF- TO MEA URES FECTS OF INHALED BETA EM!TTING RADIONUCLCES FOR NU- DIVISION OF RE ACTOR SYSTEM SAFETY 4 60720-870413) NUR CR 5 DA ASE C YSTE [EAG DOSE RATES AND COVSUSTION CHARACTER!STICS IN THE FITS VESSE L NUREG/CR 4016 V02 APPUCATION OF SUV MAUD A TEST OF AN NUREG CR 36 C ST NALYS iMPLEVENT AT ON Of INTER.tCTIVE COMPUTER-BASED VETHOO FOR ORGANtZiNG PROPOSED CHANGES IN YtTAL ARE A REQUiREVENTS EXPERT ASSESSMENT OF HUVAN PE RFORM ANCE AND DIVISION CA ENG!NEERiNG SAFE TY (860W 8704 t3i RE UAB:UTY Volume il Appenoces NUREG/CR 3145 V05 GEOPHYSCAL INVEST GATONS OF THE NUREG/CR4550 V03 ANALYS:S OF CORE DAMAGE FREC-'ENCY WESTERN OH O-INDIAN A REGON Final Report October 1981 FROM INTERNAL EVENTS SUARY UNrT 1 Septm.er 1966 NUREG/CR-4550 V04 ANALYS!S OF CORE DAM AGE FREQUENCY i NUREG/CR 3232 DET AILED STUD'ES OF SE LICTED W E LL E x. FROM INTERNAL EVENTS PE ACH BOTTOM UNIT 2 POSED FRACTURE ZONES IN THE ADiRONDACK MOUNT AlNS NUREG/CR4550 V05 ANALYSIS OF CORE DAV AGE FREQUENCY DOVE.NEW YORK FROM INTERNAL EVENTS SEQUOY AH UNIT 1 NUREG/CR 3412 V02 CONT A:NVE NT INTEGR1Ty NUREG/CR 4551 VI DRF E V AL U A TON OF SEVERE ACCIDENT PROGR AM Prcgess Recort Apr41963 -December 1964 R:SKS AND THE POTENTIAL FOR FuSk REDUCTON SURRY NUREG/CR 3444 V04 THE IUPACT OF LWR DECONTAM NATONS PO AER ST ATON UNtT 1 Dra't For Comment ON SOUDiFCATON W ASTE DISPOSAL AND ASSOCIATED OCCU. NUR E G / CR-4551 V2 DRF EVALUATION OF SEVERE ACCOENT PATONAL E APOSUAF Annua! Repori Fiscal Year 1986 RISKS AND THE POTENTIAL FOR RISK REDUCTION SEQUOY AH NUREGICR M61 STRESS CORRDSiON CR ACnrNG OF LOW. POWER $7ATON UNIT 1 Dra't for Comment STRENGTH CARBON STEELS IN CANDOATE HPGH-LEVEL NUREG CR 4610 EFFECTS Of LATER AL SEPAR AT!ON OF CrDC W ASTE REPOSITORY ENV.RONMENTS AND VET ALUC CORE DEBR:S ON THE B AR V* I CONTA N NUREG CR 43cM V03 N2 ACOUSTC EV:SSON FLA A RELATON-VEN T OR rW E LL FLODR SH:P FOR INSERVCE VON:TORiNG OF NUCLE AR PRESSURE NUREG/CR 4616 ROOT CAUSES OF CCVPONENT F A'LUAES VESSELS Progress Rept Apr4 Sectember 1986 PROGRAM Vetncos And Apc+cabors NUAEG'CR 4469 V04 NONDESTRUCTIVE EXAM.NATON (NDE) RE. NUREG'CR-4672 ANALYS'S OF INSTRUVENT TU9E RUPTUAES iN UA8ruTY FOR 'NSE RvlCE iNSPECTON OF UGHT W ATER WE STINGHOUSE 4 LOOP PRE SSURi2ED W ATER RE ACTOAS AE ACTORS S~niants.,a1 Resort October 1995 March iB6 NUREG/CR 46A) THE AV AL.H f DR AULIC AND CHAR ACTER:STiC NUR E G / CR-4 4 91 DEVELOPVENT OF VODELS FOR W ARV PRES. MODELS FOR PACS ED DEBR:S BEDS TRE SSrNG NUREG'CR 4541 E xPER VENT AL ASSESSMENT OF THE SE AUNG NUR E G 'C R-46v6 CONT A:NVENT VE NTN AN ALY sis FOR THE PE ACH BOTTOM ATOV.C POAER ST ATON EFFECirvENESS OF ROCn FRACTURE GROUTING NURE G 'CR-4685 POST PUOC E NE DISPLACE VE NT ON FAULTS NUREG"CR 4700 V1 DRF CONT A1NVENT EV E NT ANALY S S FOR POSTULAT E 0 SEVERE ACCtDE NT S SURRY POAER WITKN THE

• ENTUCAY RwER F AULT SYSTE M OF E ANN-TRAL nENTWAY ST ATON UNIT S Dra'1 For Comment NUREG'CR 4 711 LOW UPPER SHELF TOUGHNESS HiG4TR ANSL NURE G'CR--4700 Y2 DAF CONT A NVE NT E VE NT ANO S S FOR TCW TEMPERATURE T EST INSERT IN HSST PTSE 2 bESSEL POSTULAT E D SEVERE ACCDE NT S SEQUO AH PO4ER AND W'DE PLATE TE ST SPEC'VENS Feai Report ST ATON UN*T 1 Dra't Repor1 For Comment

152 NRC Contract Sponsor index NUREG /CR-4 718 EXPER VENTAL SUPPORT AND DEVELOPVENT OF S:NGLE ROD FUEL CODES PROGRAM Summary Report DiVISON OF ENGINEER <NG & SYSTEMS TECHNOLOGY (POST 8?O411) NUREG/CR-4742 UE LPROG-PW R/ MOD 1 ANAOSIS OF A TULB' ACC DENT SEQUENCE NUREG/CR-4885. SEiSVC HAZARD CHARACTERIZATON OF THE EASTERN UNITED STATES Cornparatwo Evaluation Of The LLNL NUREG / CR-4 752 CO:NCOENT STEAM GENERATOR TUBE RUP- And EPRI SWd.es TURE AND STUCKOPEN SAFETY REUEF VALVE CARRYOVER TESTS VB-2 Steam Generator Tra%+nt Response Test Program DivlSON OF LICENSEE FERFORVANCE & QUALITY EVALUATION (po ST g7cag3) NUREG/UR 4788 AN ANALYT6 CAL AND E APER VENT AL INVESil. GATION OF NATURAL C:RCULATION TRANS.ENTS IN A VOCEL NUREGICA-4640- HANDBOOK OF SOFTWARE OVALITY ASSUR-PRESSURIZED W ATER REACTOR ANCE TECHNOUES APPtlCABLE TO THE NUCLEAR INDUSTRY. NUREG/CR-4789 THE SiUULATION OF THER90HYDRAUUC PHE- OFF CE OF NUCLEAR REACTOR REGULATON, DIRECTOR (851125 g 734 p y NOVENA IN A PRESSURIZED W ATER REACTOR PR' MARY LOOP NUREG/CR 4798 IRON OACE AEROSOL EXPER VENTS IN NUREGiCR-3469 V03 OCCUPATONAL DOSE REDUCTON AT NU-STEAM-AIR ATMOSPHERES NSPP YESTS 501-505 AND 511. DATA CLEAR POWER PLANTS Annotaled BMog/aphy Of Selected Road. ngs in Ra44 ton Protecton And ALARA RECORD REPORT' NUREG/CR-4824 EV ALUATION INTEGRAL OFCONTINUING Ex. D4VISON OF HUMAN FACTORS TECHNOLOGY (851125-870411) PER.VENTAL CAPABluTY (CEC) CONCEPTS FOR UGHT W ATER NUREG/CR 3968 STUDY OF OPERATING PROCEDURES IN NU. AE^ CLEAR POWER PLANTS Prachces And Prc6tems gggEkCR 48 E VO "S PP N NUREG/CR 4613 EVALUATON OF NUCLEAR POWER PLANT OP. ESPONSE TO SEVERE HIGHW AY AND RAtLW AY ACCOENT CONDITIONS Main ERATING PROCEDURES CLASS)FICATONS AND R INTERF ACES Protnems And Techniques For smorovement NUR CR-4829 V02- SH:PP!NG CONT A:NE R RESPONSE TO Dly!SiON OF PRESSURIZED W ATER REACTOR LCENSING . A VERE HW Y AND RAILW AY ACCOENT 5 g gE R 39 V03 FUEL PERFORMANCE ANNUAL REPORT NUREG/CR-4843 VC1 UN'VERSITY OF MARYLAND AT COLLEGE FOR 1985 PARK (UMCP) 2x4 LOOP TEST FACIUTY Annual Report For 1985 NUREG/CR-4552 A REVPW OF THE SEABROOK STATON PROS-DivlSON OF ACC DENT EVALUATON (POST 840101) AB'USTC SAFETY ASSESSVENT Containment Faelure Modes And NV A E GICA-4 793 RE SULTS OF SEV SCALE MOD-2C SMALL. Ra$olo@ cal Source Tems BREAX LOSSOF.CCOLANT ACCOENT W1THOUT HPI (S NH) E x. NUREG/CR-4797. PROGRESS REVIEWS OF Six SAFETY PARAVE-PER VENT SER ES TER OtSPLAY SYSTEUS NUREG/CR 4Bf,8 VETALLURGCAL EVALUATION OF AN 18-INCH EDO RESOURCE MANAGEMENT COST & ST ATISTICAL ANALYSIS STAFF W1123 870413) FEEDWATER LINE FAILURE AT THE SURRY UNIT 2 PCWER STA-TION NUREG/CR 4012 V02 AEP.ACEVENT ENERGY COSTS FOR NU-CLEAR ELECT RICITY-GE NER ATING UNITS :N THE UNITED D:VISON OF PRESSURIZED WATER REACTOR LCENSING B

                                                                        ;85tg25.e7o433)

STATES 1987 1991 NUREG/CR-4801. CUMATOLOGY OF EXTREME WINDS IN SOUTH. ERN CAUFORNIA OFFICE OF NUCLE AR RE ACTOR REGULATION (POST 4/28/80) OFFCE C+ NUCLE AR RE ACTOR REGULATON, DIRECTOR (POST DivtSON OF SAFETY REVIEW & OVERSIGHT (851125-870411) NUREG/CR 4448 SHUTDOAN DECAY HE AT REMOVAL ANALYSIS NUR G/ R-3495 CALCULATON OF FAtLURE IMPORT ANCE VEAS- OF A GENER AL ELECTRIC BWR3/ MARK ICase Study URES FOR BASIC EVENTS AND PLANT SYSTEMS IN NUCLE AR OF A WESTINGHOUSE 2-LOOP PRESSUR!2ED WATER NU EG/ R 44 5 PROBAB'U$ TIC R:SA ASSESSVENT (PRA) IN- C EG,7O CR 4626 0 iMPROYtNG THE REllABluTY OF OPEN-N E R 4783 ANALYSTS OF BALANCE OF-PLANT R E G ULA. CYCLE W ATER SYSTEVS App 4caton Of Bofouling Surveistance TOAY ISSUE S Final Report And Control Techneques To Sediment And Corros on Fouting At Nu-NUR E G / CR-4964 UPDATE Or TABLE S4 NONAADiOLOGCAL EN. clear Power Piants VIRC-NV E NT AL PARAVETERS FOR A REFERENCE UGHT. NUREG/CR 4653 GASPAR u - TECHNCAL REFERENCE AND USER NUREG 4 1 SA Y k E OF T E USE Of NU E CR 4713 SHUTDOWN DECAY HEAT REMOVAL ANALYSiG GRAPHITE IN NUCLEAR RE ACTOR % LICENSED BY THE U S OF A BABCOCK AND WILCOx PRE SSURIZED WATER NRC RE ACTOR Case St4 D:V'SION OF OPE RATON AL EV ENTS ASSESSUENT (POST 870411 NUREG/CR-4762 SHUTDOWN DECAY HEAT REMOV AL ANALYS:S NUREG/CR400 v01 N1 GE NE RIC COVvuNCA TONS iNDE A L shngs Of Comm u n<ances (1971 19%) OF A W E SitNGHOUSE 3 LOOP PRESSUR: ZED WATER RE ACTOR Case Study NUREG 'CR 46 F) V02 GENERC COVVJNCATONS INDEx Users NUREG/CR-4 776 RE SPONSE OF SEtSMIC CATEGORY t TANKS TO Vasai EARTHOUAkE E ACITAT60N b

