ML20056A438

NRC Research Program on Plant Aging: Listings and Summaries of Reports Issued Through May 1990

ML20056A438
Person / Time
Issue date:	07/31/1990
From:	Eva Hill, Kondic N NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To:
References
NUREG-1377, NUREG-1377-R01, NUREG-1377-R1, NUDOCS 9008070371
Download: ML20056A438 (62)

Text

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

NUREG-1377 Rev.1 NRC Research Program on Plant Aging: Listing and Summaries of Reports

~ Issued Through May 1990 U.S. Nuclear Regulatory Commission Office of Nuclear Regulatory Research N N. Kondic, E. L liill

,+>****%,

a-PDR

4 AVAILABILITY NOTICE Availability of Reference Materials Cited in NRC Publications Most documents cited in NRC publications will be available from one of the following souNest 1.

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

The Superintendent of Documents, U.S. Governinent Printing Office, P.O. Box 37082.

Washington, DC 20013 7082 1

3.

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

Referenced docu'nonts available for inspection and copying for a fee from the NRC Public Document Room hclude NRC correspondence and internal NRC memoranda; NRC Office of p

Inspection and Enforcement butletins, circulars, information notices, inspection and investi-gotion notices; Licensee Event Reports; vendor reports and correspondence; Commission papers; and applicant and licensee documents and correspondence.

The following documents in the NUREG series are available for purchase from the GPO Sales Program: formal NRC staff and contractor reports, NRC sponsored conference proceed-ings, and NRC booklets and brochures. Also available are Regulatory Guides, NRC regula-tions in the Code of Federal Regulations, and Nuclear Regulatory Commission issuarmes.

Documents available from the National Technical Information Service include NUREG series reports and technical reports prepared by other federal agencies and reports prepared by the Atomic Energy Commission, forerunner agency to the Nuclear Regulatory Commission.

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

Documonts such as theses, dissertations, foreign reports and translations, and non-NRC conference proceedings are available for purchase from the organization sponsoring the publication cited.

Single copios of NRC draft reports are available free, to the extent of supply, upon written request to the Office of information Resources Management, Distribution Section, U.S.

Nuclear Regulatory Commission, Washington, DC 20555.

Copios of industry codos and standards used in a substantivo manner in the NRC regulatory process are maintained at the NRC Library, 7920 Norfolk Avenue, Bethesda, Maryland, and are available thoro for reference use by the public. Codes and standards are usually copy-righted and may be purchased from the originating organization or, if they are American National Standards, from the American National Standards Institute,1430 Broadway, New York. NY 10018.

l NUREG-1377 Rev.1 NRC Research Program on Plant Aging: Listing and Summaries of Reports Issued Through May 1990 Manuscript Completed: May 1990 Date Published: July 1990 N. N. Kondic, E. L 11i11' Division of Engineering Omce of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, DC 20555 i

f. mag

• Program Management, Policy Development, and Analysis Staff I

ABSTRACT

'the U.S. Nuclear Regulatory Commission is conducting the Nuclear Plant Aging Research (NPAR) Program.'Ihis is a comprehensive hardwarc-oriented engineering reseamh program focused on understanding the aging mechanisms of mmponents and systems in nuclear plants. The NPAR program also focuses on methods for simulating and monitoring the aging related degradation of these components and systems. In addition,it provides recom-mendations for effective maintenance to manage aging and for the implementation of the research results in the regulatory prtwess.

'Ihis document contains a listing and index of reports generated in the NPAR Program that were issued through May 1990 and summaries of those reports. Each summary describes the elements of the research etwered in the report and outlines the significant results. For the convenience of the user, the reports arc indexed by personal author, corporate author, and subject.

b til NUREG-1377 A

4 i

I t

i t

Contents Page Abstract.................................................................................

iii Preface.................................................................................

sil Acknowledgeme nt........................................................................

is lit rod uction.............................................................................

I Main Citations And Su mmaries.............................................................

3 Personal AuthorIndex 35 Corporat e Au t hor I ndex....................................................................

43 S u bj ect i ndex............................................................................

47 Chronological listing 53 v

NUREG-1377

I I

PREFACE The Officc of Nuclear tlegulatory llescatch of thc U.S.

ating system. level aging effects based on operating Nuclear llegulatory Commission (NilC) is conducting experience and risk evaluation of the aging phenomena a hardware oriented engineering research program has been largely completed. Significant accomplish.

dealing with the aging of nuclear power plant compo-ments have included identifying major technical safety nents and systems. 'Ihis program is described in issues and defining the risk significance of major light NUlti!O-Il44, Itev,1,

• Nuclear Plant Aging fle-water reactor components and structures for applica-Search (NPAlt) Program Plan," published in Septem-tion to plant life extension and license renewal, ber 1987.

'this document contains summaries of NitC sponsored Significant progress has been made in defining aging reports that were generated in the NPAlt Program.

degradation mechanisms and in developing effective I!ach summary describes thc objectives of the research, inonitoring and surveillance methods for many of the identifies the contractor and the authors involved, and components and systems identified in NUltl!O-ll44, outlines significant research results. If the readers of itev,1,'lhese components and systems include motor-this document need additional information on a par-operated valves, check valves, solenoid operated ticular report and the findings discussed therein, they valves, electric motors, emergency diesel generators, are encouraged to contact the authors directly, chargers and inverters, circuit breakers and relays, bat-teries, auxiliary feedwater pumps, and reactor protec-

'lhis report is updated annually to incorporate summa-tion systems. Progress has also been made in develop-ties of new NPAll reports. Comments are welcome ing models and approaches to evaluate the relative and will be considered in developing subsequent revi-impact of aging on risk.'the Phase I research for eval sions of this document.

4%

hh ton 'agins, Chief lilectrical & hicchanical lingineering Ilranch Division of lingineering Office of Nuclear llegulatory ltescarch vii NUlt!!O-1377

ACKNOWLEDGEMENT The following valuable contributions to the preparation of this document are appreciated:

Members of III!S lilectrical & Mechanical lingineering tiranch, in particular M. Vagins for suggestions and advice and J. Vora with the other Nuclear I'lant Aging flescarch program managers for their timely inputs.

The lilectronic Composition Services Section for expeditious and high quality processing of the text and the litiS/Dl! secretarial staff, in particular, !!.11awkins and !!. Ilodge for their effort on the manuscript.

ix NUlti!G-1377 o

_A_______

~v INTRODUCTION This document is a listing and index of reports re-tifiable, recommendations are made for improve-lated to the Nuclear Plant Aging itescarch (NPAll) ments. '!he information contained in the reports Program issued through May 1990. The first listing is in should be of interest to those assessing the aging and alphanutneric order by report number and includes a reliability of nuclear power plant components,includ-summary of each report.'Ihree indexes are provided to ing rescarchers and designers as well as rnaintenance aid the user in retrieving a specific report: Personal and operations personnel.

Author Index, Corporate Author index, and Subject index. Finally, there is a listing in chronological order Most of the documents cited in this report are avail-by date of publication.

able from one of the following sources:

Most of the reports contain a description of the 3,.Ihe NitC Public Document iloom, 21201.

components or systems bemg examined and identify Street NW., lower level, Washington, DC, the prmeipal stressors leading to agmg. Ihey fre-cluently contain an analysis and Statistical assersment

2. 'lhe Superintendent of Documents,U.S. Gov-of failure data obtained from 1.icensee livent lleports ernment Printing Office, Post Office flox and other sources of component failure data for oper.

37082, Washington, DC 20013-7082.

ating nuclear power plants. Current surveillance and

3. 'the National Technical Information Service, monitoring practices are also reviewed and, when iden-Springfield, VA 22161.

1 NUltliG-1377 I

1

1 i

MAIN CITATIONS AND SUMMARIES i

1 1hc reports listed in this compilation are arranged alphanumerically by report number, with unnum-bered reports preceding the numbered reports.'the bibliographic information is followed by a summary of each report, UNNUMBERED REPORTS rics of 14 reports are presented in this publication.

1hus the results of these studies are made more readily Letter Report, M. Subudhi," Review of Aging;Scismic available for rapid survey, directing attemion to spe-i Cortclation Studies on Nuclear Plant Equipment,"

cific reports of intcrest and facilitating the utilit.ation of 4

llrookhaven National labomtory, January 1985.

research results in the regulatory process.

During the last decade, the issue relating to aging-1hc 14 reports are grouped into three categories:

. seismic cortclation of nuclear. grade equipment and (1) carly scoping and background studies, including a '

4 their components has received special attention by survey of aged power plant facilitics, operating experi-both the NRC and the utility industry with the aim of ence teviews of Ileensee I! vent Reports (LER$) to preventing catastrophic failures of aged nuclear power identify aging trends, workshops to obtain experts' plant components during a scismic event. This report opinions, and aging / risk considerations

(2) reports on summarizes the work performed by the Seismic Quall-developing a methodology for aging analysis and on fication Utilitics Group (SQUG) based on real carth-cvaluation and use of a signature analysis technique quake data, by NUTliCil for Sandia National Labora-(MOVATS); and (3) Phase I results of aging research tories, and by !!PRI at Wyle, liased on the above, an on nine components, including electric motors, battery outline of the work to be carried out at ilNL under the chargers / inverters, electrical cables, pressure trans-NPAll scope relating to identifying the aged comle mitters, diesel generators, motor opered valves, nents sensitive to scismic loadings is provided, check valves, auxiliary feedwater pumps, and snubbers.

!!Oll, Inc., sponsored by the Scismic Qualification I!ach summary has four sections: llackground, Sum.

Utilities Group has gathered a comparative data base mary, Results/ Findings, and Utilization of Research on the performance of equipment in five fossil. fueled Results in the Regulatory Process, plants consisting of 24 units and a high voltage DC to-1his teport is considered a "living" document.1 hat AC converter station.These plants have experienced is, research results and summaries of additional sc-four damaging California carthquakes o! Richter Mag-lected reports may be added periodically,

' nitudes 5.1 to 6.6. Peak horizontal ground accelera-Technical Integration Review Groufor i for Aging and I.lfe tions(PG A)of these carthquakes nmged between 0.2 g MWs 11RGALEX),

• Plan and 0.5 g.1hc actual carthquake induced effects on A 'ing and Life-lixtension Activitics," (.S. Nuclear b

equ pment were compared with equipment qualifica-gegulatory Commission, May 1987, tion data from three nuclear plants.

'lhe Technicat integration Review Group for Aging 1hc objective of the pMot progrttm was to deter

• and Life lixtension (I'litOALEX) was established to mine the feasibility of establishing criteria for assessinR facilitate the planning and integration of NRC activi-the scismic adequacy of equipment in nuclear powei tics related to reactor aging and life extension. The giants based on evaluation and application of data to be initial objectives of TlRO ALliX were to identify tech-acquired on the characteristics and seismic perform-nical safety and regulatory policy issues related to reac-ance of equipment in nonnuclear power facilitics that tor aging and life extension and to develop a plan to -

have been subjected to strong motion carthquakes.

integrate NRC and external activities to resolve the

- Application of the criteria would provide a valid basis issues.'Ihis report contains the plan developed by TIR-for assessing the need for subsequent qualification ef-GALEX, which consists of the following main ele-forts in the nuclear industry and for defining the extent ments:

< of the effort, A summary and discussion of the major techni-e Letter Refubmitted in Connection with the Nucleart, l N. Rib," Summaries of Research Re-ill e tor n li e

ports An overview of ongoing programs and activitics Plant Aging Research (NPAR) Program," lingineer.

ing and Economics Research, Inc. (til!R), Reston, related to reactor aging and life extension, in-

' VA, September,1986, cluding both NRC and external programs and Jihe results of Phase I cfforts in the NRC NPAR activitics, i

e itecommendations for future NRC actions to I

program for selected electrical and mechanical compo-nents since 1984 have been published. To help main-address reactor aging and life extension in a i

tain cognizance of this wealth of information, summa-timely, efficicut, and well integrated manner, w

3

. NURiiG-1377 L

in XL w

Main Citations and Summaries NUMBERED REPORTS an carthquake frequency. Scismic testing was per-formed with a motor teth unloaded and loaded by an BNI, Technical Report A-3270-II-26-It4,11. Miller, attached hydraulic pump that served as a dynamome.

"Scopig l'est on Co,ntainment Pur{c and Vent ter. SignPicant operating parameters such as current, Decem r i St.

whage, ad temperaWre were monitored before, dur-ing, and af ser scismic loading, and no noticeable differ.

Degradation of shaft scal material used m.contain*

ences were observed. F.xisting deficiencies in one of the ment purge and vent butterfly valves may initiate valve motor bearings and in the stator winding were not seal leakage thus breaching containment. A scoping affected or magnified by the seismic excitations, test was performed to gather information on the be-

.lhin p describes the test plan, includes details havior of the seal material (cthylene propylene)when of the pmcedure, and presents findings of the scismic exposed to severe accident conditions (i.e., steam at

. tests and operating / static tests on both motors.

350'F/120 psig and 400'F/232 psig). Three separate test sequencc8 were performed with the test assembly

,this testing was part of the NRC NPAR program, monitored for leakage. The results of these tests re-and its results are an mtegral part of the llrookhaven vealed no seal leakaget however, shaft. seal degrada.

National l aboratory's overall agmg assessment of mo-tion was evident, lors, which was published as NURl!G/CR-4156.

l'or two test sequences, the prescribed procedure llNI. Technical Report A-3270-12-85, M. M. Silver, was revised to include modified temperature profiles R. Vasudevan, and M. Subudhi, " pilot Assessment:

and scal testing sequences.

Impact of Aging on the S,cismic Performance of Sc.

lected Equipment Types, llrookhaven National Removal and inspection of the valve seat following Iaboratory, December 1985.

r,ome test sequences revealed minor remolding of the

'the NRC has initiated a number of specific re-seat material at the disc /imdy interface with no de' scarch programsin support of the NPAR program, to formities noted. Approximately one week later, cracks better understand the impact of equipment aging on developed in the scut. The cracks were in an area that plant safety and to recommend reahstic operating and would be compressed by the retaining ring and in no maintenance procedures to improve plant availability instance affected the scaling integrity of the valve.

and enhance safety.This pilot study was perforrned to The results of the scoping test revealed no shaft.

investigate the feasibility of using plant (-xperience scal leakage. 'the seal degradation and cracking was data to assess the relationship betweca equipment ag-visually evident in the cornpressed retaining portion of ing and scismic performance capacity..

the seat. llowever, the result should not be construed After a brief review of available information on as representing the entire ethylene propylene family plant experience at many California sites for content (clastomers prepared from ethylene and propylene and quality, data related to performance, maintenance, monomers). Varying the relationship of these mono-and failure history were collected for a r. ample set of mers affects the characteristics of the clastometer and equipment types. This pilot study selected the equip-its ability to withstand environmental conditions. It ment types for investigation from the highest priority should also be noted that all mechanisms by which group specified in a previous NPAR study,'lhe equip-rubber deteriorates with time are attributable to envi-ment types studied were electric motors, motor-ronmental conditions. 'Ihe. Parker Seal Company operated valves, relays, circuit breakers, and motor states that it is environment, not age, that is significant control centers.

to seal life, both in storage and in actual servicci

• the acquired equipment data consisted of installa-IINi, Technical He rt A-3270-ll-145, J.11. Taylor, tion date, chronological listing of preventive and cor.

rective maintenance activities, failed state and cause of M. Subudhi, J, igins, J. Curreri, M. Reich, F. Cifuentes, and 1. Nehring, "Scismic lindurance failure, carthquake data (i.e., free field acceleration, i

Tests of Naturally Aged Small Electric Motors,"

Richter magnitude, date), and equipment status befesc.

Ilrookhaven National 14aboratory, November 1985.

and after the carthquake, Two naturally aged 10-IIP electric motors were The pilot study was successful in demonstrating obtained from an older nucicar power plant that is that experience data can be extracted and utilized to i

ready for decommissioning. The motors were utiliecd address the relationship between scismic performance to drive fan cooler units in an outside environment for capacity and aging of plant equipment, it is strongly 12 years. 'lhese motors were first tested for their dy-recommended that future research be conducted to

.namic characteristics. 'lhey both were subjected to acquire experience data for other important equip-u scismic excitation with generic floor resptmse spectra ment types and to investigate other California power

(GFRS) that encompass Safe Shutdown liarthquake plants. Such research will provide the maximum (SSE) accelerations applicable to most nuclear plants amount of actual experience data to address the aging-in the United States. The tests showed that the first seismic relationship in a practical manner, lessons fundamental frequency is well above the rigid range of learned from a review of these data can be used as 4

NURl!G-1377 l

e

.n a

r L

i htin Citations and S~mmaries i

input to develop practical maintenance and opera-

'the plan discusses the criteria for prioritizing plant, 5

ting procedures to enhance safety and improve plant system, and component selection for analysis to deter-reliability, mine the effects of aging.'the use of failure modes and cffccts analysis in conjunction with the results of natu.

BNL Technical Report A-3270 3-86. A. C. Sugarman, ral and accelerated aging tests arc discussed as means ht. W. Sheets, and M. Subudhi " Testing Program for understanding and predicting the phenomena.'lhe for the Monitoring of Degradation in a Contlnuous effects of aging on the failure rates of components are Duty 460 Volt Class ll",10 IIP lilectric Motor,'

being determined principally from plant data with a

Ilrookhaven National I aboratory, h1 arch 1986, physical and phenomenological models used for inter-

• fhis report presents an evaluation of potential polation in areas not included in the data basc. 'these maintenance techniques for monitoring age related results will be integrated with a plant risk model to be degradation in a continuous-duty 460 volt, Class II, used in addressing the question "how old is old 10, IIP clectric motor. The program follows up the enough."

(

analyses and recommendations outlined in the draft

'Ihc NRC NPAR program has completed several L

of NUREO/CR.4156,

• Operating thpen,ence and component level aging assessments that include the Aging Scismic Assessment of lilectric Motors, by identification of dominant compenent failurc modes M. Subudhi el al. In this study, the following stressors based on plant operating experience.*lhe studies pro-t on dielectrics are evaluated: temperature, frequent v de recommendations for monitoring as well as miti-starts, overload, and high vpttage gradient.

gating age related component degradations, in general, the motor tests are conducted by con.

Utilizing results from the component level studies tinuously reversing motor direction for five hours, fol-and work performed by other NRC contractors for lowed by a half hour with the motor runn ng under no system data assessment and system level risk analysis, i

load in a single direction and a half hour with the motor this program evaluates the impact of component fall-turned off and stationary. During the half, hour of ren-ures on plant system performance.'lhe study performs ning under no load, measurements of bearmg vibration in depth system level failure data reviews, evaluates i

and movement of stator end turns (measured with ac-current industry practices for system maintenance, celerometers epoxied to the end turns) were made, testing, and operation and probabilistic risk assessment Also, a number of insulation tests were conducted.To (pRA) techniques to understand and to predict the accelerate the degradation of the test motor (includinS mpact of aging on system avail thility. Recommenda-insulation, bearings, and lubrication), a plug reverse tions for improving the system performance by means test was performed.

of degradation monitoring and timely preventive and

'the result's of the exploratory testing program re-corrective maintenance are addressed, 'Ihis project vealed which insulation and bearing tests can best be integrates its prmlucts with the llNL programs it r op.

used in utilities' procedures for preventive mainte.

crational safety reliability research and performance nance, corrective maintenance, and surveillance for indicators.

safety related motors.

The first phase of this research effort concentrates -

This testing is meant for motors rated for contin-on understanding various system designs from plant uous use. A separate test plan will be required for safety analysis reports, evaluating failure data from intermittent duty motors (e.g., valve actuator motors);

plant operating experience data bases, applying PRA such a plan should include typical valve actuator tests analyses, assessing industry wide surveillance and such as the open/close cycling test and the insulation maintenance practices, and identifying system func.

tests discussed in Section 4.0 of the presently reported tional indicators that are used to monitor the rate of

program, system degradation resulting from aging and service wear The program separates failures on demand from BNL Technical Report A-3270-12-86, R. Fullwomi, time dependent failures. It categorizes age related J. C liig ins, M. Subudhi, and J.11. Taylor, "A ing failures separately from random and design type fail-and Life htension Assessment Propram (ALE I) ures. It produces results useful for the resolution of-Systems Level Plan," 11rookhaven National I;ibora-pertinent unresolved safety issues and for review and tory, December 1986.

nspection of operating NPPs. The second phase, if This system level program plan for Ati!AP pre-authorized and performed, will provide recommenda-4 sents and explains the llNL structured approach to tions for improving system performance through en-assessing the effects of the aging of nuclear power hanced maintenance practices and reliability monitor-plant components and systems on safe operation and ing, which will be focused on the most risk sensitive the extension of plant operation beyond the originally areas of a system. Recommendations are made for planned plant life, it should be noted that this plan is improvements in pertinent regulatory guides, industry prepared in a generic fashion and could be used by standards, etc. 'this program plan delineates the goals anyone for a system assessment.

and major tasks to be completed in each phase.The 5

NURHO-1377 q

I' hiain Citations and Summaries current version of the program plan is considered to be "the need for a comprehensive program to identtfy a draft and will be revised and updated as the first few the potential safety problems associated with plant system assessments are completed using this method-aging was stressed. It was suggested that the effects of ology,'lhis will produce a final proven methodology time related degradation on the safety of the complete that can be applied ta the remaining systerns.

reactor system should be evaluated in terms of the risk to the public. One should consider multiple causes that NtlitP.G-1141,11 ht. hiorris and J. P. Yora,

• Nuclear have typically been associated with abnormal occur.

Plant Ag ng Research (NPAR,) Pro ram Plan," U.S.

Nuclear egulatory Commission, J ly 1985.

rences. Since individual component failures create problems, time related degradation will ultimately NURI:G-1144. J. P. Voni,

• Nuclear Plant Aging have to be addressed in terms of maintenance, moni.

Rercatch (NPAlt) Program Plan," Rev. I, U.S.

toring, surveillance, etc., of components.

Nuclear Regulatory Commission, September 1987*

A large number of phenomena that can cause fall-

'lhe Nuclear Plant Aging Research (NPAR) pro-urcs were discussed; a detailed list of parts / materials, gram described in this plan is intended to resolve tech-including lubricants and other additives that must be nical safety issues related to the aging degradation of considered, was given; seemingly minor changes in the electrical and mechanical cornponents, safety and sup-chemical constituents of a material or in the manufac.

port systems, and civil engineering structures used in turing process can cause significant effects and changes commercial nuclear power plants. 'the aging period of in the system during operation (e.g., water chemistry interest includes the period covered by the original effects).

operating license m well as the period of extended plant life that may be requested in utility applications Replacement parts were noted as a potential for license renewals.

source of problems.'ihe effects of storage on parts and the possibility that new parts may be different from the limphasis ha been pIv

? identifying and char

• original ones were mentioned.

acterizing the mechanh

.iterial and component

.lhere were extensive discussions on the limitations

[

degradation during rsen

/.i utilizing the research iesults in the regulator >ym ess.'l he research includes of accelerated aging tests. The use of naturally aged evaluating methods of mspection, surveillance, conds-equipment for test purposes was suggested. Sacrificial tion monitoring, and mamtenance as means of manag-replacement of equipment was identified as a source ing and mitigating aging effects that may affect safe for naturally aged plant equipment.

plant operation. Specifically, the goals of the prograrn hiaintenance and surveillance in plants and their are im relationship to time-related degradation were exten-identify and characterite aging mechanisms and sively discussed.

e effects that could cause degradation of compo' NUREG/CP-0100, A. F. !!eranck,

• Proceedings of the nents, systems, and civd engineering structures International Nuclear Power Plant Aging Sympo-and, if unchecked, impair plant safety, sium," U.S. Nuclear Regulatory Commission, h1 arch Evaluate residual life of components, systems, 1989-and civil structures and identify methods of in-

'lhis report presents the proceedings of the Inter-spection, surveillance, and monitoring that will national Nuclear Power Plant Aging Symposium that ensure timely detection of aging effects before was held at the !!yatt Regency llotel in liethesda, loss of safety functions.

h1aryland, on August 30-31 and September 1,1988, Evaluate the effectiveness of storage, mainten.

• lhe Symposium was presented in cooperation with the e

ance, repair, and replacement practices in miti.

American Nuclear Society, the American Society of gating the rate and extent of degradation caused Civil Engineers, the American Society of hicchanical by aging.

linginects, and the Institute of Elcevical and Electron-ics !!ngineers. 'there were approximately 550 partici.

NUltEG/CP-0036, (Compilation by) 11. E. Hader and pants from 16 countries at the Symposium.

l A.1-lanchey,"Proceedinns of the Workshop on Nuclear Plant Aging," Sandia National Iaborato.

A total of 48 papers were presented in 7 techm.eal ries, SAND 82-2.64C, November 1982.

sessions:

'the objective of the workshop, held August 4-5,

1. Aging Research Programs, 1982, in Hethesda, hiaryland, was to facilitate an ex-

2. Aging of Structures and hiechanical liquip-change of thoughts between the NRC and industry on

ment, time related degradation and its influence on reactor

3. Aging of Electrical Equipment, safety. 'the specific goals were to define the problem,

4. Aging of Systems and Components, to discuss the state of knowledge on aging phenomena,

$. Reliability, and to identify future activities necessary to u nderstand

6. Role of hiaintenance in Aging hianagement, the problem.

7. Aging of Vessels and Steam Generators.

NURl!G-1377 6

L

Main Citations Cnd Summaries NUREG/CR-2641, J. P. Drago. R. J. Ilorkowski, D. I1.

tive maintenance actions obtained directly from nu.

Pike, and F. F. Goldberg, "the in. Plant Reliability clear plant maintenance files. A comprehensive valve Data liase for Nuclear lower Plant Components:

population is also included. *l'his report presents data Data Collection and Methodolog1/1 1-827), July frorn one PWR and one DWR power plant, R

rt," Oak g Nationallaboratory OR

.the report demonstrates the degree of distinction

'the development of a component reliability data and refinement in the rellability statistia that is possi, Imse for use in nuclear power plant probabilistic risk ble with data from the 11,RDS and suggests a general assessments and reliability studies is presented. 'Ihc format Mscbac of sWtakcHaMty stabsMo data rources are the in. plant maintenance work re.

satisfy needs within the nuclear data gathering com.

quest records from a sample of nuclear power plants.

munity. 'the examples given in the various tables and

'this data base is called the in. Plant Reliability Data figures suggest a useful method of comparing valve System (IPRDS). Its features are compa'ed with other data and arc reprewntadw of the &gme to which tc ty stadsdes for any particular valve can be as.

data sources such as the Licensec I! vent Report (LliR) certained.

system, the Nuclear Plant Reliability Data (NPRD) system, and 111111! Standard 500. Generic descriptions One objecu,ve of this report is m examine the im.

of nuclear power plant systems formulated for IPRDS pmvement possible using IPRDS in refining the statts-are outlined in the text, ties to ultimately focus on the reliability of particular

'#E#" "

""'" "I# * " " Y""

"E "the major objective of the program described is to ennmnments. Anotkr @cun is to genemte emn.

provide an improved multipurpose data base. Compw nents of each t)oI c of NSSS are included in the data to the efficacy of the suggested formats for document.

base, ing valve information and the various methods used for in addition to providing information on past fallute comparison in this report.

rates and component down times, the IPRDS may be

'Ihc report gives breakdowns of failure rates by used for:

failure modes and by failure causes showing calculated revising component test mtervals and allowable maintenance frequencies and repair times. IPRDS re.

e down times; pair time distributions, although unavailable from identifying generic problems and recurring fall.

111Rs, are also presented and evaluated, e

utes; Preliminary results obtalned from the pilot data identifying the variables (e.g., environment, ogw base in this report indicate WASl1-1400 statistics to be e

crating mode, system, maintenance polky, etc.)

nonconservative in reliability estimates for some valve that control component failure rates; types in certain failure modes.

providing an extensive data base against which NOREG/CR-3543, O.- A. Mu 1, R.11. Gallaher, e

to comparc existing data sources (e.g., Ll!Rs M. I. Casada and 11. C. I

,"Surve of Operating lix criences from LliRs to entify ing 'I rends,'

and NPRDs) to assess the degree to which these Oa{ Ridge National imboratory,01 L-NSIC-216, data sources accurately reflect the actual com.

January 984.

ponent reliability;.

'lhis report describes the preliminary results of an e correlating current incidents with previous fail-utes, allowing for extrapolation in the near fu-related failures available in operatm, hn@ngage assmment oNn mat n perunm t g expenence re-ture.

ports. 'this assessment, by the Nuclear Operations identifying trends and patterns in the fail

• Analysis Center (NOAC) at Oak Ridge National latxw e

ute characterisucs of particular components or ratory, utilized the computerited files of Licensec aggregations of compments; and

!! vent Reports (LliRs) and their predecessors to exam.

identifying failure mechanisms over time for use inc age.related degradation of safety.related equip-e in defining the aging requirements for compo-ment.

nent qualification.

