ML20090J496

Research News.Volume 5,Number 1

ML20090J496
Person / Time
Issue date:	03/31/1992
From:	NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To:
References
NUREG-BR-0112, NUREG-BR-0112-V05-N1, NUREG-BR-112, NUREG-BR-112-V5-N1, NUDOCS 9203170272
Download: ML20090J496 (12)

Text

_.

NUREGIBR-0112 a nouq'o

@~%... ),, RESEARCHNEWS OFFICE OF NUCLEAR REGULATORY MESEARCH U.S. NUCLEAR REGULATORY COMMISSION VOLUME S, NUMBER 1 MARCH 1992 NRC-Developed System Codes 4.

overreliance on the contractor for evaluation NOW Running on PCs f the results.

Georgs P. Marino, DSIR Now, however, the situation is changing rapidly.

The swift advances in personal computer technol-For the past 30 years, the government and the nu-ogy are making it possible for NRC stati to run clear industry have invested hundreds of millions many of the NRC computor codes on PCs (with of dollars for research and technical assistance standard enhancements) at their workplace. To programs to better understand how nuclear take advantage of this improving staie of affairs, power reactors behave under normal, off normal, the Office of Nuclear Regulatory Research (RES) and severe accident conditions. Most of the has recently contracted through the Small Busi-knowledge acquired from these programs has ness innovative Research (SBIR) program for the been assimilated into major computer codes that development of PC-based full-scale versions of describe nuclear reactor behavior and accident many NRC codes complete with plotting pack-consequences under various scenarios. Until very ages and a user friendly interface program. The recently, rnost of these codes were so large and contractor, Risk Management Associates, Inc, complex that they could run effectively only on (RMA), also supp!!ed the source codes as well as such mainframe systems as the CRAY and the a compilation system on five " enhanced" PCs.

Control Data Corporetion CDC 7600. As a result, The staff can therefore not only run these codes staff members who needed to get information on site, but can also examine, modfy, and recom-from these codes had to use the codes on a main-pile the original source code, if necessary, for spe-frame computer system operated by outside con-clalized scenarios or "what if" problems.

tractors. This has resulted in such unfavorable and costly consequences to the agency as:

4 Complied versions of these codes can be run on 1.

High cost and long waiting times for results an IBM PC-compatible desktop computer with an -

of requested computer runs; intel 80386 main CPU (central processing unit), an Intel 80387 math coprocessor, and 7 megabytes 2.

Restriction of runs to major problems with no of extended RAM (random access memory),

allowance for multiple "what if* runs to help Codes such as CORCON, FRAPCON, MINET, the staff analyze multiple accident scenarios; and PRAMIS require less RAM, but any code can be executed if sufficient RAM is available. As 3.

Isolation of the users from the intimats physl.

stated earlier, the source codes are also available l

cal and mathematical details of the codes re-along with the compilation tools required to allow l

quired to familiarize themselves with the users to modify the code on the five special PCs j

codes' strengths and weaknesses; and supplied by RMA.

i 1

1 920317o272 92o331

$"otbI PDR

- r l

i Future modifications to the five RMA suppiled PCs The 16 codes currently (or soon to be) on site at

)

are expected to decrease, by an order of magni-Nicholson Lane / South are listed here, and an as-1 tude, the execution times for typical problems by terisk indicates codes currently available.

j using the new-Reduced Instruction Set Chip t

MELCOR*

}

(RISC) processor running in the background un-der the new Windows 3.0 envirenment Thus us-A severe accident code for core, containment, 3

ers of the RMA machines can have full use of their and fission product behaviori used in PRA l

PCs for other tasks while simultaneously _execut.

(probabliistic risk assessment) analyses-ing long running MELCOR or RELAP5 problems-e RELAP5*

on the RISC chip board, f

A thL,1al hydraulic systems code for both PWR and BWR general system applications.

i l

In addition to the RMA supplied codes listed e

MACCS*

above, RES also has PC versions of other codes I

A consequence analm code for radiological l

of use to the NRC staff. The IRRAS (discussed in effects of fission product release scenarios, the May 1991 Research News) and SARA codes j

can be used to_do fault tree analyses and front-e CONTAIN*

l-end PRA computations. Finally, RES has recently I

A general containment behavior code, rnost of =

developed and obtained computer codes for which is embedded in.MELCOR, F

j analysis oi toxic gases and radionuclides in reac-i tor control rooms as part of the resolution of Ge-STCP' neric Issue 83, " Control Room Habitability

• These codes have been named CRH, EXTRAN, The Source Term Code Package is a group of severe accident codes with a function similar and FRFP and are being tested by both RES t MELCOR but made up of earlier codes such (SAIB) and NRR' as MARCH. TRAP / MELT, and-CORCON (see l

below).