6 I . Contractor Index This index lists, in alphabetical order, the contractors that prepared the NUREG/CR reports listed in this compilation. Listed below each contractor are the NUREG/CR numbers and titles of their reports. If further information is needed, refer to the rnain citation by the NUREG, CR number. i AECL, CHALK RIVER NUCLEAR LABORATORIES NUREG/CR 4912 DATING GROUND W ATER AND THE EVALUATION NUREG/CR 4821 REACTOR COOLANT PUMP SHAFT SE AL STABILi- OF REPOSITORIES FOR RADCACTIVE W ASTE ' NUREG/CR4919- FIELD TESTING OF BENTOMTE AND CEMENT TY DURING STATON BLACKOUT-AERONAUTICAL RESEARCH ASSOCIATES OF PRINCETON NUREG/CR4983 THE SEAUN3 PERFORM ANCE OF BENTONITE / NUREG/CR4820 COVPARISON OF THE 1982 SEADEX OISPERSON E 8 ^L k OATA WITH RESULTS FROM A NUMBER OF OtFFERENT MODELS 6[CR E PE ASSESSMENT OF THE SE AUNG ' PERFORMANCE OF BENTONITE BOREHOLE PLUGS AEROSPACE CORP. NUREGICR-4847- CA$E HISTORIES OF WEST VALLEY SPENT FUEL ARMY,0EPT. OF, ARMY ENGINEER WATERWAYS EXPERIMENT SHIPMENTS Final Report r STATION ! AMERICAN CHEMICAL SOCIETY NUREG/CR 5041 vot: RECOVVENDATCNS TO THE NRC FOR j NUREG/CP 0078 PROCEEOiNGS OF THE STMPOSIUV ON CHEMI- REVTW CRITERIA FOR ALTERNATIVE VETHODS OF LOW LEVEL CAL PHENOVENA ASSOCIATED WiTH R AD'OACTivlTY RELEASES RADIOACTIVE W ASTE DISPOSAL Tan 2a Be6ce-Ground Va/ts. DURING SEVERE NUCLEAR PLANT ACCCENTS AUSTRALIAN ATOMIC ENERGY COMMIS$10N AMES LA80RATORY ENERGY & MINERAL RESOURCES RESE ARCH

• INSTITUTE NUREG/CR $040 RADiONUCLIDE MiGRATCN AROUND URANIUM f AN ALOGUE OF RADCACTivE W ASTE i NVREG/CR-48'O AN EVALUATCN OF THE EFFECTS OF DESGN ORE BOO!E S REPOSITOAIES Amua! Repo t ror 1984-1985 t l DETAILS ON THE CAPACITY OF LWR STEEL CONTAtNVENT BUILDINGS NUREG/CR 5060: 1.N APPROACH TO THE M ATHEMATICAL MODEL+

l

• h ANALYSl$ & W ASUREMENT SERVICES CORP.

NUREG'CR-4928 DEGRADATON OF NUCLEAR PLANT TEVPERA-

• TURE SEN!CRS g g g ARGONNE NATIONAL LADORATORY NUREG/CA 4711. LOW UPPER SHELF TOUGHNESS.HIGH TRANSI.

NUREG/CR 4012 V02. REPLACEMENT ENERGV COSTS FOR NUCLE. TION TEVPERATURE TEST INSEHT IN HSST PTSE-2 VESSEL AND AR ELECTRaCITY GENERATING UNITS IN THE UNITED WCE-PLATE TEST SPEC VENS FeaI Report [ ] , ST ATES 19871991

NUREG/CR-4667 V03 ENVIRONVENTALLY ASSISTED CRACklNG IN BATTELLE HUMAN AFFAIRS RESE ARCH CENTERS NUREG/CR 3968 STUDY OF OPERATING PROCEDURES IN NUCLE-NURE / 4 V Tiv cob FF ik 5$tR8 AR POWER PLANTS Pract<es And Protnems i OF FIS$10N NEUTRONS AND GAVMA RAYS AT OCCUDATONAL NUREG/CR 4613 EVALUATON OF NUCLEAR POWER PLANT OPER- l EXPOSURE LEVELS vo6ume 1 Studes On The Genetc ENects in AtlNG PROCEDURES CLASS!FICATIONS AND Mce Of 60 Eoval Once WeeOy Esposures to Fason Neutrons And INTERF ACES Protaems And Techneques For improvement i Gamma Res

! NUREG/CR-4704 V02 RELATIVE BOLOGICAL EFFECTIVENESS iRBE) BATTELLE MEMORIAL INSTITUTE OF FISSCN NEUTRONS AND GAMMA RAYS AT OCCUPATCNAL EXPOSURE LEVELS Vo6ume la Stuees On the ENects Of 60 Equal NUREG/CR 4956 SYSTEM PERFORVANCE OF HGH-LEVEL WASTE Once-Weeuy Exposures To Fssion Neutrons And Gamma Rays On PACK AGE COMPONENTS Suvval Of Ma NUREG/CR-4744 V01 Nt LONG TERV EVBRITTLEVENT OF CAST B ATTELLE MEMORIAL INSTITUTE, COLUMBUS LABORATORIES DUPLEX STAINLESS STEELS IN LWR SYSTEMS Semannual NUREG-1150 DRF VI FC REACTOR ALSK REFERENCE DOCUMENT Van Report Dra et For Comment NUHW 4 V 1'N L ERV EMBRITTLEVENT OF CAST NUREG/CA 3861 ST RE SS-CORROSCN CRACKING OF LOW-DUPLEX STAINLESS STEELS IN LWR SYSTEMS Senannual STHENGTH CARBON STEELS 6N CANDIDATE HGH-LEVEL W ASTE Report Apni-Septemtier 1986 REPOSiTO9Y ENVIRONVENTS NUREG/CR4744 V02 N1 LONG TERM EVERITTLEVENf OF CAST PHASE DUPLE X STAINLESS STEELS IN LWR SYSTEVS Ser% annual NURE G/CR 4062 V05 DEGRADED PiPM PROGRAV Report October 19% March 1987 tl Semannual Recort Ap+Septamter 1986

• NURE G/CR4813 ASSIS$ VENT OF LEAK OETECTCN SYSTEMS N JR E G / CR-4696 CONTA'NMFNT VENTtNG ANALY95 FOR THE PE ACH BOTTOM ATCM'C POWER ST ATON 7 NUR G/ 4 UY U GLASS ANALOGUES AS G 795 LON3-T E RM PERFORVANCE OF HIG+ LEVEL  ; .,

APPLIED TO ALTERATON OF NUCLEAR W ASTE GL ASS GLASS W ASTE FORMS , NUREG/CR4964 UPDATE OF TABLE S 3 NONRADCLOGICAL ENVI NURES/CRA53 APPROX M ATE VETHOO5 FOR FRACTURE A'tALY. RONMENTAL PARAVETERS FCA A REFERENCE UGHT4 ATER SES OF THROUGH4 ALL CRACF ED P6 PES RE ACTCR Uransum Momg V 8 ting And Ennchment NUREG/CR @ TWO PHASE FLOW REGtVE TRANSITON CRITE- NUREG /CR4672 E*PER:YENTAL AND ANALYTICAL ASSESSVENT RtA IN POni ORYOUT REGION BASED ON FLOW VISUALt?ATON OF CIRCUVrE RE N RALLY SURF ACE-CRAC* E D PtPE S UNDER l E NPE RlVE NT S BENDM NUREG/CR4977 ASSESSVENT OF DESIGN BASIS FOR LOOCAR-G/ E PE N L ASSESSMENT OF THE SEALING NURE G/CR4878 AN AL Y S;S OF E n PE R.VE NTS ON STAINLESS [ EFFECTnENESS OF ROCK FRACTURE GROUTING STEEL FLU) wet DS Tor <al Recori NUREG/CR 4654 RADONUCUDE TRANSPORT AS VAPOR NUREG'CR 4954 LONG TERM PERFORMANCE OF SPE NT FUEL THROUGH UNSATURATE D F R ACTUR*D Rgg UNSATUR AT E D F LOW AND TRANSPORT W ASTE FORVS NURE GrCR4655 THROUGH FRACTURED ROCR RELATED TO HCH LEVEt, W ASTE NUREG CR 49t$ LONG TERM PERFCCMANCE OF CONTAINER MA-RE POSITORiE 5 F eel Report . Phase 11 TE R)ALS FOH HGwLEWL W ASTE 153

154 Contractor Indox j BATTELLE MEMORIAL INSTITUTE, PACIFIC NORTHWEST NUREG'CR 4B08 V.NTEO USER S VANUAL i LABORATORIES NUREG/CR 4648 STEAM GENERATOR GROUP PROJECT Annuai 1 NUREG/CR 2850 V05 POPULATON DOSE COYM TVENTS DUE TO Report 1985 l

• RADCACTIVE RELEASES F ROM NUCLEAR POWER PLANT SITES NUREG/CR 4850 STE AM GENERATOR GROUP PROJECT L iu -

' iN tS83 Secordry Sde Ema%nat.on Finaf Repyt NUR E Q iCR-3231 PIPE TO-PIPE IMPACT PROGR AM NUREG'CR 4%6 FE AS B:UTY STUDY ON A DATA BASED SYSTEM 1 NUREG/CR 3620 SO2 INTRUDER DOSE PATHW AY ANALYSIS FOR FOR DECts>ONS REGARD NG OCCUPATCNAL R ADIATON PRO-THE ONSJTE DISPOSAL OF RADtOACTivE W ASTES The ONSITE/ TECTON VE ASURE S j M A111 Computer Program NUREGICR 4689 llRCALOY 4 01CATON AT 1300 TO 2400 DE-i NUREGICR.3950 V03 FUEL PERFOnVANCE ANNUAL REPORT FOR GREES C

 ,                                   1985 NU R E G / CH-4890 HEAT OF RE ACTON OF MOLTEN Z RCON UM

] NUREG<CR 3M8 STUDY OF OPERATING PROCEDURES IN NUCLE- WiTH UO2 AA POWER PLANTS Pract<es And Prot / ems NUR E G / CR.48 91 PROPERTIES OF REACTOR FUEL ROO VATER;ALS NUREG/CR-4300 V03 N2 ACOUSTC EM:SSON/ FLAW RELATON- AT HIGH TEVPE R ATURES Final Summag Report Seve e Core SH.D FOR INSERvlCE MONITOR NG OF NbCLEAR PRESSURE Damage P'ocerty Tests Procya n VESSELS Progress Rept.AproSeptember 1966 NUREG,CR 4938 OCCUPATONAL RADIATON EXPOSURES ASSOCi. NUREG/CR t300 V04 N1 ACOUST C EM SSON/ FLAW RELATON-

!                                                                                                         ATED WITH ALTERNATWE METHOOS OF LOW. LEVEL WASTE Dis-SH P FOR IN SERVICE VONITOR:NG OF NUCLEAR PHESSURE                   POSAL VESSELS Pr*>yess Report Octoter 1986 March 1987.

NUREG/CR-4310 V03 REV1E W OF LOHT W ATER RE ACTOR REGU- NUREG'CR 4958 tVPACT OF PROPOSED hNANCIAL ASSURANCE LATORY REQUiREVENTS Assessment Of SeWted Regulatory Re- REQU6AEVENTS ON NUCLE AR MATER'ALS LICENSE ES ouvements T at Vay Have Va/grtai importance To R sa Postaccdent NUR E G /OR-4959 PERFORVANCE TESTING OF EXTREMITY DOSb UETERS Sa npung System Turtane M ssaes Comtnstde Gas Controtchecoal NUR E G/ CR-4970 ST A:NL E SS STEEL ROUND Fate s ROB N TEST CentnfugaN Cast Sta uess Steet Screenq Phase NUR E G / CR-4418 OOSE CALCULATON FOR CONTAM.N ATON OF NUREG/CR-4976 PLANT RHt20 SPHERE PROCESSE S INFLUENCING { THE SKIN USING THE COVPUTER CODE VARSKIN R AD&ONUCLOE VOBiuT Y IN SO t NUREG/CR 4469 v04 NONDESTRUCTIVE EXAM NtTON (NDE) REll- NUREG/CR-5002 UETHODS FOR RECURRhG LOSS TESTS ) AB:UTY FOR INSE RVICE INSPECT ON OF UGHT W ATER NUR E G /CR S)C3 DE S)GN OF A M AT E R' AL CONTROL AND AC-j RE ACTORS Sernanrwal Report Octot>er 1985 Varch 1986 COUNT!NG SYSTEV TO PROTECT AGAINST CONCEALVENT OF NUAEG/CR 4469 VOS NONDESTRUCTIVE E N AM N ATON (NDE) Rett- DiVERSCN BY F ALS'FCATON AND cot.LUSiON l Ability FOR INSE RvlCF INSPECTON OF LIGHT WATER AE ACTORS Semannua! Report Apr4-Septemter 1986 NUAEG/CR 5006 PRA AFPLCATiON PROGRAM FOR INSPECTON ] AT OCONEE UNIT 3 i NUREG/CA-4469 V06 NONDESTRUCTIVE ExAY NATON (NDE) REU-AB:UTY FOR INSE RV CE INSPECTON OF UGHT W ATER BROOKHAVEN NATION AL LABORATORY REACTORS Semannuar Report Octotor 1986 Much 1967. NUREG/CA.4465 V02 THf IMP ACT OF FUEL CLADD;NG F AILURE NUR E G/ C A-0054 PROCEEDINGS OF THE WORKSHOP ON Soil-STRUCTURE tNTERACTON EVENTS ON OCCUDATCN AL RAOlATICN EXPOSURES AT NUCLE- NbREG/CP 0082 Voi PROCEEDINGS OF THE FOURTEEN a WATER AR POAER PLANTS Case Stay PAR Dunng An CMap RE ACTOR SAF ETY INFORMATON VE ETiNG NUREG/CR-4583 V02 DEVELOFVENT AND V ALC ATON OF A RE AL- NUREG/CP-0082 V02 PRXEED-NGS OF THE FOURTEENTH W ATER TIVE SArT-UT SYSTEM FOR THE INSPECTON OF UGHT W ATER RE ACTOR SAFETY INrORM ATCN ME ETiNG REACTOR COVPONENTS Annuaf Report.Octotier 1964 Septemter NUREG/CP 0092 V03 PROCEEO NGS OF THE FOURTEENTH W ATER 1995 RE ACTOR SAF ETY INFORV ATiON VE ET;NG i NUREG/CA-4583 V03 DEVELOPVENT AND V ALCATON OF A RE AL- NUREG/CP-0082 V04 PROCEED'NGS OF THE FOURTEENTH W ATER l T;VE SAFT-UT SY STEM FCA THE INSPECTION OF UGHT W ATER RE ACTOR SAFETY INF ORV ATON VEETiNG REACTOR COVDONENTS Annual ReportOctater 1985 Septemte, NUREGeCP-0082 VCS PROCEED:NGS OF THE FOURTEENTH W ATER i 1986 REACTOR SAFETY INFORMATON VEET NG NUREG/CR 4590 V0t A G;NG OF NUCLE AR STATION O*ESEL NUREG/CP-0082 VD6 PROCEED:NGS OF THE FOURTEENTH W ATER l GENER ATORS Evauston Of Oporatq And Esped Esoer.ence Phase RE ACTOR SAFETY INFORMATON VEETiN3 l Std, NURE G J CP-0084 PROCE EDWGS OF THE WOR