Abstracts of operating experience reports from NUREG/CR-3154. R. J. llorkowski, W. K. Kahl, T.1.

commercial power plants reported from 1969 to 1982 liebble,1. R. I'ragola, and J. W. Johnson, "t he in.

were surveyed. Over 7000 cvents were reviewed. Data Plant Reliability Data liase for Nuclear Plant Com.

included the system, comp ment subpart, the age.

ponents: Inteiim Report 'the Valve Component." '

related failure mechanism, the severity, and the Oak Ridge Nationallaboratory ORNt/I'M-8647, method of detcetion of the failure. Wear, corrosion.

December 1983.

crud, and fatigue were the identified failure mecha.

this document details the collection and prelimi-nisms in over one third of the 3098 arc related events.

nary analyses of data related to valves in the in Plant About two-thirds of the failure severities were judged Reliability Data System (IPRDS). *lhe data base is as a degraded state, and one third were judged as cata.

developed primarily from historical records of correc-strophic failures. Pump and valve problems made up 7

NURl!G-1377

l l

hialn Citations end Summaries almost 307o of the failed components. Almost two-direct relationship between the failure and the failure thirds of the reported failures were detected by routine mechanism. Thus the emphasis of the program was surveillance testing indicating that such practices are redirected toward exploring the relationship of the effective techniques for moaitoring and detecting age failure to the failure mechanism.

degradation of discrete components and systems. A

'the usults of this preliminary investigation indi-substantial number of events resulted from setpoint cated that about 707c of the significant failures re-

drift, rted for the fluid systems analyzed were due to only NURI:G/CR-3818, N. II. Clark and D.1. Ilerry, "Re, our failure mechanisms (causesh crosion, corrosion, port of Results of Nuclear Power Plant Agmg vibration, and for eign materials. Ihis was subsequently Workshop " Sandia National laboratories, verified by detailed study of several more plant systems SANDS 4-0374, August 1984, and corroborated by field data obtained from person.

'the objective of the workshops was to identify nel interviews. In addition, there appears to be a strong whether there is any evidence of component or strue-conclation between the cause of component failure tural time related degradation,i.e., aging problems, in and the system m which the component operates.

a nuclear power plant and, if so, what problems are of

'the survey points out, with evidence, that the iden-greatest importance, l'ifteen representatives from na-tification and climination of the system level causes of tional laboratories, architect / engineers, nuclear steam component failures is a viable approach to preventing supply system vendors, research firms, and one univer-and mitigating the major reported aging effects.

sity participated. Questionnaires and group discussions screened over 112 components believed to be suscepti-NURL:G/CR-39%, hi, R. Dinsel, ht. R. Donaldson, and ble to excessive aging; pressure and temperature sen.

1; T. Soberano, "In Situ Testing of the Shippingport hors, valve operators, and snubbers emerged by con.

Atomic Power Station Illectrical Circuits," Idaho sensus as the most important. Potential aging problems Nationallingineering Iaboratory,!!O0-2443, April N

related to off normal common mode cifects or prob-lems that were just developing at the time were outside

'ihis report discusses the results of electrical in situ the scope of the workshops because little or no first-testing of selected circuits and components at the Ship.

hand experience was available for these off normal or pinpport Atomic Pow er Station in Shippingport, Penn-yet to-be explored circumstances. Recommendations sylvania.%c goal was to determine the extent of aging are made for a systematic approach to rating compo-or degradation of various circuits from the original nents in terms of overall safety and for a cooperative plant and the two major core plant upgrades (repre-effort between industry research groups and regulatory senting a total of three distinct age groups)as well as to research groups to resolve known aging problems and evaluate previously developed surveillance technol-toidentifyoff normatoryct to developagingissues.In ogy. 'the electrical testing was performed using the addition to some well known aging mechanisms (e.g.,

lilectrical Circuit Characterization and Diagnostic neutron embrittlement of pressure vessels) or prob-(IICCAD) system developed by 110&O for the U.S.

lems that manifest themselves as equipment failures Department of linergy to use at Th11-2. Testing in-(e.g., steam generator tube degradation), there is con-ciuded measuremenis of voltage, effective series ca-cern that other types of aging problems may be devel-pacitance, effective series inductance, impedance, oping. Their effects increase as nuclear power plants effective scries resistance, de resistance, insulation re-get older, and some aging processes could eventually sistance, and time-domain reflectometry (l'DR) pa-affect power plant availability or safety.

rameters. The circuits evaluated included pressurizer heaters, control rod position indicator cables, miscella.

NURl!G/CR-3819, J. A. Rose, R. Steele, Jr., K. G.

neous primary system resistance temperature detec-DeWall, and 11. C. Cornwell, " Survey of Aged

."E tors (RTDs). nuclear instrumentation cables, and INratr),li l'7, J safety injection system motor operated valves. It should be noted that the operability of these circuits The survey concentrated on component failures m.

was tested seveiaiyears after plant operation was con-LWR safety related systems as determined from oper-cluded at Shippingport. There was no need to retain ating histories. Only failures that were determined to the circuits in working condition following plant shut-bc age related were meluded.

down, so no effort was expended for that purpose.nc The age related failure information gathered from in situ measurements and analysis of the data con-the plant histories was analyzed for reoccurring failure firmed the effectiveness of the liCCAD system for patterns, liarly program emphasis was on isolating spe-detecting degradation of circuit connections and cific equipment with high failure rates that were not splices along the high resistance paths; most of the already the concern of other research efforts. The re-problems were caused by corrosion. Results indicate a sulting (gathered) data could not support the identifi-correlation between the chronological age of circuits cation of specific equipment. It did, however, imply a and circuit degradation.

NURiiG-1377 8

i-htin Cit;tions cnd Summaries NUREG/CR-4144. T, Davis, A. Shafaghi, R. Kurth, and NUREG/CR-4234, W. L Greenstreet, G. A. hiurphyf F. lxverenz, *1mportance Ranking Based on Aging and D. M. Eissenberg, "d vafves Used in Engi-Aring and Senice Wear o Consideration of Comp"onents included in Probabil.

Electric hiotor Operate istic Risk Assessmenth. Pacific Northwest labora-nected Safety Feature S stems of Nuclear Power tory, PNtr5389, April 1985.

Plants " Vol.1. Oak Rid c National laboratory, ORNtr6170/V1, June 1 85, i

The method outlined in the report ranks power

.Ihis report deals with motor operated valves, fo-i plant components by using a risk duc to aging sensitiv.

cusing on monitoring defects and degradation of nu-i ity measure that describes the change in risk due changes in component failure rate (without describ, to clear plant safety equipment.*Ihc contents include the mg evaluation and identification of practical and cost-closely the aging phenomena and the resulting time-cffective methods for detecting, monitoring, and as-dependent component failure rate).

sessing the severity, failure modes, and causes (mainly

'Ihc output from this study can be combined with aging and service wear) of time-dependent degrada.

that from other studies (data, analytical or experimen.

tion in nuclear plants. Also being considered are tal) that identify the components most susceptible to manufacturcr recommended maintenance and sur-aging.

veillance practices and the selection of measurable i

parameters (including functional indicators) for use in

'ihe applications use average component unavail*

assessing operational readiness, establishing degrada-ability equations currently empkiyed in probabilistic tion trends, and detecting incipient failures. *lhe re-risk assessment (PRA) to calculatr the risk due to-part's results are based on information derived from aging sensitivity. A more exact calcu'ation is possible by operating experience records, nuclear industry reports, using unavailability equations tha' include the time-manufacturcr supplied information, and input from dependent characteristics of compnent failure rates; architect engineer firms and plant operators, however, these time dependent ct aracteristics are not Failure modes are identified for both the valve and well known. The risk due to.agint senshivity measure the motor operator assembly. For cach failure mode, presented here is therefore segregated from these fa lute causes are listed by subcomponent or sub-time-dependent effects and add esses only the time-assembly, and parameters potentially useful for detect.

independent portion of aging ph nomena.'Ihc results ing degradation that could lead to failure are identified.

identify the components that show the highest poten-tial for risk due to aging phenomena,

,the method emerging from this analysis of the data can provide capabilitics for establishmg degradation

'Ihree operating NSSS were analyzed, and it was trends prior to failure and developing guidance for found that the most risk significant components arc in effective and safe maintenance.

the auxiliary feedwater system, the reactor protection system, and the service water systems, e.g., pumps, NUREG/CR-4234,11. D. Ilaynes, " Aging and Senice check valves, motor operated valves, circuit breakers, Wear of Electric hiotor Operated Valves Used m f'

and actuating circuits.

Engineered Safety-Feature Systems of Nuclear Power Plants: Apmg Assessments and hionitoring Future research on the time dependent portion of hiethod Evaluaticns," Vol. 2 Oak Ridge National aging phenomena for these components is needed to laboratory, ORNL 6170/V2, August 1989.

completely describe the impact on risk.

hiotor operated valves (hiOVs) are located in al.

most all plant fluid systems. 'lheir failures have re-NUREG/CR-4156, hi. Subudhi E. L llurns, and J.11.

suited in significant plant maintenance efforts. hiore Taylor," Operating Experience and Aging Scismic important, the operational readiness of nuclear plant Assessment of Electric hiotors," llrookhaven safety related systems has often been affected by National laboratory, ilNL-NUREO-51861, June hiOV degradation and failure 'lhus, in recent years, 1985.

hiOVs have received considerable attention by the Nuclear Regulatory Commission and the nuclear

. A limited number of electne motor categories with power industry and were identified as a component for direct safety significance were identified, and failures study by the NRC NPAR program. In support of the due to insulation degradation were surveyed.

NPAR Program, a comprehensive Phase 11 aging as-Age sensitive components (with respect to materi, sessment on hiOVs was performed by the Oak Ridge als and design feat ures) were reviewed, potential elec, National laboratory (ORNL), and the results of this trical and mechanical hazards were considered, opera, study are presented in this report, tional and accident stressors were determined, and An evaluation of commercially available h10V monitorable functional indicators were identified.'Ihe monitoring methods was carried out, as well as an as-contribution of pertinent scismic effects was assessed, sessment of other potentially useful techniques.*lhese and failure modes, mechanisms, and causes were re-assessments led to the identification of an effective, viewed from existing data bases.

nonintrusive, and remote technique, motor current 9

NUlti!G-1377

Main Citations Ond Summaries signature analysis (htCSA). The capabilities of moni-for example, diffcrences in motor current signatures of toring methods (especially hiCSA) for detecting similar htOVs that were indicative of control switch changes in operating conditions and h10V degradation setting variations and differences in component wear.

were investigated in controlled laboratory tests at The influences of refurbishing and inactivity on htOV ORN!,in situ hiOV tests at a neighboring nuclear operations were clearly seen in motor current signa-power plant, and the gate valve flow interruption blow-tures as well.

down test in lluntsville, Alabama.

ORNL participated in the gate valve flow interrup.

The background information and the work leading tion blowdown test program carried out under the di-to the selected monitoring rnethod are summarized rection of thc ldaho National Engineering laboratory below. A primary objective of this study was to identify at Wyle laboratories in Huntsville, Alabama.This test effective methods for monitoring the condition of was an excellent opportunity for hiOV diagnostic stud-motor operated valves used in safety related systems ics and, rnore important, a means for determining the of nuclear power plants. In response to a need for influences of high blowdown flow on the operation of improved methods for monitoring h10V condition, boiling water reactor isolation valves.1hc reduction in several systems that use a variety of sensing devices and operating " margin" of a MOV due to the presence of signal processing equipment tmd provide signatures additional valve running loads was imposed by high that yield useful diagnostic information have been de-flow.1his was observed in motor current and torque-veloped in the last few years. As part of the Phase 11 switch angular position signatures, as illustrated in this h10V study, one of the motor operated valve analysis study. In addition, the effects of differential pressure,

& test systems (hiOVKrS) was evaluated in depth, fluid temperature, and line voltage on h10V operation

'lhis evaluation and a description of four other com-were clearly seen, mercially available systems are included in this report.

Ihc report presents information that should be in addition, the type and potential value of ding, useful in resolving hiOV issues concerning the NRC nostic information from many measurable parameters and the nuclear industry. Important areas not covered were determined by ORNL tests using hiOVs by the Phase 11 work are identified, and recommenda.

tions for additional work are included.

mounted on test stands. Ihc selected parameters are (1) valve stem position, (2) valve stem velocity,(3) valve NOREG/CR-4257, S. Ahmed, A. Carfagno, and O. J.

stem strain, (4) torque and limit switch actuation Toman, " Inspection, Surveillance, and hionitoring (times of occurrence),(5) internal and external motor of Electrical Equipment inside Containment of Nu-temperatures, (6) vibration (several locations), G) clear Power Plants-With Applications to Electrical torque switch angular position, and (8) motor current.

Cables," Vol.1. Oak Ridge National Iaboratory, ORN1JSUll/83-28915/1, August 1985.

The tests led to the conclusion that the single most The purpose of this report is to describe currently mformative measurable pr.rameter was also the one available methodology for detecting and determining that was most easily acquired, i.e., the motor current, the emount and rate of age related deterioration of h1CSA was found to provide detailed information re-safety related equipment. The general concepts of lated to the condition of the motor, motor operator, monitoring equipment condition for this purpose are and valve across a wide range of values of parameters described. The goal is to detect deterioration in the and their variations, the recordmg and the analysis can incipient stage, prior to inservice failure and prior to be donc during valve operation to render mformation the point at which equipment can no longer be ex-that characterizes transient and penodic occurrences.

pected to perform its function when exposed to design Several tests were carried out to investigate the basis accident conditions.

capabilitics of monitoring methods (especially hiCS A)

The application of condition monitoring is dis-for detecting changes in operating conditions and cussed specifically for electric cables. The goal is to h10V degradation. Results from selected laboratory determine the degree of cable degradation and to pre-tests presented in the report illustrate examples of (1) dict the remaining useful life. In situ nondestructive valve stem taper, (2) stem nut wear, (3) degraded volt

• testing and destructive laboratory testing are discussed age, (4) degraded valve stem lubrication, (5) worm-gcar as are their limitations. Interim recommendations tooth wear, (6) obstruction in valve seat area, G) motor are given for the implementation of a condition-pinion disengagement, (8) degraded worm and worm-monitoring program for cables.

gear lubrication, (9) stem packing adjustments, and NUREG/CR-4257, O. J. Toman, " Inspection, Surwil-(10) torque-switch settings.

lance, and hionitormg of Electrical Equipment m in situ signature analysis tests were carried out by Nuclear Power Plants. Vol. 2: Pressure Transmit-ORNL on a total of 20 aged hiOVs at a neighboring ters," Oak Ridge National laboratory, ORNI) nuclear power plant. Five of these h10Vs were later SUll/83-28915/3/V2, August 1986.

rclested after they were refurbished. Selected results This report describes the types of pressure trans-from these tests are presented in this report and show, mitters commonly used in nuclear power plants l

NUREO-1377 10

Main Cit:tions and Summaries I

t i

according to their application.The stresses that affect cacy of existing tests in determining the effects of aging these transmitters include ambient temperature, hu-and degradation mechanisms. 'these tests include r'

midity, radiation, process (fluid) medium pressure, and breakaway force, drag force, velocity / acceleration temperaturc.'Ihc most common effects of the stresses range for activation in tension or compression, release on the transmitters are calibration shifts. "Ihc evalu-rates within specified tension / compression limits, and ation of failure data contained in IJcensec Event restricted thermal movement. The snubber operating f

Reports indicates that total failure of pressure trans-experience was reviewed using licensec event reports mitters occurs relatively infrequently, and other historical data for a period of more than 10 Cornparison of as found and as lef t calibration data years. Data were statistically analyzed using arbitrary is described as a partial means of evaluating the level of snubber populations. Value impact was considered in deterioration of a transmitter. Care must be taken to terms of exposure to a radioactive environmer:t for l

. ensure that variations in method or procedure do not examination / testing and in terms of the influence of produce erroneous data and wrong conclusions. 'the lost snubber function and subsequent testing program precision of the comparative measurements must also expansion on the costs and operation of a nuclear i

power plant.'the implications of the observed trends be high.

were assessed; recommendations include modifying or i

'!he evaluation of calibration data alone will not improving the examination and testing procedures to ensure the capability of operating under design basis enhance snubber reliability. Optimitation of snubber i

accident conditions. II, with time, steam or moisture populad ns5c We nmovalof unnecesery snub-penetrates the transmitter housing, the transmitter bers was also considered, clectronics will becorac inaccurate and may fail.'lhere-fore, the integrity of the housing scal must also be NUREG/CR-4302, W.1. Greenstreet O. A. Murphy, cvaluatid periodically to be able to predict continued Aging and R. II. Gallaher, and D. M. Eissenberg, "lingmected Senice Wear of Check Valves Ur.ed m

- performance capability.

A livaluation of inservice failures is recommended to SafetyFeature stems of Nuclear Power Plants "

Vol.1. Oak Rid National laboratory, allow further differentiation between sudden failures ORNir6193/V, December 1985, (having no precursor) and failures that c;m be detected in the incipient state. Such evaluations would aid in the

'the report addresses detecting defects and moni.

further development of monitoring techniques. Ile-toring the degradation of nuclear plant safety equip-cause some of the transmitter failures are of the sud.

ment. *lhe program is concerned with identifying and den type, periodic operability checks are an important evaluating practical and cost effective methods for de-means of detecting failures very soon after their occur-tecting, monitoring, and assessing the severity of time-rence so that a significant number of failed (inactive or dependent degradation (aging and se vice wear) of inaccurate) transmitters do not remain undetected.

check valves in nuclear plants. 'lhese methods will A combination of operability monitoring and condi, allow degradation trends to be detected prior to failurc 1

tion monitoring may be used to improve the probab!!ity and allow guidance for effective maintenance to be of successfully weathering aging processes and acci-developed.

dent conditions.

"the topics considered are failure modes and causes E

• "E "E ""

NUREG/CR-4279' S 11 Ilush' P O Ileas!er and recommended mamtenanec and surveillanec practices, U

rid te fn c u$c s

$ fey-d and measurable, parameters (including functional indi.

cators) for use m assessmg operational readmess, es-Piping and Components of Nuclear Power Plants "

Vol.1. Pacific Northwest laboratory, PNI.-5479, tablishing degradation trends, and detecting incipient February 1986.

failure. 'Ihc results presented are based on informa-tion derived from operating experience records, nu-

'this report presents an overview of hydraulic and clear industry reports, manufacturer supplied infor-mechanical snubbers used on nuclear piping systems mation, and plant operators, and components. 'lhe functions and functional re-quirements of snubbers are outlined.The real versus Failure modes for check valves are identified and l

perceived need for snubbers is reviewed based primar.

are examined by identifying methods for detceting fail.

ily on studies conducted by a Pressure Vessel Research urcs and differentiating between their causes. For cach Committee. Tests conducted to qualify snubbers, to failure mode, failure causes are listed by component or accept them on a case by case basis, and to. stablish subassembly, and parameters potentially useful for de-c their fitness for continued operation are reviewed.

tecting degradation that could icad to failure are tabu.

lated.

'this report had Iwo primary purposes:(1) to assess the effects of various aging mechanisms on hydraulic The report also identifies parameters potentially and mechanical snubber operation (e.g., leaking of useful for enhancing the detection of degradation and 3

seals. functional failures) and (2) to determine the effi-incipient failure: t! ese parameters include dimensions, 11 NURiiG-1377 f.

hiain Citations and Summaries bolt torque, noise. appearance, roughness, and objectives of this program are to (1)identtfy c necrns cracking.

related to the aging and senice wear of equipment NUllLG/ Cit-4380. J. I Crowley and D. hl. I!issenbeg operating in nuclear power plants,(2) assess their pos-

"livaluation of the hiotor O crated Valve Analy6 sib!c impact on plant safety, (3) identify effective in-and Test System (hiOVATS to Detect Degrada-spection, surveillance, and rnonitoring methods, and tion, incorrect Adjustments, and Other Abnormali.

(4) recommend suitable maintenance practices to miti-ties in hiotor Operated Valves." Oak Ridge gate aging related concerns and diminish the rate of National laboratory, ORN!A226, January 1986.

degradation due to aging and service wear.

An important aspect of the NPAll program strat.

• lhe designs of battery chargers (3 types)and inver-egy is to demonstrate the utility of condition monitor-ters (4 types) and the materials for their construction ing, signature analysis, and other surveillance methods are reviewed to identify age-sensitive components. Op.

for detecting, differentiating, and trending various crational and accidental stressors are determined, and types of abnormalities in the components so that cor-their effect on promoting aging degradation are as-rective measures can be implemented prior to loss of sessed. Variations in plant electrical designs, as well as safety f unction. A field test program was carried out to systern and component impacts were studied.17ailure evaluate valve signature analysis as a surveillance modes, mechanisms, and causes were reviewed from method to achieve these results as well as to detect operating experience and existing data banks. 'the incorrect adjustments in motor operated valves, the study also considered seismic effects on age degraded technique specified in the title (h10 VATS)is the sub-components of battery chargers and inverters, ject of this report, in situ signature traces were OD-

'the perfortnance indicators that et n be monitored tained in 36 motor operated valves at four nuclear to assess cornponcru deterioration due to aging or piant sites. Described are the test equipment package, other relevant stressors are identified. Conforming the method of obtaining the signatures, and determina-with the NPAR strategy as outlir.ed in the program tions made as a result of analyzing thern. Ilased on the plan, the study also includes a review of current stan-results of the signature analysis technique and those dards and guides, mainteriance programs, and research obtained from the field-test program, the capabilities activities pertaining to safety related battery chargers and limitations of h10 VATS are discussed.

and inverters for nuclear power plants.

NUltEG/CR-4457, J. L lidson and J 11. liardin, NUREG/ Cit-1590, K. R.160pingarner, J. W. Vause,

" Aging of Class 111 !!atteries in Safety Systems of D. A. Dinpce, and J. F Nesbitt," Aging of Nuclear Nuclear Power Plants," Idaho National lingineering Station Diesel Generators: livaluation of Operating laboratory,1100-2488, J uly 1987.

and lixpert !!xperience." Vols. I and 2. Pacific

'Ihis report presents the results of a study of aging Northwest laboratory, PNL-5S32, August 1987, effects on safety-relatcd batteries in nuclear power Pacific Northwest laboratory evaluated opera-plants. *lhe purpose is to evaluate the aging effects tional and expert experience pertaining to the aging caused by battery operation in a nuclear facility and to degradation of diesel generators in nuclear plant sen>.

evaluate maintenance, testing, and monitoring prac-ice. 'lhe research identified and characterized the tices with respect to the effectiveness of these practices contribution of aging to emergency diesel generator in detecting and mitigating the effects of aging. 'the failures.

study follows the NRC NPAR approach and investi-Volume I reviews diesel generator experience to gates the materials used in battery construction. It also identify the systems and components most subject to identifies stressors and aging mechanisms, presents aging degradation and isolates the major causes of fail-operating and testing experience related to aging ef-ure that may affect future operational readiness.

Icets, analyzes battery-failure event reports in various livaluations show that, as plants age, the percentage of data bases, and evaluates recommended maintenance aging related failures increases and failure modes practices. Data bases that were analped included the change. A compilation is presented of recommended NRC's 1.icensee livent Report system, the Institute for corrective actions for the aging related failures identi.

Nuclear Power Operations' Nuclear Plant Reliability fied, and the trend of these failures is discussed. This Data System, the Oak Ridge National laboratory's study also includes a review of current relevant indus-In Plant Reliability Data System, and the S. ht. Stoller try programs, research, and standards. Volume 1 pre-Corporation's Nuclear Power 11xperience data base, sents the results of the Phase I research that identifies NURI'G/CR-4564. W.11. Gunther, ht. Subudhi, and the components and systems most susceptible to aging J. I1. Taylor, " Operating Ilxperience and Aging-degradation and the major causes of such degradation.

Scismic Assessment of flattery Chargers and inver.

Volume 2 reports the results of a workshop held on ters," llrookhaven National laboratory, hiay 28 and 29,1986, with industry representatives to IlNL-NURl!O-51971 June 1986.

discuss the technical issues associated with aging of Dattery chargers and inverters are vital components nuclear service emergency diesel pencrators 'Ihe tech-of the nuclear power plant electrical safety system.The nical issues discussed most extensively were man /

NURI!O-1377 12 1

9

1 i.

[

Main CitationsCnd Summaries machine interfaces, component interfaces, thermal relationship of maintenance to ischi methods is iden-L gradients of startup and cooldown, and the need for an tified. Predictive, preventive, and corrective mainten-accurate industry data base for trend analysis of the ante practices arc discussed and evaluated.

diesel generator systern-Appendices contain a detailed discussion on ISCM methods, failure data base information, auxiliary feed.

NUREG/CR-4597, bl. l Adams and II. hiakay," Aging water pump (AUXFi,) installation lists (location sur.

and Service Wear of Auxiliary Feedwater l' umps for PWR Nuclear Power Plants. Vol.1: Operating vey), a discussion of low flow testing, auxiliary feed-Ilxperience and Failure Identification, Oak Ridge water systern descriptions (with flow 4tiagrams and

- National I.almratory, ORN1.-6282/V1, July 1986.

schemes), AUXFP minimum flow rate criteria, and L

In this report, typical auxiliary feedwater pump fea.

E"ihlines proposed by Westinghouse for full flow tures are described in terms of configuration details, testing. Note:'lhe draft of this Vol. 2 (with the same materials of construction. operating requirements and titic) was issued by Westinghouse Electric Corpora.

males of operation. Failure rnodes and causes due to tion, Generation Technology Systems Division, in aging and service wear are identified and explained.

April 1986, coauthored by D, ht. Kitch, bl. Vuckovich, and measurable parameters (including functional indi.

W. V, Cesarski, and P. J. Sowatskey, y

cators) for potential use in assessing operational readi-NUREG/CR-4652 D. J. Naus. ** Concrete Component ness, establishing degradation trends, and detecting Aging and its Significanec Relative to 1.ife Exten-incipient failures are outlined.

sfon of Nuclear Power Plants " Oak Ridge National A series of measures to correct present deficiencies Iaboratory, ORN1/I'ht-10059, September 1986.

in survelliance, monitoring, and insenice testing prac,

'ihe objectives of this study are to (1) expand upo,n the work that was initiated in the first two Illectne tices is discussed. The main body of the report is sup, pleinented by a nutnber of relevant appendices; in Power Research Institute studics relative to longevity particular, a major appendix is included on engineering and life extension considerations of safety related con-and design information useful to assess operational crete components in light water reactor (1.WR) facili-L readiness, ties and (2) provide background that will logically lead to subsequent development of a methodology for NURI'.G/CR-4597, D ht. Kitch, J, S. Schlonski, P, J.

assessing and predicting the effects of aging on the Sowatskey, and W. V, Cesarski, " Aging and Service performance of concrete-based materials and compo.

Wear of Auxiliaiy Feedwater Pumps for PWR Nu' nents' clear Power Plants. Vol. 2: Aging" Assessments and Applications of safety related concr tc compo.

hionitoring hiethod Evaluations Dak Ridge National laboratory, ORNlr6282/V2, June 1988.

nents to 1.WR technology are identified, and pertinent structures (containment buildings, containment base

'the subjects specified in the title are described and mats, biological shield walls, main building, and auxil-discussed in four major sections; lary buildings) and the materials of which they are

1. Failure causes, constructed (concrete, mild stect reinforcement, pre.

2. Description of inspection, surveillance, and stressing systems, embedments, and anchorages) are condition monitoring (ISCht) methods, vescribed. llistorical performance of concrete compo-

3. livaluation of IScht methods, and nents was established through information presented on concrete longevity and component behavior in both

4. ; Role of maintenance in alleviating aging and l.WR and high temperature gas cooled reactor appil-senice wear, cations. Also, a review of problems mvolymg concrete Failure causes attributable to aging and senice comp (ments in both general civil engineering and nu.

- wear are given and ranked in terms of importance, clear power applications is given. The majority of the Cause identifications are made on the basis of experi' problems identified in conjunction with nuclear power

)

ence, postservice e,xaminations, and in situ assess.

applications were minort they include concrete crack-ments.

ing, concrete voids, or low concrete strengths at an hicasurable parameten; related to failure causes carly age. Five incidents involving 1.WR concrete con-are identified. ISCH 1 methods are specified, and evalu-tainments that atc considered significant arc described ations are made based on Westinghouse experience.

in detail.