't

\\

_CORCON*

.j e

It should be noted that running some of the more complex codes such as RELAPs 1ELCOR, and A code describing the behavior of liquid corium i

SCDAP/RELAP requires (1) exps se in under.

and concrete interactions.

standing the underlying principles used in each e

.ORIGEN2*

code, (2) familiarization with and access to input de' and (3) proper interpretation and usage of _

A code that computes the core inventory of fis-the output files Thus the user should have access.

slon products,s to user manuals for the codes and, preferably, BWRSAR*

some formal training and guidance.

i A core behavior code for severe accidents in

~ '

~

BWRs (some modules are being incorporated into MELCOR).

e In c' nclusion, RES developed a PC based cal-o culational capability whereby the NRC staff can e

EVNTREE perform in-house analyses using codes devel-A code that processes event trees in PRAs to.

oped by the agency over the past 25 te 30 years, calculate - their frequencies, of occurrence This capability does not eliminate the need for (used in NUREG-1150).;-_

contractual projects; however, it does allow the l

• - ' PRAMIS staff to expend agency funds more efficiently and to gain'a better understanding of the strengths -

A code that computes risk for given sequence and weaknesses of our current analysis pack-frequencies and consequence analyses (used-ages.'

in NUREG-1150),

j l

I i

2-I e

,.-r---

-re

+ -,

-,c--

e XSOR canism. regional tectonics, and oll and minera! cx-A parametric code for computing source terms ploration.

for various scenarios. For a specific source term via a MELCOR or STCP calculation, XSOR The first day was devoted to background presen-approximates the total sourco term (used in tations to develop a common base for the working NUREG-1150),

group sessions. The second and third days in-volved discussions in four working g'oups: Warto e

FRAPCON Package / Waste Form, Near Fleid Frocesses/En-A steady-state oporation fuol olement behavior vironment, Far Field Processes / Environment, code.

and Tectonics / Volcanism. The final session in-volved a summary presentation from each work-FRAP-T6 ing group and an open discussion of the working A transient (LOCA, ATWA, etc.) fuel element group summaries. Aside from specific technical behavior code, recommendations, it was clear that almost all par-ticipants agreed on several aspects of the use of e

MARCHa analogs:

An early severo accident core behavior code 1.

Significant effort needs to be applied to un-used in STCP.

derstanding how repository processes and e

MINET, systems work on the spatial (kdometers) and temporal (thousands of years) scales perti-A thermal-hydraulic behavior code for analyz-nent to repository performance, in order to ing transients in liquid-metal reactors.

have " reasonable assurance" that predictivo SCDAP/RELAP methods are credible, they must be sup-e ported by data relevant to these scales and A highly detailed core and thermal-hydraulic time periods, behavior code for severe accident 'and acci-dont management analyses.

2.

Natural analogs are the only way to address model applicability over the regulatory peri-RES/WBB and CNWRA Sponsor ods of concern. They are also the best '

source of information for large scale sys-DRA/WMB 3.

Natural analog ctudies need to be carefully evaluated against appropriate criteria aimed On July 23-25, the RES Waste Management at ensuring the applicability of their results.

Branch (WMB) and the Center for Nuclear Waste Such criteria have been proposed by the Regulatory Analyses (CNWRA) sponsored a Natural Analog Working Group (NAWG) workshop in San Antonio, Texas, on the role of sponsored by the Commission of the Euro-4 natucal analogs in geologic disposal of high-level pean Communities. The NRC representative nuclearwaste. Approximately50technicalexperts to NAWG ls Dr. Kovach.

from throughrW the United States met to discuss the potential uces and applicability of natural ana-4.

Appropriate natural analogs represent op-logs to the problems facing the HLW disposal pro-portunities that must be carefully developed.

gram. Dr. Linda Kovach (RES/WMB), the NRC The scope is often too large for one sponsor project manager for the workshop, Dr. Ralph to handle. International cooperative efforts Cady (RES/WMB), Dr. John Bradbury (NMSS/

that maximize the effectiveness of the lnvesti-HLHP), and Dr. William Ott (RES/WMB) partici-gations and ensure involvement of the best -

pated in the workshop along with representatives technical experts offer the best chance of from CNWRA and the Department of Energy and success (e.g., the international Alligator Riv-its contractors. Technical experts were invited to ers Analog Project, which is supported by bring in special perspectives in such areas as vol-five countries).