• SHOP ON A CON l NUREG/CR 4590 v02 AG.NG OF NUCLE AR STATON D:E SE L T AINVE NT PE RF ORV A NCE DE SGN OBJECTIVE V AY 12-CENE R ATORS Evavation of Operatq And E ;+r1 13.1966 HARPERS F ERRY WE ST V!RG'N.A Esperence Workshop NUREG/CR 233t V06 N2 SAFETY RESE ARCH PROGRAVS SPON-NUREG/CR 4613 EV ALUATON OF NUCLEAR POWER PLANT OPER. SORED BY OFFICE OF NUCLEAR REGULATORY ATING PROCEDURES CLASSlF CATONS AND RE SE ARCH (barterry Progress Report Apni-)vne 19%

INTE RF ACE S Protsems And Tec% quo For Morovement NUREG/CR 2331 Voe N3 SAFETY RESEARCH PROGA AMS SPON. NUREG/CR 4626 V02 IVPROViNG THE RE U AB:UT V OF OPE N- SORED BY OF F CE OF NUCLEAR RE GULATORY CYCLE W ATER SYSTEMS Apphcation Of Bic%ng Surrema<e And RESE ARCH Ovanerty Proyess Repo1. Juty Septemtier 19B6 Cont pi Technques To Seament Ard Gar +oson Fouhng At Nscle, NUREG/CR 2331 VD6 N4 SAFETY RESSARCH PROGRAMS SPON-Poner Piants SORED BY OF F IC E OF NVCLEAR RE GULATOR Y NUREG/cR 4640 HANDBCOA OF SCJTW ARE QU AUTY ASSURANCE RESE ARCH (Laderty Proyess Report Octoter Deemt+r 1966 TECHNIOUES APPLCABLE TO THE NUCLE AR INDUSTRY NURE G4 CR 2331 V07 N1 SA)ETY RE SE ARCH PROGRAVS SPON-NUREG/CR 4653 GASPAR il TECHNCAL REFERENCE AND USER SORED BY OF F CE OF NUCLEAR RE GULATOR Y GUOE RE SE ARCH Ouarierty Progress Aeport Ja%a'y Varch 1987 NUR E G / CR- 4695 M ATER:AL CONTROL AND ACCOUNTING (VC& A) NURE G/CR 2907 VOS R AD'OACT1.E VATERiALS RELE ASCO FROM LOSS DETECTON DUR.NG TRANSITON PERODS AND PROCE SS NUCLE AR PCr4ER PLANTS Annua? Report 1984 UPSET CONDiTONS NUREG'CR 3444 V04 THE iVPACT OF LWR DECONTAV NATONS NUREG/CR 4M8 E XPER WNT AL SUPPORT AND CEVELOFVENT OF ON SOLO.F CATON A ASTE D'SPOSAL AND ASSOCI ATED OCCU-5:NGLE ROO FUEL CODES PROGRAM Summary Repor1 P ATON AL E a POSUnE Annuat Repod. Frus Yew 1986 NUREG/CR 4 736 COVisuS TION A E ROSOL S FORMED DURING NUAE G/CR 340 V03 OCCUDATONAL DOSE REDUCTON AT NU-BURN NG OF R ADC ACTIVE LY CONT AV N ATED V ATE RIALS E x- CLE AR POWE R PLANTS Annota'ed Bet %7aphy Of Sekected Read PE R VE NT A L RE SUL T S rgs in Aaaate Protecten And ALARA NUREG/CR-4768 V01 VETHOOOLOGY AND APPLCATON OF SUR y NURE G'CR 4016 V02 APPUCATON OF St 'M M AUD A TEST OF AN ROGATE PLANT PRA AN ALYSiS TO THE F ANCHO SECO POAE R INTE R ACT r E COMPUT E R Ei ASE D VETHOO FOR Or> AN: LNG PLANT Tao 1 Anaps Of A NO-t Ar4 Oconee PR As E s PE R T ASSE SSVE NT Or HUVAN PE RF OnV ANCE AND NUREG/CR 4768 V02 UETHODOLCXiv AND APPL ICATON OF SUR- RE U A B UT Y voyer.e u Apg.rv>ces ROGATE PLANT PRA AN ALYS:S TO THE R ANCHO SECO POWER NUREGeCR 44c5 PRO 8 A Euu ST C R.St A SSE S SVE NT (PRA) IN PL ANT F nal Rev SGHTS NUREG/CR 4773 DE SK,N F E ATURES TO F AC:UT ATE INTERNATON NUREG/CR 44M V02 DATA B ASE Ch NUCLE aR PC A E R PLANT At SAF E GU ARDS AT M iE D-OLDE CONVE RSON F AC+UT!E S DOSE RE DUCTON AF SE ARCH PROJECIS NURE G tCR-4 779 NE A DATA F OR AE ROS%S GENE R ATE D BY RE. NUREG'CR 4M2 A RE CE A OF THE SE Af3 roc + ST ATON PROB ABI LEaMS OF PRESS,%2ED PC7ADE RS AND SOLUTONS IN ST ATC A:R USTic SAF E T v ASSE SSVE NT Cetarv-eat Fabre Uns And Ras oog< a' Sarce T&s NUREG<CR 4601 CUM ATOLOGY OF E x TRE ME W1NDS J. SOUTH NJE G/C R 4 715 AN A ~i NG A SSE SSVE NT OF RE LA Y S AND C'R E RN CAUFORN; A cuiT GRE D ERS AND S v STE M ATE R actions l l

Contractor Index 155 NUREG/CR4730. EVALUATON OF POTENTIAL MIXED WASTES CON. COMPUTATIONAL MECHANICS TAIN!NG LE AD, CHROMfUM.USED Oil.OR ORGANIC LiOU1DS NUREG/CR-4491: DEVELOPMENT OF MODELS FOR W ARM PRES-NURE G/CR-4 719 RAMONA 38 CALCULATONS FOR BROWNS TRESSING FERRY ATWS STUDY, NUREG/CR4810 EVALUATON OF DESEL UNAVAILABILITY AND CONFERENCE OF RADIATION CONTROL PROGRAW OtRECTORS,INC. ,

,                                                                                         RISM EFFECTIVE SURVEILLANCE TEST INTERVALS                                                                                                                                                             NUREG/CR4787: CONFERENCE OF RADATON CONTROL PRO-NUREG/CR4668 METALLURGCAL EVALUATION OF AN 18-INCH                                                                                                                                                                    GRAM DRECTORS' INFORMATON FOR LICENS!NG LOW LEVEL FEEDWATER LINE FAILURE AT THE SURRY UNIT 2 POWER STA-                                                                                                                                                      RADCACTIVE W ASTE INCINERATORS AND COMPACTORS.

TON NUREG/CR4683 REVIEW OF RESEARCH ON UNCERTAINTIES IN CORTEST COLUMSUS, INC. 4 ESTIMATES OF SOURCE TERMS FROM SEVERE ACCCENTS IN NUREG/CR4955. LONG TERM PERFORMANCE OF CONTAINER MA. L TERtALS FOR HGH-LEVEL WASTE-NU /CR4 NE ETATION OF SCASSAY MEASUREMENTS ]" NUREG/CR4897: LOW LEVEL WASTE SOURCE TERM DANE & ANATES, E EVALUAfiON Recew of PutAshed Modehng A/d Expenmental WortAnd Presentabon Of Lo* Level waste Source Term Modekng NUREG/CR4953 CORRELATON OF RADOOOINE RESUSPENS80N j W1TH TEMPERATURE AT TMb2. Framework And Prehmnary Modei Develor ment NUREG/CR4981: A SAFETY ASSESSMENT OF THE USE OF GRAPH- DAYlO W. TAYLOR NAVAL RESEARCH & DEVELOPMENT CENTER a ITE IN NUCLEAR REACTORS LCENSED BY THE U S NRC NUREG/CR-4962. SEVERE ACCIDENTS IN SPENT FUEL POOLS IN NUREG/CR4818 TRANSITON RANGE DROP TOWER J R CURVE I SUPPORT OF GENERC SAFETY ISSUE 8; TESTING OF A106 STEEL 4 NUREG/CR4985 INDAN POINT 2 REACTOR COOLANT PUMP SEAL OY N ATR E K, INC. EVALVATONS NUREG/CR 5037. FIRE ENytRONMENT DETERMtNATON IN THE LA- NUREG/CR 5011: APPLCATON OF THE ADAPTIVE PREDICTIVE SALLE NUCLEAR POWER PLANT CONTROL ROOM CONTROLLERS TO PLANT SAFETY SURVEILLANCE UTILI2iNG ON-LINE PLANT ANALY2ER BURNS & ROE CO. EG4G IDAHO, INC. (SUBS. OF EG&G, INC.)  ;

  !                                                                           NUREG/CR4781 DRFT: STUDY OF SEVERE ACCCENT MITCAllON I

SYSTEMS NUREG/CR 3956 tN SITU TESTING OF THE SHIPPiNGPORT ATOMIC POWER ST ATON ELECTRCAL CIRCUlTS CouFORNIA UNIV. OF, SERKELEY, CA NUREG/CR4165 SEVERE ACCOENT SEQUENCE ANALYSIS PRO-NUREG/CR-4918 V01. CONTROL OF WATER INFILTRATION INTO GRAM ANTCIPATED TRANSIENT WITHOUT SCRAM S:MULA. NEAR SURFACE Ltw DISPOSAL UNITS Annual ReportOctober 1985 TONS FOR BROWNS FERRY NUCLEAR PLANT UNfT 1.

                                                                                           . Septemter 1966                                                                                                                                                                                       NUAEG/CR4407 PIPE BREAK FREOVENCY ESTIMATION FOR NU-CLEAR POWER PLANTS LOS ANGELES, C A CALIFORNIA,                                                                                  UNIV                                                                                                                              NUREG/C ^           ^ "              'E BATTERIES IN SAFETY SYS-l                                                                               NUREG/CA-4941                                                                                        TH [ OF'E APPLCATON OF VALUE-tMPACT ANALYSIS                                                                          OF N      E         ER      TS TO US: A-45 Summary Report Of UCLA Stud.es On value-impact Anal-NUREG/CR4531: AN INVESTIGATON OF INTEGRAL FACILITY SCAL.