On the same basis, recommendations are given on Potential environmental stressors and aging factors -

inspection, surveillance, and condition monitoring, to which 1.WR safety.related components could be f

L*lhe ISCH 1 methods are intended to yield required subjected are identified and discussed in terms of dura-capabilitics for establishing operational readiness as bility factors related to the materials used to fabricate well as for detecting and tracking degradation and its the components 'lhe current technology for detecting trends.

concretc aging phenomena is also presented in terms

'the role of maintenance in alleviating and mitigat-of methods applicable to the particular material system ing aging and service wear effects is discussed, and the that could experience deteriorating effects. Remedial 13 NURl!O-1377 a

l hiain Citati(ms and Summaries measures for the repair or replacement of degraded trol, and logic relays, as well as molded-cas.e and metal.

concrete components and their effectiveness are dis-clad switchgear circuit breakers. Analysis of nuclear cussed. Finally, considerations relative to developing a power plant failure data confirmed that normally ener-damage methodology for assessing the durability fac-gized relays commonly used in safety systems suffer tor, deterioration rates, and prediction of structural from more rapid deterioration than do deencrpized reliability are outlined, relays.'the failures were attributable to coil deteriora.

Conclusions and recommendations of the report tion, changes in dimensions of critical organic com-note the need for (1) obtaining aging data from decom-Ivnents, and changes in characteristics of timing missioned plants, (2) using inservice inspection pro-diaphragms from thermal deterioration. Some of the grams to provide aging trends, (3) developing a meth.

failure modes will prevent fail safe operation. 'Ihe odology to quantitatively and uniformly (i.e., using the electrical controf and mechanical portions of metal-same procedures) assess structural reliability as af.

clad switchycar were found to be more failure prone fected by aging or degradation of structural materials, than the main contacts and are extinguishing systems, and (4) performing research in support of all these Analysis of failure data for circuit breakers and relays needs, la should be stressed that there is no widely indicated a pencral trend of increasing failure rates in accepted standardi/ed methodology for quantifying the period of 6 to 11 years following the start of com.

the condition and capacity of an indnidual concrete mercial operation of the plants. 'Ihc aging interaction structure, study evaluated the interaction of aged relays and cir-cuit breakers in a safety injection system with regard to NUlti:G/ Cit-4692.,0. A. hiurphy and J. W. Cletcher five events requiring the system to Start operation.

11. " Operating laperience lleview of l'ailures of.

gr ilure of redundant trains from common mode fail.

a Power O erated Itclic,f Yahes and lilock \\ alves in ut e of a particular type of circuit breaker or relay is not Nuclear 'ower Plants, Oak Itidpe National l aboratory, OltN!JNO AC-233. October 1987, expected. llowever, the number of different types of

'this report contains a review of nuclear power E"Icntial failures supports the need for a strong plant operating events involving failures of power-mmntenana and edann pmpmm to prnent mub operated relicI valves (POltW) and associated bhick tiple age-related failures from affect, g redundant m

valves (llW).Of the 230 eventsidentified,101 involved ety Wnt POltV mechanical failure, 91 were attributable to NUlti:G/ cit-4731 V. N. Shah and P. I!. hiacDonald, POltV control failure,6 involved design or fabrication "ltesidual 1.ife Assessment of hiajor 1.ight Water of the POltVs, and 32 involved llV failures, The report lleactor Components," Vol.1, Idaho National lingi.

contains a compilation of the POltV and ilV failure neering i ahoratory, l!GO-2469, J une 1987.

events, including failure cause and severity.'lhe events are identified as to plant and valve manufacturer. An NU.lti:G/ Cit-4731, V. N. Shah and P.11. hiacDonald,

.llesidual I.ife Assessment of hia assessment of the need to upgrade POllW and llVs to itcactor Components-Overview,{or IJght Water

• Vol. 2, Idaho safety grade status concludes that such action would National lingmeering laboratory, 110 0 -2469, improve POltV and ilV reliability. *lhe greatest im.

November 19S9.

provement in reliability would result from using newer, lhis report presents an assessment of the aging more reliable POltV designs and improving testing, (time-dependent degradation) of selected major light diagnostics, and maintenance applied to POltVs and water reactor comp (ments and structures. The stres-IIVs, particularly to the llV motor operators. A sum-sors, possible degradation sites and mechanisms, mary of interviews conducted with four POltV manu*

potential failure modes and currently used non.

facturers is also included in the report-destructive examinations, inservice inspection (ISI),

NUlti:G/ Cit-4715 G. J. Toman, V. P. llacanskas, T A.

and life assessment methods are discussed for major Shook, and C. C, Iadlow, " An Aging Assessment light water reactor componer s. Volurne 1 covers of itelay and Circuit lireakers and System Interae.

PWit and llWit pressure vest ils, PWit containment tions," llrookhaven National l aboratory, Franklin structures, PWit reactor coola it piping PWit steam itescarch Center, Philadelphia, PA, generators, llWit recirculation piping, and reactor ilNI.-NUltt!G-52017, June 1987.

pressure vessel supports. Volume 2 covers PWit reac-As part of the NitC NI All program, Franklin lle-tor coolant pumps, PWit pressurifers, PWit pres-search Center analyicd the effects of aging on safety-suriier surge and spray lines, PWit reactor coolant related circuit breakers and relays under contract to system charging and safety injection noules, PWit llrookhaven National l aboramry. Circuit br eakers and feedwater lines, PWit control rod drive mechanisms relays in a PW!( safety injection system were evaluated and reactor internals, llWit containments, ilWit feed.

with respect to the aging caused by system operation.

water and main steam lines, llWit control ral drive The effect of circuit breaker and relay deterioration on mechanisms and reactor internals, PWit and ilWit the ability of the system to perform its safety functions electrical cables and connections, and PWit and ilWit was also evaluated. The study included protective, con-emergency diesel generators. Unresolved technical l

NUltliG-1377 14 6

g

I hiain Cit tions and Sumntries e

issues related to understanding and managing the ag.

NUREG/CR-4769, W,11. Vesely " Risk !! valuations of ing of these major commments, including require.

Aging Phenornena:The Linear Aging Reliability ments for advanced ISI and life assessment methods, hhlcl and its lixtensions." Idaho National lingmeenng 1.aboratory, !!OO-2746, April 1987, are alw discussed, A model for failure rates of light water reactor NUREG/CH-4740,1. C. hteyer,

• Nuclear Plant Aging safety system components due to aging mechanisms Research on Reactor Protection Systems," Idaho has been developed from basic phemenological con.

National fin incering laboratory,1100-2467, siderations. In the treatment, the occurrences of dete-I""""'I b'

rioration are modeled as following a Poisson probabil-j

'this report presents the results of a review of oper-ity process.'lhe severity of damage is allowed to have ating experienec for the reactor inp system (RTS) and any distribution; however, the damage is assumed to the engmected safety feature actualmg system (liS-accumulate independently, Irinally, the fal!ure rate is FAS) reported in licensec t! vent Reports (L11Rs), the modeled as being proportional to the accuniutated Nuclear Power lixperience data base, the Nuclear iamage. Using this treatment, the linear aging failure-plant Reliability Data System, and plant maintenance rate nulclis obtained.The applicability of the linear records.'the purpose of the review was to evaluate the aging model to various mechanisms is discussed. 'the potential significance of aging, including cycling, trips model is also extended to cover nonlinear and depend-and testing, as a contributor to degradation of the R'lh:

ent aging phenomena.The implementation of the lin-and IISI'AS. Tables show the percentage of events for car aging model is demonstrated by applying it to the RTS and ilSFAS classified by cause, components, and aging data collected in the NRC NPAR program.

subcomp(ments for cach of the nuclear steam supply NUREG/CR-4819, V. P. ilacanskas, G. C. Roberts, and system vendors. A tepresentative liabcock and Wilcox O. J.Toman. "Agmg and Senice Wear of Solenoid-plant was selected for detailed study.The NRC NPAR pemte stems of Nuclear g1 ower i,d Valves Und in Safet xperience and guidelines were followed in performing the detailed tants. Vol.1: Operatin study that identified materials susceptible to aging.

Failure identification," Oak Ri National laborn-stressors, environmental factors, and failure modes for tory, ORNl/SUll/83-28915/4/\\ 1. h1 arch 1987.

the RTS and !!SFAS and the relevant generic instru*

An assessment of the types and uses of solenoid-mentation and control systems. Functional indicators operated valves (SOVs)ln nuclear power plant safety-

't of degradation are listed, testing requirements evalu-related service is provided in the report. *lhrough a.

L ated, and regulatory issues discussed.

description of the operation of each SOV combined NUREG/CR-4747,11. hl hl.de and D. G. Satterwhite, with knowledge of nuclear power plant applications.

"An A 'ng Failure Survey of 1.ight Water Reactor and operational occurrences, the significant stressors Safety ystems and Components," Vol.1. Idaho responsible for degradation of SOV performance are Nation I lingineering 1.aboratory,1100-2473, J uly identified. A review of actual operating experience 1987.

(including failure data) leads to the identification of -

NUREG/CR-4747,11. hl. hicale and D. G. Satterwhite, potential nondestructive in situ testing which, if prop-

"An A 'ng Failure Survey of 1.lght Water Reactor erly developed, could provide the methodology for

- Safety ystems and Components," Vol. 2, Idaho monitoring the degmdation of SOVs. Recommenda-Nation I lingineering iahoratory, !!OO-2473, J uly tions are outlined for continuing the study into the test 1988.

methodology development phase.

This report describes the methods, analyses, re-NUREG/CR-4928.11. hl. liasemian, K. hl Petersen, suits, and conclusions of two different aging studies.

T. W. Kerlin, R.1. Anderson and K. !! Ilolbert,

'Ihc first study was a survey of light water reactor con.

"Deg"radation of Nuct:ar Plant Temperature Sen-ponent failures associated with 15 selected safety and sors, Analysis and hicasurement Services Corpora-support systems. Analysts used computerized sorting tion, Knoxville, TN, J une 1987, techniques to classify component failures into generic A program was established and initial tests were failure categories.The second study was a careful exa.

performed to evaluate long-term performance of resis-mination of component failure records to identify and tance temperature detectors (RTDs)of the type used categorize the reported causes of component failures.

in U.S. nuclear power plants.'this report addresses the The systems evaluated in the failure cause analysis effect of aging on R7D calibration accuraev and re-were the auxiliary feedwater, Class 11! clectric power s[xmse time. The Phase I rJort (lasting about distribution, high-pressure injection, and service 6 months) included exposure et 13 safety grade RTD water. Tables and figures indicate the systems and the elements to simulated I.Wr. temperature regimes.

components within the systems that are most affected Full calibrations were perio med initially and monthtl,

' by aging. linginecting insights drawn from the data are sensors were monitueu and cross-checked contin :-

provided, Volume 2 presents all of the Volume i data ously during exposure, and resptmse time tests v 40 from FY-86 combined with the data gathered in performed before and after exposure. Short t a ca'i-FY-87.

bration drifts of as much as 1.8'F(l'C) werc observM 15 NURl!O-1377.-

4 O

s

hiain Citations and Summaries -

i l

l

- Another result w;is that small response times were plants. *Ihe study indicates the kinds of tests to con-essentially unaffected by the testing performed, duct, how and when to conduct them, and to which

'this program has demonstrated that there is a motors the tests should be applied.

sound reason for concern about the accuracy of tem' Iblume 2: FunctionalIndicator Tcsts on a Small perature measurements in nuclear power plants.

Electric Afotor Subjected to Accc/ crated Aging These limited tests should be exptmded in a Phase II A 10-horsepower electric motor was artificially program to mvolve more sensprs and longer exposures to simulated LWR conditions m order to obtain statisti-aged by plug reverse cycling for test purposes. The motor was manufactured in 1967 and was in service at a cally significant data. Such data are needed to establish the length of meaningful testing or replacement inter-commercial nuclear pe ~er plant for twelve years. Vari-ous tests were performed on the motor throughout the vals for safety, grade RIDS. An Important corollary aging process. The motor failed after 3.79 million re-benefit from this expanded pn n would be a better versals (3 seconds per reversal) over seven months of determination of achievable,

ies in RTD call-

bration, testing. Each test parameter was trended to assess its suitability in monitoring aging and service wear degra-NUREG/ Cit-4939, ht. Subudhi, W. E. Gunther, J. I1.

dation in motors. Results and conclusions are discussed

'ibylor, R. Lofaro, K. hl. Skreiner, A. C. Sugarman, relative to the applicability of the tests performed to and hl. W. Sheets, " Improving Motor Rellability in motor maintenance programs of nuclear power plants.

Nuclear Power Plantsf Volume 1: Performance Evaluation and Maintenance Practices; Volume 2:

Iblame 3: Failure Analysis and Diagnostic Tcsts on a Functional Indicator Tests on a Small filectric Naturally Aged large Electric Afotor Motor Subjected to Accelerated Aging; Volume 3:

Stator coils of a naturally failed 400-hp motor from Failure Analysis and Diagnostic Tests on a Naturally the llrookhaven National laboratory test reactor facil.

Aged Electric Motor; Hrookhaven National labora-tory, HNirNUREG-52031, November 1987.

ity were tested for their dielectric integrities. The mo-tor was used to drive the primaty reactor coolant pump lblume 1: Performance Evaluation and Alaintenance for the last 20 years. Maintenance activities on this Practices motor during its entire service life were minimal, with This report presents recommendations for devel-the exception of mcggering it periodically The stator oping a cost effective program for performance evalu-consisted of ninety individual coils, which were sepa-ntion and maintenance of electric motors in nuclear rated for testing. Seven different dielectric tests were power plants. These recommendations are based on performed on the coils. Each set of data from the current industry practices, available techniques for tested coils indicated a spectrum of variation depend-monitoring degradation in motor components, manu-ing on their aging conditions and characteristics. By facturers' recommendations, operating experience, comparing the test data to baseline data, the test meth-and results from two laboratory tests on aged motors, ods were assessed for application to motor mainte-The test results (on a small and a large motor) provide nance programs in nuclear power plants. Alsoincluded

- the basis for recommending the various functionalindi-in this study are results of an investigation to determine cators for maintenance programs.

the cause of this motor's failure.The aged condition of The overall preventive program is separated into a second identical primary pump motor, which is of the two broad areas of activity aimed at mitigating the same age and is presently in operation, is discussed.

potential effects of equipment aging: performance Recommendations relating to the applicability of each evaluation and equipment maintenance.The latterin-of the dielectric test methods to motor maintenance volves actually maintaining the condition of the equip-programs are formulated, ment, while the former involves monitoring degrada.

tion due to agmg. The monitoring methods are further NUREG/CR-4967, L. C. Meyer, " Nuclear Plant A,ging Research on High Pressure injection Systems, categorized as periodic testing, surveillance testing, Idaho National Lngineering Laboratory, continuous monitoring, and inspections.

EGG-2514, August 1989.

This study focuses on relevant methods and proce.

This report presents the results of a review of light

' dures with the goal of maintaining the motors in a water reactor high pressure injection system (HPIS) nuclear facility operationally ready. This includes an operating experience reported in the Nuclear Power evaluation of various functional indicators to deter-Experience Data Hase, Licensee Event Reports mine their suitability for trending assessments when (LERs), the Nuclear Plant Reliability Data System, monitoring the condition of motor components."Ihe and plant records, intrusiveness of tmt methods and the present state of Operating experience of nuc! car power plants was the art for using the test equipment in a plant environ-evaluated to determine the significance of aging-ment are discussed.

related service wear on equipment and its possible implementation of the information provided in this impact on safety. The HPIS and those portions of re-report will improve motor reliability in nuclear power lated systems needed for operation of the HPIS were l

NUREG-1377 16 1

1 A

L

Main Citations and Summaries p

s selected for detailed study in order to evaluate the and renUr the valve inoperable for subsequent safety potential significance of aging as a contributor to the fur-'.L.s.

degradation of that system. Tables show the percent-An extensive investigation was conducted to try to age of significant events for llPIS classified by cause, isolate the cause of the poor performance of the motor

, component, and subcomponent for PWRs and !!WRs.

operator. This investigation included follow on in situ A representative liabcock and Wilcox plant was sc.

tests at ilDR, dynamometer testing of the motor op-lected for detailed study, crator at the Limitorque laboratory, testing of the The NPAR guk!clines provided the framework torque spring at INEI, dynamometer testing of the through which the effect of aging on llPIS was studied, motor alone at the Peericss Motor laboratory, ar:d n and these guidelines were followed throughout the mathematical a alysis of the llDR power circuit.The l

report, which presents an identification of failure investigation identified three causes of the motor-modes, a preliminary identification of failure causes operator's poor performanec: torque spring agirig, due to aging and serTice wear degradation, and a review hcating of the motor windings, and resistance in the de of current inspection, surveillance, and monitoring power cabling at liDR.The investigation also demon-methods, including manufacturer recommended sur.

strated that normal plant testing of valves is not ade-a veillance and maintenance practices. 'lhe detailed quate to ensure proper performance under flow and

.I study identifies materials susceptible to aging, various pressure loads in combination.

l stressors, and environmental factors. Performance pa-During the follow on tests at ilDR, we found that, f

rameters or functional indicators potentially useful in when the valve was subjected to flow loads and pres-detecting degradation are also identified, and prelimi-sure loads in combination, the valve either torqued out nary recommendations are made regarding inspection, in the partially open position, stalled in the partially j

surveillance, and monitoring methods, open position, or stalled in the fully closed position, in addition to the above engineering evaluation, the depending on the load and the torque switch setting.

' components that contributed to sys'.cm unavailability the valve torqued out in the fully closed position only were determined, ar/t the contribution of aging to when pressure and flow loads were very low.

. IIPIS unavailabilito w.s evaluated. 'the unavailability Undersized power supply cabling resulting in high assessment utilized an existing probabiGstic risk assess.

resistance has surfaced as a problem in at least two dc

- ment, the linear aging model, and generic failure data, motor operators in the field. Though the other factors i

contributed to the anomalous performance of the valve NUREG/CR-4977. R. Steele, Jr. ar.d J. G. Arendts, at IIDR, undersized cabling was the main cause 'the "Sil AG Test Senes: Seismic Research on an Aged NRC has recently issued an information notice regard-

' m a Piping (11p)R):

S. tem in ing the issue.

United States Gate Siw

aktor None of the three problems discovered during the

. the Decommissione 8

"B HDR tests and follow on investigation would be de-sY19

$ th, i C

5. -

tected during the normal m plant testing where the 1

valves are subjected to no load or to pressure loads

]

NUREG/CR-4977 R acelc. Jr. at:' '

Arendts, mic P-

• an Aged alonciThe problems are detectable only at higher

-i "Sil AG Test Sen.

System in h)adings, that is, flow loads in combination with pres-United States Ga s -

m

- g (IIDR):

sure loads, where the load slows the motor down to the the Decommissior.

N m.

me Appendices," V(' '.

,' 9w gineering extent that momentum cannot carry the unit through 1

Laboratory, EGl - " '

W complete closure and torqueout.

Thisreportdesc 9 w.uion. results, and NUREG/CR-4985, M. Subudhi, J. I1. Tay: lor, conclusions of the lho.A uetermit i the cause J. Clinton, C. J. Czajkowski, and J. W cks, " Indian of the reduced performance of a naturally a gcd Cranc Point 2 Reactor Coolant Pump Seal Evaluations,"

l gate valve with a Limitorque motor op< utor. The Brookhaven National laboratory, motor operated valve served 25 years in the Ship-IINieNUREG-52095, August 1987.

pingport Atomic Powernat a nsa feedwaterisolation This report summarizes the findings on Westing-valve before being refurbisheti and installed in a piping house reactor coolant pump (RCP) seal performance system in the Heissdampfreaktor(llDR), where valve at Indian Point 2. This study considered a significant operability in typical pressure and temperature emi-number of RCP seal failures. Consolidated Edison in-ronments and during simulated earthquakes was stud.

itiated a research effort to determine the causes of ied. During the test program it was discovered that, these failures and to develop appropriate ameliorative under some hydraulic loadings, the motor operator action to enhance seal reliability.The DNL work is an failed to reach torque levels high enough to open the outgrowth of the first-phase effort performed by Fail-closing torque switch. Failure of the torque switch to ute Analysis Associates. The objectives of the ilNI.

open caused the motor to stall in normal plant service, program are to determine the root causes of seat fail-stalling an operator motor can cause motor burnout ure and to provide recommendations for improving 17 NURilG-1377 A

)

Main Citations and Summaries

- s5al r' e!! ability.This program made notable advances in to allow plant operators to conclude that valve per-understanding the root causes of RCp seal failure, For formance has or has not degraded to the point where the first time, actual failed seals were examined in corrective maintenance becomes necessary.-

+

detall in llNL's hot cell, and laboratory tests were lhe required information is assumed to be obtain.

conducted to determine failure causes. 'lhis report ab!c through analysis of in rush current to the coil of summarizes findings and presents conclusions and ree-the SOV. Various SOVs were tested in an experimen.

ommendellons based on review of plant operating and tal air systern set up in the laboratory, in rush current maintenance data, consultation with Westinghouse data acquired on degraded and new SOVs were ana.

and utilitics, review of prior RCP seal studies (includ-lyzed to determine behavior signature models.

.ing previous llNL work), ad hl and in depth ex-Laborato:y conditions provided the opportunity to aminations of the first twp e'rcyeafused seals simulate perturbations caused by the valve function, received from the plant-which would differ from actuation to actuation. A vis-1 NUREG/CR-4992, G. C Robytv. V. P. flacanskas, an..

ual examination of this time. varying waveform re.

G.J. Toman,"gr and Service Wear of Multi.-

vealed distinct and repeatable variations for different stage Sw!!ches in Safety S ' stems of Nuc! car et anomatics.

Power Plants," Vol.1. Oak Rid e National labora-This technique could identify gross changes and (tity, ORN1/SUll/83-28915/5

1. September 1987.

render characteristic signatures that could be used for An assessment of the types and uses of multistage various comparisons and to trend valve degradation switches in nuclear power plant safety related service mechanisms and their consequences over time.

is provided. Through a description of the operation of Utilization of the laboratory technique in an oper-each type of switch combined with knowledge of nu-ating nuclear power plant would be somewhat imprac-clear power plant applications and operational occur-tical since the installed valves are not equipped with J

rences, the significant stressors responsible for multi-synchronous switching capability. Analytical research stage switch deterioration are ident;fied. A review of was therefore conducted to develop a technique to operating experience (failure data) leads to identifi-analyze similar electrical data obtained under asyn-cation of potentialcand recommended monitoring chronous conditions typical of an operating plant. For i

techniques for early detection of incipient failures.

such field application, the technique developed would Although the operating experience does notjustify use a clip-on current probe, thus enabling all measure-extensive deterioration monitoring of multistage ments to be made from outside the reactor building switches, nondestructive testing methods that could be without disturbing any electrical connections. The in-t

'used to evaluate the condition of switches are identi-rush current to the solenoid-operated valve is analyzed

' fled '!he report presents a detailed description of the in real time using a personal computer and fast Fourier components, materials of construction, and operation transform techniques.

- of each of the multistage switches included in the as.

1 sessment. Also,it provides an analysis of failure data NUREG/CR-5051, W. !!. Gunther, R. Lewis, and from the LER system. An analysis of the various failure M. Subudhi," Detecting and Mitigating flattery Charger and inverter Aging,"2108, August 1988.

llrookhaven National

. modes of multistage rotary switches and their related laboratory, llNL-NUREG-5

- causes is also given. The existing recommended and This report is the second on the two step approach -

required maintenance and surveillance practices are for assessing the safety and operational aspectsof bat-

. listed. Several techniques with a potential for assessm8 tery charge r and invert er aging in nuclear power plants.

the condition of switch components and possibly pre-Analyses include an assessment of the recent operating dicting age related failures are identified. It is recom-experiences with battery chargers and inver.crs and a mended that inservice failures be analyzed to deter-discussion of improvements in reliabihty that may be mine whether the failures are due to random defects or -

achieved through modification of theeqdpment'scon-are the result ofgeneric deficiencies that would require figuration and an increased inspection frequency. The corrective action.

results are evaluated from a survey of the current NUREG/CR-5008, R. D. Meininger and T Ji Weir, maintenance anpl test practices used in nuclear power

" Development of a Testing and Analysis Methodol-P.lants, along with the manufacturer's recommenda-ogy to Determine the Functional Condition of Sole, tions for maintaining equipment operability. Advanced noid Operated Valves," Pentek, Inc., Coraopolis, designs for unmterruptible power systems, subcomp-

PA, September 1987. '

onent improvements, and current monitoring and pro.

The objective of this research was to develop a tective equipment are described and related to their simple, reliable, ctmdition monitoring system that will potential applicability in nuclear power plants.

l provide surveillance informatiu.. vilhout requiring dis.

A naturally aged inverter and battery charger were connection or disassembly of solenoid-operated valves tested at ilNI toevaluate the naturallyagedcondition, (SOVs) installed in operating nuclear power plants.

the effectiveness of condition monitoring techniques, The information provided must be sufficiently reliable and the practicality of selected maintenance and moni-NURIIG-1377-18 0

il

Main Citations and Summaries

-l toring procedures. A portion of this research effort is manufacturing methods, and the current maintenance, covered in RIL No.159, " Nuclear Plant Aging Re-surveillance, and monitoring techniques applied to scarch: Safety Related inverters," November 9,1988.

MCCs. A significant result described in this report i

A maintenance pmgram for brittery chargers and concerns the identification of important MCC failurc inverters is recommended. As described in this report, modes, causes, and mechanisms from plant opera.

3 such a program incorponites inspecdon, monitormg, tional experience. Frequencies of failures determined :

• 4 testing, and repair activities that should be performed for the various subcomponents of MCCs are also de-l scribed, in addition, recommendations are provided for l

to detect and mitigate aging effects and thereby ensure functional indicators to monhor the performance of 1

the operational readiness of this important equipment MCCs. These functional indicators will be evaluated throughout the plant's operating life.

during Phase 2 of the pmgram.

NUREG/CR-5052, J. C, liiggins, R. Infaro.

M. Subudhi, R. Fullwel, and J,11. Taylor, NUREG/CR-5057, K. R. Iloopingarner and F.11.

" Operating 11xperience and Aging Assessment of Zaloudek, " Aging Mitigation and Improved Pro-Component Cooling Water Systems in Pressurized gmms for Nuclear Service Diesel Generators,"

. Water Reactors," llrookhaven National laboratory, Pacific Northwest I aboratory, PNlr6397, December 1989.

llNI-NURl!G-52117. July 1988 An aging assessment of component cooling water

'the study of diesel generator aging for the NI(C (CCW) systems in PWits was performed as part of the NPAR program was performed in two phases. In Phase 1, plant operating experience and data were used NPAR program.'the objectives were to provide a tech.

nical basis for the identification and evaluation of deg.

to pmduce a new data base related to aging, reliability, radation caused by age.The information generated will and operational readiness of nuclear service dicsci 1

be used to assess the impact of aging on plant safety generators. Phase ll is chiefly concerned with mcasures

-and to develop effective mitigating actions for the for mitigating the effects of aging.

- CCW system. 'the effect of time on this system was

'this report proposes a detailed management, test-characterized by using the " Aging and Life lixtension ing, and maintenance program for emergency dicsci 9

Assessment Program (All!AP) Systems Level Plan", _

generators based on studies and research developed in developed by llrookhaven National I almratory. Fall.

Phase 11 of this effort..'Ihc proposed program would ure data from various national data bases were re-lead to three expected results: (1) reduction of several viewed and analyzed to identify predominant failure of the stressors identified in Phase I that have been nmdes, causes, and mechanisms in CCW systems.

shown to accelerate aging of diesel generators, (2) an Time. dependent failure rates for major components improved reliability and state of operational readiness, were calculated to identify aging trends. Plant. specific and (3) an increased confidence in the future availabil-

. data were obtained and evaluated to supplement data ity and reliability of diesel generators. The pro [msed base results.

new program would integrate testing, inspection, monitoring, trending, maintenance, and other cic-EA computer program (PitAAGI!) was developed ments for a better approach to mitigating diesel gen.