3

Variations in Material Propertles of and revised in 1990, was prepared to assist those Linde 80 Weld Metal Measured inv Iv dinaddressingtheagingandthepotential g

for license renewal of nuclear power plants to lo-cate information being geneiated in the NPAR DEMEB program. Revision 2 contains a listing and index of rep ris that were issued through June 1991 and The staff of the Heavy Section Steel Irradiation summaries of those reports. Each summary de-Pro 9 ram at Oak Rid 9e National Laborato'Y are scribes the elements of the research covered in completing work to measure and document the the report and outlines the significant results. For variation in copper content and initial Charpy V the convenience of the user, the reports are in-and RTwor properties of Linde 80 weld metal from dexed by personal author, corporate author, and the reactor vessel of the canceled Midland plant. It subject' I

is noted that Linde 80 wold metal was used in tab-ricating the Yankee Rowe reactor vessel. The Mid-The NPAR program, conducted by RES, is a com-land specimens were from the beltline circumfer-prehensive hardware-oriented engineering re-ential wold and the circumferential weld joinin0 search program focused on understanding the two shell courses at the main coolant nozzle ele-aging mechanisms of components and systems vation. The weld wire and flux are typical of the in nuclear power plants. The program also fo-wire and flux used for some 16 other reactor ves-cuses on methods for simulating and monitoring sets fabricated by Babcock and Wilcox, the aging-related degradation of these compo-nents and systems. In addition, it provides recom-The variation in weld metal properties represent-mendations for effective maintenance to manage ing the entire circumference and through the aging and for the implementation of the research I

results in the regulatory process.

thickness is:

I Copper content 0.21 to 0.46%

Most of the reports generated in the NPAR pro-RT

-22 to + 54'F gram contain a description of the components or

?

gg7 CV upper shelf 66 to 79 ft lb systems being examined and identify the principal stressors leading to aging. They frequently con-This wide variation in such critical properties has tain an analysis and statistical assessment of fall-been suspected but had not been documented so ure data obtained from Licensee Event Reports dramatically. These data were used by the RES and other sources of component failure data for staff in the sensitivity study of the Yankee Rowe re-operating nuclear power plants. Current surveil-actor that served as background for the Commis-lance and monitoring practices are also reviewed slon decision on Yankee Rowe on July 31,1991.

and, when identifiable, recommendations are The data will be added to the data base for future made for improvements.

probabilistic analyses of the 17 reactor vessels containing unde 80 weld metal.

National Academy of Sciences Com-mittee on Fracture Characterization 30 Titles Added to Listing of NPAR and Fluid Flow Meets in Washington l

Reports l

N. N. Kondic, DE/EMEB, and E. L. Hill, PMPDAS/RES The initial meeting of the National Academy of Sci-ences Committee on Fracture Characterization l

Revision 2 to NUREG-1377, "NRC Research Pro-ar d Fluid Flow was held in Washington, DC. The I

gram on Plant Aging: Listing and Summaries of principal objective of the committee is to prepare a Reports issued Through June 1991," published in study report that reviews, synthesizes, and inte-July, added 30 titles to the listing of reports gener-grates recent research concerning techniques ated in the Nuclear Plant Aging Research (NPAR) ad approaches to fracture characterization and j

program. NUREG-1377, first published in 1989 fluid flow in rock fractures. The study is funded in a

4

I part by RES. RES was requested by the Commit-Report Published on Availability of tee Chair to provide a brief overview of NRC m-search issues and ongoing studies to address Instrumentation During Severe them. Short overviews were provided on nuclear Accidents waste, mining, tunneling, dams, and under-NUREG!CR-5691, " Instrumentation Availability ground reservolts (i.0,, oil, gas, water, and geo-thermal) as they relate to fracture characterization for a Pressurized Water Reactor With a Large Dry Containment During Severo Accidents," covers and fluid flow. The committee prepared a draft work by ldaho National Engineering Laboratory in study outline and is beginning a llterature review, support of the NRC Accident Management Re-search Procram, it evaluates the availability of in-Criterla Being Developed for struments to supply accident management infor-Accident Management Plans mation during a broad range of severe accidents for a pressurized water reactor with a largo dry A report, NUREG/CR-5543, "A Systematic Proc.

containment, Results from this evaluation include oss for Developing and Assessing Accident Man.

(1) Identification of plant conditions that would af-agement Plans," that describes an approach for fact instrument performance and information deve!oping critena to be used by NRC staff for as, needs during severe accidentsi(2) definition of sessing the adoquacy of licensees' accident man, envelopes or parameters that would be important agement programs has been issued. This report, in assessing the performance of plant instrumen-the first of two on this approach, describes a pro, tation for a broad range of severe accident so-totype process for developing an accident man, quences, and (3) assessment of the availability of agement program based on the five framework plant instrumentation during severe accidents, elements of an accident management plan.

Ti1ese results form a technical basis for NRC staff Based on this process, a preliminary set of as-evaluation of Industry's capability to effectively sessment criteria are derived. These preliminary monitor and diagnose the progression of severe criteria will be refined and improved after the pro, accidents, to prescribe preventive or mitigative totype process is validated through application, actions, and to evaluate the effectiveness of acci-which is currently in progress, and williorm the ba.

dent management actions, sis for the second report.