YS's in Rewon To USl A45 ING AND DATA RELATON METHOOS ONTEGRAL SYSTEM TEST l C ALIFORNIA, UNIV. OF, SAN OfEGO, CA PROGRAMJ NUREG/CR-4903 V03 SELECTON OF EARTHOUAkE RESISTANT NUREG/CR4616 ROOT CAUSE S OF COMPONENT F AIL URE S DES GN CRITERIA FOR NUCLEAR POWER PLANTS METHODOLO, PROGRAM Methods And Appi. cations . s 1 GY AND TECHNCAL CASES Dsiocaton Models Of Near Source NUREG/CR4617. ONSITE ASSESSMENTS OF THE EFFECTfvENESS Eartnquake Ground Motion A Review AND IMPACTS OF UPGRADED EMERGENCY OPERATING PROCE-DURES l CAUFORNIA, UNIV. OF, SANTA SARSARA, CA NUREG/CR-4672. ANALYSIS OF INSTRUMENT TUBE RUPTURES IN i NUREG/CR4978 THE COOLDOWN ASPECTS OF THE TMi-2 ACCI- WESTINGHOUSE 4-LOOP PRESSURl2ED WATER REACTORS  ; OENT. NUREG/CR-4701 V02 SAFETY ASSESSMENT OF ALTERNATIVES TO  ! i OF LOW-LEVEL RADIOACTIVE SHALLOW-LAND BURIAL

C ALSPAN CORP. ($USS, ARVIN INDUSTRIES /FR ANKUN RESE ARCH WASTE volume 2 Envvonmental Cordtens ANectng Pekapty Of En-CENTER) gineered Barners t

NUREG/CR4819 Vol. AGING AND SERVCE WEAR OF SOLENOO. NUREG/CR-4731 V01 RESOUAL LIFE ASSESSMENT OF MAJOR OPERATED VALVES USED IN SAFETY SYSTEMS OF NUCLEAR LIGHT W ATER RE ACTOR COMPONENTS OVERVIEW Volume 1. POWER PLANTSvolume 10perating Emperence And Fa4ure identh NUREG/CR4734 SEfSUC TESTING OF TYPCAL CONTA!NVENT cat.on PIPING PENETRATON SYSTEMS NUREG/CR 4952 EXPER MENTAL STUDY OF FILLET WELD UNDER- NUREG/CR 4741 FEEDW ATER T RANSiENT AND SMALL BRE AK l CUT EFFECTS ON WELDED TUBING STRUCTURES UNDER CEN- LOSS OF COOLANT ACCOENT ANALYSES FOR THE BELLEFONTE TRC AND ECCENTRC CYCLIC LOADINGS NUCLEAR PLANT. NUREG/CR-4747 V01. AN AGING FAILURE SURVEY OF L!GHT CAN AD A, GOYT. OF W ATER RE ACTOR SAFETY SYSTEMS AND COMPONENTS NUREG/CR4753 V02 CANADIAN SEISMC AGREEMENT Annual NUREG/CR4769 RISK EVALUATONS OF AGING PHENOMENAihe Report Linear Agng RetiaMty Model And its Ertensions NUREG/CR4/06 TRANSPORT BEHAVOR OF IOO1NE IN EFFLUENT CANADIAN C04HAERCIAL CORP. RADOACTIVITY MONITORING SVSTE MS NUREG/CR4753 V02 CANADtAN SEISMIC AGREEMENT Annual NUREG/CR-4793 RESULTS OF SEM: SCALE MOD 2C SMALL-BREAK Report LOSS-OFCOOLANT ACCOENT WITHOUT HPt (S NH) E *PERIMENT R E,S f CEN A ELECTRICITY GENERATING DOARD. BERKELEY NUCLE AR M: SCALE MOO 2C TEST S NH 3 , NUREG/CR 4752 COINCOENT STE AM GENERATOR TUBE RUPTURE NUREGICR4802 AN EVALUATION OF TR AC PF1tMOO1 COMPUTER i ANO STUCKOPEN SAFETY RELIEF VALVE CARRYOVER CODE PERFOAMANCE DURING POSTTEST S.MULATONS Or SE-TESTS UB-2 Steam Generator Trangent Response Test Program M! SCALE MOOL2C FEEDW ATER LINE BRE AA TRANSIE NTS COLORADO STATE UtelV PORT COLUNS, CO NUREG/CR4821 RE ACTOR COOLANT PUMP SHAFT SE AL ST AB:Li-NUREG/CR4651 DEVELOH8ENT OF RtPRAP DESIGN CRITERIA gy TY DUR;NG STATON BJCkOUT. RIPRAP TESTING IN FLUMES Phase i NUREG/CR 4824 EVALUATON OF INTEGRAL CONTINUtNG EWERt- ' MENTAL CAPABILITY (CEC) CONCEPT S FOR LIGHT W ATER RE AC. COesteERCE, DEPT. OF, NATOMAL DURE AU OF ST ANDARDS TOR RESE ARCH . PWR SCALING CONCE PTS NUREG/CR 4644 DRFT. INTEGPATED RE LtAB117 Y AND R:Sa ANALT- , NUREG/CR 4735 V01: EV ALUATON AND COMPILATION OF DOE w ASTE PACKAGE TEST DAT A B. annual Repor1 Decemter 1M5 $15 SYSTEM ORRASI USER S GUOE VERSON 10 (DRArT) Juh 1M6 NUREG/CR 4645 AN ANALYS S OF THE SE MLSCALE MOD-2C S NH 3 NUREGrCR4735 VC2 EVALUATON AND COMPtLATON OF DOE TEST US'NG THE TRAC PF1 COMPUTER PROGRAM WASTE PACKAGE TEST DAT A B. annual Report August 1986 Jeu- NUR E G 'CR46M AN ASSESSMENT OF HYDROGEN GENERATON acy 1967 FOR THE PBF SE%ERE FUEL DAM AGE SCOPING AND t 1 TESTS I

                                                                                                                                                                                                                                                  . _ . _   _ _ _ . . _        _ . . _ _ __ _ - __                 __ _ _                   _ _ __- _ _ _ _ _ _ _             _____J

l 156 Contractor index NUREG/CR-4876 SILVER 4NDfUM. CADMIUM CONTROL ROD BEHAV- NUREG/CR-5042- EVALUATION OF EXTERNAL HA2ARDS 10 NUCLE-  ! CR AND AEROSOL FORMATON IN SEVERE REACTOR ACCl- AR POWER PLANTS IN THE UNITED STATES. DENTS NUREG/CR-4925 FISSION PRODUCT BEHAVCR DURING THE PBF GA TECHNOLOGIES,1NCJGENERAL ATOM 6C CO. SEVERE FUEL DAMAGE TEST 11 I NUREG/CR4944 CONTAINMENT PENETRATION ELASTOMER SEAL NUREG/CR4846. HIGH-LEVEL WASTE PRECLOSURE SYSTEMS SAFETY ANALY$S Phase 2, F na: Report i LEAK RATE TESTS , NUREG/CR4945

SUMMARY

OF THE SEMiSCALE PROGRAM (1965* HANFORO ENGINEERING DEVELOPMENT LADORATORY  ! N /CR4946 davis-BESSE UNCERTArNTY STUOY. NUREGICR 3319 R01: LWR PRESSURE VESSEL SURVEILLANCE DO-NUREG/CR 4965 TRAC-PF1/ MOD 1 US/ JAPANESE PWR CONSERVA. SIMETRY IMPROVEMENT PROGRAM LWR Power Reactor Surved-TiVE LOCA PREDCTON ance Phyucs Dosenetry Data Base Compend um, 4 NUREGrCR 4966 V01: EVALUATON OF OPERAtlONAL SAFETY AT NUREG/CR 3320 V03 LWR PRESSURE VESSEL SURVEILLANCE 00- ! BABCOCK AND W1LCOX PLANT $ Volume 1. Results Overview S: METRY IMPROVEMENT PROGRAM PSF Physcs.Dosenetry Pro- 1 NUREG/CR4966 V02 EVALUATCN OF OPERATONAL SAFETY AT g,am . BABCOCK AND WILCOX PLANTS Volurne 2 ThermaM+/d rtuhc R*- NUREG/CR 3320 V04: LWR PRESSURE VESSEL SURVEILLANCE DO-su"8 NUREGICA-5010 RELAP5,MCO2 ASSESSMENT USING SEMiSCALE S! METRY IMPROVEMENT PROGRAM PSF Metahurgy Program EXPER MENTS S NH-1 AND S-LM-2 NUREG/CR-4307 V03: LWR PRESSURE VESSEL SURVEILLANCE 00-

                                                                                               $! METRY IMPROVEMENT PROGRAM 1986 Annual Report. October                         !

ELECTRtC POWER RESEARCH INSTITUTE 1985 September 1986 { NURE 12 RE RT O THE ACCCF.NT AT THE CHERN08YI, NV-gggggggggggg  ! NUREG 1250 RQ1 REPORT ON THE ACCCENT AT THE CHERNOBYL NUREG/CP 0086 VOI: PROCEEDINGS OF THE 19TH DOE /NRC NU.  ; NUCLE AR POA ER ST ATON CLEAR AIR CLEANtNG CONFERENCE hem in 6 Seattle. Wash ngton. August 18-21.1986 $ ENERGY TECHNOLOGY ENGINEERING CENTER NUREG/CP.0086 V02 PROCEEDINGS OF THE 19TH DOE /NAC NV-huREG/CR4859 SEISMC FRAGIUTY TEST OF A 64NCH DIAMETER CLEAR AIR CLEAN 1NG COVERENCE Held in PtPE SYSTEM- Seattle.W ashing +on.Avgust 16-21.1986. ENE RGY, DEPT. OF ILLINOIS, STATE OF

NUREG-1250 REPORT ON THE ACCCENT AT THE CHERNOBYL NV-NUREG/CR-2478 V03 A STUDY OF TRENCH COVERS TO M#M12E NU 12 R0

RE ON THE ACC1 DENT AT THE CHERNOBYL INFILTRATION At WASTE DISPOSAL SITES Foal Rept i

NUCLEAR POWER STATION

• INHALATION TDXICOLOGY RESEARCH INSTITUTE E NERG Y, INC- NUREG/CR-5025 EXPER MENTAL STUOtES OF THE EARLY EFFECTS o NUREG 1150 DRF V1 F C. REACTOR RISK REFERENCE OF INHALED BETA EMITTING RADONUCLCES FOR NUCLE AR AC.

DOCUME NT Man Recort Dra't For Comment CCENT A:SK ASSESSMENT Phase il Report a NUREGICR4826 VC2 SEISMC MARGIN FEVIEW OF THE MA:NE i

YANK EE ATOMC POWER STATON Volume 2 Systems AneWs INSTITUTE OF NUCLEAR POWER OPERATONS  !

J d NUREG/CR4834 V01: RECOVERf ACTONS IN PRA FOR THE RISK NUREG 1250 REPORT ON THE ACCCENT AT THE CHERNOBYL NU-METHODS INTEGRATION AND EVALUATION PROGRAM CLEAR POWER STATON + (RM;EP) Volume 1.Deve6opment Of The Data Based Method NUREG 1250 Rot. REPORT ON THE ACCIDENT AT THE CHERNOBYL i ENGINE E R$ INTE RN ATiON AL. INC, ^ " NURE G/CR4623 IN-SITU STRESS MEASUREMENTS IN THE KENTUCKY, UNIV OF, LEXINGTON, KY EARTH $ CRUST IN THE EASTERN UNITED STATES NUREG/CR4685 POST PLCCENE O!SPLACEMENT ON FAULTS

• ENVIRONMENTAL PROTECTION AGENCY WITHaN THE KENTUCKY RIVER FAULT SYSTEM OF EASTCEN.

NUREG-1250. REPORT ON THE ACCCENT AT THE CHERNO9YL NV. TRAL KENTUCKY. CLEAR POWER STATCN NUREG-1250 RO1 REPORT ON THE ACCCENT AT THE CHERNOGYL LAMONT-DOHERTY GEOLOGIC AL OSSERVATORY NUCLEAR POWER STATCN NUREG/CR4851: SEISMCITY 1886-09 IN THE SOUTHEASTERN UNITED STATES The AMershock Sequence Of The Charleston. South I E CE, INC-4 Cvoima Ea'thquase NUREGICR-4826 V03 SEISMtC MARGIN REVIEW OF THE MA:NE " YAN*.EE ATOMC POWER STATON Votene 3 Frag *ty AnaWs LAWRENCE BERKELEY LADORATORY EUROPE AN COMMUNITIES. COMMIS$40N OF NUREG/CR-4161 VC2 CRITICAL PAR 4 METERS FOR A H1GH-LEVEL NUREG/CR 4977 STAINLESS STEEL ROUND $T ROB N TEST Centntugalty Cast Stainness Steel Screerwng Phase REG / V LP AMETERS FOR A HIGH-LEVEL ME REPOMORt Yh 3 Se l FBR SAFETY LABOR ATORY,18ARAKI PREFECTURE. JAPAN NUREG/CR 4645 TOUGH USER'S GUCE. NUREG/CR 4765 M AS CROSS SECTON PREPROCESSOR USER'S NUREG/CP 008E

SUMMARY

REPORT OF THE SYMPOSivu ON SEIS-l FEDERAL EMERGENCY MANAGEMENT AGENCY MC AND GEOLOGC SITING CRITERLA FCA NUCLEAR PCWER i NUREG.0654 S01 A01: CRITERtA FOR PREPARATON AND EVAttia.- PLANTS j TON OF RADCtQGCAL EMERGENCY RESPONSF PLANS AND NUREG/CR-3966 METHODS FOR IMPACT ANALYS:S OF SHIPPING

,         PREPAREDNESS         IN    SUPPORT OF NUCLEAR POW ER                                 CONTAINERS 1          PLANTS Craena 3 cr Utaty oms:te Planning And Preparedness Draft                NUREG/CR-4161 V02 CRITICAL PARAMETERS FOR A HIGH-LEVEL j          Reeort                                                                               WASTE REPOSITORY volume 2 TuM