- and implemented to model a typical CCW system de, erator agmg.The more important elements of the new sign and perform probabilistic risk assessment (PR A) proposed program are summarized in the following-E calculations. Time dependent failure rates were input to the program to evaluate the effects of aging on the paragraphs.

q importance of a comp (ment-with respect to system The current fast starting and loading requirement

~

unavailability. Time dependent changes in component for testing diesel generators can produce substantial

~

-importance and system unavailability with age were harm and significant aging effects thmugh the produc.

observed and discussed, tion of large mechanical and thermal stresses, inade-quate lubrication during initiai acceleration, high rotat a NUREG/CR-5053, W. Shier and M. Subudhi, "Operat-ing and sliding pressures, overspeeding, etc. An Assessment of Motor improved testing program including slow starting and mg P.xperience and gir H<

l

ratory, 15 !

i2118, July h8.

k>ading would induce fewer aging effects in the emery j

gency diesel generator by largely chmm, atmg a umque As part of the NRC NPAR pmgram, an assessment aging stressor. In the course of the monthly testmg h

was made of the characteristics of agmg and service program, adequate data should be collected for about i

wear of motor control centers (MCCs). M CCs pe rform 30 engine operating parameters discussed in this re-an important function m the operation and control of a port that could indicate degrading performance or an -

i

- large number of safety-related motors; thus the oper*

impending component failure. For many important ability and reliability of MCCs can affect the overall components, the implementation of such a program i

safety of nuclear plants.

could detect approaching performance failure and This report follows the NPAR stmtegy and investi-allow orderly repair. Monitoring and trending will not f gates the operadonal performance, the design and be able to detect all components with degraded i

19 NURl!O-1377

~

1

[

Main Citations and Summaries performance, but the deterioration that will be de-for the diesel generator are very high reliability with tected by the recommended tests is significant to aging the dumWiity to produce power until the emergency and reliability cweerns. Condition monitoring and passes in.he reactor cooling requirements drop off.

trending can provide important indications of possible Acceptance of this mission envelope for the diesel.

long term component or system degradaton.'this ac-generator system would result in a reduction of the tivity should detect many potential component / system aging degradation of many important engine compo-failures before the system actually fails. Cost and safety nents through less harmful test requirements. In sum-benefits would accrue from avoiding both eqmpment mary, a more practical mission envelope for the dicsci damage and unscheduled downtime by anticipalmg generator system would include an increased start and these failures and providmg timely repairl load time (within 5 minutes), with the power icvel maintenance.The monthly test program should ensure reduced below the calculated full load (core and con-that the operatmg parameters listed in the report are tainment sprays not needed). From an overall mission within their maximum and minimum limits as apphea-standpoint, it appears that safety concerns are better ble. llowever, it is not necessary to trend every pa-served by testing the engines for reliability rather than rameter for effective results. When a limiting (maxi.

for maximum starting accelerations and very rapid mum or minimum) value is being approached, the utill-loading, which do not seem necessary.

ties should trend the approach to avoid failt!res and schedule repair before limits are exceeded.

This portion of the NPAR study was initiated to develop for NRC consideration information on poten.

Several recommendations were developed regard-tial safety problems related to the aging of dicsci gen-ing maintenance procedures and training. One impor-erators. General applications of the study results were tant recommendation is that teardown of the diesel expected for (1) improvement of dicsci reliability, (2) engines solely for the purpose of inspection should be modification of plant technical specifications, (3) im-avoided unless there is a definite indication that opera-provement in the application of resources by the NRC tion is degraded or there is an impending component and the utilitics, and (4) development of specific re, failure based on performance data trends. The current scarch information needed to change some regulatory practical periodic intrusive maintenance and engine requirements. All of these end uses of the research overhauls has been found to be less favorable for en-have been accomplished or are under active considera.

suring safety than engine overhauls based on monitor-tion. Collectively, the safety implications of these ing and trending results or on a need to correct specific changes and research recommendations are important.

engine defects. Therefore, this report recommends that the periodic overhaul requirements be reeval*

NUREG/CR-5141, V. P. Ilac:mskas, G. J. Toman, and uated. Further, an understanding of the governor, as S. P. Carfagno, "Aginn and Qualification Research well as of the engine / generator, must be developed by on Solenoid Operated Valves," Franklin Research providing the maintenance staff with adequate training Center, Norristown, PA, August 1988.

and motivation. Finally, this report recommends that Tests were conducted on three way direct acting engine inspections and preventive maintenance be m.

solenoid-operated valves (SOVs). Some SOVs had creased to mitigate the agmg and wear results of the been aged naturally through service in nuclear power vibration stressor, focusmg on the engine and instru-plants, and others were subjected to accelerated aging, mentation mounted on the engme. Vibration cannot Thermal aging was conducted with both air and nitro-be eliminated, but its effects can be mitigated by keep' gen as the process gas. Operational aging was simu-ing fasteners / fittings tight and by frequently recalibrat-lated by putting the specimens through operational mg mstrumentation subject to thts vibration, cycles at certain intervals during the accelerated ther.

The mission profile for the dicsci generator is based mal aging with the environmental temperature con-on a large break LOCA with loss of all offsite power.

trolled at a level representative of service conditions.

With over 1000 reactor-years of operation in U.S. regu.

The progmm also included simulation of a design basis latory history without a large break LOCA, it may be event (DilE) that consisted of gamma irradiation appropriate to redefine the mission profile for the and a main-steam line-break loss of-coolant accident diesel. generator with consequent benefits. For a loss (MSLil/LOCA) simulation. After each major segment of offsite power, with or without a small break LOCA of the test program (aging, irradiation, and MSLill event, the needs for emergency electric power and the LOCA simulation), some of the valve specimens were dicsci mission profile are much less stringent. In this subjected to operational testing and then disassembled case, the need for power can be delayed and the emer-for inspection and measurement of physical properties.

gency power needs are reduced, but the need for emer-Performance of the Automatic Switch Co.(ASCO) gency power may remain for several(3 to 4) days.The SOVs was affected in the early stages of the program by prevention of station blackout appears to be the most an organic deposit of undetermined origin. Removal of realistic mission envelope.The technical requirements the deposit climinated the problem.

NUREG-1377 20

{

Main Citations and Summaries A naturally aged ASCO SOV with Buna N seals NUREG/CR-5181, I. C, Meyer and J.1. Edson, and a new ASCO SOV with EPDM seals were sub-

" Nuclear Plant Aging Research:The 1E Power jected to accelerated aging with nitrogen as the process System," Idaho National Engineering Laboratory, gas.1hese valves were the only ones to go through the h00-2545, May 1990.

entire test program without a failure to transfer and This in depth engineering study of the Class lE

. without any significant leakage.

Power System is conducted in accordance with the Valcor Engineering Co. SOVs suffered from stick.

NRC NPAR program and guidelines.The report pro-i ing of the shaft seal O. rings, which made it impossible vides (1) an identification of failure modes, (2) a pre-to complete the accelerated thermal aging. Repeated liminary identification of failure causes due to aging tests and changes in test procedures failed to alter this and service wear degradation, and (3) a review of cur-situation.

rent inspection, surveillance, and monitoring methods, including manufacturer recommended surveillance it is possible that the stresses of accelerated aging and maintenance practices. Also, performance pa-produced effects that are not representative of service rameters potentially useful m detecting degradation

' aging. Seal deterioration in the Valcor SOVs caused are identified in this report, and preliminary recom.

leakage following Di1E irradiation. 'Ihc naturally aged mendations are made regardmg mspection, surveil-Valcor SOV performed satisfactorily during the first lance, and nmnitoring nwthods, high temperature portion of the MSLB/LOCA profile but malfunctioned during most of the rest of the test.

A description of a typical Class lE power system is j

Deteriorationof theclastomericpartsof the ASCO P"5?nted for a pressurized water reactor (PWR) with specific mamtenance information from a cooperating -

- SOVs did not appear to be sufficient to account for the utility. The Class lE power systems provide electric observed failures to transfer, which evidently were p wer for the safety systems in the plant, including an caused by coil deterioration. Elastomeric parts of Val, enwgency power source (usually dicscl generators) j cor SOVs, both from the naturally aged SOV and from and three subsystems: the alternating current (ac)

.l the one that had not been aged, experienced substan-p wer systems, the direct current (de) power system, tlal deterioration.

and the vital ac power system. Each of the major Class i

NUREG/CR-5159, ht. S. Kalsi, C. L. Horst, and J. K.

IE power components is described, and the results of l

" Prediction of Check Valve Performance and component aging studies are summarized where appli-

)

Wang,dation in Nucicar Power Plant Systems," Kalsi cable. The ac power system used -in typical nuclear j

Degra

- May 1988. g, Inc., Sugar Land, TX, KEl No.1559, power plants is a dual train cascading bus system that Engineerin includes circuit breakers, transformers, relays, load Degradation and failure of swing check valves and centers, and motor control center switch gear. The i

resulting damage to plant equipment has led to a need de system includes battery chargers, batteries, inver.

p to develop a method to predict performance and degra-ters, and associated control breakers. The vital dation of these mlves in nuclear power plant systems.

120-Vac loads include the engineered safety feature f

'this Phase I investigation developed methods that can cabinets and the reactor protection systems.

'j be used to predict the stability of the check valve disk The review of operating experience included data j

when there are flow disturbances such as elbows, from the following generic data bases: Licensee Event -

reducers, and generalized turbulence sou rces within 10 Reports (LERs), Nuclear Plant Reliability Data Sys-1 pipe diameters upstream of the valve, hiajor findings tem (NPRDS), Nuclear Power Experience (NPE), and include the flow velocity requirca to achieve a full-plant maintenance data from one cooperating utility.

open stable disk position, the magnitude of disk motion

'Ihe L.ER records indicate that the Class 1B power I

developed with these upstream disturbances (with flow subsystem failures were distributed as follows: emer-velocities below full open conditions), and disk natural gency power generation,31.7%; medium-voltage sub-j l:

frequency data that can be used to predict wear and systems, 21.2%; low-voltage ac (less than 600 V),

fatigue damage. Reducers were found to cause little or 19.8%; and de system,9.8%. The most frequent com.

i no performance degradation. Effects of cibows located ponent failures were circuit breake rs,66.3%; inverters, within 5 diameters of the check valve must be consid-9.9%; and batteries,9.5% Thc leading causes of circu it i

cred, while severe turbulence sources have a signifi-breaker faults were mechanical malfunction, 25%;

l cant effect at distances up to 10 diameters upstream of electrical malfunction, 22%;' and sticking, 7E The the valve.

three leading causes of relay faults were drift,46%;

Clearway swing check designs were found to be electrical malfunction,11%; and sticking,10E The particularly sensitive to manufacturing tolerances and NPRDS data review listed the Class 1B power compo-installation variables making them likely candidates for nents in order of frequency of failure as follows: dicsci premature failure. Reducing the disk full-opening an-engines, inverters, and circuit breakers. The overall gic on these designs results in significant performance fraction of Class 1B electrical component failures re-improvement, lated to aging was 32.7% 1lowever, because of system L

l 21 NURHO-1377 l

Main Citations and Summaries J t

redurtdancy and fail. safe design, only 2.4% of Class IE

_ componcat temperatures and circuit characteristics electrical component failures caused total loss of sys-were similar to original acceptance test measurements.

tem function.

Based on these observations, it is concluded that the Approximately 8% of all events in the NPE data inverter and battery charger have not aged substan-base for all systems were associated with the safety tially.

electrical system. The NPE list ed breakers, motor con-

'lhe two primary monitoring techniques employed

- trol centers, and switchgear as having the most fre-were temperature measurements and electrical quent failures, at 36.l E'ihis was followed by inverters waveform observation. Internal panel temperature and chargers,15%; diesel generators,10%; transform-and individual component temperatures were re-ers, 3.4%; and batteries, 3% 'lhe plant data also corded at regular intervals during steady state and showed that breakers caused the most work requests in inmsient operations. Thermocouples imbedded within the maintenance data base, followed by batteries, the the transformer and inductor windings and attached to battery charger, and the generator. (llatteries were SCR and capacitor surfaces provided a nonobtrusive' high on the list because of frequent preventive main-means of monitoring component operation. Readings 3

tenance tasks such as adding water and testing.)

taken were compared to original acceptance test data.

The review of codes and standards included general Circuit waveforms were observed on an hourly basis design critcria, regulatory guides, and IEEE standards.

during steady-state operation and at the time load tran-

]

There were three recommendations for regulatory sients were applied. The inverter output voltage and guides:(1) Regulatory Guide 1,118 should include the the SCR gate current waveforms remained relatively issues of testing and inspection for the lightning pro.

constant regardless of the applied loads.

tection system and power ground system, (2) Regula-Finally, this test report recommends that individual tory G uide 1.32 should address the issues of cleanliness fusing of filter capacitors be considered in order to in switchgear area, and (3) Regulatory Guide 1,9 preclude a capacitor failure in the short circuit mode -

should be extended to include the pmblems of dicsci from rendering the inverter inoperable. Also, equip generator aging, ment acceptance testing should be modified to obtam Approximately 40 IEEE standards applicable to the most limiting design operating conditions for all Class lE power systems and associated components major subcomponents. Results indicated that aging were reviewed and tabulated. The IEEE reviews each had not substantially affected equipment operation, standard approximately every 5 years. The authors rec.

On the other hand, the monitoring techniques em-ommend that aging be included in this review. Stan.

ployed were sensitive to changes m measurable compo.

dards provide design and application guidance but gen.

ncnt and equipment parameters. Thus comparing the crally do not provide specific recommendations for momtoring results with the ongm, al acceptance test 1

maintenance, testing, inservice inspection, and moni, data is a viable method of detecting degradation prior toring of age related degradation, to catastrophic failure, Aging research ctm phiy a supporting role in solving NUREG/CR-5248, L S. Levy, D.11. Jarrell, and '

outstanding safety issues. For example, component E. P. Collins, "Prioritization of TIRG ALEX-degradation duc to nging is one factor to consider in the Recommended Components for Further Aping plant coping analysis required by the NRC rule on Research," Pacific No,rthwest Laboratory Science station blackout,-

Applications International Corp., PNL-6701 -

Novpmber 1988,

'NUREG/CR-5192, W. E. Gunther," Testing of a in April 1986, the NRC established the Technical Naturally Aged Nuclear Power Plant Inverter and Integration Review Group for Aging and Life Exten.

-Ilattery Charger," Ilmokhaven National Laboratory, sion activities. In May 1987, TIRGALEX finalized its liNL-NUREG-52158, September 1988.

plan (FIRG ALEX 1987), which identified the safety-A naturally aged inverter and battery charger ob-related structures and components that should be pri.

tained from the Shippingport facility were tested as critized for subsequent evaluation in the NRC NPAR n

part of the NPAR program.The objectives of this test.

program.This report documents the results of an ex-

ing were to' evaluate the naturally aged equipment pcrt panel workshop established to perform the -

state,udetermine the effectiveness of condition-prioritization activity. Prioritization was based primar.

monitoring recommendations, and obtain insight into ily on criteria derived from a specially developed risk-

'the practicality of preventive maintenance and moni-based methodology that incorporates the effect on

- toring methods.

plant risk of component aging and the effectiveness of Testing indicates that the equipment has retained current industry aging management practices in miti-its ability to respond to load transients. With the excep gating that aging.

tion of silicon controlled rectifiers (SCRs), which were An additional set of criteria was the importance of found to be operating with case temperatures (*F) aging research on structures and components to the 20% higher than those during the acceptance test, resolution of generic safety issues and to identified NUREG-1377 22

hiain Citations and Summaries regulatory needs. 'lhe resultant categori/.ation was ntsms were wear and cabbration duft. The predonn-used to provide addiuonal mformation to decision nant failure nmde was leakape lollowed by loss ol fune-makers but was not used to calculate final rankmps.

tion and wrong signal. The data also indicated that The expert panel workshop was conducted within aPluosiniately 65% of the f ailures were detected by the the following ground rules:

current test and mspection practices Ilowever,27% of the tailures were not detected until an openttional Obtam all relevant mformation on aring of cut-e rent plants (i.e., during their ongInal license abnornuthy oaund hus sows dun cumndy em-ployed mamtenance and monitoimg pracuces are not g

completely successful m detectmg all armg degrada-1)evelop an unJetstandmg 01 aging and its ef-non. In evaluating the effect of hulure on 1(llit per-e fects ne.. defmc the contribution of aymp to formance, it was found that over 50% resulted m plant risk),

degraded system operahon, while approumately 20%

Assess the adequacy of current mdustry prac-resulted m a loss of redundancy. Other sigiuficant ef-o tices for managing component agmy within ac-fects of 1(1111 failures include loss of shutdown coolmg ceptable lesels of nsk, ca}ubihty, radiologica! ieleases, reactor scrams and 1 valuate the imjuirtance of the armg of mdivid.

actuatior' of engmeered safety features. Actual plant e

records for h1illstone Unit I were obtained and re-ual components and comlxment pr oups on plant

nsk, viewed. 'I he results showed coa.sistency with data base hndings Apply the "l(isk Sigmficance of Loniininent Ap-e

'lhe probabilistic work entiuled the im ple -

mp" methodology (bemp developed by W. I; personal-computei based pro.

entauon 01 a Vesch of SAIC under the NPAlt program) to the priontization, gram M AAUl -l% dmloped to pnf(um tune-dependent probabilisue nsk assessment (PI(A)

Use operanonal f.ailure data, e

uculamn 'I he lillit model used was based on the Use espert judgment through an interdisciph-Peach lionoin design ' lime dependent fadure lates e

nary panel-for major components weie deseloped fiom the data Suess the unportance of agmp research to the base findmps and were used in the pn. gram to calculate e

resolution of genene safety issues and to user system availabihty and component unportances for needs identified by the ()lfice of Nuclear 1(cac-vanous ages. The PI( A results showed that, when the tor llegulation to aid N1(C decision-makers but time-dependent agmg factors are accounted foi, two not to formally pnontue the components.

sigmficant system ellects are seen: (1) system unavail-abihty mereases nuleiatch with age and (2) the rela-NUltEQCil-5268, it. l.ol.ato, hl. Subudhi, W. !!

tu bponances of conNents q chmo;e wah apt hunther. %. Shier, t(.1 ullwood, and J.11. I avlor.

or lowtyme adant upuon opmuon, nuwaW

" Apmp Study of Iloilmy' Watet i(cactor l(esidtia bration ol msuumentation was the most important lleat itemoval System, llrookhasen Nanonal I.aboratory, llNI c N UlllW52177, J une 1%9 contnbutor to system unavailabihty. llowever, during latn gam agum can cauw numnwperated valves to As part of ongomg efforts to understand and man-baonu njuauy uninntant. Pil A calculations for shut-age the effects of agmg m nuclear power plants, an

@wn coolny opnahon Wowed these sahes to be the aging assessment of a vital system, the resiJual heat removal (lliilt) sy stem in lxuling water reactors mom unpgant contnbunn3 to unasailability through-out pl mt &

(llWils), was performed. I his repm t presents the re-Ihe followmg conclusions resulted irom this sults and discusses the impact of 1(1 lit system agmg on aswwment:

plant safety. 'Ihe work was performed as part of the N1(C NPAlt program. The 1(111( study was done ac-Aymg E/]ccta cordmg to the methodology developed by llNl.as part Armg has a moderate impact on 1(111< compo-e of the Agmp and I ife latension Awessment Program nent failure rates (0 to 17i per year mcrease)

( Al.li Al ) System 1.evel Plan The selected approach and system unava: lability (2-fold to 4-fold in-uses two parallel work paths, one applymg determin-crease m 50 yearst This contnbution of aging istic techniques and the other probabihstic techmques.

effects may be attnbutcJ to two factors- (l) to characterve agmg.

l(llit is a safety system and has relauvely strm-The deternumstic work performed for the 1(1111 gent testing and momtonnp icqmrements that system study msolved a review of past operating data identify agmg degradauon before perf ormance from sanous national data bases. The data covered all is adverseh alfected and (2 ) the 1(llit system is operatmg unies of the 1(1110 They showed that ap.

typically mamtamed m standby, w hich nuni-proxunately 709 of the failmes reported were due to nu/cs esposuic to wear related degradauon.

Pichnunary compansons of unavailabihty for aging. 'I he donunant cause of failure was f ound to be e

normal sersice, while the donunant hulure mecha standhy and conimuoush operatmg systems 23 N t il(I ( i 1377

z Main Citations and Summaries g

if(

have shown that standby systems are potentially previous work on a continuously operating system.This

' less severely affected by aging. Using this result should be addressed in future work. In addition, the l

u E

. as a basis, the differences in operation and man-relatively stringent tests and inspecticas performed for i

agement of these two. types of systems will be the RilR system may contribute to the aging effects, further evaluated with the ultimate goal of de-NUREG/CR-5334. D.11. Clauss, " Severe Accident veloping methods that are effective in mitigat-Testing of Electrical Penetration Assemblics,"

= mg aging effects.

Sandia National laboratories, SANDS 9-0327;

'e Examination of plant specific failure data has November 1989-

onfirmed that failure trends for certain compo.

Since the "three hiile Island incident, the risk and nents in some plants cim differ from industry consequences of severe accidents have been a major s

averages. Although aging was found to have a focus of reactor safety research. The performance of 1

moderate impact on the RHR system based on the containment building has a significant effect on average values, the impact on plants for which accident consequencet thus considerable effort has -

- the data differ from these average values could been directed toward understanding and predicting the be significant. This will be addressed in future functional failure of containments. The containment

work, pressure boundary typically includes numerous me-c n ala elec penetmhns, cad d whp.

Data Anal' sis J

resents a potentialleakage path, Results have confirmed that generic failure Several studies completed in the early 1980s indi.

o rates may not accurately represent individual cated that electrical penetration assemblies could be 1

plants for all applications. The uncertainty in an important leak path that merited further study. A nsk estimates may be reduced by updating cal-report by the Oak Ridge National Laboratory on se-culations with actual plant data, vere accident sequence analysis for llWR Mark I con-i e Mechanical components'in the RilR system tainments concluded that the temperatures in the show a low to moderate increase (8% to 17%

drywell were high enough to possibly cause failure of peryear)in failure rate with age, while electrical the seals that could result in leakage. NUREG-0772~

components such as switches and sensors show identified electrical penetration assemblies as having little or no increase (0 to 3% per year).

"one of the largest uncertainties associated with pre-

' DesSn Considcrations dicting the amount of radionuclides released.",These studies provided the major impetus for NRC to mitiate g

Plants with a common suction line supplying all a research program on these assemblies. Sandia Na-e

- loops of the RHR while in the shutdown cooling tional Imboratories managed a program to conduct a mode should consider placing increased atten-background study and to recommend and perform tests tion on motor. operated valves (MOVs) in the to generate data that could be used to assess the leak k

suction line during lateryears of plant life since potential when the assemblics are subjected to severe

- aging can increase the probability of MOV fail-accident conditions. These tests are described in this ure and lead to a temporary loss of shutdown report.

cooling capability. Piping and other components Electrical penetration assemblics are used to pro-in nonredundant supply Imes should also be

- vide a leak tight pass.through in nucicar power plant considered.-

containment buildings for electrical cables with power,

e - Plants using a common minimum flow line for control, and instrumentation applications. The design Itwo RHR pumps should closely monitor pump has evol.ved to a modular concept that consists of elec-performance since aging car degrade perform-trical conductors contained within stainless steel tubes

'ance and lead to dead-headed pump operation (modules) that are scaled, and possible failure. _

Three designs, D; O. O'llrien, Conax, and Westing.

The findings presented in this report form a sound house, were tested under simulated severe accident technical basis for understanding and managing the conditiens for a PWR, a llWR Mark I drywell, and a

cffects of aging in RHR systems. The results also pro.

IlWR Mark lit wetwell, respectively, to generate engi-vide the framework for future Phase 11 work. Although necting data (leak rate, temperature, insulation resis-

' the time dependent aging effects appear to be moder-tance, and electrical continuity) for assessing their leak alc for the RHR system, ndditional work is necessary to potential. None of the assemblies leaked during the-

complete the 't,ging assessment. Since this is predomi-severe accident tests, which c:m be attributed to the use

nantly a standby system, exposure to operating stresses of redundant seals and to the fact that the outboard is limited, which could contribute to the mitigation of containment seals in all three designs were never ex.

aging effects. Ilowever, as plants continue to age and posed to temperatures that exceeded the service limits

operating time increases, the RHR system could expe-of the seal materials.The exceptionalleak integrity of rience rapid increases in failure rates, as was found in the three designs tested in this program should not be

' NUREG-1377 24 m

Main Citations and Summaries f

assumed to ap' ply to all other designs in use for at least NUREG/CR-$379, D. H. Jarrell, A. B. Johnson, Jr.,

two reasons:

P. W. Zimmerman, and M. L Gore, " Nuclear Plant Senice Water System Aging Depradation Assess-

1. There are a large number of diverse designs in ment: Phase 1," Vol.1, I acific Northwest I.abora-use. In particular, assemblics manufactured tory, PNie6560, June 1989.

prior to 1971 were not subject to national stan*

The senice water system represents the final heat dards and were often manufactured in the field, transfer loop between decay heat generated in the whereas the three tested in this program were nuclear core and the safe dispersal of that heat energy subject to rigorous quality assurance and were into the environment.The objective of this assessment designed to meet the standards of IEEE is to demonstrate that aging phenomena in the service 317-1976 and IEEE 323-1974.

water system can be identified and quantified so that

2. The leak potential is highly dependent on the aging degradation of system components can be de-tected and mitigated before the system availability is temperatures to which the assembly is sub, jected. As research continues and more analyses reduced below an acceptable threshold.1he following of severe accident sequences are conducted, the goals of the assessment were directly denved from the

" worst case" loads may change. Therefore, the NRC NPAR program plan:

leakage potential must be reevaluated as the

1. To identify the principal aging degradation understanding of severe accident loads is im.

mechanisms, to assess their impact on opera-proved. Ileat transfer effects must be consid-tional readiness, and to provide a methodology cred to determine the temperature of the out.

for mitigating the effects of service water system board containment seals, which end up control.

aging on nuclear plant safety, ling the potential for leakage.

2. To examine the current surveillance specifica-tions and evaluate their ability Io provide accu.

The results of these tests should not be construed as rate reliability information.

suggesting that all designs will not leak under severe accident conditions; the performance of all compo.

3. To provide a means to evaluate the effective-nents of the containment pressure boundary must be ness of maintenance on mitigating aging-cvaluated on a case by case basis with all loads consid.

degradation phenomena.

cred.1he performance is also affected by thermal and

4. To produce an inspection plan that optimizes adiation aging. Given good information on the con-the effectiveness of inspections based on system tainment loads, a heat transfer analysis to determine risk reduction.

the approximate temperature profiles, knowledge of

5. To use the infonnation generated by this assess-the time temperature thresholds for the scalant mate-ment to resolve related generie issues and pro-rials used, and the proper exercise of engineering judg-vide guidance for developing regulatory criteria ment, a reasonable evaluation of the leakage potential on aging and life extension.

of other designs can be made.

The following approach was used during the initial The electrical performance of the assemblies was phase of the assessment:

monitored in these tests by measuring the insulation Perform a literature search of government and e

resistance and electrical continuity of the conductors.

private sector reports that are related to service The resistance degraded rapidly during the severe acci-water, aging-related degradation, and potential dent tests, although the rate depended more on the metho'dologies for analysis.

type of cable and loads than on the particular design Assemble a data base that contains a listing of e

bemg tested, Under the specific severe accident condi-the configurations, characteristics, and water tions that were simulated, the data suggest that all sources for the service water systems in all com-electrical systems supplied in the W estinghousc assem-bly would have functioned for about 4 days; those sup-mercial nuclear power plants in the U.S.

• Obtain and examine the available service water plied in the D. G. O'Brien would have functioned for about 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />; and those supplied in the Conax may data from large generic data bases, i.e., the Nu-have functioned for only about 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. Some cables clear Plant Reliability Data System, l.icensee would be expected to function beyond these times.

Event Reports, Nuclear Power 11xperience, in-However,it must be noted that conclusions regarding spection reports, and other relevant plant refer-j the electrical performance of systems inside the con.

ence data. Analyze the service water system of a lainment building based solely on insulation resistance specific power plant for aging-related degrada-data must be made with caution.The performance of tion phenomena from the available data ob-tained from this data base, the electrical systcms would depend on the voltage, Perform a fault-tree analysis of the service l

current, and impedance requirements for a specific conductor application.

water system of a typical plant to examine 25 NUREG-1377

Main Citations and Summaries I

failure propagation and determine specific in.

NUREG/CR-5383,11. M. Hashemian. K. M. Petersen, put requirements of probabilistic risk analyses.

R. E. Fain, and J. J. Gingrich, *Effect of Aging on i

Response Time of Nuclear Plant Pressure Sensors,"

e - Develop an m depth questionnaire protocol for Analysis and Measurement Services Corporation, examining the information resources at a plant Knoxville, TN, June 1989, where such resources are not available in the A research program was initiated to study the ci-standard data bases. Subsequently, visit a nu-fects of normal aging on the dynamic performance of clear power plant and solicit the required infor-safety-related pressure transmitters (i.e., sensors) in mation.

nuclear power plants. The project began with an ex-Analyze the information obtained from the in-perimental assessment of the conventional and new e

depth plant interrogation and draw contrasts testing methods for measuring the response time of and conclusions in regard to the data base-pressure transmitters.1his was followed by developing 1

Use the plant information to perform an interim a laboratory setup and performing initial tests to study e

assessment of degradation mechanisms and to the agmg characteristics of representative transmitters focus future investigations, f the type used m nuclear power plants.

The following is a summary of the conclusions of There is need to ensure that the current testing the assessment to date:

methods, regulatory requirements, and industry stan-dards and practices are adequate to track age-related

1. Aging related degradation _ of open service degradation. The project examined the validity of the water systems, i.e., systems that have a direct available methods for response-time testing of pres-interface to raw water without chemical control, sure transmitters and reviewed the historical data for in nuclear plants is prevalent and constitutes a evidence of performance degradation problems or valid safety concern. Based on actual plant data, trends. Current intenals for response time testing and the primary degradation mechanism found in calibrating pressure transmitters are based on refuel-the open systems is corrosion compounded by ing schedules, apparently for two reasons:

the accumulation of biologic and inorganic ma-There is no method available for on line calibra-e terial. This conclusion directly contradicts the tion of pressure transmitters, and, until re-results,of a failure analysis performed using in-cently, response time testing could not be per,

formation obtained from the NPRDS data base, formed on line, which indicated that the torque switches of mo-The available data base of degradation rates and tor-operated valves were the prime cause of system failure.