International Cooperative Group-Study Provides a Unified Radiation Damage Mechanisms-interpretation of Thermal Mixing Meets -

Experiments The third meeting of the International Cooperative Group-Radiation Damage Mechanisms (ICG-Thermal mixing in relation to pressurized thermal RDM) in Raleigh, North Carolina, was followed by shock has been examined in experiments a one-day workshop on the applicability of dpa throughout the world in a variety of scales ranging (displacements per atom) as a damage parameter from 1/5 to full scale The University of California at for reactor irradiations. The ICG-RDM, initlated by Santa Barbara used the regional mixing model the NRC, is now an ad hoc group encompassing and the associated computer programs REMIX membership from eleven different countries to ex-and NEWMIS to interpret these data in a compre-change information on detailed studies of reactor hensive fashion. These interpretations indicate irradiation damage mechanismsi The members that cooldown transients and the degree of stratifi-are limited to those actively involved in such stud-cation can be predicted with confidence. The re-les at their home laboratories, n,o the discussions sults of this work have been published in NUREG/

can get to the fine details of the radiation damage CR-5677, "A Unified Interpretation of 1/5 to Full-process. From such discussions, however, gen-Scale Thermal Mixing Experiments Related to eral conclusions are drawn conceming how dam-Pressurized Thermal Shock." This report includes age is created and how it might be avoided, and universal stratification solutions in graphical form -

what directions can be charted for future efforts, and a simple procedure for hand calculation.

The group drew very close to agreement on 5

4 several damage mechanisms, including the effect qulted before the true significance to plant opera-of copper and the generation of matrix defectu by tion is understood.

knock on atoms. Cooperation and exchange of materials between members continues to be out-ReEort Published on Severe 4

standing; clearly, this is a primary benefit of this ondeavor.

Accident Management A report, NUREG/CR-5702, " Accident Manage-The workshop on the applicabi!ity of dpa as a ment Information Needs for a BWR with a Mark I damage parameter was equally well attended.

Containment," was issued as part of a program to Here, the peripheral issue of the influence of identify plant information necessary for plant per-thermal neutrons on embrittlement of PWR sup-sonnel to (1) diagnose that an accident is in pro-port structures was also thoroughly discussed.

gress, (2) select and implement strategies to pro-While no clear answer was possible about thermal vent or mitigate the accident, and (3) monitor the neutrons, the workshop did feel that dpa was the effectiveness of these strateglos. This study used j

best possible damage parameter available for use the same methodology as a similar study reported today and thould supplant the fluence greater in NUREG/CR-5513 (April 1990), which identified than 1 MeV currently in use, the Information needs for a PWR with a large dry containment. The recent study concluded that there is insuffclent instrumentation to determine if UMCP Conducts Experiments on the containment remains inerted and if the con-Safety During Reactor Shutdown tainment boundary is being challenged once mol-ten core material has penetrated the reactor vos-The University of Maryland at Cnilege Park se!. A follow-on study is in progress to determine (UMCP) has conducted a series of shutdown the effect of a wide range of severe accident envi-safety experiments in their thermal-hydraulic facil-ronments on the capability of existing BWR instru-ity, which models Babcock and Wilcox (B&W) mentation.

plant geometry. Parameters varied were those that could affect reflux cooling effectiveness dur-RES Hosts 19th Water Reactor Safety ing a loss of residual heat removal while in shut-down operation, e.g., water level, power level, Meeting venting, and feed and bleed operation, to obtain More than 600 persons-from the United States experimental data on the ability to establish reflux and abroad, and from government, industry, aca-or boiler / condenser modes of cooling during demia, public interest groups, and the NRC staff-shutdown. The issue of greatest concem is the attended the 19th Water Reactor Safety informa-pressure rise needed for steam to reach condens-tion meeting sponsored by the Office of Nuclear ing surfaces in the steam generators when empty Regulatory Research, spaces in the reactor coolant system (RCS) are filled with air, if the pressure rise needed is suffi-Chairman Selin opened the three-day session ciently great, temporary structures in the RCS with a discussion of the priorities he has set for his could be blown out, leading to a loss-of-coolant tenure. Also at the opening session, Eric accident. There are' effectively no applicable ex-Beckjord, Director, RES, welcomed the partici-perimental data available. The UMCP facility is the pants. At the plenary session Tuesday afternoon, only operational facility in the world modeling the Mr Beckjord discussed developments in the RES B&W once-through steam generators, it is be-program.

lieved that the steam generator design is a key fac-tor in the system response. As with most thermal-Breakout sessions were held on a variety of topics hydraulic experiments, the purpose of the UMCP including severe accident resarch, pressure experiments is to provide an understanding of the vessel and piping integrity, advanced reactor re-phenomena that occur, not a direct demonstra-search, metallurgy and nondestructive examina-tion of power plant operation. Therefore, signifi-tion, structural engineering, aging of compo-cant analyses of the experimental data will be re-nents, advanced passive light-water reactors, 6

i human f actors research, human factors issues ro-Not Exceeding 12 Inches (0.3 m)." Issued 6/91, lated to advanced passive light water reactors, so-Centact: W. Campbell, RES/DE/EMEB.

vere accident policy implementation, carth scl-onces, probabilistic risk assessment, accident Draft Regulatory Guides issued During management, and thermal hydraulics. RES em-py.g gg4 ployees who were session chairs included Charles Ader, David Bessette, Jack Burns, Frank Coffman, James Costello, Farouk Eitawila, James Draft Regu!atory Guide DG-1008,

• Reactor Cool-ant Pump Seals." Issued 4/91.