, NUREG-1250 REFORT ON THE ACCCENT AT THE CHERNOen NU- NUREG/CRat61 V03 CRITICAL PARAMETERS FOR A HIGH-LEVEL i CLE AR POM 9 STATON W ASTE REPOSITORY. Volume 3 San NUREG 125r Hot REPORT ON THE ACCtOENT AT THE CHERNOBYL NUREG/CR 4500 SsGPt A USER S MANUAL FOR FAST COMPUTA-NUCLE AR PO6ER STATON TON OF THE PROSABILISTC PERFORMANCE OF COMPLEX SYS-3 FR ANKLIN INSTITUTE DS NUREG/CR 4 715 AN AGING ASSESSMENT OF RELAYS AND CIR- NUREG/CR4626 YO1 SEISMC MARGtN REV1EW OF THE MAINE d Culf BREArERS AND SYSTEM INTERACTONS Y ANaEE ATOUC POWER STATON Volume 1 Surreary Report NUREG/CR4826 VO2 SErSMC MARGtN REVIEW OF THE MAfNE FUTURE RESOURCES ASSOCIATES,INC. Y ANm EE ATOMC POWER ST ATON Volume 2 Systems AnaWs - NUREG-1150 DRF v1 FC REACTOR R;SK REFE RE NCE NUREG/CR-4826 V03 SEISMC M ARGiN REvtEW CF THE M AINE I DOCUUENT Mam Report Dra't For Comment V ANKEE ATOMC POWER $TATON Volume 3 FragSty Anaiyss

 ;      NUREG /CR 4910 RELAY CHATT E R AND OPERATOR RESPONSE                            NUREG/CR4829 V01 SHIPPING CONT A.lNE R RESPONSE TO j         AFTER A LARGE E ARTHOUAKE Art improved PRA Met %sogy W'th                            StEVERE HiGNW AY AND RAILW AY ACCCENT CONDITCNS Mac Case Stu$es                                                                          Report I

i J l 1 i i L -

i r l Contractor index 157 NUREG/CR4829 V02. SHIPPING CONTAINER RESPONSE TO NUREG/CR-4894. A USER'S GUCE TO THE NRC'S PtPING FRAC. SEVERE HIGHWAY AND RAILWAY ACCCENT TURE MECHANCS DATA BASE (PiFRAC). CONDITCNS Appendaces NUREGICR-4561. DEVELOPMENT OF SITE SPECIFIC RESPONSE MATHTECH, INC, SPECTRA. NUREG/CR 5036 COST ANALYSl$ FOR IMPLEMENTATCN OF PRO-NUREG/CR4885 SEISMC HAZARD CHARACTERi2ATION OF THE POSED CHANGES IN VIT AL AREA REOUIREMENTS. EASTERN UNITED STATES Comparatere Evaluation Of The LLNL Ar4 E PRI Stu$es M6CHIGAN, UNIV. OF, ANN ARDOR, Mi NUREGICR4899. COMPONENT F R AGILITY RESEARCH NUREG/CR 3145 V05. GEOPHYSCAL INVESTCATCNS OF THE

                                                                                                          "           "**'             *D" # '        '9" l    NU E            4      V         COM           FRAGIUTY RESEARCH                               '

PROGRAM Phase i Demonstraton Tests Summary Reoort NUREG/CR4900 VC2 COMPONENT FRAGtUT'Y RESEARCH MITRE CORP. ' NUREG/CR-4783 ANALYSIS OF BALANCE OF-PLANT REGULATORY ?' NU E / R 50 AR M R U P ANALYSIS. ISSUES Feal Report NUREG/CR 5042. EVALUATCN OF EXTERNAL HAZARDS TO NUCLE. AR POWER PLANTS IN THE UNITED STATES. MOHR & ASSOCIATES i 2 LOS ALAMOS NATIONAL LADORATORY NUREG/CR-5059 VOID FRACTON MEASUREMENT LIQUID LEVtL NUREGICR46'5 V02: MODEUNG STUDY OF SOLUTE TRANSPORT DETECTON CONCEPT ASSESSMENT AD DEVELOPMENT. IN THE UNSATURATED 2ONE Workshop Proceedeos NEV AD A, UNIV. OF. RENO, NV NUREG/CR4737-. INTERPRETATIVE ANALYSIS OF DATA FOR , SOLUTE TRANSPORT IN THE UNSATURATED 2ONE NUREG/CR4852 THE MEERS FAULT. TECTONIC ACTIVITY IN NUREG/CR-4765. MXS CROSS-SECTON PREPROCESSOR USER'S SOUTHWESTERN OKLAHOMA. MANUAL. , NUREG/CR-4776 RESPONSE OF SEISMC CATEGORY l TANKS TO NEW YORK, STATE UNIV. OF, ALBANY, NY 4 E ARTHOUAKE EXCITATCN NUREG/CR 3232: DETAILED STUDES OF SELECTEDMELL EXPOSED ' NUREG/CR4814 SOURCES OF CORRELATON BETWEEN FRACTURE ZONES ;N THE ADRONDACK MOUNTAINS DOME.NEW EXPERTS Ermpincal Ressts From Two Entremet YORK. , NUREG/CR 4875 CHARACTERIZATON OF CRUSHED TUFF FOR THE ! EVALUATCN OF THE FATE OF TRACERS IN TRANSPORT *TUDES OAK RIDGE NATIONAL LADORATORY IN THE UNSATURATED 2ONE- NUREG/CR-2000 V05N12 LICENSEE EVENT REPORT (LER) NUREG/CR 4892 A STUDY Of THE EFFECTS OF PENETRATON COMPluTON For Month of Dece 1966 FRAMING ON STEEL CONTA:NMENT BUCKLING CAPACITY- NUREG/CR.2000 V06 N1: LCENSEE EVENT REPORT (LER) NUREGICR4 dO1: EFFEUTS FROM INFLUENT BOUNDARY CONDi' TONS ON TRACER MIGRATION ANO SPATIAL VARtABILITY FEA- COMPtLATON NUREG/CR 2000 ForV06Month of Janua/y 1987' EVENT N2: LICENSEE REPORT (LER) L TURES IN INTERMEDIATE-SCALE EXPERIMENTS COMPILATON For Month Of February 1967 NUREG/CR4904 INVESTIGATON OF STEEL CONTAINMENT BUCK- NUREG/CR-2000 V06 N3 LCEN$EE EVENT REPORT (LER) , COMPILATON For Month Of Much 1987. , NU 9 AN AS ENT OF LOSS-OF CONTAINMENT PO- NUREG/CR-2000 V06 N4: LICENSEE EN,ENT REPORT (LER) TENTIAL BECAUSE OF KNUCKLE BUCKLING FOR 4.1 STEEL CON- COMPILATON For Month Of Apnf 1987. NUREG/CR 2000 V06 N5: LICENSEE EVENT REPORT (LER) l NU G 493 ESPONSE OF CENTRfFUGAL AND AXI. VANE COMPILATION For Month Of May 1987. , BLOWERS TO LARGE PRESSURE TRANS!ENTS NUREG/CR-2000 V06 N6 LICENSED EVENT REPORT (LER) NUREG/CR4987. S,MULATED SEISMC TESTS ON 1/42 AND 1/14 COMPILATCN For Month Of June 1967. d SCALE CATEGORY I AUXILIARY BUILDING , NUREG/CR4986. A TRAC PFirMOD1 ANALYSIS OF THE GINNA NUREGICR 2000 V06 N7. LCENSEE EVENT REPORT (LE R) TUBE RUPTURE EVENT ON JANUARY 25.1982_ COMPtLATCN For Month Of M 1987. , 1

;                                                                                    NUREG,'A2000 V06 N8: LICENSEE EVENT REPORT (LER)

LOYELACE BIOMED & ENYlRONMENTAL RESEARCH INSTITVTE COMPILATON For Month Of August 1987. i NUREG/CR4986 RADtATON DOSL ESTIMATES AND HAZARD EVAL. NUREG/CR-2000 V06 N9 LCENSEE EVENT REPORT (LER) UATIONS FOR INHALED AIRBORNE RAD 40NUCliDES Fnat Report. COMPtLATON For Month Of September 1987. NUREGICR 2000 V06N10; LCENSE E EVENT REPORT (LE R) MARYLAND, UNIV. OF. COLLEGE PARK, MD COMPILATON For Month Of October 1987. NUREG/CR4768. AN ANALYTCAL AND EXPER. MENTAL INVESTIGA- NUREG/CR-2000 V06N11: LICENSEE EVENT REPORT (LER) TON OF NATURAL CIRCULATCN TRANSIENTS IN A MODEL PRES- COMPILATON For Month Of November 1967 SURt2ED WATER REACTOR NUREG OR4134 RO1: REPOSITORY ENVIRONMENTAL PARAM-NUREG/CR-4789 THE S4MULATCN OF THEPMOHYDRAvlC PHE- ETERS AND MODELS RELEVANT TO ASSESSING THE PERFORM-NOMENA IN A PRES $URl2ED W ATER REACTOR PR: MARY LOOP ANCE OF HIGH-LEVEL WASTE PACKAGES (BASALT TUFF AND  ! NUREG/CR4643 V01- UNrVERSITY OF M.AYLAND AT COLLEGE SALT) ' PARK (UMCP) 2X4 LOOP TEST F ACILITY.Antoal Repor1 For 1965 NUREG/CR42iG V03 N2 HEAVY SECTON STEEL TECMNOLOGY ' NUREG/CR4918 V01: CONTROL OF WATER INFILTRATCN LNTO pRocqAy S,m, annual Progress Repor1 Fcr Aprd-September 1986. NEAR SURF ACE LLW DISPOSAL UNITS Annual ReportOcteter 1965 NUREGICR4219 YO4 N1 HEAVY SECTON STEEL TECHNOLOGY

       . September 1966                                                                 PROGRAM Serrmannual Progress Report For October 1966 . Mrch t:ASSACHUSETTS INSTITUTE OF TECHNOLOGY CAM 8 MIDGE, MA                             N     G/CR4577. AUTOMATED LONG TERM SURVEILLANCE OF A NUREG/CR 4922 STE AM SEPARATOR MODELING FOR VARCUS                                 CCMMERCIAL NUCLEAR POWER PLANT.                                          l NUREGICR4610 EFFECTS OF LATERAL SEPARATCN OF OXCtC NUR /CR                        T    AN MITGATON OF EROSIVE COR-                    AND METALLC CORE DEBRt$ ON THE BWR MK t CONTAINMENT ROSIVE WE AR IN SECONDARY PIPING SYSTEMS OF NUCLEAR                              DRYWELL FLOOR.

POWER PLANTS NUREGICR 4651 DEVELOPMENT OF RIPRAP DE$1GN CRITERLA BY MATERIALS ENGINEERtNG ASSOCIATES,INC. A PRAP TESTING IN FLUMES Phase L NUREG/CR-4674 V03. PRECURSORS TO POTENTlAL SEVERE CORE NUREG/CR-3229 VOS STRUCTURAL INTEGRITY OF W ATER REAC- DAMAGE ACCCENTS 1964.A STATUS REPORT Man Report And Ap-TOR PRES $URE BOUNDARY COMPONENTS Annual Regeri Fo, perdues A And B 99 4 NUREGICR-4491. DEVELOPMENT OF MODELS FOR WARM PRES- NUREG/CR4674 V04 PRECURSORS TO POTENTLAL SEVERE CORE DAMAGE ACCCENTS 1984,A STATUS REPORT Appercies C,0 And TRrSS:No NUREGICR-4724 F AtiGUE CRACK GROWTH RATES IN PRES $URE E YESSEL AND PtPtNG STEELS IN LWR ENVIRONMENTS Feal Report NUREG/CR4689 THERMAL-HYDRAULC AND CHARACTERJSTC NUME G/CR4841 FRACTUAE EVALVATON OF SURF ACE CRACKS MODELS FOR PACKED DEBRIS BEDS NUREG/CR4692 OPERATING E*PERIENCE REVIEW OF FAILURES I EMBEDOED IN RE ACTOR VESSEL CLADDINGurwr saated Bend Speernen Ressts OF POWER OPERATED RELIEF VALVES AND BLOCK VALVES IN NURE GrCR-4863 SURFACE SPECTROSCOPY OF PRESSURE NUCLEAR ECWER PLANTS ' VESSEL STEEL FATIGUE FRACTURE SURF ACE FILMS FORVED IN NUREG/CR-4706 V01 N1 PROGRESS IN EYALUATON OF RADCNV-PAR ENV)RONMENTS CLCf GEOCHEMCAL INFORMATON DEVELOPED BY DOE M6GH- i f l