! rends is not sufficiently reliable to ;ustify test-ing mtervals longer than one refueling cycle.

2. Based on multiple plant samplings, the current level of surveillance and postmamtenance test-While testing based on refueling intervals may be j

ing performed on the system is not sufficient t adequate, there is concern that the rate of degradation accurately trend or detect system degradat,on of pressure transmitter performance may increase as i

due to aging phenomena.

the current generation of plants becomes older. Fur-thermore, on-line testing methods based on new tech-

3. While postmaintenance surveillance does give nologies are becoming available to permit more fre-some measure of the effectiveness of system quent testing of transmitters and to predict incipient modification and repair efforts, sufficient infor-failures.These considerations have motivated research mation on monitoring operational condition and.

such as that covered in this report to ensure that practi-postmaintenance testing is not available to char-cal test methods and adequate test schedules are used acterize more precisely the effectiveness of to verify proper and timely performance of safety-maintenance.

system pressure transmitters in nuclear power plants.

4. To improve the accuracy of data to a point that The project included a search of the licensee event.

would allow a high degree of confidence in the report (LER) data base for pressure-sensing system analysis of aging degradation, a root cause logic problems and reviews of Regulatory Guide 1.'118 and scheme needs to be developed for use in defin-of the industry standards on performance testing of ing the depth of knowledge and the documen-pressure transmitters.The following conclusions have tation required to accurately characterize an been reached:

aging-related comp (ment failure.

Five reasonably effective methods are available

5. Clearresolution of relevantaging relatedsafety for response-time testing of pressure transmit-issues will require the specification of additional ters in nuclear power plants. These methods are documentation of failure data and regulatory referred to as step test, ramp test, frequency requirements to ensure adequate safety margin test, noise analysis, and power interrupt test, under aged or extended. life conditions.

Two of the five methods (noise analysis and NUREG-1377 26

Y T

Main Citations tnd Summaries G

. power interrupt test) have the advantage of pro-mental and scismic qualification of transmitters.

i e

viding on-line measurement capability at nor.

1-lowever, the transmitter qualification data are '

3 p

- mal operating conditions.

not sufficient to address norm 1 aging.

I e The consequences of aging at simulated plant The aging research covered in this report was a -

E ccmditions were calibration shifts and response.

feasibility studyt it used accelerated aging to accommo-L

. time degradation, the former being the more

. date the short (6 months) duration of the project. Since L

pronounced problem, accelerated aging does not necessarily simulate normal The LER data base contains 1,325 cases of re, aging, the aging results in this report must be viewed as

'i 5

e ported problems with pressure sensing systems preliminary. Furthermore, this study was concerned

~

over a nine-year period (1980-1988). Potential with the performance of the portion of the pressure.

i age related cases account for 38% of the re.

sensing system and electronics located in the harsh h- - -

ported problems in this period. A notable num.

environment of the plantt the power supply and other ber of LERs reported problems with blockages, components of the pressure sensing channel that are G

freezing, and void (bubble) formation in sensing kicated in the control room, cabic spreadmg room, or i

other mild environments were not studied.

L lines.

Regulatory Guide 1.118, lELIE Standard 338 NUREG/CR-5386, D. P. Ilrown, G. R. Palmer, E. V.

e and ISA Standard 67.06 can benefit from minor Werry, and D. E. lilahnik "Hasis for Snubber Aging recommended revisions to account for recent.

Research: Nuclear Plant Aging Research Program, Pacific Noithwest laboratory, lake Enginecrmg advances in performance testing technologies Company, Wyle laboratones, PNL-6911, January

'y and from new information that has become-0.

. available since these documents were initially Th.is report proposes a research plan to address the generated.

sa ety conmns of ngmg in sn@bers used on pipmg and The six month studyof the dynamic performance of large equ ment in commerdal pm power Nam pressure transmitters covered the following areas:

The prr, posed program will provide the structure for Assessment of Response Time Testing Methods, the Phase Il Snubber Aging Study ior the NRC NPAR e

An experimental assessment of the five meth-program, to be performed at nuclear power plants and ods mentioned above involved laboratory test-in test laboratories. This research would be an exten-4 ing of more than twenty pressure transmitters sion of the work performed by the Pacific Northwest

- with all five methods. Reselts showed that the laboratory (PNL)in the Phase i Snubber Aging Study, methods are equally effective but vary widely in the primary objectives of which were to conduct an

' difficulty of implementation in nuclear power initial aging assessment of snubbers and to evaluate the I

plants.Two of the five methods (noise analysis -

-concept of reducing the number of snubbers in com-and power interrupt test) can be performed re-mercial nuclear power plants.' Although snubber re-L motely on installed tnmsmitters while the plant duction programs may reduce their total population by is at normal operating conditions.

50 to 80%, this will not mitigate the concern for manag.

-l e : Aging Study. Laboratory research on aging we ing the aging of the remaining snubbers, indeed, the -

initiated and preliminary results were obtained, remaining ' snubbers may become more important to

~

.The work involved response time testing and plant safety than the original population. The pro-calibration checks of a number of transmitters posed Phase 11 research work is based, in part, on a e

after exposure to heat, humidity, vibration, study of snubbers in' U.S. nuclear power plants by the.

pressure, cycling, and overpressurization condi-

' lake Enginecting Company conducted for PNL under tions. The effect of these conditions was an in-the NPAR program. A survey of U.S. utilities con.

.tl P

crease in response time and calibration shifts, ducted for PNL by Wyle laboratories on the-use of -

the latter being the more pronounced problem.

snubbers in nuclear plants was also used to identify

. research needs.

f e ' Reylew of Related Studies. All published experi.

a mental work on aging of pressure transmitters The following are key elements of the proposed has concentrated on the effects of aging on snubber research:

static performance of the transmitters as op-Review of existing service data, posed to the dynamic performance reported Development of service life monitoring guide-e herem.The related studies concluded that aging

ines, affects the performance of pressure transmit-Evaluation of the effects of comI1ression set in e

ters and that temperature is the dommant stres-hydraulle seals, sor. Most of the studies on performance of nu-Evaluation of accelerated methods for predict-

- clear plant pressure transmitters were spon-sored by the NRC.The only other major work ing seal life, identification of seals most affected by aging.

- as performed by manufacturers for environ-w e

+

27 NUREG-1377

.l t i

~

4 MalriCitations and Summaries.-

-f 4

Ihe bsnefits to be derived from the research are failure histories of AIM system components are con-g

principally safety related, including enhanced failure sidered from the perspectives of how the failures were

.t

• f prediction and scismic protection of safety-related pip-detected and the significance of the failures. Results of--

. g'

ing and equipment, mitigation of snubber aging effects, a detailed review of operating and monitoring practices.

reduction of stafIradiation exposures, and reduction of at a plant owned by a cooperating utility are presented.

rad waste Numerous technical benefits are also ex.

General system configurations and pertinent data are

?

Jpected, including the identification of aging trends, provided for Westinghouse and llabcock and Wilcox j

1 information useful in developing guidelines for moni-units.

toring service life, the lechnical bases for determining service life, the effects of compression set in seals, and The report includes an identification of the general :

s

-improvements in snubbe design, materials, and types of AIM system design configurations, an analysis maintenance. Regulatorrbenefits anticipated include of historical failure data, and a detailed review of a

contributions to Standard Review Plans, Regulatory cooperating utility's AFW system design and their cut-Guides, Plant Techmcal Specifications, and ASME/

rent operating and monitoring practices.

ANS! OM-4 Standards based on the broader, more Historically, and particularly since the 'three Mile Lcomprehensive data base that would be developed.

Island 2 accident, the AFW system has been recog.

The research proposed is designed to address the

".ized as critical to successful mitigation of plant tran-

- following questions about the aging of mechanical and sients and accidents. In recent years, operating inct.

, hydraulic snubbers:

dents myolvmg failures of AFW system components q

have been among the leading events identified m How do snubbers age and degrade?

NUREO/CR-4674, Vols.1-8, " Precursors to Poten-d t

e e.What are the failure characteristics of snub-tial Severe Core Damage Accidents," in which the bers?

leading risk significant events are identified for several What are the safety implications of snubber calendar years, in the years 1984 through 1986, seven M

-e

. aging?-

of the top ten events at PWRs, from a core damage risk -

eL What technical information is needed to im.

standpoint, involved partialortotalfailureof the AIM prove the performance and life expectancy of system. Operational problems with these systems have snubbers?

been diverse in nature. The report lists six events re-sultmg m NRC Bulletms and Information Notices as

. 'the results will contribute toward more reliabic examples of the diverse types of failures involving the and predictable snubbers in the nuclear power industry AFW systems. Numerous other operating experiences and thus willimprove nuclear plant safety. lmplement-have resulted in feedback to the industry through both cation of the research plan will also provide a data base the NRC and the Institute of Nuclear Power Opera-i

' for use in addressing regulatory and snubber technol-tions (INPO).

T

'ogy issues. The data base will be made available to

nuclear utilities, snubber manufacturers, snubber serv-In reviewing the role that aging plays m. faih res

- ice companies, and the NRC. Planned interfaces will.

such as those of AFW systems three important po}mts ensure technology transfer to utilitics and manufactur-rnust be considered. First, a-combination of factors,

ers, meluding design, maintenance, operation,-agmg, and other considerations may be involved. These factorsL

-NilAEG/CR-5404, D. A. Casada, " Auxiliary Feedwater are not necessarily independent of one another.

di r t

-65 i,

l r 1

- Second, systems age only a_s the individual compo..

nents age. Other studies performed under the NPAR

... This review of the t.uxiliary feedwater (AFW) sys-

- program address important components within.the -

a tem used at pressurized water reactor (PWR) plants AFW system and discuss the aging stressors for thesci

. has been conducted under the auspices of the NRC individual components.

NPAR program. The primary purposes of the review were to (1) determine -the potential and historical Third, a study performed by INEL reviewed histori-sources and modes of failure within the AFW system, cil failure data from the Nuclear Plant Reliability Data

. (2) identify currently applied means of detecting System (NPRDS) and made judgments as to whether j

~

' known sources and modes of degradation and failure, or not individual failure episodes were related to aging.

and (3) evaluate the general effectiveness of current Hecause of the above three points, the ORNL ap.

. monitoring practices and identify specific areas where proach to the AFW system study has been to focus 1

enhancements appear needed.

attention on how and to what extent the various AFW

.The report reviews historical failure data available system components fail, how the failures have been

' from the Nuclear Plant Reliability Data System, Licen.

and can be detected, and what is the value of existing

i see Event Report Sequence Coding and Search Sys.

testing requirements and practices, rather than at-tem, and Nuclear Power Experience data bases. The tempting to focus on the extent to which aging (versus j

e h

-: NUREG-1377 -

28 i

t

~%

f

Main Citations and Summ ries design or operating practices, for example) is responsi-NUREG/CR-5419, M Villaran, IL Fullwood, and ble for failure or degradation.

M. Subudhi, " Aging Assessment of Instrument Air Systems in Nuclear Power Plants," llrookhaven National laboratory, llNlrNUllEG-52212, An analysis of historical failure data involving A13V January 1990, systems was completed by a detailed review of an exist-ing AITV system and the associated monitoring prac.

As part of ongoing efforts to understand and man-tices of a cooperating utility The single largest source age the effects of aging in nuclear power plants, an of ATTY system degradation, based upon the analysis of aging assessment was performed for the instrument air historical failure data, is the turbine drive for Algy system, a system that recently has been the subject of pumps. It should be noted that the turbine proper has much scrutiny Despite its nonsafety classification,(n.

been a relatively reliable and rugged piece of equip strument air has been a factor in a number of poten, ment, llowever, the turbine auxiliaries, including the tially serious events.This report presents the results of governor control and the trip and throttle valve, have theassessmentanddiscussestheimpact of agingof the contributed substantially to the overall turbiae instrument air system on system availability and plant

~

problems, safety,1his work was performed as part of the NRC NPAR program. The objective of this study was to identify all the aging modes and their causes that The sum of the failures of motor operators and air should be mitigated to achieve reliable operation of all operators for valves resulted in approximately the safety related air equipment. Also included is an in-same number of AFW system degradations as did fail-terim review of typical maintenance activities for air i

urcs of the turbine drives alone. Pump failures and systems in the nuclear power industry.

check valve failures were also significant contributors to system degradation.

To perform the complex task of analyzing an entire system, the Agingand Life Extension Assessment Pro-For each type of component and for the various gram (ALEAP) System Level Plan was developed by llr khaven National Laboratory (BNL) and applied l

sources of component failures, the methods of failure detection were designated and tabulated. The most successfully in previous studtes. Ihc yvork used two notable feature of this aspect of the study was that parallel work paths. one usmg determmistie techniques T

i failures related to instrumentation and control domi-to assess the impact of agmg on compressed air system nated the group of failures that were detected during performance, and the other using probabilistic meth-l demand conditions (as opposed to failures detected as ods. The results from both paths were used to charac-l the result of pericdic monitoring or routine observa, terize aging in the mstrument mr system. The findmgs I

tions made by operators or other personnel), hlany of from this study, some of which have applications be-the potential failure sources that were not detectable yond the mstrument and service air systems, formed a by the current monitoring practices were related to the technical basis for understanding the effects of agmg m, instrumentation and control portion of the system, c mpressed air systems. The major conclusions from this work are:

This study identified aging trends in component It was also observed that a number of conditions e

related to design basis demands are not being periodi.

failure rates, the relative importance of compo-cally verified. lixamples of these include pump capaci-nents, and system unavailability. All these ties not being verified at design flow / pressure condi-trends could have a deteriorating impact on sys-i tions, turbines not being verified to be capable of deliv-tem availability and consequently on plant ering required torque at low steam pressures, various safety in later years.

control sequences no' Scing checked, and automatic Compressors, air system valves, and air dryers, e

pump suction transfers not bemg tested-made up the majority of failures.The failures in passive components such as piping, after-Another observation made was that some compo.

coolers / moisture separators, and receivers in-ner ts or certain parts or aspects of components appear creased with time, but these still constituted to be tested in excess of what failure history indicates to only a small percentage of overall failures.

be appropriate. On the other hand, other aspects of The effectiveness and quantity of preventive e

certain parts of the ATTV systems are either never maintenance devoted to a component signifi.

tested or receive less than thorough testing. It appears cantly reduced the number of failures experi.

1 that improved testing requirements are needed in or-enced. Ilowever, existing maintenance pro-der to reduce excessive testing while at the same time grams within the industry lack uniformity, and ensuring that thorough performance verification is quality assurance is not rigorous because the conducted periodically.

system is classified as "nonsafety."

}

l 29 NURl!G-1377

Main Citations and Summaries Individual plant maintenance records forinstru-and support system piping was the most impor-o ment and service air systems were found to be tant contributor to system unavailability; during the most comprehensive source of data for per.

the later years, aging can cause com pressors and forming aging analyses.

air dryers / filters to become increasingly As a continuously operating system with mini, important, e

mal cont rol room instrumentation because of its

'Ihe findings presented in this report form a sound nonsafety classification, most problems in the technical basis for understanding and managing the air system are detected by local monitoring and effects of aging in instrument air systems. Future work indication, walkdown type inspection, and pre.

will include improvements to current maintenance, ventive maintenance inspection or surveillance, monitoring, training, surveillance, and off normal re-Review of compressed air system designs and sp nse precedures to mitigate degradation due to e

studies using a PRA based system model re.

88* 8' vealed that the redundancy of key components NUREG/CR-5479,11. DarrJano and R. C. Kryter, (compressors, dryers, instrument air / service air

" Current Applications of Vibration hionitoring and cross connect valve) was an important factor in Neutron Noise Analysis: Detection and Analysis of system mailability. 'Ihc overall design configu, Structural Degradation of Reactor Vessel Internals ration affected the pervasiveness of air system from Operational Aging," Oak Ridge National problems.

laboratory, ORN!/I'M-11398, February 1990.

The detection of degradation in PWR internals due

• Total loss of air events are uncommon. The to operational aging is becoming more and more im-majority of events resulted in degraded opera-p rtant to U.S. utilitics as the median age of U.S.

tion (Iow pressure, air quality out of limits). Nor-malwearof thesystemandcontaminationof the

". Elm pgwu plants inemam. p,nho@fymg plant life g and detec-tm of agmg erects should aid m justi air dominate the problems rd system failure.

eM s and mdt in sab and nm dunt opp Procedures and testing for the response of per.

tion during the present and extended life pen,od. It has sonnel and equipment to these conditions been demonstrated that monitoring programs based on should be develoIicd.

neutron noise and vibration measurements utihz, g m

lluman error was a significant cause of failures signature analysis can effectively detect, and in some e

in critical components such as compressors and cases diagnose, degradation of reactor vessel internals.

dryers, as well as at the system and intersystem Such programs have the potential to reduce plant level. Training should be augmented in two key downtime, make periodic maintenance more effective, areas:(1) operation and maintenance of critical and increase plant safety.

air system components and (2) understanding hionitoring of reactor internals can be considered a the importance of instrument air to other plant particular application of the general concept of predic-systems, particularly safety systems.

tive maintenance, the techniques of which are already The outside systems that were most often af-widely used in industry to monitor rotating machinery, e

fccted by instrument air problems are contain-Predictive maintenance will be further implemented as ment isolation, main feedwater/ main steam, (1) its benefits become better documented, (2) famili-auxiliary feedwater, and the llWR scram sys-arity with the techniques and their applications grows, tem. The most commonly affected components and (3) better hardware and software become avail-were air operated and solenoid-operated able. A similar statement could apply to the monitoring

. valves.

of reactorinternals. Although this monitoring has been The probabilistic work entailed the develop-spotty in the U.S., the above-mentioned techniques e

ment of a computer program (PRAAGH IA) have been widely applied in Europe, particularly in using a PR A-based instrument air system model France and the Federal Republic of Germany, where to perform time-dependent PRA calculations, they are currently (in 1989) 5 to 10 years ahead ohhose Time dependent failure rates were developed in this country. U.S. utilities could benefit from the from the data base and other inputs to the pro-experience in liurope, where, in many cases, internals gram to calculate system unavailability and com.

monitorinF has been integrated into regular plant ponent importances for various ages. The re, maintenance programs. Thus U.S. utilities could im-sults showed that, when the time-dependent ef, plement effective monitoring programs with a mini-fects of aging for the worst case are accounted mum of nperimentation and wasted effort, for, there are two significant system effects:(1)

The tuport begins with a description of some promi-system unavailability increases moderately with nent mechanisms through which degradation of reac-age and (2) the relative importance of compo-tor intctnals occurs; the cause of most cases of this nents changes with age. During early operation, degradation is flow-induced vibration. Other mecha-leakage in both instrument air / service air piping nisms are also reviewed. This is followed by a brief NURiiG-1377 30

m 9

A'.L,

- Main Citations and Summaries th 3 g

[

$4 f, '

M Nescription of vibration monitoring and neutron noise central station nuclear plant, the Shippingport Station.

4 J

1 analysis, including a comparison and evaluation of parallels commercial pressurized water reactors in re-

these two methods. Next. current practices are summa-actor, steam, auxiliary, support, and safety systems.

y rized, and examples of applications of these methodsin The 25-year service life (1957 to 1982) covers alniost

' ~ iboth the U.S. and !!urope (mainly West Germany and the entire period of currently operating reactors. Also,.

- France) nre given. 'the teport concludes with guide-because of substantial modifications during: the lines for setting up what the authors consider to be a mid-1960s and 1970s, it offers unique examples of f

12 T : reasonable internals monitoring program--for U.S.

identical or similar equ_ipment used side by side with -

utilities.

the original equipment but representing different vin-4 tages and degrees of aging. As part of the Shippingport

_l NUREG/CR-5491,11.~ P. Allen and A.11. Johnson, Jr.,

Station aging evaluation work, more than 200 items,

[,.

' ' "Shippingport Station Aging Evaluation." Pacific ranging in size from small instruments and material Northwest laboratory, PNir7191, January 1990.

samples to main coolant pumps, have been removed.

,M This report describes a research plan to address and shipped to designated laboratories. These items.

q 1

osafety concerns on aging of snubbers used on piping include battery chargers, inverters, relays. breakers, 4

- and equipment in commercial nuclear power plants.

switches, power and control cables, electrical penetra-The work is to be performed under Phase !! of the tions, check valves, solenoid valves, and motor-b'M '

s Snubber Aging Study of the NRC NPAR program with operated valves. Samples of piping from various plant

- the Pacific Northwest laboratory (PNL)as the prime systems also have been acquired for radiological char-

}

contractor. Research conducted by PNL under Phase !

acterization studies, and samples from the primary sys-provided an initial assessment of. snubber operation tem components will be used for material degradation 3

= based primarily on a review of Ilcensee event reports.

studies.

The work proposed is an extension of Phase I activities Data and records relevant to thi procurement, op.

and covers research at nuclear power plants and in test cration, and maintenance of these materials and com.

laboratories.The report includes t echnical background ponents have been obtained to support the detailed -

on the design and use of snubbers in commercial nu-aging evaluations. In situ assessments of Shippingport 4

" clear power applications and a discussion of the pri-Station components also have been conducted, includ-i mary failure modes of both hydraulic and mechanical ing preremovat visual and physical examinations of -

snubbers. The anticipated safety, technical, and regu-components, tests of electrical circuits, and special latory benefits of the work, along with concerns of the measurements to assist in the selection of specific com-1 NRC and the utilities, are also subjects of the report.

ponents for further evaluation. Although ; detailed ~

l The Shippingport Atomic Power Station, presently evaluations of the naturally aged components and ma.

j h,?;<

- (1989 in the final stages of decommissioning, has been =

terial from the Shippingport Station have not been j

^

f a'maj)or source of naturally aged equipment for the completed, the results from preliminary studies indi.

2 NPAR and other NRC programs. The evaluation of cate the value of the aging information that may ulti-

. naturally aged components is an element of the NPAR matcly be obtained.

program strategy, llecause naturally aged components PN1-5722, D. I!. Illahnik and R; L. Goodman, and materials experience the actual service-related ex-Operating IIxperience and Aging Assessment of

, ternal stressors, corrosion and wear, testing procc-ECCS Pump Room Coolers," Pacific Northwest 1

!dures, and maintenance practices, the evaluation of Imboratory, October 1986.

l

such components is valuable. One is able to verify This report provides a preliminary aging assess.

4 degradation models, to validate -aging projections ment of safety-related room coolers for the emergency

based on the extrapolation of accelerated test data,and

. core cooling system (ECCS) pump rooms in nuclear to detect unexpected agmg mechanisms (surprises)-

power plants. The assessment conSrms to the NRC f that could significantly affect the safety performances NPAR program strategy and'is based on limited m

of components or systems-information obtained through public and private data j

. 'Despite their importance for plant studies, natu.

bases, equipment vendors, utility contacts, literature (rally aged components of the desired type and vintage searches, and expert opimon.

q y'

, l are not readily available.The best source of these com-Description of the.ECCS pump room cooler sys-j ponents is operational equipment from retired plants.

tems were based on FSARs and vendor supplied infor-The decommissioning of the Shippingport Station, par-mation. Data from LERs, review of maintenance i ticularly because it was managed by the U.S. Depart-requests at a reactor plant, and discussions with per-l sment'of Energy, represents a valuable opportunity to sonnel that do utility repair and maintenance work Jconduct in situ assessments at an aged reactor and to were used to determine the operating experience of

- obtain a variety of naturally aged and degraded compo-pump room coolers, l'ailure modes, causes, frequency

nents and ' samples for detailed aging evaluations by rates, and methods of detection are summarized from s NRC contractors. As-the first U.S. large scale, the-operating records. hlaintenance actions and 31 NURiiG-1377

Main Citations and Summ2 ries -

modifications needed as a result of the operator experi-allows meaningful predictions to be made for long-ence are addressed. Operational stressors are summa-term, low-dose-rate radiation aging conditions. Using rized, manufactur' r recommendations for maintenan.

historical data from Sandia's radiation aging program e

ce and surveillance are listed, and aging and service-on nuclear power plant cable materials, the authors wear monitoring are brictly evaluated, have successfully applied the time-temperature dose-rate superposition approach to four different materi-PN14287, K. R. Iloopingarner,11, J. Kirkwood, and als: hypalon, neoprene, polyethylene, and PVC jacket P. J. Lonzecky, " Study Group Review of Nuclear material. For two of these materials, extrapolated pre.

i Service Diesel Generator Testing and Agmg hiitiga' dictions based on the superimposed data were found to tion," Pacific Northwest laboratory, hlarch 1988-be in excellent agreement with 12 year, low dose rate As part of the NPAR program, the Pacific North, nuclear power plant results.

west laboratory is performing a diesel generator aging WYIE 60103-X, J. F. Gleason, R. A. Del.our, J. hi.

assessment study, in the on going NPAR Phase 11 of 11 mm nd, and P. A. Lubeski. l'est Plan for the the a8"8 study, efforts have been focused on a8'n8 Comprehensive Aging Assessment of Circuit Ilreak-i mitigation and other success strategies for improvm!

g ers and Relays for Nuclear Plant Aging Research l

nuclear plant diesel generator operation and mainten-(NPAR) Program, Phase II," Wyle laboratories, ance and also increasing its reliability.

Iluntsytile, AI, July 1989.

j A study group of dicsci experts, the authors of this This entry refers to seven individually bound re-report, met on April 29 and 30,1987, to resolve issues ports, each presenting the test plan for a specific type on mitigating diesel generator aging and improving of circuit breaker or relay:

q operations, testing, and maintenance.The focus of the 60103-1 hiolded case circuit breakers study group was to (1) address the diesel generator 60103-2 hietal clad circuit breakers agmg stressors tesulting from the present penodic test-60103-3 Auxiliary relays mg practices of the nuclear m, dustry and (2) propose 60103-4 Control relays j

potential mitigating measures. A new recommended 60103-5 Protective relays testmg program was developed and is documented in 60103-6 Timing relays this report. The report lays out the conclusions and 60103-7 Electronic relays recommendations of the study group. The experts agreed that, if these recommendations are put into The purpose of these reports is to provide details of practice, many of the engine aging stressors (e.g., those the tests planned for the types of circuit breakers and due to fast start) could be reduced or climinated; an.

relays under investigation in Phase II of the Compre-other consequence could be a reduction of failures and hensive Aging Assessment of Circuit lireakers and j

an improvement in operability and reliability.

Relays. This work is being performed by Wyle l abora-tories for the NRC NPAR program, which is intended SAND 88-0754 UC-78, K. T. Gillen and R. L Clough, to resolve technical safety issues related to the aging

" Time Temperature Dose Rate Superposition: A degradation of electrical and mechanical components, hiethodology for Predicting Cable Degradation Un-safety systems, support systems, and civil structures der Ambient Nuclear Power Plant Ag g Condi-used in commercial nuclear power plants. Tbc aging tions " Sandia National Laboratones, ugust 1988.

period of interest includes the period of normal li-Time temperature superposition is an empirical censed plant operation as well as the, period of ex-approach that has been used in polymers for more than tended plant life that may be requested m utility apph-cations for hcense renewals.

I 30 years to make thermal aging predictions during ex-perimentally inaccessible times. Given the historical The Phase I report, NUREG/CR-4715,"An Aging success of time temperature superposition, the Assessment of Relays and Circuit Ilreakers and System authors have expanded this approach for combined Interactions," showed that relays and circuit breakers l

radiation-thermal environments, yielding an empirical are important nuclear plant components that are sus-

)

time temperature dose rate shifting procedure. The ceptible to degradation with time. Thus Phase II, a procedure derives an isothermal curve for a given comprehensive aging assessment of relays and circuit amount of material damage versus dose rate at a se-breakers, was implemented to provide (1) a review and lected reference temperature. This is done by finding verification of improved inspection, surveillance, J

the Arrhenius activation energy that causes higher-monitoring, and maintenance methods: (2)in situ ex-temperature dose rate data to superpose when shifted aminations and data gathering for operating equip-to the reference temperature. The resulting super-ment: (3) postsenice examinations of naturally aged posed curve at the reference temperature extends to components or components with simulated degrada-much lower dose rates that are experimentally inacces-tion; (4) an evaluation of the role of maintenance in sible because of the long time periods that would be mitigating the effects of aging:(5)cvaluations of meth-required to simulate aging. This procedure therefore ods for predicting residuals and service life; and NUREG-1377 32

Main Citations and Summaries (6) recommendations for using research restilts in the strategy, list and elaborate on the objectives of the regulatory process. Specific goals of the program are:

research, and define the testing to be performed on Teidentify and characterize aging effects that if naturally aged and degraded equipment in order to e

unchecked, could cause degradation of compo.

determine the methods most effective for detecting nents and subsystems of circuit breakers and age degradation. Emphasis has been placed on identi-relays and thereby impair plant safety, fying and characterizing the mechanisms of material To identify methods of inspection, surveillance, and component degradation during service and using e

and monitoring and to evaluate the residual life research results in the regulatory process.

of components and subsystems of circuit break.