Contact:

J. Jack-Johnson, Norman Lauben, Richard McMullen, son, RES/DSlR/ElB' Zoltan Rosztoczy, Charles Serpan, Brian Sheron, and Gerald Weidenhamer-Draft Regulatory Guide DG-1009, " Standard For-mat and Content of TechnicalInformation for Ap-The meeting was held October 28 to 30 at the plications To Renew Nuclear Power Plant Operat-Bethosda Pooks Hiii Marriot. The program was co-ing Licenses " issued 12/90.

Contact:

J. Vora, ordinated by Brookhaven National Laboratory.

RES/DE/EMEB.

Regulatory Guides Draft Regulatory Guide DG-3003, " Format and Content for the License Application for the High-Active Regulatory Guides issued During Level Waste Repository." issued 11/90.

Contact:

C. Prichard, RES/DE/WMB.

g,gg Draft Regulatory Guido DG-4002, Proposed Sup-Regulatory Guide 1.84, Revision 27, " Design and plement 1 to Regulatory Guide 4.2, " Guidance for Fabrication Code Case Acceptability-ASME the Preparation of Supplemental Environmental Section 111, Division 1.* lssued 11/90.

Contact:

E.

Reports in Support of an Application to Renew a Woolridge, RES/DE/MEB.

Nuclear Power Station Operating License." is-Regulatory Guide 1.85, Revision 27, " Materials Code Case Acceptability-ASME Section 111, Divi-Draft Regulatory Guide DG-5002, " Material Con-sion 1." Issued 11/90.

Contact:

E. Woolridge, trol and Accounting for Uranium Enrichment Fa-RES/DE/MEB.

cilities Authorized To Produce Special Nuclear Material of Low Strategic Significance." Issued Regulatory Guide 1.147, Revision 8 " Inservice In-2/91.

Contact:

H. Tovmasslan, RES/DRA/RDB.

spection Code Case Acceptability-ASME Sec-tion XI, Division 1." Issued 11/90.

Contact:

E.

Draft Regulatory Guide DG-8003, Proposed Revi-Woolridge, RES/DE/MEB.

slon 1 to Regulatory Guide 8.25, " Air Sampling in the Workplace." issued 9/01.

Contact:

S.

Regulatory Guide 5.66, "Acenss Authorization McGuire, RES/DRA/RPHEB.

Program for Nuclear Power Plants." issu9d 6/91,

Contact:

S. Frattali, RES/DRA/RDB.

Regulatory Guides Withdrawn During FY 1991 Regulatory Guide 7.11 (DG-7001),

" Fracture Toughness Criteria of Base Material for Ferritic Regulatory Guide 1.2 (Safety Guide 2), " Thermal Steel Shipping Cask Containment Vessels with a Shock to Reactor Pressure Vessels," W;thdrawn 6/91,

Contact:

A. Hiser, RES/DE/MEB.

Maximum Wall Thickness of 4 Inches (0.1 m) " is-sued 6/91.

Contact:

W. Campbell, RES/DE/

Regulatory Guide 1.17, Revision 1, " Protection of EMEB.

Nuclear Power Plants Against Industrial Sabo-tage." Withdrawn 5/91.

Contact:

S. Frattali, RES/

Regulatory Guide 7.12 (DG-7002),

" Fracture DRA/RDB.

Toughness Criteria of Base Material for Ferritic Steel Shipping Cask Containment Vessels with a Regulatory Guide 1.58, Revision 1, " Qualification Wall Thickness Greater Than 4 Inches (0.1 m) But of Nuclear Power Plant inspection, Examination, 7

and Testing Personnel." Withdrawn 6/91. Con-RM077, Access Authorization Program for Nu-tact: O. Gormley, RES/DRA/ARGIB.

clear Power Plants (10 CFR 73). Final rule pub-lished in Federa/ Register 4/25/91 (56 FR 18997).

Regulatory Guide 1.64, Revision 2, " Quality As-Correction published 5/29/91 (56 FR 24239) Con-surance Requirements for the Design of Nuclear tact: S. Frattall, RES/DRA/RDB.

Power Plants." Withdrawn 6/91.

Contact:

O.

RM095, Quality Management Program and Gormley, RES/DRA/ARGIB.

Misadministrations (10 CFR 2,35). Final rule pub-lished in Federal Register 7/26/91 (56 FR 34104),

Regulatory Guide 1.88, Revision 2, " Collection, effective 1/27/92.

Contact:

A. Tse, RES/DRA/

Storage, and Maintenance of Nuc! ear Power Plant RDB.

Quality Assurance Records." Withdrawn 6/91.