158 Contract:r Index LEVEL NUCLEAR W ASTE R E POSITOR Y SITE PROSIG. INC. PRO.'E CTS Semia6rval Repori For Octoter 1985. March 1146 NUREGICA 4491 DEVELOPVENT OF MODELS FOR WARY PRES-NUREG/CR 4711. LOW UPPE R- SH E LF TOUGHNESS HGH-TRANSi- TRESSaNG TON TEVPE RATURE TEST INSERT IN HSST PTSE 2 VESSEL AND WOE PLATE TEST SPEC. MENS Final Report PURDUE UNty., WEST LAFAYETTE,IN NUHEG/CR 4712. REGULATORY ANALYSIS OF REGULATORY GUCE NUREGrCR5034 AN UPDATE OF ViDCONiiNENT TECTONISM 105 (REVISON 3. DRAFT 2) - IN SERVICE INSPECTON OF UN-GROUTED TENDONS IN PRESTRESSED CONCRETE CONT A:N- REMOTE TECHNOLOGY CORP. MENTS NUREG/CR-4815 DEMONSTRATON TESTNG OF A SURVEILLANCE NUREG/CR-4722 SOURCE TERM EST1MATON US;NG MENU-TACT ROBOT AT 840ANS F ERRY NUCLE AR PLANT Ana'ys,s Of Costs NUREG/CR 4758 A RE T R AN MODE L OF THE CALVERT CLIFFS 1 And Benehts PRESSUR! ZED WATER RE ACTOR FOR ASSESS:NG THE SAFETY IMPLICATONS OF CONTROL SYSTEMS ROCHESTER. UNIV. OF, ROCHESTE R. NY NUREG/CR-4760. TEST OF 64N T HICK PRESSURE VESSELS Seres NUREG /CR 4 351 NEPHROTOMCITY OF URANYL FLUORCE AND RE-3 Intermeoiate Test Vessef V-6A Teanng Behanor Of Low Upper Sherf VERSrB'LITY OF RENAL LNJURY rN THE RAT UnteM, NURE G /CR-4 798 IRON OXCE AEROSOL ExrERMENTS IN STEAM- RONDOUT ASSOCIATES, INC. A!R ATMOSPHERES NSPP TESTS 501505 AND $11. DATA RECORD NUREGICR-4822 BROAD BAND SEISMC C ATA ANALYS:S Septemter REPORT. 1984 Septemter 1966 NUREG/CR-4917 OD:NE PARTITON COEFFICIENT MEASUREVENTS AT S MULATED PWR STEAM GENERATOR CONDITONSinterm SANDIA NATIONAL LABORATORIES Data Report NUREG/CR 2452 R.56 METHODOLOGY FOR GEOLOGO D SPOSAL NUREG/CR 4819 V01 AGtNG AND SERVCE WE AR OF SOLENOID- OF RADOACTIVE WASTE Fina1 Report OPERATED VALVES USED IN SAFETY SYSTEMS OF NUCLEAR NUREG/CR 3024 SUSTAINED CONCRETE ATTACK 8Y LOW-POWER PLANTS Vo6mu 1 Oceraung Eugenence And Fahre identh TEVPERATURE.FR AGVENTED CORF DEBR!S c4' ion. NUREG/CR 3412 V02 CONT A1NVE NT INTEGRITY NUREG/CR 4660 FLA A DENSITY EXAM:NATONS OF A CLAD BOfL- PROGR AM Pryess Rcport April 19Js3 Decemter 1964 ING WATER REACTOR PRESSURE VESSEL SEGVENT NUR E G, CR-3468 HrCROGEN air STEAM FLAVVAB'LITY LIMITS NUREG/CR 4B45 THE SOLUBILITY OF ELECTRODEPOSITED TCCV) AND COVBUSTCN CHARACTER.STICS IN THE FITS VESSEL OxlDES NUREG /CR4495 CALCULATON OF F ARURE iVPORTANCE MEAS-NUAEG/CR-4836 ANALYS:S OF THE NESD:P2 AND NESO(P3 R ADIAL URES FOR BASC EVENTS AND PLANT SYSTEMS iN NUCLEAR SH: ELD AND CAVITY ExPER4VE NTS POAER PL ANTS NUREG/CR-4$30 CRACOARREST BEHAVOR IN SEN WOE PLATES NUREG/CR-3925 PEV S AiFT tt SE L F.TE ACH1NG OF OUENCHED AND TEVPERED A $33 GRADE B STEEL TESTED CURRICULUM Nstratwe Protaems For The SaMa Wasie tsotaton UtCER NONtSOTHE AVAL CONDITONS Flow And Transwt Vy1et For Fractured UMa NUREG/CR 4943 FREPARATON OF DESIGN SPECIFICATONS AND NUqEG/CR-40M SEISVC FRAG >LITY TESTS OF NEW AND ACCEL-DESGN FiEPORTS FOR PUMPS. VALVES pip:NG AND P1 PING SUP. ERATED-AGED CLASS 1E GATTER f CE LL S PCRT S USED iN SAFETY RELATED PORTONS OF NUCLEAR NUREG/CR-4216 E nFER VE NTAL RESUU S FOR A 18 SCALE STEEL POWER PLANTS MODEL NJCLE AR POAE R PLANT CONTA:NVENT PRESSURf2ED NUE E G / CR-4990 HE AVY-SECT 0N STEEL TECHNOLOG Y TO FAftuRE PROGRAM Fue Year Pian FY 1M1990 NURE G, CR-4 301 STATUS AEPORT ON EOUiPVENT OUAttFICATON NUREG/CR 5017 UMESTONE CONCRETE AEROSOL E2PER#ENTS ISSUES RESE ARCH AND RE SOLUTON

N STE AM air ATMDSPHERES NSPP Tests 521522 AN $31. Data NURE G'CR 4320 THE RELATONSH.P AND INFLUENCES OF FUEL Record Report AND COOLANT SYSTEM PROCESSES DUR:NG LAR SEVERE ACCl-OKLAHOM A, UNIV. OF, NORM AN. OK DENTS NUREG/CR 4449 SHJTDOAN DECAY HEAT REMOS AL ANALYSIS OF N') REG /CR 4937 INVESTIGATON OF THE MEERS FAULT IN SOUTH-WE STERN Okl AMOM A A GENER AL ELECTRC BARTVARK iCase Star NLAEG/CR 445e SHUTDOAN DECAY HE AT REMOVAL ANALYSIS Or ONT ARIO HYDRO A AESilNGHOU5E 2 LOOP FRESSUAtlED A ATER REACTOR Case 0

ERA D GE C E BATT RY CEL $ NU C 44527 V01 AN E nPERNENTAL IN/ESTOATON OF IN. TERNALL Y iGN:T,E D F AE S iN NUCLE AA POWER PLANT CONTRCL P Al .AM E T E R, INC. CAB NE TS Pa1 t Catanet E Mecs Tests NUREGrCR 4524 CLOSEOUT OF !E BULLETIN BO 24 PRE,ENTON NUREG/CR-4530 VG2 U S /F RE NCH JO NT RESE ARCH PROGRAM OF DAMAGE DUE TD A ATER LE AKAGE iNSOE CONTA:NVENT RE G AADiNG THE. BEHAVOR OF POO MER BASE M ATE RIALS SUB-(OCTOEE R I ? 19?O !NDIAN PO:NT 2 Evf NTI ;ECTED TD BE TA R ADi ATON vove 2 Phase 2a Saeen.rg Tests NURE G/CR-4663 CLOSEOUT OF tE BULLETIN 83 01 F AtLURE OF AE. NUREG Ci4 4534 ANALYS S OF D$FLSON FLAME TESTS 1 ACTOR TR P Br& > ERS (AEST:NGHOUSE D8 50) TO OPEN ON NUALG'CR 4W V01 ANAOSiS OF CORE DAMAGE FREOUENCY l AUTOM ATC TR P SIGNAL FROM INTE RN AL EiENTS METHOCOLOGY GUCE UNE S NUREG/CR 4M4 CLOSEOUT OF IE BULLE TIN B3 04 F AtLUAE OF NUREG'CR 4%0 V03 ANALYS S CF CORE DAMAGE FREQUENCY THE UNDERVOL TAGE TR P FUNCTION OF RE ACTOR TR+ BRE A'o F RW ATERNAL EVENTS SURRY UNIT 1 ERS NV A E G < C R 4 %Q V34 AN ALY S-S OF CORE DAVAGE FREOUENCY NURE G<CR 4690 YOI N1 GENERC CC'VVUNCAT ONS FROV tNTE RN AL EVENTS PE ACH BOTTOM UN:7 2 u NURE G'CR 4'50 V05 A N AL Y 5:5 CF CORE DAVAGE FREQUENCY 4NDE A l stNs Of Ccnm evcat.ons 0 971 19A6) NUREG'OR4t/3 V02 GE NE RC COVVJNCATONS INDE x User s F ROV INTERN AL EVE NTS SEQUOY AH UN:T 1 M ana NUAEG:CR 4%0 vo@T1 AN AUS<S OF CORE DAVAGE FREQUEN-CY TROM ATE RN A EiE NT5 GA AND GULF UN T 1 M*n Report PENNSYLVANI A STATE UNIV., UNIVERSITY PARK, PA NJAEGeCR 4%O vW12 AN ALYStS OF CORE DAM AGE FREQUEN-NURE G/CR 47M EV ALUATON OF PROTECTIVE ACTON R:S* S Cr rROV INTERN AL E S E NTS GR AND GULF UN,71 Appenoges NAEG/CR 4%1 VI DRF E V A U A T ON OF SENERE ACCOE NT PE NTE K,1NC Ris* S AND THE POT E N DA L FOR kS* RE DUCTON SURR Y NURE G rCR *ns DE iE LO& VE NT OF A TESTWG AND AN ALvS S PO A E R ST AT ON UN T 1 D+1 Fcv Coment VETHODOLOGY TO DETERV NE THE FUNCTONAL CONDiTON OF NURE G'CR 4E51 v2 DR5 E v' AL u A T ON OF EEVERE ACCOE NT SDL E NOO OPE A 4 TE D V ALVE S RtS* S AND THE POTE NTi AL F OR R;5* RE DUCTON SEOUOf AH PO A E R ST AT ON LN T 1 Dra't F or Comment PfCK ARD LO*E & GARRICK INC. NUREG CH 4tti %3 PT1 E V ALUAT ON OF SE V E RE ACCCENT R:S*S NUAEG/CR 4X2 VETHODS FOR THE EL C#T ATON AND USE OF AND THE POT E N TI AL FOR R;SF' RE DUCT ON PE ACH E sFERT CP NON lN R*S* ASSESSME NT Phase i A Cot (aiEva%a BDTTDV LN 7 2 Von Rr pv DWt F y Wet ton And D*Ns For Future Researcn NURE G'CR 4tti v3 PT2 E v A< U ATiON OF SE vf RE ACUCE NT R S* 5 i AND THE FOT E N h A L FOR RS* REDUCTON FE ACH PROF E SSiON AL AN AL Y SIS, INC. 60 TTOU UN!T 2 Apves Le F or Comet NUREG CR 4H2 OPE R AT AG E RPE R.E NCE REOE A Or F A1URE S NJREG LR 4* st. 4 CM f u A: u AT ON OF SEVERE ACCCE NT OF POW E R OPER AT E D REl :E F V Al.vE S ANO BLON V ALN E S IN R'S* S AND THE PO' E N D AL FOR k S* RE DUCTON GRAND NUCLE AR FOAE R PLANTS GULF UN'T 1 Dran Fcw Cawt