The testing consists of performing and evaluating ers and relays that will ensure timely detection various methods of inspection, surveillance, condition of significant agmg effects before loss of their monitoring, and maintenance, including simulated safety function.

degradation, to aid in determining the usefulness of To evaluate the effectiveness of storage, main-these methods for managing the effects of aging on safe e

tenance, repair, and replacement practices in plant operation. He devices chosen for testing are mitigating the rate and extent of degradation representative of circuit breakers and rt: lays that have caused by aging, been in use in nuclear power plants. New, used, and l

Methods are available to detect and mitigate aging aged specimens up to 40 years old have been located degradation and thereby to minimize its impact. The from a variety of sources, including Wyle stock and reports describe the background of the research nuclear plants.

l 33 NUlmG-1377

PERSONAL AUTHOR INDEX This index lists, in alphabetical order, all participating authors of each report listed in the main citation listing. !!ach name is followed by the number and the title of the reports prepared by the author, if further information is needed, refer to the main citation by the report number, Adams, M.L.

Heranck, A.F.

NUREG/CR-4597," Aging and Service Weat of Aux.

NUREG/CP-0100," Proceedings of the International iliary Feedwater Pumps for PWR Nuclear Power Nuclear Power Plant Aging Symposium."

Plants, Vol.1: Operating lixperience and Failure iden-

. tification." -

Bersy. D.L.

NUREG/CR-3818, " Report of Results of Nuclear Ahmed, S.

Power Plant Aging Workshop."

NURl!G/CR-4257, " Inspection. Surveillance, and i

Monitoring of Electrical Equipment inside Contain.

Blahnik, D.E.

ment of Nuclear Power Plants-With Applications to PNI-5722," Operating Experience and Aging Assess-

)

Electrical Cables."

ment of ECCS Pump Room Coolers."

[

Allen, R.l'.

Horkowski, R.J.

NURl!G/CR-5491, "Shippingport Station Aging NURl!G/CR-2641, "'lhe in. Plant Reliability Data

!! valuation."

llase for Nuclear Power Plant Comp <ments: Data Col-lection and hiethodology Report."

Anderson, R.L.

NUREG/CR-3154, "The in Plant Reliability Data NURl!G/CR-4928, " Degradation of Nuclear Plant Base for Nuclear Plant Components: Interim Temperature Sensors."

Report-The Valve Component."

Arendts, J G.

Brown, D.I'.

NUREG/CR-4977, "SilAO Test Series: Scismic Re-NUREG/CR-5386, "llasis for Snubber Aging Re-

)

search on an Aged United States Gate Valve and on a search: Nuclear Plant Aging Research Program."

Piping System in the Decommissioned Heissdampf-i reaktor (ilDR): Summary," Vol.1.

Burns, E.L.

NUREG/CR-4977, "Sil AG Test Series: Seismic Re-NUREG!CR-4156, "Opereting Experience and Ag.

scarch on an Aged United States Gate Valve and on a ing Se smic Assessment of Electric Motors."

Piping System in the Decommissioned licissdampf-reaktor (IIDR): Appendices," Vol. 2.

Bush, S.II.

NUREG/CR-4279, " Aging and Service Wear of fly-Hacanskas, V.I'.

draulic and hicchanical Snubbers Used on Safety-NUREG/CR-4715,"An Aging Assessment of Relays Related Piping and Components of Nuclear Power and Circuit lireakers and System Interactions."

PI""18' V I' I' NUREG/CR-4819, " Aging and Service Wear of So!c.

Carfagno, A.

noid-Operated Valves Used in Safety Systems of Nu-NUREG/CR-4257, " Inspection, Surveillance, and i

clear Power Plants, Vol.1: Operating Experience and hionitoring of Electrical liquipment inside Contain.

Failure Identification."

ment of Nuclear Power Plants-With Applications to NUREG/CR-4992," Aging and Service Wear of hiul.

Electrical Cables."

tistage Switches Used in Safety Systems of Nuclear NUREG/CR-5141, " Aging and Qualification Re-Power Plants," Vol.1.

scarch on Solenoid Operated Valves."

NUREG/CR-5141, " Aging and Qualification Re-i search on Solenoid Operated Valves "

Ctesada, M.L.

NU R EG/CR-3543, " Survey or Operating Experiences Bader, H.E.

from 1.ERs to identify Aging Trends."

NUREG/CP-0036," Proceedings of the Workshop on NUREGICR-5334," Severe AccidentTestingof Elec-Nuclear Plant Aging."

trical Penetration Assemblies."

35 NURl!G-1377 n

n

i Personal AuthuIndex Cesarski, W.V.

Cndkowski, C.J.

NUREG/CR-4597. " Aging and Service Wear of Aux-NUREG/CR-4985," Indian Point 2 Reactor Coolant iliary Feedwater Pumps for PWR Nuclear Power Pump Seal Evaluations."

Plants, Vol. 2: Aging Assessments and Monitoring Method Evaluations."

Damiano. B.

NUREG/CR-5479, " Current Applications of Vibra-Cifuentes, F.

tion Monitoring and Neutron Noise Analysis: Detec-UNL Technical Report A-3270-11-85, "Scismic tion and Analysis of Structural Degradation of Reactor Endurance Tests of Naturally Aged Small Electric VesselInternals from Operational Aging."

Motors."

Davis, T.

Clark, N.H.

NUREG/CR-4144, "importance Ranking Based on NUREG/CR-3818, " Report of Results of Nuclear Aging Consideration of Components included in Probabilistic Risk Assessments "

Power Plant Aging Workshop "

Defour, R.A.

Clauss, D.B.

WYLE 60103-X," Test Plan for the Comprehensive NUREG/CR-5334." Severe AccidentTestingof Elec-Aging Assessment of Circuit lireakers and Relays for trical Penetration Assemblics" Nuclear Plant Aging Research (NPAR) Program, Cletcher, J.W.

NUREG/CR-4692," Operating Experience Review of Dewall, K.G.

Pa!!ures of Power Operated Relief Valves and Block NUREG/CR-3819. " Survey of Aged Power Plant Valves m Nuclear Power Plants."

Facilities."

Clinton, J.

Dingee, D.A.

NUREG/CR-4985," Indian Point 2 Reactor Coolant NUREG/CR-4590," Aging of Nuclear Station Diesel Pump Seal Evaluations."

Generators: Evaluation of Operating and Expert Ex-perience," Vols. I and 2.

SAND 88-0754 UC-78, " Time Tem,,crature-Dose Dinsel, M.R.

Rate Superposition: A Methodology 'or Predicting Ca-NUREG/CR-3956, "In Situ Testing of the Ship-ble Degradation Under Ambient Nuclear Power Plant pingport Atomic Power Station Electrical Circuits."

Aging Conditions."

Dodge, R.E.

Collins, E.P.

NUREG/CR-4279, " Aging and Service Wear of Hy-NUREG/CR-5248,"Prioritization of TIRAGALEX-draulic and Mechanical Snubbers Used on Safety-Recommended Components for Further Aging Related Piping and Components of Nuclear Power Research."

Plants," Vol.1.

Cornwell, B.C.

Donaldson, M.R.

NUREG/CR-3819, " Survey of Aged Power Plant NUREGICR-3956, "In Situ Testing of the Ship-Facilities."

pingport Atomic Power Station Electrical Circuits."

Crowley, J.L.

Drago, J.P.

NUREGICR-2641 "The in Plant Reliability Data NUREG/CR-4380, " Evaluation of the Motor-llase for Nuclear Power Plant Components: Data Col-Operated Valve Analysis and Test System (MOVATS) lection and Methodology Report.

to _ Detect Degradation, Incorrect Adjustments, and Other Abnormalities in Motor Operated Valves."

Edson, J.L.

Curreri, J.

NUREG/CR-4457, " Aging of Class lE Datteries in Saf ty Systems of Nuclear Power Plants."

BNL Technical Report A-3270-Il-85, " Seismic En-durance Tests of Naturally Aged Small Electric NUREG/CR-5181, " Nuclear Plant Aging Research:

Motors."

The IE Power System."

NUREG-1377 36 n

rL

Personal Author Index Eissenberg, D.ht.

Gleason, J.F.

N URiiG/CR-4234, " Aging and Service Wear of !!lec-WYl.E 60103-X. "fest Plan for the C9mprehensive tric Motor Operated Valves Used in linginected Aging Assessment of Cirruit Dreakers and Relays for Safety-Feature Systems of Nuclear Power Plants,"

Nuclear Plant Aging Research (NPAR) Program.

Vol.1.

Phase II,"

NURl!G/CR-4302, " Aging and Service Wear of Goldberg, F.F.

Check Valves Used in lingineered Safety Feature Sys-NURiiG/CR-2641, "The In Plant Reliability Data tems of Nuclear Power Plants, Vol.1.

Ilase for Nuclear Power Plant Components: Data Col-NURl!G/CR-4380, "livaluation of the Motor, lection and Methodology Report."

Operated Valve Analysis andTest System (MOVATS) to Detect Degradation, incorrect Adjustments, and Goodman, it.L.

Other Abnorrnalities in Motor Operated Valves."

PNie5722 " Operating lixperience and Aging Assess-ment of ECCS Pump Room Coolers."

Fain, it.E.

Gore, bl.L.

NURiiG/CR-5383, "lifIcct of Aging on Response NURl!G/CR-5379," Nuclear Plant Service Water Sys-

, Time of Nuclear Plant Pressure Sensors."

tem Aging Degradation Assessment: Phase 1," Voi.1.

Fragola, J.it.

Greenstreet, W.L.

NURiiG/CR-3154, "The in Plant Reliability Data NUREG/CR-4234," Aging and Service Wear of Elec.

Ilase for Nuclear Plant Components: Interim Re.

tric Motor Operated Valves Used in Engineered port-The Valve Component,"

Safety. Feature Systems of Nuclear Power Plants,"

Vol.1.

Fullwood,11.

NURl!G/CR-4302, " Aging and Service Wear of IlNL Technical Report A-3270-12-86, " Aging and Check Valves Used in lingineered Safety Feature Sys-life lixtension Assessment Program (Al.EAP) Sys-tems of Nuclear Power Plants, Vol.1.

tems i.evel Plan."

Gunther, W.E.

NUREG/CR 5052,"Operatinglixperienceand Aging NUREG/CR-4564, " Operating fixperience and Ag-Assessment of Component Cooling Water Systems in ing-Seismic Assessment of flattery Chargers and in.

Pressurized Water Reactors."

verters."

NUREG/CR-5268, " Aging Study of Holling Water NUREG/CR-4939, " Improving Motor Reliability in i

Reactor Residual IIcat Removal System."

Nuclear Power Plants;" Volume 1: Performance Evaluation and Maintenance Practices: Volume 2:

NUREG/CR-5419," Aging Assessment ofInstrument Functional Indicator Tests on a Small Electric Motor -

Air Systems in Nuclear Power Plants."

Subjected to Accelerated Aging: Volume 3: Failure Analysis and Diagnostic Tests on a Naturally Aged Gallaher,11.11.

Electric Motor.

NUREG/CR-3543," Survey of Operating Experiences NUREG/CR-5051," Detecting and Mitigating Battery from 1.!!Rs to identify Aging Trends."

Charger and Inverter Aging."

NUREG/CR-4302, " Aging and Service Wear of NUREG/CR-5192,"Festing of a Naturally Aged Nu-Check Valves Used in lingineered Safety Feature Sys, clear Power Plant Inverter and Battery Charger."

D tems of Nuclear Power Plants " Voi.1.

NUREG/CR-5268, " Aging Study of Boiling Water Reactor Residuallleat Removal System."

Gillen, K.T.

"**U" SAND 88-0754 UC-78, " Time-Temperature Dose Rate Superposition: A Methodology for PredictingCa-WYLI! 60103-X, " rest Plan for the Comprehensive ble Degradation Under Ambient Nuclear Power Plant Aging Assessment of Circult Ilreakers and Relays for Aging Conditions."

Nuclear Plant Aging Research (NPAR) Program, I hase 11.,

Gingrich, J.J.

Ilanchey, L.A.

NURI!G/CR-5383, "liffect of Aging on Response NUREG/CP-0036, " Proceedings of the Workshop on Time of Nuclear Plant Pressure Seasors."

Nuclear Plant Agirig."

37 NUREG-1377

/V

/s 1

Personal AuthorIndex

)

liardin, J.E.

PNL-6287. " Study Group iteview of Nuclear Service Diesel Generator Testmg and Aging Mitigation.

NURilG/CR-4457, " Aging of Class 111 llatteries in Safety Systems of Nuclear Power Plants."

llorst, C.L.

NUREG/CR-5159. " Prediction of Check Valve Per-linshemian, li.M.

formance and Degmdation in Nuclear Power Plant i

NURiiG/CR-4928,

• Degradation of Nuclear Plant Systems."

Temperature Sensors."

lloy,ll.C.

NURl!G/CR-5383, *llffect of Aging on Response Time of Nuclear Plant Pressure Sensors "

NURI!G/CR-3543,"Surveyof Operating !!xperiences 3

from I.liRs to identify Aging Trends."

l llaynes, ll D.

Jarrell, D.ll.

NURiiG/CR-4234," Aging and Service Wear of !!!cc-NURI!G/CR-5248, "Prioritization of TIRG All!X.

tn,e Motor-Operated Valves Used m I!ngineered Recommended Components for Further Aging Safety Feature Systems of Nuclear Power Plants: Ag-Research."

ing Assessments and Monitoring Method livalu-ations," Vol. 2.

NURl!G/CR-5379," Nuclear Plant Service WaterSys-1 tem Aging Degradation Assessment: Phase 1," Vol.1.

Hensh, M.

f Johnson, A.ll, drauhe and Mecham, Aging and Service Wear of Ily.

N URl!G/CR-5379," Nuclear Plant Service Water Sys-N URI!G/CR-4279, "

cal Snubbers Used on Safety-tem Aging Degradation Assessment: Phase I," Vol.1.

Related Piping and Components of Nuclear i ower Plants," Vol.1.

NUREGICR-5491. "Shippingport Station Aging livaluation."

o IIchble, T.L.

Johnson, J.W.

f NURiiG/CR-3154 "The In Plant Reliability Data NURl!G/CR-3154, "The in-Plant Reliability Data llase for Nuclear Plant Components: Interim Re-Ilase for Nuclear Plant Components: Interim

(

port-The Valve Component.

Report-The Valve Component."

{

-f Iliggins, J.C.

Kahl, W.K.

llNL Technaal Report A4270-ll-85, "Scismic lin-NUREG/CR-3154, "The in Plant Reliability Data durance Tests of Naturatly Aged Small lilectric Mo-Ilase for Nuclear Plant Components: Interim Re-tors."

port-The Valve Component."

[

s llNL Technical Report A-3270-12-86, " Aging and g gyg;' g,g' 1

Life Extension Assessment Program (Al.liAP) Sys-d tems Level Plan."

NUREG/CR-5159, " Prediction of Check Valve Per-fonnance and Degradation in Nuclear Power Plant NURiiG/CR-5052," Operating lixperience and Aging Systems."

Assessment of Component Cooling Water Systems in Pressurized Water Reactors."

Kerlin, T.W.

l NURl!G/CR-4928, " Degradation of Nuclear Plant l

llolbert, K.E.

Temperaiute Sensors."

NURl!G/CR-4928, " Degradation of Nuclear Plant Temperature Sensors."

Kirkwood, II.J.

PNL-6287," Study Group Review of Nuclear Service Iloopingarner, K.ll Diesel GeneratorTesting and Aging Mitigation."

q NURI!G/CR-4590," Aging of Nuclear Station Diesel Kileh, D.M*

4 Generators: Evaluation of Operating and lixpen lix, perience." Vols. I and 2.

NURiiG/CR-4597," Aging and Service Wear of Aux-iliary Feedwater Pumps for PWR Nuclear Power NURIiG/CR-5057, " Aging Mitigation and improved Plants, Vol. 2: Aging Assessments and Monitoring Programs for Nuclear Sersice Diesel Generators."

Method livaluations."

NUREG-1377 38 A

6

Personal AuthorIndex 1

Kryter, It.C.

hiacDonald, P.E.

j NUREG/CR-5479, " Current Applications of Vibra-NUREG/CR-4731."Residuallife Assessment of My tion hionitoring and Neutron Noise Analysis: Detec.

jor IJght Water Reactor Components," Vol.1.

tion and Analysis of Structural Degradation of Reactor NUREG/CR-4731 " Residual Life Assessment of Ma-VesselInternals from Operational Agmg" jor Light Water Reactor Components-Overview,"

Vol. 2.

Kurth,11.

NUREG/CR-4144, *1mportance Ranking Ilased on hiakay, E.

1 Aging Consideration of Components Included in NUREG/CR-4597. " Aging and Service Wear of Aux-Probabilistic Risk Assessments."

aliary Feedwater Pumps for PWit Nuclear Power Plants, Vol.1: Operating Experience and Failure Iden-Leverenz, F.

tification."

NURl!G/CR-4144, "importance Ranking liased on hicale, ll.hl.

ses men s.E " "

NURiiG/CR-4747."An Aging Failure Survey of Light r i bi t I sk Water Reactor Safety Systems and Components,"

Vol.1.

Levy, l.S.

NURl!G/CR-5248, "Prioritization of TIRGALEX-

",UREG/CR-4747. "An Aging Failure Survey of Light, 3

Recommended Components for Further Aging Re-

",U actor Safety Systems and Components, g3 search.,

4 hicininger, It.D.

Lewis,11.

NUREG/CR-5008 " Development of a Testing and NU R EG/CR-5051, " Detecting and Mitigating liattery Analysis Methodology to Determine the Functional Chargcr and Inverter Aging."

Condition of Solenoid Operated Valves."

Lodlow, C.C.

hieyer, L,C.

NUREG/CR-4715,"An Aging Assessment of Relays NUREG/CR-1740,." Nuclear Plant-Aging Research '

and Circuit Ilreakers and System Interactions."

on Reactor Protection Systems.

NUREGICRwl967, " Nuclear Plant Aging Research Lofaro, II.

on Iligh Pressure injection Systems."

- )

NUltt!G/CR-4939, *1mproving Motor Reliability in NUREG/CR-5181, " Nuclear Plant Aging Research:

i Nuclear Power Plants:" Volume 1: Performance The IE Power System."

I! valuation and Maintenance Practices: Volume 2:

Functional Indicator Tests on a Small lilectric Motor h1 iller,11.

Subjected to Accelerated Aging: Volume 3: Failure UNI. Tecimical Report A-3270-Il-26-84. " Scoping Analysis and Diagnostic Tests on a Naturally Aged Test on Containment Purge and Vent Valve Seat

' Electric Motor.

Material."

NURl!G/CR-5052," Operating Experience and Aging hlorris' ll.h1*

Assessment of Component Cooling Water Systems in Pressurized Water Reactors."

NURl!G-il44, " Nuclear Plant Aging Research (NPAR) Program Plan."

NUREG/CR-5268, " Aging Study of Iloiling Water Reactor Residual lleat Removal System."

h1urphy,G.A.

NURiiG/CR-3543," Survey of Operating Experiences Lonzecky, P.J.

from 1.ERs to identify Aging Trends."

PNir6287,'" Study Group Review of Nuclear Senice NUREG/CR-4234, " Aging and Senice Wear of Elec-Diesel Generator Testing and Aging Mitigation."

tric Motor Gperated Valves Used in lingineered Safety Feature Systems of Nuclear Power Plants,"

Lubeski, P.A.

Vol.1.

W YLE 60103-X.l'est Plan for Comprehensive Aging NUREG/CR-4302, " Aging and Service Wear of Assessment of Circuit lireakers and Relays for Nuclear Check Valves Used in Engineered Safety-Feature Sys-Plant Aging Research (NPAR) Program, Phase II."

tems of Nuclear Power Plants," Vol.1.

1 39 NURI!G-1377 f

A.

Personal AuthorIndex NURl!G/CR-4692, " Operating lixperience Review of NUREG/CR-4992," Aging and Service Wear of hiul-Failures of Power Operated Relief Valves and Block listage Switches Used in Safety Systems of Nuclear Valves in Nuclear Power Plants."

Power Plants," Vol.1.

Naus, D.J.

Rose, J.A.

j (EG/CR-3819," Survey of Aged Power Plant Fa-l NURl!G/CR-4652

• Concrete Component Agingand C'

C8' Its Significance Relative to Life Extension of Nuclear Power Plants."

Sattemhite, D.G.

NUREG/CR-4747,"An Aging Failure Survey of L.ight Nehn,ng,1,.

Water Reactor Safety Systems and Components,"

l DNL Technical Report A-3270-11-85 "Scismic En-Vol.1.

d ince Tests of Naturally Aged Small Electric hio-NUREGICR-4747,"An Aging Failure Survey of Light Water Reactor Safety Systems and Components" Vol. 2.

Nesbitt, J.F.

Schlonski, J.S.

NUREG/CR-4590," Aging of Nuclear Station Diesel Ocnerators: livaluation of Operating and 11xpert Ex-NUREG/CR-4992," Aging and Service Wear of hiul-l perience " Vols. I and 2.

tistage Switches Used in Safety Systems of Nuclear Power Plants," Vol.1.

Palmer, G.R.

Shafaghi, A.

NURl!G/CR-5386, "llasis for Snubber Aging Rc' NUREG/CR-4144, "importance Ranking liased on search: Nuclear Plant Aging Research Program."

Aging Consideration of Components included in j

Probabilistic Risk Assessments."

Petersen, K.M.

ah, V.N.

l NURI!G/CR-4928, " Degradation of Nuclear Plant Temperature Sensors."

NUREG/CR-4731," Residual 1.ife Assessment of hla-jor Light Water Reactor Components," Vol.1.

NUREG/CR-5383, "Effect of Aging on Response NUREG/CR-4731. " Residual Life Assessment of hia-

, lime of Nuclear Plant i,ressure Sensors.,,

jor Light Water Reactor Components-Overview,"

I Vol. 2.

Pike, D.II.

NUREG/CR-2641 "The in Plant Reliability Data Sheets, M.W.

f Ilase for Nuclear Power Plant Components: Data Col-bNL Technical Report A-3270-3-86,." Testing Pro-lection and blethodology Report."

gram for the hionitoring of Degradation in a Continu.

ous Duty 460 Volt Class "11",10-HP Electric hiotor."

Reich, M.

NUREG/CR-4939, almproving hiotor Reliability in Nuclear Power Plants;". Volume 1: Performance Eval-llN!, Technical Report A-3270-11-85, "Scismic En.

uation and hiainten;nce Practices; Volume 2: Func-durance Tests of Naturally Aged Small Electric hio, tional Indicator Tests on a Small Electric hiotor

. tors."

Subjected to Accelerated Aging: Volume 3: Failure Ah ysis and Di gnostic Tests n a Naturally Aged Rib' IN*

lilectric hiotor.

Letter Report. L N. Rib, " Summaries of Research Reports Submitted in Connection with the Nuclear Shier, W.

Plant AgingResearch(NPAR) Program." Engineering NUREG/CR-5053," Operating lixperience and Aging j

and Economics Research, Inc. (IiER).'

Assessment of hiotor Control Centers."

NUREG/CR-5268, " Aging Study of Boiling Water l

Roberts, G.C.

Reactor Residual lleat Removal System."

NUREGICR-4819, " Aging and Service Wear of Sole-noid. Operated Valves Used in Safety Systems of Nu.

Shook, T.A.

clear Power Plants, Vol.1: Operating lixperience and NURI!G/CR-4715,"An Aging Assessment of Relays Failure Identification."

and Circuit Ilreakers and System Interactions.

ll 1

NURl!G-1377 40 g

- J\\

d

Personal Authorindex Silver, M.M.

NUREG/ Cit-4156, " Operating Experience and llNLTechnical Report A-3270-12-85," Pilot Assess-Aging Seismic Assessment of Electric Motors."

ment: Impact of Aj;ing on the Seismic Performance of NUREG/CR-4564, " Operating Experience and Selected liquipment 'lypes "

Aging Scismic Assessment of llattery Chargers and Inverters."

Skrciner, K.M.

N81 REG /CR-4939, "Irnproving Motor Reliability in NURiiG/CR-4939, " Improving Motor Reliability in Nuclear Power Plants;" Volume 1: Performance Nuclear Power Plants;" Volume 1: Performance

!! valuation and Maintenance Practices; Volume 2:

Evaluation and Maintenance Practices: Volume 2:

Functional Indicator Tests on a Small Electric Motor J

Functional Indicator Tests on a Small Electric Motor Subjected to Accelerated Aging; Volume 3: Failure Subjected to Accelerated Aging: Volume 3: Uniture Analysis and Diagnostic Tests on a Naturally Aged Analysis and Diagnostic Tests on a Naturally Aged I!!ectric Motor.

Electric Motor.

NUREG/CR-4985," Indian Point 2 Reactor Coolant Pump Seal !! valuations."

Soberano, Fil,.

i NURl!G/CR-3956, "In Situ Testing of the Ship-NURI!G/CR-5051," Detecting and Mitigating liattery pingport Atomic Power Station lilectrical Circuits."

Charger and Inverter Aging.

NUREGICR-5052,"OperatingIIxperience and Aging Sowatskey, P.J.

Assessment of Component Cooling Water Systems in Pwssurized Water Reactors."

NUREG/CR-4597," Aging and Service Wear of Aux.

iliary Feedwater Pumps for PWR Nuclear Power NURl!G/CR-5053," Operating lixperience and Aging Plants, Vol. 2: Aging Assessments and Monitoring Assessment of Motor Control Centers."

Method Evaluations "

NURl!G/CR-5268, " Aging Study of Iloiting Water Reactor Residual lleat Removal System."

Steele, R.

NUREG/CR-5419," Aging Assessment ofinstrument NUREG/CR-3819," Survey of Aged Power Plant 1,a' Air Systems in Nuclear Power Plants "

edities."

NUREG/CR-4977, "Sil AG Test Series: Seismic Re-Sugarman, A.C.

scarch on an Aged United States Gate Valve and on a llNL Technical Report A-3270-3-86, " Testing Pro-Piping System in the Decommissioned Ileissdampf-gram for the Monitoring of Degradation in a Continu-freaktor (IIDR): Summary," Vol.1.

ous Duty 460 Volt Class "11",10-1IP Illectric Motor."

NUREG/CR-4977, "SilAG Test Series: Seismic Re-NUREG/CR-4939, " Improving Motor Reliability in search on an Aged United States Gate Valve and on a Nuclear Power Plants;" Volume 1: Performance Piping System in the Decommissioned Heissdampf.

Evaluation and Maintenance Practices; Volume 2:

freaktor (llDR): Appendices " Vol. 2, Functional Indicator Tests on a Small Illectric Motor Subjected to Accelerated Aging; Volume 3: Failure Subudhi, M.

Analysis and Diagnostic Tests on a Naturally Aged I lectric Motor.

Letter Report, M. Subudhi," Review of Aging Seismic Correlation Studies on Nuclear Plant liquipment,"

Taylor, J.ll.

f Ilrookhaven Nationallaboratory, January 1985, llNL Technical Report A-3270-Il-85, " Seismic En-IINL Technical Report A-3270-Il-85, " Seismic En-durance Tests of Naturally Aged Small Electric Mo-durance Tests of Naturally Aged Small lilectric Mo-tors."

tors?

IINL Technical Report A-3270-12-86 " Aging and DNLTechnical Report A-3270-12-85," Pilot Assess-Life lixtension Assessment Program (All!AP) Sys-ment: Impact of Aging on the Seismic Performance of tems Level Plan."

Selected liquipment Types "

NUREG/CR-4156, " Operating Experience and IINL Technical Report A-3270-3-86, " Testing Pro.

Aging-Scismic Assessment of Electric Motors."

gram for the Monitoring of Degradation in a Continu-NURl!G/CR-4564, " Operating lixperience and

- ous Duty 460 Volt Class "11",10-IIP lilectric Motor."

Aging Scismic Assessment of Hattery Chargers and I"YCflC'S-llNL Technical Report A-3270-12-86, " Aging and Life Extension Assessment Program (ALEAP) Sys-NURI!G/CR-4939, " improving Motor Reliability in i

tems Level Plan."

Nuclear Power Plants;" Volume 1: Performance 41 NUREG-1377 f

/\\ :

A

(

Personal Authorindex Evaluation and hiaintenance Practices: Volume 2:

Yesely, W.E.