Contact:

O. Gormley, RES/DRA/ARGIB.

RM100, Custody and Long Term Care of Uranium and Thorium Mill Tallings Disposal Sites (10 CFR Regulatory Guide 1.123, Revision 1, " Quality As-40). Final rule published in Federal Register surance Requirements for Control of Procurement 10/30/90 (55 FR 45591), effective 11/29/90. Con-of items and Services for Nuclear Power Plants.'

tact: M. Halsfield, RES/DE/WMB.

Withdrawn 6/91.

Contact:

O. Gormley, RES/DRA/

ARGIB.

RM119, Notifications of incidents (10 CFR 20,30, 31,34,39,40,70). Final rule publishod in Federal Regulatory Guide 1.144, Revision 1, " Auditing of Reglater 8/16/91 (56 FR 40757), offective Quality Assurance Programs for Nuclear Power 10/15/91,

Contact:

J. Mate, RES/DRA/RDB.

Plants." Withdrawn 6/91.

Contact:

O. Gormley, RES/DRA/ARGlB.

RM129, Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Eve.nts (10 CFR 50). Final rule published in Regulatory Guide 1.146, " Qualification of Quality Assurance Program Audit Personnel for Nuclear Federal Register 5/15/91 (56 FR 22300), effective 6/14/91.

Contact:

A. Hiser, RES/DE/MEB.

Power Plants." Withdrawn 6/91.

Contact:

O.

Gormley, RES/DRA/ARGIB.

RM133, Monitoring the Effectiveness of Mainte-nance at Nuclear Power Plants (10 CFR 50). Final Draft Regulatory Guide SG 301-4, ' Standard For-rule published in Federal Register 7/10/91 (56 FR mat and Content Guide for Access Authorization 31306), effective 7/10/96.

Contact:

R. Riggs, Plans for Nuclear Power Plants." Withdrawn 5/91.

RES/DSIR/SAIB.

Contact:

S. Frattall, RES/DRA/RDB.

RM165, Emergency Response Data System (10 CFR 50). Final rule ilished in FederalRegister RULEMAKINGS 8/13/91 (56 FR 40178), effective 9/12/91.

Contact:

M. Au, RES/DRA/RDB.

Final Rulemakings Published During FY 1991 RM190, Enforcement of Nondiscrimination on the Basis of Handicap in Federally Assisted Programs RM025, Criteria and Procedures for the Reporting (10 CFR 4). Final rulemaking published in Federal of Defects and Conditions of Construction Permits (10 CFR 21, 50). Final rule published in Federal Register 12/19/90 (55 FR 52136).

Contact:

E.

Tucker, SDBU.

Register 7/31/91 (56 FR 36081), effective 10/19/91.

Contact:

W. Jones AEOD.

RM197, ASNT Certification of Industrial Radiogra-phers (10 CFR 34). Final rule published in Federal RM033, Standards for Protection Against Radia-Register 3/19/91 (56 FR 11504). Correction pub-l tion (10 CFR 2,19, 20, 30, 31, 32, 34, 35, 39, 40, lished 5/1/91 (56 FR 19920).

Contact:

D. Nellis, 50, 51, 70). Final rule published in Federal Reg!s-RES/DRA/RPHEB.

ter 5/21/91 (56 FR 23309). Correction published 5/24/91 (56 FR 23956). Amended 7/15/91 (56 FR RM218. Revisions to Procedures To lssue Orders, 32071)

Contact:

H.Peterson RES/DRA/RPHEB.

Deliberate Misconduct by Unlicensed Persons 6

(10 CFR 2, 30, 40, 50, 00, 01, 70, 72,110,150).

RM305, imports from South Africa (10 CFR 110).

Final rulo pubilshed in Fodor..I Rogistor 8/15/91 Final rulo published in Fodotal Register 8/13/91 (56 FR 40604), offectivo 9/10/91.

Contact:

J.

(50 FR 38335), offectivo B/13/91.

Contact:

R.

Ueberrnan, OE.

Hauber, IP.

AM253, Operators' Licensos (10 CFR 2,65;. Final RM307 Chango in Commerc!al Tolophone Num-rulo published in Fodotal Registor 7/15/91 (50 FR bor for Rogion V (10 CFR 20,21,73). Final rulo 32050), offoctivo 8/14/91.

Contact:

R. Gallo, NRR.

pubilshod in Fodoral Roglsfor 8/21/91 (50 FR 41440), offectivo 0/2/91.

Contact:

D. Moyer, ADM.

RM262. Fitnoss for Duty Programs (10 CFR 20).

Final rulo penkhod in Fodotal Rogistor 8/26/91 Proposed Rulemakings Published During (50 FR 41922), offectivo 9/25/91.

Contact:

E.

py 1991 McPock, NRR/DRIS/RSGB.