C:ntract:r hid:x 159 NUREG/CR 4645 TOUGH USER S GU'DE NUREG'CR-5028 ON THE MELTING AND REFREEltNG OF POROUS NUREG/CR-4679 OUANTITATivE DAT A ON THE F CE BEHAVCR OF ME DI A COVBUSTiBL E M ATERi ALS FOUND IN NUCLEAR POWER PLANTS A L%rature Recew SC& A INC. NUREGrCR 4661 ENCLOSURE ENV'RONVENT CHARACTEJZATON NUREGICR-5036 COST ANALYS!$ FOR sVPLE MENT ATCN OF PRO-TESTING FOR THE BASE LINE VAUDATON OF COVPUTER F RE POSED CHANGES tN MTAL AREA REQUiRFVENTS SVULATION CODES NVAEG/CR-4 700 V1 DRF CONT A AVE NT En ENT ANALYSrS FOR SCIENCE & ENGINEERING ASSOCIATES,INC. POSTULATED SEVERE ACCCENTS SURRY POWER STATON. UNIT NypEG/CR S335 DAT A BASE OF SYSTEM AVERAGE DOSE RATES 1 Dra't For Comment AT NUCLEAR POWER PLANTS Final Re4cr1 NUREGICR-4700 V2 DAF CONTAiNVENT EVENT ANALYSIS FOR NUREG/CR-5036 COST ANALYSIS FOR iMPLEMENTATCN OF PRO-POSTULATED SEVERE ACCCE N T S SEQUOYAH FCAER POSED CHANGES IN VITAL ARE A REQUIREVE NTS STATCN UNIT 1 Drs't Report For Commeat NUREG/CR4 700 V4 DAF CON T A;NVE NT EVENT ANALYSIS FOR SCIENCE APPLICATIONS INTERNATIONAL CORP,(FORMERLY POSTULATED SEVERE ACCCE NTS GRAND GULF NUCLEAR SCIENCE APPLIC ATIONS, NURE C 710 S A NT ENG,E4EER NUREG/CR-4550 V01 AdALYS:S OF CORE DAMAGE FREQUENCY FROM INTEPNAL EVENTS VETHODOLOGY GUCEUNES v A.PRESSUR: HEAT REMOVAL ANALYS:S OF A COMBUSTON ZED W ATER NUREG/CA-4530 Y06PT1: AN ALYS'S OF CORE DAVAGE FREOUEN-Cf FROM INTEPNAL EVENTS GRAND GULF, UNIT 1 Man Report NU EG/CR 4 1 DOWN DEC AY HEAT REMOVAL ANALYSJS OF NUREG/CR-4550 V06PT2 ANALYST $ OF CORE DAVAGE FREQUEN. A BABCOCK AND WILCOx PRESSUR 2ED W ATER REACTOR Case CY FROM INTERNAL EVENTS GRAND GULF UNIT 1 Accen:1.ces g, NUREG /CR-4616 ROOT CAUSES OF COMFONENT F A: LURE S NUR d/CR 4719 COOLABtUT Y OF STRAf tF:ED UO2 DEBRIS IN SOOtUV wtTH DOWNW ARD HE AT REMOVAL The Dt3 Espenment PROGRAM Methods And A@i<atcns NUREGICR 4727 SMSS SUSTA NED HE ATED VETALL'C VELT/ CON, NUREG/CR 4797' PROGRESS REVIEWS OF SLA S AFETY PAR AVE-CAETE INTERACTCNS WlTH OVE RLY:NG WATE A POOLS TER DISPLAY SYSTEMS NUREG/CR 4742 VELPROG. PAR / MODI ANALYSIS OF A TULB' AC-CtDENT SEQUENCE sri lNTERN ATION AL NUREG/CH-4762 SHUTDOWN DECAY HE AT REMOV AL ANALYS'S OF NUREG/CR 4950 YO1- THE SHOREUNE E NVERONVE NT AT VOS-A WESTINGHOU'#E 3-LOOP PAESSUR' LED W ATER REACTOR Case PHERIC DISPERSON EXPERNENT (SE ADEX) Espenment Dery Study ton NUREu/CR.4766 USER S VANUAL FOR THE NEFTRAN CCVPUTER NUR E G/ CR-d ' . V02 THE SHORELINE ENviRONVENT AT V OS-CODE PMERC DiSPERSON E *PER VENT (SEADExj veieoro+c9 cal And NUREGICA-4767 SHUTDOWN DECAY HE/.T REVOVAL ANALYS>S OF Gas Traar Data A GENER AL ELECTRIC B AR4/V AAK l Case SiqATCN PROGRAM NUR E G / CR-4 7 72 ACCCE NT SEQUENCE EV ALU STRUCTUAAL & EARTHOUAKE ENGINEERING CONSULTANTS HUMAN REUABtUTY ANALYS>S PROCEDURE NUREG/CR 4903 V01- SELECTCN OF EARTHOU A* E RES'ST ANT NUREGICR 4761 DAFT STUDY OF SEVE RE ACCCENT V;TGATCN DESGN CRITER'A FOR NUCLEAR POWER PLANTS VETHODOLO-GY A D TECHNCAL CAEES Drect Empocal Scaw Cf Respor'se N RE CR 4803 THE POSS B:UTY OF LOCAL DE T ON A T CNS b '# " * ' ' DURiNG OEGRADED-CORE ACCCENTS IN THE BE'.LEFONTE NU- ygp(j[R 2 SE NO fT UA QTANT DESGN CRtTER:A FOR NUCLE AR POWER PLANTS VETHODOLO-NU C 46 5 V E ACTOR SAFETY RESE ARCH SEU4NNUAL GY AND TECHNtCAL CASES Methods f or Int %xton Of Gew9 cal REPORT JanuaTJune 196f Data into Charactenzaten Of Artwe Fasts And Se smoty And NUREG/CR-4&,?S A PREL V NARY EN ALUATON OF THE ECONCUC Risk FOA CLE ANUP OF NUCLE AR VATER:AL LICENSE E CONTAM, NUREG/CR-4903 V03 SELECTCN OF E ART HOU Ak E RE S:ST ANT N ATCN INCCENTS DESGN CRITERIA FOR NUCLEAR POWER PLANTS VETHOCCLO-NURE G / CR-4630 VELCOR VAUDATION AND VER#CATON 1966 GY AND TECHN? CAL CASES Dstocato MWs O' Ne ar Source PAPERS Eartha,ame Ground Motori A Rewen NUREGICA 4834 Voi RECOVERY ACTONS IN PRA FOR THE RISK METHODS ATE GR ATON AND E V AL UAT ON PROGRAV U S. NAVAL AC ADEMY, ANNAPOUS, MD (RV EPJ Volume 1 Development Of The Da a Based Met *oj NUR E G' CR-4 818 TRANSITION RANGE DROP TOAER J R CURVE NUREG/CR 4846 HiGH LEVEL W AS T E PRECLOSURE SiSTEMS TEST:NG OF A106 STEEL SAFE TY AN ALYS'S Fnase 2 Fraf Repyt NUREGICR 4835 DE VE LOPVE NI AND A PPLCATON OF A COMPUT- UNITED ENGINEERS & CONSTRUCTORS,INC.(SUBS OF RAYTHEON ER MODEL FOR LARGE SCALE FLAVE ACCELERATCN EnPERh CO) MENTS NUREG/CR 4921 ENG!NEER:NG AND OU ALITY ASSURANCE COST NUREG/CR-4870 AN EVALUATCN OF THE EFFECTS OF DES:GN F ACTORS ASSOCIATE D MTH NUCLE AR PLANT V 3D FCATCN j DET AILS ON THE CAPACITY OF LAR STEEL CONT A'NVE NT BU!L DWGS VANDERBILT UNIV NASHVILLE, TN 1 EXPER MENT NUREG'CR-4936 AN INTEGRATED GEOLOGCAL GEOFHf SCAL AND NUREG/CR NUR 4P7* E G /CR-4 Bs RE SULTS

                   . POSTCON  A POST FROM PROCE THE CCH'SSOR AND UN'TGEOCHEWC                                               CON ~ AL INVESTGATON OF THE MAJOR FRACTURES ON VERSON PAOGR AM FOR THE CONT AW COMPUTE R CODE                                                                     THE E AST SCE OF THE NEW MADRO E ARTHOUAAE 2CNE NUREG/CR 4696 CONTA.NVE NT L OADS DUE TO D, RECT CONT AiN-VENT HEAT;NG AND ASSOCIATED HYDPOGE N BEHA vCR Aratys.s                                                      VIRGINIA POLYMCHNIC INSTITUTE & STATE UNIV, BLACKSBURG, AM Coculatons Mn the CONTA!N Code                                                                                  ya NURE G/CR 4905 DE TONa&LITY OF H2 A:R Of tUENT U ETURE S                                                          NAf 0',CR-4973        INT R APLAf f SEiSUCITY OUT SIDE OF THE NUREG/CR-4M9 VELPROG PAR /UDEC A VECHANtSTC CODE FOR                                                                          bI# Ib AN ALYS!S OF RE ACTOR CORE VE LT PROGRE SSCN AND \ E SSE'.                                                                 A4         INT R APLAT E SE :SM OT Y IN THE E ASTEPN ATT ACK UNDER SEVERE ACCCENT COND# TONS UN TED STATES NUREG/CR 4913 ROUND-ROB N PRETEST ANALYbES OF A 16                                                                NUR E G, CR-4 975 A A E v'E W OF THE RE SOL vNG PO A E R OF RE-SCALE REINFORCED CONCRE TE CONT A.NVENT MODEL SUBJECT FLECTCN SEiSMOLOGV UETHODS TO DETECT SUBSURFACE TO STATC INTE RN AL PRESSUR 2ATCN NUR E G IC A-4 )41 THE APPUCATCN Of V AL UE "VP ACT AN AtySr5                                                        F AULTS AND OR CHANGES iN LAYE R THC> NE SS W ASTE M AN AGEMENT GROUP,1NC.

ss n A st o S 4 NUEEG CA 4 78 EV ALU ATCN OF UNUERT AWTrE S IN >RR AD' ATE D NURE G rCR-4942 E OutPVE NT OPERAB'uTY DUR WG ST ATCN BLACKOUT E VENTS HARDA ARS CHAR ACTER 2ATCN NURE GrCR 4944 CONT A% VENT PE NE TR ATCN Es ASTOVER SE AL LEA > RATE TESTS WESTINGHOUSE ELECTRC CORP-NukEG/CR4x3 BORON CARB CE STE AV RE ACTCNS WiTH NUREG'CR 4752 COtNCCENT STE AV GENERATCO TU6E kJPTLRE CE SIUM HY DROu CE AND MTH CE S:LV iCODE AT 127cw IN AN AND STI.Cn OPEN SAFETY REUEF V A:,s E CARAVOVER INCONE L 600 SySTE U TE STS UB 2 Svam Generator Trawnt Revo%e Test Nyam NURE G/CR 449 AW MVETR C AN ALYS'S OF 1 F SC A E Rf iN- NURE G CH 4662 V01 COGNiTWE ENwAONVE NT S UMT0N AN FORCED CONCRE TE CONT A:NVf NT BuhD NG UsM A E$5TR:B ARTJ O AL WTE LUGE NCE SYSTE V F OR Huv AN Pt M OW ANCE UTED CR ACm % VODE L F OR THE CONT RETE ASSE SSVENT VcNme 1 Summaq AN Ovewn

160 Contractor Index { NUAEG/CA 4M2 V02 COGNITIVE ENVIRONVENT S MULATON AN WESTON GEOPHYS6C AL CORP, ARTiFCIAL INTELLIGENCE SYSTEM FOR HUMAN PERFORMANCE NURE G/CR4957 SURiEY OF GEOPHfSCAL TECW.OJES FOR ASSESSVENT. Volume 2 Mo#W Hurran intenton Formulaton. SITE CHARACTER 62ATON IN B ASALT. SALT AND it,,fF NUREG/CR-4M2 V03 CCGNITIVE ENVtRONVENT S MULATON AN WYLE LABORATORIES ARTIFCIAL INTELLGENCE SYSTEM FOR HUMAN PERFORV ANCE NURE G/ CR-4 900 V01. ASSESSMENT Volume 3 Copytve Rehatuh*y AnaWs Techn9A COMPONENT F R AG!LITY R E SE ARCH PROGRAM Phase i Dewstraton Tests Sumre4*y Repryt NUR E G /CR-47)0 VC2 CCVPONE N T F RAwLIT Y RESEARCH PROGR AM Phase 1 Devatrat.on Tests APGend<es l

i  : i  !'

!                                              international Organization Index                                                                                              ;

This index lists, in alphabetical order, the countries and performing organizations that pre- ' pared the NUREG/lA reports listed in this compilation. Listed below each country and per. 3 forming organization are the NUREG/lA numbers and titles of their reports. If further infor-j mation is needed, refer to the main citation by the NUREG/lA number. i t i {- 4 ! ' M r % vo.Maor l Nerona.oco4 TstauAt u xiss tests is A stu ANNuta  ;

oo*NeoWER W1TH INTERACTING flows FROM COLO LEGS  ;

i E j ' q i b i t P 1 i P ., j I 9.-{ L 161 f

Licensed Facility Index This index lists the facilities that were the subject of NRC staff or contractor reports. The facility names are arranged in alphabetical order. They are preceded by their Docket number and followed by the report number. If further information is needed, refer to tho main citation by the NUREG number, uc. ~ A o,se Nxer P n W i S m a Un or $25 cm & w ., r werP w S m W t un a en P;e# CC I 9veMee ia@y AJ'@ O 424 AW A n:f4 4xer P 41 W i Se&N Nf E 3 M P SM 5'N U464 IP/ 5'am W i CO*fveen? Elv CC NAU C4'$ 5^4 P;ey 2 5'N R4!! Bry Sam W 2 Qrwye4a ft Eny Oc VME3 M'6 SM