Functional Indicator Tests on a Small Electric hiotor NUREG/CR-4769, " Risk Evaluations of Agmg Phe-Subjected to Accelerated Aging: Volume 3: Failure nomena: The Linear Aging Reliability Model and its Analysis and Diagnostic Tests on a Naturally Aged Extensions."

Electric Motor.

NURilG/CR-4985," Indian Point 2 Reactor Coolant Villaran, M.

Pump Seal Evaluations."

NUREG/CR-5419," Aging Assessment ofInstrument NUREG/CR-5052," Operating Experience and Aging Air Systems in Nuclear Power Plants."

Assessment of Component Cooling Water Systems in Pressurized Water Reactors."

Vora, J.P.

NUREG-ll44," Nuclear Plant Aging Research

' NUREG/CR-5268, " Aging Study of Iloiling Water

("I AN) E*E'"* I I""'

Reactor Residual Ileat Removal System."

NURl!G-il44, " Nuclear Plant Aging Rese rch Toman, G.J.

(NPAR) Program Plan," Rev.1, NUREG/CR-4257, " Inspection, Surveillance, and Monitoring of Electrical Equipment inside Contain.

Wang, J.K.

ment of Nuclear Power Plants-With Applications to NUREG/CR-5159, " Prediction of Check Valve Per-Electrical Cables," Vol.1.

formance and Degradation in Nuclear Power Plant Systems."

NUREG/CR-4257, " Inspection, Surveillance, and l

Monitoring of Electrical Equipment in Nuclear Power 9,gg$ y Plants, Vol. 2: Pressure Transmitters."

NUREG/CR-4985, " Indian Point 2 Reactor Coolant NUREG/CR-4715,"An Aging Assessment of Relays Pump Seal Evaluations."

I and Circuit Ilreakers and System Interactions "

j NUREG/CR-4819, "Agmg and Seivice Wear of Sole-Weir, T.J.

I noid Operated Valves Used in Safety Systems of Nu-NUREG/CR-5008, " Development of a Testing and a

clear Power Plants, Vol.1: Operating lixperience and Analysis Methodology to Determine the Functional Failure Identification."

Condition of Solenoid Operated Valves."

l NUREG/CR-5141, " Aging and Qualification Re-search on Solenoid Operated Valves."

Werry, E.T,.

J NUREG/CR-5386, "llasis for Snubber Aging Re-Vasudevan, R.

search: Nuclear Plant Aging Research Program."

f IINLTechnical Report A-3270-12-85," Pilot Assess-ment: Impact of Aging on the Scismic Performance of

,Zaloudek, F.R.

Selected liquipment Types."

NUREG/CR-5057, " Aging Mitigation and improved Programs for Nuclear Service Diesel Generators."

l Vause, J.W.

t NUREG/CR-4590, " Aging of Nuclear Station Diesel Zimmerman, P.W.

Generators: Evaluation of Operating and Expert Ex.

NUREG/CR-5379, " Nuclear Plant Service Water Sys.

perience," Vols. I and 2.

tem Aging Degradation Assessment: Phase I," Vol.1.

1 1

j l

NUREG-1377 42 1

A A

a

i l'

i l

CORPORATE AUTilOR INDEX

'this index lists, in alphabetical order, the organizations that prepared the reports listed in this compila.

tion. Listed below each organization are the numbers and titles of its reports, if further information is

f needed, refer to the main citation by the report number.

Analysis and Measurement Servlees Corp.

NUld!G/CR-5052,"Operatinglixperienceand Aging

]

Assessment of Component Cooling Water Systems in e

NURl!G/CR-4928, " Degradation of Nuclear Plant Pressurved Water Reactors.,

Temperature Sensors."

NURl!G/CR-5053," Operating Experierce and Aging NUREG/CR-5383, "Effect of Aging on Response Assessment of hiotor Control Centers."

Time of Nuclear Plant Pressure Sensors."

NURIIG/CR-5192,"Testingof a Naturally Aged Nu-i clear Power PI nt Inverter and llattery Charger."

llrookhaven National Laboratory (llNL)

NURl!G/CR-5268, " Aging Study of Iloiting Water 1.etter Iteport, hi, Subudhi,"Reviev> of Aging Seismic Reactor Residual Heat Remmal System, Correlation Studies on Nuclear Plant Equipment,"

llrookhaven National 1 aboratory, January 1985.

NURl!G/CR-5419,* Aging Assessment ofinstrument Air Systems in Nuclear Power Plants."

llNL Technical Report A-3270-Il-26-84, " Scoping I

Test on Containment Purge and Vent valve Seal Engineering and Economics llesearch, Inc.

hiaterial."

(EElt) llNL Technical Report A-3270-11-85, "Scismic lin-i.etter Report, I N. Rib, " Summaries of Research dumnce Tests of Naturally Aged Small lilectric Reports Submitted in Connection with the Nuclear hiotors."

Plant Aging Research (NPAR) Program," Engineering and liconomics Research, Inc. (EER).

IINLTechm, cal Report A-3270-12-85," Pilot Assess-ment: Impact of Aging on the Seismic Performance of Franklin ltesearch Center Selected liquipment Types" NURl!G/CR-4715."An Aging Assessment of Relays llNL Technical Report A-3270-3-86, " Testing Pro, and Circuit lireakers and System Interactions."

gram for the hionitoring of Degradation in a Continu.

NURl!G/CR-5141, " Aging and Qualification Re-i ous Duty 460 Volt Class "11",10-1IP lilectric hiotor "

search on Solenoid Operated Valves."

I IINL Technical Report A-3270-12-86, " Aging and Idaho National Engineering Laboratory Life lixtension Assessment Program (Al IIAP) Sys-

,g tems i.evel I lan.

3 NURl!G/CR-3819," Survey of Aged Power Plant Fa-NUREG/CR-4156, " Operating Experience and eitities,"

Aging Seismic Assessment of lilectric hiotors."

NURiiG/CR-3956, "In Situ Testing of the Ship.

NURIIGICR-4564, " Operating Ilxperience and pingport Atomic Power Station lilectrical Circuits."

Aging-Scismic Assessment of llattery Chargers and NURl!G/CR-4457, " Aging of Class 111 llatteries in Inverters' Safety Systems of Nuclear Power Plants."

NUREG/CR-4715."An Aging Assessment of Relays NURl!G/CR-4731," Residual I.ife Assessment of bla-and Circuit lireakers and System Interactions."

jor Light Water Reactor Components," Vol.1.

NURl!G/CR-4939. " Improving hiotor Reliability in NUREG/CR-4731," Residual Life Assessment of hla.

Nuclear Power Plants;" Volume 1: Performance lival-jor 1.ight Water Reactor Components-Overview,"

uation and hiaintenance Practices; Volume 2: Func-Vol. 2.

tional Indicator Tests on a Small lilectric hiotor NURIiG/CR-4740, " Nuclear Plant Aging Research Subjected to Accelerated Aging: Volume 3: Failure

<m Reactor Protection Systems."

Analysis and Diagnostic,lests on a Naturally Aged lilectric hiotor.

~

NURl!GICR-4747,"An Aging Failure SuiveyofI ight Water Reactor Safety Systems and Components,"

NUREG/CR-4985, " Indian Point 2 Reactor Coolant voi,1.

Pump Seal livaluations "

NURiiGICR-4747,"An AgingFailureSurveyof Light NURl!G/CR-5051," Detecting and Niitigatingliattery Water Reactor Safety Systems and Components,"

Charger and Inverter Aging."

Vol. 2.

43 NURl!G-1377

Corporate AuthorIndex idaho National Engineering Laboratory NUREG/CR-4234, " Aging and Service Wear of Elec-(INEL) (Cont.)

tric Motor Operated Valve > Used in Engineered et cature % stems of &ckar Pown Mants,"

NUREG/CR-4769," Risk Evaluations of Aging Phe-g*

• nomena: The Linear Aging Reliability Model and lis Extensions."

NUREG/CR-4234, " Aging and Service Wear of Elec.

tri: Motor Operated Valve. U:e i in Enginected NUREG/CR.1967, " Nuclear Plant Aging Research on liigh Pressure Injection Systems."

SafetyRature Systems of Nuckar Pown Ilants: Ag.

ing Assessments and Monitonng Method Evalu.

NUREGICR-4977," SHAG Test Series: Scismic Re-ations," Vol. 2.

search on an Aged United States Gate Valve and on a Pipmg System in the Decommissioned lleissdampf.

NUREGICR-4257, " Inspection Surveillance, and reaktor (llDR): Summary, Vol.1.

hionitoring of Electrical Equipment inside Contain.

ment of Nuclear Power Plants-With Applications to NUREG/CR-4977,"SilAG Test Series: Seismic Re-Electrical Cables."

search on an Aged United States Gate Valve and on a Piping System in the Decommissioned lleissdampf-NUREG/CR-4257, " Inspection, Surveillance, and reaktor (IIDR): Appendices," Vol. 2.

Monitoring of Electrical Equipment in Nuclear Power Plants, Vol. 2: Pressure 'l ransmitters.,

NUREGICR-5181, " Nuclear Plant Aging Research:

The IE Power System,"

NUREG/CR-4302, " Aging and Senice Wear of Check Valves Used in Engineered Safety Feature Sys-NUREG/CR-5248, "Prioritization of TIRGALEX-tems of Nuclear Power Plants " Vol.1.

Recommended Components for Further Aging Re-search."

NUREG/CR-4380, "Hvaluation of the Motor.

Operated Valve Analysis and Test System (MOVATS)

Kalsi EnE ncering, Inc.

t Detect Degradation, incorrect Adjustments, and i

Other Abnormalities in Motor. Operated Valves "

NUREGICR-5159," Prediction of Check Valve Per-formance and Degradation in Nuclear Power Plant NUREG/CR-4597," Aging and Senice Wear of Aux-Systems."

iliary Feedwater Pumps for PWR Nuclear Power Plants, Vol.1: Operating Experience and Failure Iden-Lake Engineering Company tification."

NUREG/CR-5386, " Basis for Snubber Aging Re-NUREG/CR-4597 " Aging and Service Wear of Aux-search: Nuclear Plant Aging Research Program."

iliary Feedwater Pumps for PWR Nuclear Power Plants, Vol. 2: Aging Assessments and Monito:ing Nuclear Regulatory Conunission (NRC)

Method Evaluations."

Technical Integration Review Group for Aging and NUREG/CR-4652," Concrete Component Agingand Life Extension (FIRO ALEX), " Plan for Integration of its Significance Relative to Life Extension of Nuclear Aging and Life-Extension Activities."

Power Plants."

NUREG-Il44, " Nuclear Plant Aging Research NUREG/CR-4692, " Operating Experienec Review of (NPAR) Program Plan."

FaPues of Power Operated llelief Valves and Block NUREG-1144, " Nuclear Plant Aging Research Valves in Nuclear Power Plants."

(NPAR) Program Plan," Rev.1.

NUREG/CR-4819, " Aging and Service Wear of Sole-NUREG/CP-0100," Proceedings cf the International noid-Operated Valves Used in Safety Systems of Nu.

Nuclear Power Plant Aging Syniposium."

clear Power Plants, Vol.1: Operating Experience and Failure Identification."

Oak Ridge National Laboratory (ORNL)

NUREG/CR-4992, " Aging and Senice Wear of Mul-NUREG/CR-2641, "The in. Plant Reliability Data tistage Switches Used in Safety Systems of Nuclear Base for Nuclear Power Plant Components: Data Col-Power Plants," Vol.1.

lection and Methodology Report."

NUREG/CR-5404," Auxiliary Feedwater System Ag-NUREG/CR-3154, "The in. Plant Reliability Data ing Study," Vol.1.

Dase for Nuclear Plant Components: Interim Report-The Valve Component, NUREG/CR-5479, " Current Applications of Vibra-tion Monitoring and Neutron Noise Analysis: Detec-NUREGICR-3543," Survey of Operating Experiences tion and Analysis of Structural Degradation of Reactor frorii LERs to identify Aging Trends."

Vessel Internals from Operational Aging "

NUREG-1377 44

Corporate Authorindex Pacific Northwest Laboratory (PNL)

Pentek, Inc.

' NUREG/CR-4144, "importance Ranking liased on NUREG/CR-5008, " Development of a Testing and Aging Consideration of Compor.ents included in Analysis hiethodology to Determine the Functional Probabilistic Risk Assessments."

Condition of Solenoid Operated Valves."

NUREG/CR-4279, " Aging and Service Wear of Ily.

Sandia National Laboratories (SAND) draulic and Mechanical Snubbers Used on Safety-NUREG/CP-0036,

• Proceedings of the Workshop on Related Piping and Components of Nuclear Power Nuclear Plant Aging" Plants," Vol.1.

NUREG/CR-3818. " Report of Results of Nuclear

""I ^8 "8 #"#'

P NUREGiCR-4590. " Aging of Nuclear Station Diesel Generators: Evaluation et Operating and thpert Ex-NUREG/CR-5334,

• Severe Accident Testh.gof Elec-perience," Vols. I and 2.

trical Penetration Assert,blies "

SAND 88-0754 UC-78, " Time Temi,ere'cre Dose NURl!G/CR4057, " Aging Mitigation and improved Rate Superposition: A Methodologyfor Predicting Ce-Psograms for Nuclear Service Diesel Generators."

ble Drgradation Under Ambient Nucleat Power Plant NURIIG/CR-5379," Nuclear Plant Service Water Sys-tem Aging Dettadation Assessment: Phase 1," Vol.1.

Science Applications International Corp, NUREG/CR-5.'48, "Prioritization of TIRGAIFX.

NURI'G/ Cit-$386, "llasis for Snubber Aging Re-nended Components fas further Aging Re-search

• Nor; car Plant Aging Research Pmgram."

t NUREG/CR-5491, 'Shipohgport Station Aging Wyle Laboratories Evaluation.

NUREG/CR-5386, aliasis for Snubber Aging Re-PNie5732 "Optra'ing lixperience and Aging Assess-search: Nuclear Plant Aging Research Program."

ment of ECCS Pun p Room Coolers."

WYLE 60103-X, " Test Plan for the Comprehensive Aging Assessment of Circuit lireakers and Relays for PNir6287," Study Group Review of Nuclear Service Nuclear Plant Aging Research (NPAR) Program, Diesel Generator Testing and Aging Mitigation."

Phase !!,"

2%

45 NUREG-1377

SUBJECT INDEX This index lists, in alphabetical order, the organizations that prepared the reports listed in this compila-tion. Ilsted below each organization are the numbers and titles of its reports. If further information is needed, refer to the main citation by the report number.

In this index, the reports are listed under one or more of the following subjects:

1.

Aging, including Plans, Surveys, Analyses, hiethods, and hiodels:

2.

Diesel Ocnerators and Related Systems;

3. litectric Power Systems, incading Cables Trays. Connectors, Circuit 11reakers, Switches, and Itclated Componcnts; 4.

blectrical liquipment, f.u:luding hiotors, llattenes, Chargers, and Inverters;

$. Ir.strumentation and hicaturement hiethods; 6.

hiaihtenance; 7.

hiajor Components: Reacter Vessels, Steam Generators, Pressurizers, and Structures (including Containment);

S.

hionitoring:

0 Opetuting thperies, Field itesults, and Related Data:

10. Piping, including; Valves, Seals, Supports, Snubbers, and llelated Components;

11. ProbaLilisticitisk Assessment (PR 4.);

12. Safety and Ivotection S; stems (including Itijection Systems) and Their Components;

13. Seismic i!ffects on Aging;

14. Service Water, Amiliary Feedwater, Instrument N.r.and Other Fluid Systems, including Pumps, lleat 11xchangers, and 1(clated Components.

'lhese subjects are not intended to include every subject covered in all the reports listed. Nor llo they represent n

• standard" or "oisieml" list of subjects.'they were selected to be most helpfut to knowledge.

able personnel seeking published information on the various aspects of nuclear plant aging.

Aging, including l'lans, Suiveys, Analyses, NURi!O/CR-3818. " Report of itesults of Nuclear Metliods, and Models Power Plant Aging Workshop."

Letter Report,1. N, Itib, " Summaries of Research NUR110/CR-4144, "Importance Ranking llased on Reports Submitted in Connection with the Nuclear Aging Consideration of Components included in Plant AgingResearch(NPAR) Program,"lingineering Probabilistic Risk Assessments."

and !!conomics Research, Inc. (EliR).

NURilO/CR-4652,"ConcreteComponent Agingand Its Significance Relative to Life Ilxtension of Nuclear for Aging and Technical Integration Review GroubrIntegration of Power Plants.

1.ife 11xtension (l'IRO A1.EX), " Plan Aging and Life-lixtension Activities."

NUREO/ Cit-4731."Residuallife Assessment of hia-jor Light Water Reactor Components," Vol.1.

IlNL Technical lleport A-3270-12-86, " Aging and Life Extension Assessment Program (ALEAP) Sys.

NUREO/CR-4731,"ResidualLife Assessment of hia.

tems I.evel Plan."

jor Light Water Reactor Components-Overview,"

Vol. 2.

NUREG-ll44, " Nuclear Plant Aging Research NUREO/CR-4769," Risk Evaluations of Aging Phe-(NPAR) Program Plan, nomena: The Linear Aging Reliability biodel and !ts Extensions."

NURiiG-ll44, " Nuclear Plant Aging Research (NPAR) Program Plan," Rev.1.

NURIIO/CR-5008, " Development of a Testing and Analysis hiethodology to Determine the Functional NUREO/CP-0036," Proceedings of the Workshop on Condition of Solenoid Operated Valves."

Nuclear Plant Aging."

NUREO/CR-5248, "Prioritization of TIROAll1X-NURl!O/CP-0100, " Proceedings of the International Recommended Components for Further Aging Nuclear Power Plant Aging Symposium."

Research."

47 NUREG-1377

Subject Index Aging, including I'lans, Surveys, Analyses, NUltiiG/ Cit 5181, " Nuclear Plant Aging flescarch:

Methmis, and Models (Cont.)

The 111 Power System."

NUlti!G/Cli-5386, *llasis for Snubber Aging ite.

SAND 88-0754 UC-78, " Time Temperature Dose search: Nuclear Plant Aging flescarch Program."

llate Superposition: A Methodology for Predicting Ca-ffi j' t fn '

NUlti!G/C,11-5491, "Shippingport Station Aging livaluation.,

WYl.li 60103-X, " Test Plan for the Comprehensive SAND 88-0754 t C-78, "l'ime Temperature Dose Aging Assessment of Circuit lireakers and Itclays for llate Superposition: A MethodologyIv PredictingCa.

Nccicar Plant Aging flescarch (NPAll) Program, ble Degradation Under Ambient Nuclear Power Plant Phase 11."

Agir.g Conditions."

WYLl! 60103-X," Test Plan for the Comprehensive Electrical Equipment, including Motors, !!at.

Aging Assessment of Circuit litcakers and Itclays for teries, Chargers, and Inverters Nuclear Plant Aging Research (NPAlt) Program, UNI, Technical Iteport A-3270-Il-85 " Seismic lin.

Phase 11."

durance Tests of Naturally Aged Smal! lilecuic Mo-tors."

Diesel Generators and 1(elated Systems UNI, Technical lleport A-3270-12-85,

• Pilot Assess-NUlti!G/ Cit-4590," Aging of Nuclear Station Diese!

ment: trupact of Aging on the Seismic Periormance of Generators: Evaluatian of Operating and I!xpert 1.x-Selected liquipment "lypes."

perience," Vols. I and 2.

bNI. Technical iteport A-3270 3-86, "Testne Pro.

NUlti!G/ Cit-4731, *ltesidual Life Assesstr.cnt of Ma-gram for the Monucting of Degradation in a Conum-jor 1.ight Water lleactor Components-Overview" ous Duty 460 Volt Class "11",10-IIP I!!cetric Motor."

Vol. 2.

NUlti!G/ Cit-4156, " Operating P.xperience and Ag-NUlt!!G/CR-5057, " Aging Mitigation and improved ing Seismic Assessment of I!!ectric Motors "

Programs for Nuclear Service Diesel Generators."

NUlti!G/ Cit-4457 " Aging of Class 11! llatteries in PNI,-6287,

• Study Group lleview of Nuclear Senice Safety Systems of Nuclear Power Plants."

Diesel Generator Testing and Aging Mitigation."

NUlti!G/ Cit--4564, " Operating F.xperience and Ag-I"E' Sci 5 nic Assessment of llaucry Chargers and in-Electric l'ower Systems, including Cables, Trays, Connectors, Circuit lireakers, Switches, and 1(elated Components NUltliG/ Cit-4939, " improving Motor lleliability in Power

,ous;"

ume h h donnance llNI.Technicallleport A-3270-12-85," Pilot Assess-

.atuau.on and Mainn nance Pmdecs: Wume 2:

ment: Impact of Aging on the Seismic Performance of 1 unctional Indicator 'lests on a Small lilectric Motor Selected l'quipment Types.,,

Subjected to Accelerated Aging: Volume 3: l'ailure NUltl!G/ Cit-3956, "In Situ Testing of the Ship.

Analysis and Diagnostic Tests on a Naturally Aged pingport Atomic Power Station lilectrical Circuits."

tilectric Motor, NUltl!G/ Cit-4257, " Inspection, Surveillance, and NUlti!G/ Cit-5051,

• Detecting and Mitigating liattery Monitoring of lilectrical liquipment inside Contain.

Charger and Inverter Aging."

ment of Nuclear Power Plants-With Applications to NUltl!G/ Cit-5053 *Operatinglixperienceand Aging lilectrical Cables.

Assessment of Motor Control Centers."

NUltlyG/ Cit-4715 "An Aging Assessment of it NUltliG/ Cit-5192," Testing of a Naturally Aged Nu-and Ciremt lireakers and System Interacuons,, elays clear Power Plant Inverter and llattery Charger."

NUlt!!G/ Cit-4731,*ltesidualI.ife Assessmentof Ma.

jor Light Water lleactor Components-Overview,"

lustrumentation and Measurement Methods Vol. 2.

NUltliG/ Cit-4257, " Inspection, Surveillance, and NUltliG/ Cit-4747."An Aging Failure Survey of1.ight Monitoring of lilectrical liquipment in Nuclear Power Plants, Vol. 2: Pressure Transmitters."

Water Itcactor Safety Systems and Components,"

Vol.1.

NUlti!G/ Cit-4928. " Degradation of Nuclear Plant NUlti!G/CPv-4992,

• bing and Service Wear of Mul.

Temperature Sensors."

tistage Switches Used in Safety Systems of Nuclear NUlltiG/ Cit-5383, "liffect of Aging on itesponse Power Plants." Vol.1.

Time of Nuclear Plant Pressure Sensors."

NUlti!G-1377 48 l

4 A

Subject Index Maintenance tion and Analysis of Structural Degradation of Reactor NUR110/CR-4234, " Aging and Service Wear of lilec-VenelIntemals from Operational Aging."

j tric hiotor Operated Valves Used in lingineered Safety. Feature Systems of Nuclear Power Plants,"

Monitoring Vol.1, ilNI Technical Report A-3270-3-86, " Testing Pro-NURl!O/CR-4457, " Aging of Class.111 Ilatteries in gram for the hionitoring of, Degradation in a Continu.

l ws Duty 460 Volt Class "Il,10-IIP lilectric h1otor, Safety Systerns of Nuclear Power Plants."

TechnW Report A-3270-12-86, " Aging and NURl!O/CR-4564, " Operating lixperience and Ag-

"""l "

f Ing. Seismic Assessment of flattery Chargers and

'"*8 I*I I,"I""D"#"'"C"I E'"E'"* I^bI ^I ) b 8' Inverters."

j NURI!O/CR-4597, " Aging und Service Wear of Aux-

, if,

'im i""

n Ag ng Rn ch cv 1.

iliary Feudwater Pumps for PWR Nuclear Power Plants, Vol.1: Operating lixperience and Failure NURiiO/CR-3543,*Surveyof 0peratiraglixperiences identificatbn."

from Lt!Rs to identify Aging Trends."

NURF.0/CR 4597. " Aging and Service Wear of Aux-NURI;O/CR-4234 "Aring and Scryice Wear of lilec-illhry Feedwater Pumps for PWit Nuclear Power tric hiotor Ope' 1 Valves Used in ling %ected hiethod I! valuations.'g Assessments and blonitoring Safety.Featurc

.:ms of Nuclear Pour Plants,"

Plants, Vol 2: Agin Vol.1.

j NURl!O/CR-4939, " improving hiotor Reliability in NUR130/CR-4234, " Aging and Service Wear of 1:lec-Nuclear Power 11 ants;" Volume 1: Performance tric hiotor Operated Valves Used in 1;nginected

!! valuation and hiaintenance Practices; Volume :.:

Safety-Feature Systems of Nuc! car Power Plants: Ag-i Functional Indicator Tests on a Small Electric hiotor ing Assessments and hionitoring hiethod livalu-Subjected to' Accelerated Aging: Volume 3: Failure ations " Vol. 2.

nal sa Diagnostic Tests on a Naturally Aged NURl!O/CR-4257, " Inspection, Surveillance, and hionitoring of tilectrical liquipment inside Cor.tain-NURl!O/CR-5051,"Detectingand hiitigating flattery ment of Nuclear Power Plants-With Applications to Charger and Inverter Aging "

!!!cetrical Cables."

5

- NURl!O/CR-5057, " Aging hiitigation and improved NUR110/CR-4257, " Inspection Surveillance, and Programs for Nuclear Service Diesel Ocnerators."

htonitoring of lilectrical hquipment in Nuclear Power NURi!O/CR-5181, " Nuclear Plant Aging Research:

The 111 Power System."

NURl!O/CR-4302, " Aging and Service Wear of Check Valves Used in lingineered Safety Feature Sys-PNlr$72A" Operating lixperience and Aging Assess' tems of Nuclear Power Plants," Vol.1.

i ment of I!CCS Pump Room Coolers."

NUR110/CR-4457, " Aging of Class 111 liaiteries in Midor Components: Reactor Vessels, Sicam Safety Systems of Nuclear Power Plants."

l Generators, Pressurizers, and Structures (In-NURl!O/CR-4564, " Operating !!xperience and Ag-I

ciuding Containment) ing Scismic Assenment of llattery Chargers and I"VC"Cf8 "

I NURl!O/CR-4652,"Concretc Component Aging and its Significance Relative to 1Jfc lixtension of Nuclear NURl!O/CR-4597 " Aging and Service Wear of Aux-

- Power Plants."

iliary Feedwater Pumps for PWR Nuclear Power

+

NURl!O/CR-4731," Residual Life Assessment of hia, Plants, gl.1: Operating F.xperience and Failure Iden-tification.

jor IJght Water Reactor Components," Vol.1.

NURl!O/CR-4731. " Residual Life Assessment of hla-NURi!O/CR-4597, " Aging and Service Wear of Aux.

jor Light Water Reactor Components-Overview,"

tliary Feedwater Pumps for PWR Nuclear Power Vol. 2' l'lants, Vol. 2: Agmg Assessments and hlonitoring hiethod !! valuations."

"E

-ti i netrat n d se NUREO/CR-4819. " Aging and Service Wear of Sole-e noid Operated Valves Used in Safety Systems of Nu-

' NURl!O/CR-5479, " Current Applications of Vibra-clear Power Plants, Vol.1: Operating 11xperience and

.tlon hionitoring and Neutron Noise Analysis: Detec-

' Failure identification."

'i 49 NURl!O-1377

Subject Index 4

Monlloring (Cont )

NUREG/ Cit-4302, " Aging and Senice Wear of NUREG/CR-4939, *!mproving Motor Reliability in Check Valves Used in Engineered Safety Feaiure Sys-Nuclear Power Plants;" Volume 1: Performance tems of Nuclear Power i tants, Vol.1, Evaluation and Maintenance Practices: Volume 2:

NUREG/CR-4457, " Aging of Class 18 llatteries in Functional Indicator Tests on a Small Electric Motor Safety Systems of Nuclear Power Plants."

Subjected to Accelerated Aging: Volume 3: Tailure Analysis imd Diagnostic Tests on a Naturally Aged NUREG/CR-4564, " Operating Expen.ence and Ag-Electric Motor.

tng Scismic Anessment of llattery Chargers and Inverters."

NUREG/CR-4967,

• Nuclear Plant Aging Research on liigh Pressure injection Systems."

NUREG/CR-4590," Aging of Nuclear Station Diesel Generators: Evaluation of Operating and 11rpert Ex-NUREGICR-5008, " Development of a Testing and perience," Vols. I and 2.

IC{ C on i m f er er ted 1 es "

I 7' ^8 "

Au 3

NUREG/CR-5051 " Detecting and Mitignt!ngliattery Plants, Vol.1: Operating Experience and Failure Charger and Inverter Aging "

Identification."

NUREG/CR-5053, *Operati1g Ene:Icnce and Apog NUREG/CR-4692, " Operating !!xperience Review of Assenment of Motor Control Centers."

Faitt.res of Power Operated Relief Valves and lilock NUREG/CR-5057, " Aging Mitigation and improved Programs for Neclear Senice Diesel Gencrntors."