RM128, Uconses and Radiation Safoty Requiro-RM277, Submitting Applications for the Uconsing monts for Largo ltradiators (10 CFR 19,20,21,30, of Test and Research Roactor Operators Dlroctly 36, 40, 51, 70,170). Proposed rulo publishod in to Headquartors (10 CFR 55). Final rule published Fodora/ Reglstor 12/4/90 (55 FR 50008).

Contact:

in Fodora/ Rogister 10/11/90 (55 FR 41334), effoc-S. McGuiro RES/DRA/RPHEB.

tivo 11/13/00.

Contact:

D. Lango, NRR.

RM141, Codos and Standards for Nuclear Power RM281 Operations Contor Area CodoTotophono Plants (ASME Code, 1980/1987/1988 Addonda, s

Number Chango (10 CFR 20,50). Final rulo pub.

1989 Edition) (10 CFR 50). Proposed rulo pub-lished in Fodora/ R6glster 1/10/01 (50 FR 944), of-lished in Foderal Rogistor 1/31/01 (50 FR 3796).

foctivo 1/10/91.

Contact:

M. Au, RES/DRA/RDB.

Contact:

G. Millman, RES/DE/EMEB.

RM282, Statomont of Organization and Gonoral RM215, MaterialControland Accounting nequiro-Information, Minor Amendments (10 CFR 0,1). Fl.

monts for Uranlum Enrichment Facilitics nal ruto published in Fodora/ Rogistor 11/15/90 (55 Producing S'acial Nuclear Material of Low Strate-FR 47740).

Contact:

D. Grimsloy, ADM/DFIPS.

gic SignificaN o (10 CFR 2,40,70,74). Proposed rulemaking published in Foderal Rogister RM285, Access Authorization Foo Schodulefor U.

12/17/90 (55 FR 51726). Conta;t: G. Gunderson, consoo Porsonnel(10 CFR 11,25) Final rulo pub.

RES!DRA/RDB.

(

)*

onta t D KI d, AD / EC.

RM256, Environmental Review for Ronowal of Op-orating Uconses (10 CFR 51). Proposed rulo pub-RM298, Assistance to Prospectivo Petitioners (10 lished in Federal Roglstor 9/17/91 (56 FR 47016);

CFR 2). Final rulo published in Fodoral Registor comment period ends 12/16/91.

Contact:

D.

3/12/01 (56 FR 10359).

Contact:

D. Grimsley, Cleary, RES/DSIR/RPSlB.

ADM/DFIPS.

RM286, NRC 1.lconsoo Reinvestigation Program RM300, Rovision of Foo Schedules,100% Foo (10 CFR 25). Proposed rulo published in Fodotal Rogister 7/31/01 (50 FR 36113).

Contact:

D. Kidd, Rocovery (10 CFR 52,71,170,171). Final rulo ADM/SEC.

published in Fodoral Registor 7/10/91 (50 FR 31472). Correction published 8/9/91 (50 FR RM289 Decommissioning Funding for Prema-37828).

Contact:

C. J, Holloway, OC.

turoly Shutdown Power Reactors (10 CFR 50).

Proposed rulo published in Fodoral Rogister RM304, Chango in Commercial Telephono Num 8/21/91 (56 FR 41493).

Contact:

R. Wood, NRR.

bor for Rogion V (10 CFR 20,21,73). Final rulo published in Fodoral Rogister 4/26/91 (50 FR RM290, Uranium Enrichmont Regulations (10 19258), offoctive 4/20/91.

Contact:

D. Mayor, CFR 2,40,50, 51,70,75,110,140,150,170). Pro-ADM.

posed rulo published in Federal Rogister 9/16/91 9

(50 FH 46739); comment period ends 12/2/91, rulemakin0 terminated 6/28/01 (combined with

Contact:

C. Nilson, RES/DRA/RPHEB.

RM295). Contact' H. Tovmasslan, RES/DRA/

RDB.

RM302, DOE L or DOE O Rolnvestigation Pro-gram for NRC R Access Authorization Ronewal RM233, General and Exemption Uconso Under Roquiroments (10 CFR 11) Proposed rulo pub-Section 40.22 (10 CFR 40). Uninitiated rulomaking lished in Fodotal Rop! ster 9/30/91 (56 FR 49435).

terminated 6/20/91 (combined with RM292). Con-

Contact:

R. Castanoira, NMSS/SGDB.

tact: C. Mattson, RES/DRA/RPHEB.

RM234, Timely Cleanup of Major Spills (10 CFR Rulemakings Terminated During FY 1991 50). Uninitiated rutomaking terminated 6/28/01; no nood for rulomaking at this timo.

Contact:

J.

RM103, Safety Rotated and important to Safety in Malaro, RES/DRA/RPHEB.

10 CFR Part 50 (10 CFR 50). Proposed rutomaking terminated por Commission memo dated RM244, Effects of Rolleonsing Options on Decom-6/24/91; rule no longer nooded.