 % 424     Av A i>pe %xer Pat W 1 3ecr)4 N J E 3123'                 SIN K 4']  Cl55AA 5($'em BC Ccv%sv E* years *. AE 3 N52 50 pg Co                                                   D 3' 7     Crie" Ca*s Nxer Pc.e Pn W t                                NJE3 CA 4'5e D424      Av 6 .:f4 Ver Pvt W t C+y pa Y#E S '24'                                Ba* roe Gas & Eecw F;*F C4                                                 D 441      C#" E;** 5'a* W I F*T'S PO**' CC Y3ISU53 b 4
 % -424    AW A Of4 4xer Pft W ' 367;a VME 3 ?2's                    D4f '      Cro Pw 5aw W t aros >>< Co VJE 31235 p3, y                                                   D 344      04es be%e NsCes P?*F Saw W i                               %f E 3 C A 4i46 R424      aw A 6:ye Nxer Pe W t C+:9a        NSD '2't EEG                        '>et Ehy Co pwg                                                     % 323      34x C4w 4xer bow Paat. W 2                                 Nf! 312tl
 % 425     A,W A h >fe Nx+r Prt #vt 2 CuKQ4   UE31'P 5:d                          I a:N34s&EeMCO pw Cc                                                   Dit)       3a Ie:vc*:9es nc                                           VJE 31282 M425      Aw A ore Nx*r P4t W 2 3e774 NME&pp Sy                     W4 ' 6     &a c M %xer Sam W f Musgo                                  %>G7 45% WT1 P ,, Q                                                               P?*W   4 L@ C4 D4 t2     Bese .am Pw 5 av. W 2 Nuve N/E 3 05' 5;4                  K4 '6      Gr4 9 4xer 5'am W t W sugo NAD 054tM Mi2 (p C4                                                                PC w I Lp C4 M d'2     haw how P;,* 5 av W 2 Nuve 4/E 31:95:5                    M d'i      Gat M her 5'a* W 1 V5LWo UU 3 455' to NF Le Ce                                                                P:w & le Cc
 % 4'2     kam nw P:*e 5 rce W 2 tvus,e VSE3i;9 SM                   M 4't      &at M werSam Wiunwco N#G 3 4'X to DAF (p C4                                                                Pw & L7 CC M 4t2     Eeas uv, P:*e 5 av W 2 Nutw N AD '2fl                     M2'3       *aw No P4 t CvNcWJ Yrsee Atrue Nf D uit v;i yn Lc Oc                                                                bow CC M d'2     6ene ham Pw Stav W 2 Nus% %$U '2'i                        M 2')      aam Nee Pc CaretEJ 'rece AW N AG t'!S K2 MFT Le Co                                                                Paw C4
 % die     Seype Nxer Pat W I 'ewew g         N fE3 CA4'41           M 133      as/ ton 3' Ea,6er Pat W 3 Fasc Gas & NJE3 t't4
             . aee, Ary*y                                                         f ew Cc
 $0430     Benev"e Nxer Pat W i 'evesw        N#U 38 403             M 24'      mfr P:ve 5:4v W 2 C.:n$xred Ehy UG 'E 4!24 t avt A.fS7+t                                                        C4 0' Nee V7%
 % 4M      fee *yue %xer Pn W 2 Teveswe       Nf G CE 4'4!           % 24'      maa P:e15 av. W 2 C<n6xa'e: Ehy NSE S'CD 4M5 s a en Ara *,                                                        Cc $ Neo iws 94M       BeVyM Nxet Pa* W 2 Teves'ee        VfE3".A4M3             4; 7(1     D ea M:3ee CPem Cy; Aest C'Kay IL NfE 3M4 Mi v a ei A rv',                                           M 3'3      LaS4* Cc/*, 5.av W 1 Cuwreea? N#E 3 CR MP 5'N M 4M  &aa exe Sav W I C.yvNreu* E h/ N> E 31Y2 5 3                           Env Cc C4                                                      % 3'4      645a* C#v 5'av W 2 Ccereet? %f!3 CA MP 5'N%4M    is ta*xc Saw W t Cceyou? Ehy N/!3'X2 5:4                               Eny 2 CC                                                      %M          ea?e f reee Attwc boy P.aN WVie                           Nf E 3 CE 462% d' 5'N %4M   &a*xe Sav W ' G/v creea* E hy NA! 3 'X2 5'S                            vrew AW Pae 2 Ce                                                      M X9       Wve 'rece a trmt Pw Pc Wre                                 NAE 3 CA 4?M C2
 $'% % 456 &a&XX' 5'4v W i CWWe+a** Ehy Nf E 3 '2f i                              V aaste Atyr -eP3e 2 Q                                                       MM         Uve *reet aty=c P:ve Pn Vane                               NSD CF ai2t ri3 l 5*% M 454 EMeXC Stav W i CO*Veet? E b/ Ui312'E                                   vrete A:y g Pyew Cc Cc                                                      a: E%)     Wattro Crem A yat St L).ss u                             Nf E 312%

5'N % 45' S acex4 5 av W 2 Ccmresa

• E hy UE 31X2 5') D245 VWyeNxer 6eeSaw W 1 NJE1U94 DW Cc Ny ew %.er W2. Cc 5'N M 4!' Ence:ec 5 av W 2 Cemio+a* Ew N5E3 'X2 5:4  % C: %r4 W4 Py* Nxea Sam W 2 Na;rs v>E3 ':4' SM CC M/4e9 P we Cer; 5'N M 45' &ao wyc 5'av W 2 Ce/e.a* E hy N AE 3 'X2 5 f M40 Nne V4 Pyt %xer Sam W 2 %4ps N5 E 31253 CC Mfeet beF Qr; 5'N M 4!' Ev arex< Saw W 2 Cm/m e" E ny U E i ' m M 2': Ocy4e Nxer 5 av W 2 Cue F;w Co NJE 3 3 4%e O Ca  % 1' Cryee uva 5 av W 3 Cue Pw 2 N5E3 C9 We SIN M 46? B'a*NXC 51v JY 2 '.xmy ++a* E s ay NJ E 3 ' 2 *t 5'N % 521 Fac erae 4x+r Stav W t Cry 4 45E iM5? 5'i C4 Pl4C 5sreCe C4

 % 25)     9ms f r3 Nx<r S:w 5 aw vv i        UD '23           '

5'N % 526 8w tece W er 5'av W ! Avra NSD Mi' 5'2

             'eTw%%#e 4 a'ev A#my                                                 PlV SeN*;e CC
 % 2' i    fws 8 n h e r E w 5'aw W '         UE3 CE ott             5'N % 5.'t 'miv>%x'erSav W 2 Ceya                                     UES :e!? SM
             ' eve %eeneV,AJ"F                                                    Pl'a' Serge C4
 % 2* l    Sr.cs in Nxer P:

• Saw W ' N ME3 CA4's s*N % 57, 8'u teoe %xer Stav W 2 C:74 N#E L Mi' 5'2 7eveuse lawy AJV Pl% Se%e C4

 % 29      Eneas 8v v %xer Sw Paw W '         UE a 3 4!'5            5's % 9: Fw wx her Saw W 3 Wye                                        N #E 3 C*" So
             ' eve %#e tavt &#iy                                                  Ptec Sews C4 KN        Ec., in br P3

• Saw W 2 UE i '232 .O 5'N M SE in tax wer 5a v W 3 Cera  %>E 3 M' 5'2

             'eveust n W, aAY                                                     D#ec Servict C4
 %N        6MM IF*y V er P4 v 5'4V W2         N 5# 3 CE 4 9       5'N M 5X   Fast teqe Nxer $aist W 3 U ya                              Njt 3 9249 Terrewee tav, AAv                                                    Pta, $ ewe C4 MN        IvM7 f tr*t h et hof SJ V M 2      N8f 3 If 4!*!          5'N k Id   3 a4C V F 3t \xer Sa'tf M 3 kiYa                           Nf E ) '2$ ?
             ' eve wt s aky A.f*W                                                 Pxe Serv t &

M .M ik NM f e*9 NJasbwSaw W3 NJEi:A 4'39 K 2'r Fe93 fe't.* A9+ : P;.y Satsy W 2 NAE 3 CA 45M .:4

             'rrer*e =aw Amr                                                      3* ann E eWc Co 163

108 Ucensed Facility Index n2n P s av AW P- Sam W 2 vif3 &4tsio m Ne%<^4 Ewtc Co stN n44 Sv 'eus 6:wt W t. wm trw a vffwet Sc2 h*f CC M2n Peas be At:r< Rwe Sam W 2. NLAt1CA 4tSt v3 P'2 5?N944 Neieme le:tc C4 Sw teias bewt W t %sm LOW 4 4AEGC81503 hof CC R2n Pee av AW P:,w 5:am W 2 N.9 3 CR 4M 5'NM44 Sv Teias >:wt W 1. wse Lying & VAE3Cll 534 Ne3 eta 4 Eurc Ce P-;,e Co M 2's Fee? fie AW hoe Sam W 3 v.M 3 04 aM $'Np44 $w te.n A:wt W t gste Lyq & MAEG.125$ N43e".N E*;7C C4 M3'2 VAE ,12M how C4 Revo Seco hva GreaW Sam sg.n4N Sa feias A:w' W 2 %s';e LfW 4 9/EWet SC Sca-we Vata' m- h,a Q M 3t2 Ass % $wo Vea CveaW 5 tam VAES O 4'td WP Se: raw W/tcC* M

                                                         $?N M 473 S o to4 Awt W 2, %sm Lfang & YAE3C41 Sc3 P;ew Cc WP2    Aave Sex ws Grea rig Sam       VfE3 3 4't4 W 56:*a'eMc MAS 4 L"r's                             $7s gan $g i,,,, pyt W 3, %m yn g gjgyet 5a pe M 244                                 YAE3 J 4 M4 Exed E N Grr4 W:er Pa4 W l.                        gg        Q,p,,g$3m p 9 g,rma Ee:tc 4 4AE3 CA45M W Axws un & E*:t< w                                             p;,, to M44)   Secxe %s Sam W 1 Pam: isne 4AEacu. 50              gg        g p,, 33 g7            g ,gg Cc W Nee Ma*TSN                                                                             gjg3 y43$3 y, y g

M443 Sew:.:e we Sam W i Pee: Sene 9/E3 CR 4M2 C. , w e,s~ WN S[p 5m W t m Em & MAEGOO V1 W % 444 Secx* Wer $av W 2 PA $d"fce N/E3 MM bU gy C. s + -v.

                                                                                  ,g 7 g  g   .g   gjg y g M 444 Secx4 %Xr Sam W 2 Pe*C 574e NAs 3'CA 4!!2                         *'

a -.nm, 7 % 327 Seas uer Pat W t fewuee YJE3 CA 4!M v3 GreePh W+s g( KZ New Wi4 ISWd DF S 4wt W 2 N$E3M3 LW F. % 327 Spa we hant W t Tewssee a NAEL 3 a!M it EER W8 P4*C N ggg (g DZ het kJe MT V4F $3XP W2 MME$ CRM) W327 %34* WW PWL W l teWSwe VfE3 @ 4!$1 b2 W M83 EM W'S

       .tw e y3                                          MZ        Nee W e uN Ver Sam W 2          4AE 3 'CA 43'8 M 327 $ @ t* W y Pet W i 'Frtuee      NfEd CE' 4'% I2 W               GFwW PAM W4 we, tm3                                           R212      W v w Wese Aewr? Rex >          VAES 1224 W4X   5%rr kan W r >:*e Pat W t       NUC E33240          M 29      tamee Ro., by P:wa 5m vawe 9AEIA25 SCt Cs:va %y 4 Lip C                                              AW E ect< Co

{ a

                                                                                                                 ... . m .. m ,o..                        . ..   . . . + , ~ . . . . . . ~ . , ,           . . , , . , ,

i, .41

                                           'i!.'",'#/-                     sieuOGRAPHIC DATA SHEET                                                                  ftUREG-0304. Vol. 12                        o. 4

• e....x,........ . / ,

                                           .,,,s....,,.                                                                                                          n .....<. .                                                .

Regulatory and Te nical Reports (Abstract Index Journal) l Annual Compilation .~r 1937 . ..,,... p ,,,,.o Tw.o. ., #

                                                                                                                                                                                       .op..-,.
                                                                                                                                                                               ~ ~ , .                       ....

j tiarch p 1988

                                            , . . . . o. .

• o. 3. ,4 . , .o . . . . . w . . . ~ . ; . a m., <, c .

                                                                                                                                                                 ...o..e,i. 7 o. e , ....

Division of Publications Se ices # . Office of Administration and esources Management *o -a a U.S. Nuclear Regulatory Comis ion o* [ ' f Washington DC 20555 / ,

                                           . . .~s.o. w o. . .. a . , e . . .. . w . . . u . . x . . n ~      ,c
                                                                                                                                                               'ps . . . . . . . ,

Same as 7. above. / . Reference

                                                                                                                                                                    .. . .x c o. . . . o ,~.     .

p 1987 i, w ,s........ c,.. . j i . . . c , .w . ~

                                                                                                                                                   /                                                                        !

j This journal includes all formal reports in 6e NUREG series prepared by the flRC staff and contractors; proceedings of conferencey d workshops; as well as international agreement reports. The entries in this c 7pi tion are indexed for access by title and abstract, secondary report number, pdrsona author subject, f1RC organization for

                                                                                                                          ^                                                                                                 ,

staff and international agreements, contractor. 'nternational crqanization, and i licensed ti.dlity. / i l j i . cou.. , ..s . . . . . . . . . . .,3. o i : . ,,0..

                                                                                                                                                                                                   ..,.,.,g..,,,

compilation abstract index \ Unlimited

                                                                                                                                                                                                   . u :.. ..co.u . c.. e   i s
                                                  ,....:o,     .=:                                                                                                                                   Unc1assified q q o l l.isCu y l 7,i
                                       . ,e.                                                                                                                                                                                '

vi... I \

                                                                                                                                '                                                             y     ...~.

D ' Unclassified  !

s. u.:......

                                                                                                                                                                                                   .,.a e

h eu,1,$0itang(hi saltilh* (#ritt 3ess.2*2 3.li. m .

l-Nuctran cNETo'aYSuuission "'O E#'*' UE' E " l WASWNGTON, O C. FR , =:=u .- l Main Citations M and Abstracts 'J S 7, 77 J 1 t i n i A c 13 L 19 ^4 lb PU' plV P01.1CYb d C - 0 I $T

                                                            '  t'd    ". C["      f.eN 'd P E G P>R* PIN J . e, 3 7                          rC    205'>'-
                                               " ^ # *'

Secondary Report Nornher Indax Personal Author index Subject Index 4', NRC Originating Orgaalzation

     ~

Index (Staff Reports) NRC Originating Organization index (International Agreements) NRC Contractor Sponsor Index Contractor Index International Organization Index Licensed Facility Index}}