Contact:

O.

missioning Funding (10 CFR 50). Uninitiated Gormley, RES/DRA/ARGIB.

rutomaking toiminated, topic included within RM145, Gonorat Licensos (10 CFR 31,32). Uniniti-ated rulo terminated por report to EDO 7/1/01.

RM248, Modify Existing Exemptions To Conform

Contact:

RES/DRA/RDB.

to BRC Policy (10 CFR 2,20). Proposed rulomak-ing terminated by SRM did 3/10/91 in favor of

)

RM208, Requires Notification of Follow up Sur-rulomakings RM270-RM276.

Contact:

RES/DRA/

voys or Decontamination Actions Taken by Ucon-RPHEB.

scos After Roloaso of Sito. Uninitiated ruto termi-nated 12/90.

Contact:

C. Feldman, RES/DRA/

RM260, Advanced Roactor OBE/SSE Ratio (10 RPHEB.

CFR 52). Uninitiated sulemaking terminated; rulomaking activity combined with RM147. Con-RM207, Requires Former Licensees to Moot More tact: N. Chokshi, RES/DE/6SEB.

Stringent Standards After Uconso Termination Based on Interim Standard. Uninitiated rule torm!.

RM271, Revision of Sourco Material Exemptions nated 3/14/91; NMSS to recommend licensing (10 CFR 40). Uninitiated rulemaking terminated cortdition, put on hold by Commission.

Contact:

6/28/91 (combined with RM292).

Contact:

R.

RES/DRA/RPHEB.

Mock, RES/DRA/RPHEB.

RM272, Removal of Prohibition of Radioactivo RM208, Codify Rooponor* Clauso for Terminated Uconses. Uninitiated rule terminated 3/15/91; Materials in Foods, Boveragos, and Cosmotics NMSS to recommend licensing condition, put on (10 CFR 30). Uninitiated rule terminated 3/10/91; hold by Commission.

Contact:

RES/DRA/

SRM directed statt not to proceed with rulemak-Ing

Contact:

R. Mock, RES/DRA/RPHEB.

RPHEB.

RM216, Guidance and Rulomaking on Use of PETITIONS FOR RULEMAKING Monoclonal Antibodios (10 CFR 35). Uninitiated rulemaking terminated 6/28/01 (combined with Petitions Completed During FY 1991 RM223)

Contact:

RES/DRA/RPHEB.

PRM-50-50,

Subject:

Technical Specifications, RM224, Nonpower Roactor Rulomaking issues Petitioner: Charlas Young. Denial of petition pub-(10 CFR 73), Uninitiated rutomaking terminated lished in F0deral Register 1/17/01 (56 FR 1N9).

6/28/01 (combined with RM293).

Contact:

RES/

Contact:

M. Floishman, RES/DRA/RDB.

DRA/RDB.

PRM-61-1,

Subject:

Design and Construction of RM232, Comprehensive Review of Part 21 for Zoro-Roloaso Low Lovel Radioactive Wasto Dis-Non-Roactor FacitrJas (10 CFR 21). Uniriitiated posal Facility, Petitioner:

Sierra Club, North 10 l

I

1 Carolina Chaptor. Dental of petition for rulemaking 40, 50, 51, 70, 72). Interim critoria terminated by published in Fodotal Rogistor 7/25/01 (50 FR SRM did 3/10/91; soo rutomaking RM211. Con-34035).

Contact:

M. Halsfield, HES/DE/WMB.

tact: R. Mock, RES/DRA/RPHEB.

PRM-73-0,

Subject:

Design Basis Throat for Ra-PS20, Possibio Safety impacts of Economic Por.

diological Sabotage of Nuclear Reactors, Poti-formanco incentivos. Final policy statomont pub-tioner: Nucioar Controlinst., Comm. to Brid0o the lishod in Fodora/ Rogistot 7/24/01 (50 FR 33945).

Gap. Donial of petition publishod in Fodota/Rogis-

Contact:

A. Gody, NP.R/PDTSB, tot 0/11/91 (50 FR 26782).

Contact:

C. Sawyer, i

NMSS, RESEARCH NEWS is published by the USNRC Offico of Nuclear Regulatory Research, Ann F.

POLICY STATEMENTS U '"" " ' '#

Comments, sug00stions, and articles for futuro is.

Policy Statements Completed During FY 1991 suos should bo directed to the Editor, RESEARCH NEWS, Offico of Nuclear Regulatory Research, PS07, Residual Radioactivo Contamination Crito-U.S. Nuclear Regulatory Commission, Washing-ria Applicable to Decommissioning (10 CFR 30, ton, DC 20555.

i

. v... a.1. o.. n on., or r ic., n.: - 2 n. n, s..n 11

I 4 f 5 ' n 1 t <,U'[I re i n t, ',3j f a

-oe

3 4,14 ts y.y t 1 *

• g,',~ N'E ' n,ig fyPL ir:g 7,,,,

o r,,:

IC

'.an y, THIS DOCUMENT WAS PRINTED USING RECYCLED PAPER i

_ -.