NURl!G/CPc4715."An Aging Aucssment of Rebys NUREG/CR-5181,

• Nuclear Phat Aging Research:

The IE Power System."

NUREG/CR.040, "huclear Plant Aging Research NUREG/CR-5192 " resting of a Naturally Aged No-clear Power Plant Inverter and llattery Charger "

NUREG/CR-4747,"An Aging Failure Surveyof Light Water Reactor Safety Systems and Components,"

NUREG/CR-5479, " Current Applications of Vibra-yot,1, tion Monitoring and Neutron Noise Analysis: Detec-tion and Analysis of Structural Degradation of Reactor NUREG/CR-4747,*An Aging Failure Suneyof Light Vessel Internals from Operational Aging."

Water Reactor Safety Systems and Components,"

Vol. 2.

PNI.c6287," Study Group Review of Nuclear Service Diesci Generator Testing and Aging Mitigation."

NUREG/CR-4819," Aging and Service Wear of Sole-nold Operated Valves Used in Safety Systems of Nu-Ch'"' E " C' PI""!S' V"I' I U C'"'I"E !*PC'i'"C# ""d P

I Operating Experience, Field Results, and Re.

I" U"'" Id*" # *" " "'

taled Data NUREG/CR-2641, "The in Plant Reliability Data NUREG/CR-4967 " Nuclear Plant Aging Research liase for Nuclear Power Plant Components: Data Col.

on liigh Pressure injection Systems."

lection and Methodology Report."

NUREG/CR-4992," Aging and Sen' ice Wear of Mul-NUREG/CR-3154, "The in. Plant Reliability Data tistage Switches Used in Safety Systems of Nuclear P"*C' PI""l8'" Y"I' h liase for Nuclear Plant Components: Interim Report-The Valve Component."

NUREG/CR-5052 *OpemtingExperienceand Aging NUREG/CR-3543," Sun ey of Operating Experiences

. Assessment of Component C,ooling Water Systemsin I ressurized Water Reactors.

from LERs to identify Aging Trends."

NUREG/CR-3819, " Survey of Aged Power Plant

.Ihe IE Power System.,', clear Plant Aging Res NUREG/CR-5181, %u Facilitics."

NUREG/CR-5268, " Aping Study of Iloiling Water NUREG/CR-4156,

• Operating lixperience and Ag-Reactor Residual llcat Removal System.

ing Scismic Assessment of Electric Motors."

clea an ce atu%

NUREG/CR-4234," Aging and Service Wear of Elec.

tric Motor Operated Valves Used in Enginected Y* ^E "E E*

" "^" *"#""

Safety Feature Systems of Nuclear Power Plants,"

NUREG/CR-5383, "Effect of Aging on Response Vol.1.

Time of Nuclear Plant Pressure Sensors."

{

?

NUREG-1377 50 L

n a

Subject Index Operating Experience, Field Results, and Re.

NUREG/CR -4977, "Sil AG Test Series: Seismic Re-lated Data (Cont.)

scarch on an Aged United States Gate Valve and on a NUREG/CR-5404," Auxiliary Feedwater System Ag-r( I ):

endic,

.2 ing Study," Vol.1.

NUREG/CR-4985, " Indian Point 2 Reactor Coolant NUREO/CR-5419," Aging Assessment ofInstrument Pump Seal Evaluations."

Air Systems in Nuclear Power Plants."

NUREG/CR-5008,

• Development of a Testing and PNie5722

• Operating Experience and Aging Assess-Analysis hiethoJology to Determine the Functional ment of ECCS Pump Room Coolers."

Condition of Solenoid Operated Valves."

NUREG/CR-5141, " Aging and Qualification Re-Piping, including Valves, Seals, Supports, scarch on Solenoid Operated Valves."

Snubbers, and Related Components NUREG/CR-5139,

• Prediction of Check Valve Per-IINL 1cchniad Report A-3270-ll-26-84, " Scoping formance and Degradation in Nuclear Power Plant Test on Containment Purge and Vent Valve Seal Syt.tems.'

ht >terial."

NURI!G/CR-53S6, altasis for Snubber Aging Re-IINI. Technical Report A-3270-12-85,' Pilot Assess.

search: Nuclear Plant AgMg Research Psopram."

ment: Impact of Aging on the Seismic Performance of NUR EG/CR-5491, "Shippingport Station Aging i

Selected Equipment lypes.

Evaluation."

NUREGICR-3154 "The in Plant Reliability Data i

liase for Nuclear Plant Components: Interim Probabilistle Risk Assessment (PRA)

Report-Tne Valve Component."

NURl!G/CR-4144, *Irn ortance Rank!ng liased on l

AE "E tk N Assesments.,p nents included m

""5 NURl!G/CR-4234 " Aging and Service Wear of Elec.

o tric hiotor Operated Valves Used in Engineered Safety Feature Systems of Nuclear Power Plants,"

NURiiG/CR-5268, " Aging Study of Iloiting Water Vol. I.

Reactor Residual llcal Removal System."

NURl!G/CR-4234," Aping and Service Wear of Elec-Safety nnd Protection Systems (including in.

tr,e hiotor Operated Valves Used m Engmected Safety Feature Systems of Nuclear Power Plants: Ag-jeedon S,ystems) and,I, heir Components ing Assessment anti bionitoring hiethod livaluations,"

NUREG/CR-3819," Survey of Aged Power Plant Fa-Vol. 2.

cilities."

i NUREG/CR-4279, " Aging and Service Wear of fly.

NUREG/CR-4302, " Aging and Senice Wear of draulic and hicehanical Snubbers Used on Safety-Check Valves Used in Engmeered Safety Feature Sys.

Related Piping and Cornponents of Nuclear Power tems of Nuclear Power Plantst" Vol.1.

j Plants," Vol.1, NUREG/CR-4731," Residual Life Assssment of hia.

I NURl!G/CR-4302, " Aging and Service Wear of fr{j'yght Watn Reactor Comments-Omiew,"

Check Valves Used in Engineered Safety Feature Sys-tems of Nuclear Power Plants." Vol.1.

NUREG/CR-4740, " Nuclear Plant Aging Research on Reactor Protection Systems."

NURiiG/CR-4380, *livaluation of the hiotor-Operated Valve Analysis and Test System (hlOVNIS)

NUREG/CR-4747,"An Aging FailureSurveyof Light to Detect Degradation, Incorrect Adjustments, and Water Reactor Safety Systems and Components,"

Other Abnormalities in hiotor Operated Valves."

Vol.1.

NUREG/CR-4819. " Aging and Senice Wear of Sole-NUREG/CR-4747, *An Aging Failure Survey of Light noid.Gperated Valves Used in Safety Systems of Nu-

\\y"I' *7 Reactor Safety Systems and Components,"

atc elear Power Plants, Vol.1: Operating Experience and Failure Identification."

NUREG/CR-4967, " Nuclear Plant Aging Research n High Pressure injection Systems."

NUREG/CR-4977, "SilAG Test Series: Scistnic Re-scarch on an Aged United States Gate Valve and on a NUREG/CR-4992," Aging and Service Wear of hiul-Piping System in the Decommissioned IIcissdarnpf-tistage Switches Used in Safety Systems of Nuclear reaktor (HDR): Summary," Vol.1.

Power Plants," Vol.1.

$1 NUREG-1377 4

\\

c 0

)

Subject Index Seismic Effects On Aging Plants, Vol.1: Operating Experience and Failure identification.,

Ixtter Report, M. Subudti,

• Review of Aging-Scismic Correlation Studies on Nuclear Plant Equipment,"

NUREG/CR-4597," Aging and Service Wear of Aux-Drookhaven National ! Aboratory, January 1985.

Iary Feedwater Pumps for PWR Nuclear Power IINL Technical Rerort A-3270-ll-SS, "Scismic En.

Plants, Vol. 2: Aging Assessments and Monitoring durance Tests of Naturally Aged Small Electric Method Evaluations" Motors."

NUREG/ Cit-4731,

• Residual Life Assessment of Ma.

IINL Techn'c4 iieport A-3270-12-85, "Pdot Assess-jor Light Water Reactor Components," Vol.1.

ment: Impact of Aging on the Seismic Performance of Selected Equipment 'lypes."

NUREG/CR-4731,

• Residual Life Assessment of Ma-j(i' fght Water Reactor Components-Overview,"

l NUREG/CR-4156, " Operating Experience and Aging Scismic Assessment of Elcetric Motors.'

NUREG/CR-4279," Aging and Service Weat of Hy.

NURPG/CR-4747,"An Aging Failure Survey of Light draulle and Mechanical Snubbcts Used or. Safety.

Water Reactor Safety Systen; and Components,"

Related Piping and Comp (ments of Nuc! car Power Voh1.

Plants," Vol.1.

NUREG/CR-4985, aindian point 2 Reactor Coolant NUREG/CR-4977, "SilAG Test Series: Seismic Re-Pump Seat Evaluations."

search on an Aged United States Gate Valve and on a Piping System in the Decommissioned licissdampf.

NUREG /CR-5052, *0pe rating I!xperience and Aging reaktor (IIDR): Summary," Vo!.1.

Assessment of Companent Cooling Water Systems in 5

I ressunted Wete? Reactorr."

NUREG/CR-4977,"SilAG Test Series: Scistnic Re-scarch on an Aged United States Gate Valve anJ on a NUREG/CR-5268, "A; ting Study of Iloiting Water Pipmg System m the Decommissioned lleissdampf-Reactor Residt.at lleat Removal System."

reaktor (l(DR): Appendices," Vol. 2.

NUREG/CR-5379," Nuclear Plant Sen icc Water Sys.

Service Water, Auxiliary Feedwater,Instru-tem Aging Degradation Assessment: Phase I," Vol.1.

ment Air, and Otlier Fluid Systems,includ.

Ing l' umps,llent Excliangers, and Related NUREG/CR-5404," Auxiliary Feedwater System Ag-I"8 S'Ud ' V I' I*

Y Components NUREG/CR-4597," Aging and Service Wear of Aux-NUREG/CR-5419," Aging Assessment ofInstrument iliary Feedwater Pumps for PWR Nuclear Power Air Systems in Nuclear Power Plants."

l l

l l

I i

i NUREG-1377 52 i

n r

/

CHRONOLOGICAL LISTING (In order of publication) 1.

'NURiiG/CR-2641, J. P. Drago, R. J. Ilorkowski,

10. NURl!G/CR-4234,W.L Greenstreet,G. A.Mur.

D.11. Pike, and F, F. Goldberg,"Ihe In Plant Rell-phy, and D. M. !!issenberg, " Aging and Senice ability, Data liase for Nuclear Power Plant Com;w Wear of Illectric Motor Operated Valves Used in nents: Data Collection and Methodology Report,"

lingineered Safety Feature Systems of Nuclear Oak Ridge National lateratory, ORN11111-8271, Power Plants," Vol.1. Oak Ridge National latborn-July 1982, tory, ORNie6170/VI, June 1985.

2.

• NURl!G/CP-0036, ICompilation by) 11. II. Ilader

11. NURliG/CR-3819, J. A. Rose, R. Steele, Jr., K. O, and L A. Uanchey," Proceedings of the Workshop DeWall, and 11. C. Cornwell, " Survey of Aged on Nuclear Plant Aging,"Sandia Nationallatura.

Power Plant Faci'ities," Idaho National !!ngineer.

lories, SAND 82-2264C, November 1982, ing lisborator3, !!GG-2317, J une 1985.

3.

NURl!G/CR-3154 R. J. Ilcrkewski. W. K. Mah!,

12. N URIIG-1144, 11. M. hlorria, and.1, P. Vora, T. L liebble, J. R. Fragola, and J. W. Johnsort "Nucleat Plan'. Aging Research (NPAR) Program "the In-Plant Reliability Data liase for Neelcar Plan," U.S. Nuclear Regula;ory Commissicn, July Plant Compnents: Interim Repor; 'the Valve

1985, Corr,ponent." Oak Ridge National laboratory, ORN1/Iht-8647, December 1983.

13. NURiiG/CR-4'!!?, S Ahraed. A. Carfagno, and G. J. Toman, " Inspection, Surveillance, and Moni.

4.

NURh0/CR-3543, G. A. Murphy, R. fl. Gallaher, toring of lilecitical Pquipment inside Containment M.I Casade andit.C.lloy,"Suncyof 0perating of Nuclear Power Plants-With Applications to i

Experiences from 1.l!!4 to identify Aging Trends,"

tilectrical Cables," Gak Ridge National 1;ibora.

Oak Ridge Natior.al laloratory, ORNI, tory, ORN!JSUll/83-28915!] August 1985.

NSIC-216, January 1984.

14.

IINL Technical Report A-3270-ll-85, J,11, 5.

NURiiG/CR-3818, N,11. Clark and D. L lierry, Taylor, hl. fubudhi, J. liiggins. J. Curreri, M.

" Report of Results of Nuclear Power Plant Aging Reich, F. Cifuentes, and T. Nehring, " Seismic lin.

Wor kshop," Sandia National laimratories, durance Tests of Naturally Aged Small !!!cetric q

SAND 84-0374, August 1984.

Motors,"' ilrookhaven National laboratory, November 1985.

6.

IINL Technical Report A-3270-Il-26-84,

15. IINL Technical ReImrt A-3270-12-85, M. M. Sil-

11. Miller. Scopmg lest on Contamment Purge and Vent Valve Seal Material," linmkhaven Na-ver, R Vasudevan, and M. Subudhi, " Pilot Assess-rnent:Impactof AgingontheSe of Selected liquipment 'lypes,jtsmic Performan tional lateratory, December 1984.

linokhaven Na-7.

Letter Report, M. Subudhi, " Review of Aging-tional laboratory, December 1985.

Seismic Correlation Studies o,n Nuclear Piant

16. NURI!G/CR-4302, W. L Greenstreet, G. A. Mur-liquipmer t llrookhaven National laboratory,

@y, R.11. Gallaher, and D. M. liissenberg," Aging 7

and Senice Wear of Check Valves Used in lingi-8, NURl!G/CR-4144, T.

Davis, A.

Shafaghi, nected Safety Feature Systems of Nuclear Power R. Kurth, and F. Leverenz, "importanc'e Ranking I'lants,' Vol.1, Oak Ridge National laborvtory,

]

Ilased on Aging Consideration of Components In-ORNL-6193/V1, December 1985.

cluded in Probabilistic Risk Assessments," Pacific 17, NURl!G/CR-4380, J. L Crowley and D. M

.is.

Northwest laboratory, PN!-5389, April 1985.

senberg," Evaluation of the Motor. Operated \\ Ave 9.

NURiiG/CR-4156, M. Subudhi,11 L llurns, and Anaps an st % stem WMM to Detect Degradation, incorrect Adjustments and Abnormalities m MotorOperated Valves,,Other J.11. Taylor, " Operating Experience and Aging'-

Oak Seismic Assessment of lilectric Motors," Ilrook-haven National laboratory, IINicNUREG-51861, e Nadomi Ialomimy, Mr6226, Jaguaiy June 1985.

18.

NURl!G/CR-4279, S. I1. Ilush, P. G. Ileasier, and

• Not [oping the emly NPAR program plan.raluced m a ort of the NRC NPAR Program, but med in ge, ng n h M m W # m M dew and Mechamcal Snubbers Used on Safety Related 53 NURiiG-1377 3

1 o

m

V Chronological I isting Piping and Components of Nuclear Power Plants,"

National laboratory, O R N!)S UH /83-28915/4 /V1, Vol.1. Pacific Northwest Laboratory, PNLe5479, hiarch 1987.

February 1986.

28. NUREG/CR-3956, hl.

R.

Dinscl, bl.

R.

19. IINLTechnical Report A-3270-3-86, A. C. Sugar-Donaldson, and F. T. Soberano, "In Situ Testing of man, hi. W. Sheets, and hi. Subudhi, " Testing Pro-the Shipping;mrt Atomic Power Station Electrical gram for the hionitoring of Degradation in a Con-Circuits," Idaho National Engineering laboratory, tinuous Duty 460 Volt Class *ll",10-IIP Electric EGG-2443, April 1987.

Motor," llrookhaven National laboratory, h1 arch 1986.

29. NUl(EG/CR-4769, W. E. Vesely, " Risk Evalu-ations of Aging Phenomena:The Linear Aging Re-

20. NUREG/CR-4564, W. E. Gunther, bl. Subudhi, liability hiodel and its Extensions," Idaho National and J. !!. Taylor, " Operating Experience and Ag-Engineering laboratory, EGO-2476, April 1987, j

ing Scismic Aswssment of Battery Chargers and Inverters," llrookhaven National l ateratory,

30. Technical lntegration Review Group fot Aging and a

IINLeNUREG-51971, June 1986.

Life Extension (11RGALEX),

• Plan for integra-tion of Aging and Life Extension Activitics," U.S.

21. NUREG/CR-4597, M."i Adams and E. Makay, Nuclear Rcgulatory Commission, May 1987.

" Aging and Senice Wear of Auxiliary Feedwater

31. NUREG/CR-4731, V. N. Shah and P. E. Mac.

Pumps for PWR Nuclear Power Plants, Vo!.1: Op-crating Experience and Failure Identification Dortald," Residual Life Assessment of Major Light Oak Ridge National laboratory, ORNie6282/V1, Water Reactor Components," Vol.1, Idaho Na.

July 1986, tianni Engineering laboratory EGO-2469, Junc 1987.

22. NUREG/CR-4257,0. J. Toman, " Inspection, Sur-

32. N UREG/CR-471 $, G. J. Tuman, V. P, Bacan:,kas, veillance, and Monitoring of Electrical Equipment in Nuclear Power Plants. Vol. : Pressure Trans-T. A. Shook.and C.C. lailow,"An Aging Assess-mitters, Oak Ridge National laiviatory, ORNI) rnent of Relay and Circuit lireakers and System SUll/83-28915/3/V2, August 1986.

Interactions," llrookhaven National laboratory, Franklin Research Center, Philadelphia, PA, IINieNUREG-52017, J une 1987.-

23. N UR EG /CR-4652, D. J. Naus, " Concrete Com po-nent Aging and Its Significance Relative to Life

33. NUREG/CR-4928, IL M. liashemian, K. M.

Extension of Nuclear Power Plants, Oak Ridge Petersen, T. W. Kctlin, R. L. Anderson, and K. E.

National Iaborutory, ORNi/l'M-10059, Septem-llolbert," Degradation of Nuc! car Plant Tempera-i ber 1986.

ture Sensors," Analysis and Measurement Services

'E '"" "' "

24. Letter Report, I. N. Rib, " Summaries of Research Repor s Submitted in Connection with the Nuclear

34. NUREG/CR-4747,' 11. M. Meale and D. G. Sat-Plant Aging Research (NPAR) Program," Engi*

terwhite,"An Aging Failure Survey of Light Water i

necring and Economics Research (lier)lnc., Res-Reactor Safety Systems and Components," Vol.1, ton, VA, September 1986.

Idaho National Engineering laboratory, 2f DNL-5722, D. E. Blahnik and R. L. Goodman,

• Operating Experience and Aging Assessment of

35. NUREG/CR-4457, J. L. Edson and J. E. liardin, UCCS Pump Room Coolers," Pacific Northwest

" Aging of Class 111 Itatteries in Safety Systems of laboratory, October 1986.

Nuc! car Power Plants " Idaho National Enginecr-j

26. UNL Technical Report A-3270-12-86, R.

Fullwood, J. C. Higgins, M. Subudhi, and J.11.

36. NUREG/CR-4985 M. Subudhi, J. H. Taylor, J.

Taylor " Aging and Lifc Extension Assessment Pro-Clinton, C, J. Czajkowski, and J. Weeks, " Indian gram (ALUAP) Systems Level Plan," llrookhaven Point 2 Reactor Coolant Pump Scal Evalua.

National Laboratory, December 1986, tions," Ilrookhaven National laboratory, BNie

- 27, NUREG/CR-4819. V. P.

Itacanskas, G. C.

Roberts, and G. J. Toman, " Aging and Service

37. NUREG/CR-4590, K. R. Hoopingarner, J. W.

Wear of Solenoid-Operated Valves Used in Safety Vause, D. A. Dingce, and J. F. Nesbitt, " Aging of Systems of Nuclear Power Plants, Vol.1: Operating Nuclear Station Diesel Generators: Evaluation of Experience and Failure identification," Oak Ridge Operating and Expert Experience." Vols. I and 2,

- NUREG-1377 54 s

A n

Chronological Listing Pacific Northwest Laboratory, PNir$832, August

46. NUREO/CR-4597, D. M. Kitch, J. S. Schtonskl.

1987.

P. J. Sowatskey, and W. V. Cesarski, " Aging and Service Wear of Auxiliary Feedwater Pumps for PWR Nuclear Power Plants, Vol. 2: Aging Assess-38, NUREG-ll44, J. P. Vora, "Nuc! car Plant Aging Research (NPAR) Program Plan," Rev.1 U.S.

ments and Monitonng Method Evaluations," Oak e National laboratory, ORNlr6282/V2, J une Nuclear Regulatory Commission, September 1987.

39. NUREGICR-4992, G.

C.

Roberts, V,, P.

47. NURPO/CR-4747, B. M. Meale and D. O. Sat.

Bacanskan, and O. J. Toman, " Aging and Service terwhite,"An Aging Failure Survey of IJght Water Wear of Multistage Switches Used in Safety Syb-Reactor Safety Systems and Components," Vol. 2, tems of Nuclear Power Plants," Vol.1 Oak Ridge Idaho National Engineering Imboratory, National !aboratory, ORNIJSUil/83-28915/5/V I.

EGO-2473 July 1988.

September 1987.

48. NUREO/CR-5052, J. C. Higgins, R.12 faro,

40. NUREO/CR-500F, R. D. Meininger and T. J.

M. Subudhi, R. Fullwood, and J. H. Taylor, *Oper.

Weir, " Development of a Testing and Analysis ating Experience and Aging Assessment of Compo-Methulology to Determine the Functional Condi.

nent Cooling Water Systems in Pressurized Water tion of Solenoid Operated Valves," Pentek, Inc.,

Reactors," Ilrookhaven National laboratory, Coraopolis, PA, September 1987.

BNieNUREG-52117. July 1988.

41. NUREGICR-4692, O A. Murphy and J. W.

, Operating Experic'rce and Aging Assessrnent of' Cletcher II,' Operating Experience Review of Fall' Motor Control Centers," Brookhaven National urcs of Power Operated Relief Valves and Block laboratory, BNieNUREG-52118, July 1988.

Valves in Nuclear Power Plants," Oak Ridge Na-tional Iaberatory, ORNi>NOAC-233, October

50. NUREO/CR-5051, W. E. Gunther, R. Lewis, and 1987.

M. Subudhi, Detecting and Mitigating flattery Charger and Inverter Aging," llrookhaven Na.

' 42. NUREO/CR-4939, M. Subudhi, W. E, Gunther, tional laboratory, BNieNUREG-52108, August J.11. Taylor, R. lefaro, K. M. Skrciner, A. C.

1988.

Sugarman, and M. W. Sheets. *1mproving Motor Reliability in Nuclear Power Plants;" Volume 1:

51. NUREO/CR-5141, V. P. Bacanskas, O. J. Toman,

. Performance Evaluation and Maintenance Prac.

and S. P. Carfagno," Aging and Qualification Re-tices; Volume 2: Functional Indicator Tests on a scarch on Solenoid Operated Valves," Franklin Small Electric Motor Subjected to Accelerated Research Center, Norristown, PA, August 1988.

Aging; Volume 3: Failure Analysis and Diag-nostic Tests on a Naturally Aged Electric

$2.

• SAND 88-0754 UC-78, K. T. Gillen and R. L Motort Brookhaven National laboratory, IINI, Clough," Time Temperature Dose Rate Superpo-NUREG-52031 November 1987.

sition: A Methodology for Predicting Cabic Degra.

dation Under Ambient Nuclear Power Plant Aging 8'^"E"*

43. NUREO/CR-4740, L C. Meyer, " Nuclear Plant-f9gg*

- Aging Research on Reactor Protection Systems, Idaho National Engineering laboratory,

53. NUREO/CR-5192, W. E. Gunther," Testing of a EGO-2467, January 1988.

Naturally Aged Nuclear Power Plant Inverter and ll llattery Charger," Brookhaven National labora-l

44. ' PNie6287, K. R, lloopingarner,11. J. Kirkwood, tory, UNI-NUREG-52158, September 1988.

I and P. J. lanzecky, " Study Group Review of Nu.

clear Service Diesel Ocnerator Testing and Aging

$4. NUREO/CR-5248, I. S. Levy, D. B. Jarrell, and Mitiratior.." Pacific Northwest laboratory, March E. P. Collins, "Prioritization of TIRGALEX-1988.

Recommended Components for Further Aging Re-1 search," Pacific Northwest Laboratory, Science Ap-plications International Corp., PNir6701, Novem-

45. NUREO/CR-5159, M. S. Kalsi, C.1. Horst, and ber 1988.

J. K. Wang, " Prediction of Check Valve Perform-ance and Degradation in Nuclear Power Plant Sys-t ms," Kals Engineer ng. Inc., Sugar land, TX,

, Sponsored tiy the Department of Energy (DOEt although con.

(.

, May concerned mth nuclear power plant agmg. it is not a part of the NRC NPAR program.

l' 55 NUREG-1377 i

)

j ChronologicOI Listing

$5. NUREG/CP-0100, A.F lleranck,"Proceedingsof (1IDR): Appendices " Vol. 2, Idaho National Engi-the International Nuclear Power Plant Aging Sym.

neering laboratory,110G-2505, August 1989.

posium," U.S. Nuclear Regulatory Commission, March 1989.

64.

NURl!G/CR-4731 V. N. Shah and P,11. Mac-Donald,

• Residual Lir Assessment of Major Light e

56. NUREG/CR-5268, R. lofaro, M. Subudhi, W. E.

Water Reactor Components-Overview," Vol. 2 Gunther, W. Shier, R. Fullwood, tmd J. I1. Taylor, (Draft), Idaho National !!ngineering laboratory,

" Aging Study of Iloiting Water Reactor Residual EGG-2469, November 1989.

Ileat Removal System," IIN1-NURiiG-52177, linmkhaven National laboratory, June 1989.

65. NUREG/CR-5334, D.11. Clauss, " Severe Acci-dentTesting of Electrical Penetration Assemblics "

57. NURiiG/CR-5379, D. II, Jarrell, A.11. Johnson, Sandia National laturatories, SAND 89-0327, Jr., P, W. Zimmerman, and M. L. Gore, " Nuclear November 1989.

Plant Service Water System Aging Degmdation As.

sessment: Phase 1," Vol.1. Pacific Northwest I ate-66.

NURl!G/CR-5057. K. R. Ihopingarner and F. R.

ratory, PNir6560 June 1989.

Zaloudck. " Aging Mitigation and Irrproved Pro-grams for Nuclear Service Diesel Generators," Pa-

58. NUREG/CR-5383, 11. M. liashemian, K. M.

cific Northwest laboratory, PNlr6397, December Petersen, R. E. Fain, and J. J. Gingrich, "Effect of 1989.

Aging.on Response'Dme of Nuclear Plant Pressure Sent. ors," Analysis and Measurement Services Cor.

67.

NUREG/CR-5386, D. P. Ilrown, G. R. Palmer, IL poration, Knoxville, TN, June 1989.

V. Werry, and D. E. tilahnik *llaris for Snt.dber Aging Research: Nuclear Plant Aging Mescarch

59. WYLE 60103-X, J. F. Gleason, R. A. DeFour, J.

Program, Pacific Northwest I atmratory, Lake En-M. llammond, and P. A. Lubeski, " Test Plan for gineering Company, W l4 laboratories, PNL-t the Comprehensive Aging Assessment of Circuit 6911, January 1990, litcakers and Relays for Nuclear Piant Aging Re-search (NPAR) Program, Phase 11," Wyle labora-68.

NUREGiCR-5419, M Villaran, R. Fuliwood, and tories,lluntsville, AL, July 1989.

M.Subudhi," Aging Amss nent ofinstrument Air Systems in Nuclear Power Plants," lin>okhaven Na-

60. NUREG/CR-4234,11. D. Ilaynes, " Aging and tional lateratory, ilNirNUREG-52212, January Senice Wear of filectric Motor. Operated Valves 1990.

Used in Engineered Safety Feature Systems of Nu-clear Power Plants: Aging Assessments and Moni-69.

NUREG/CR-5491, R. P. Allen and A.11. Johnson toring Method Evaluations," Vol. 2. Oak Ridge Jr., "Shippingport Station Aging Evaluation," Pa.

National laboratory, ORNL-6170/V2, August cific Northwest laboratory, PNic7191, January 1989.

1990.

61. NUREGICR-4967 L. C. Meyer, " Nuclear Plant

70. NUREG/CR-5479,11. Damiano and R. C. Kryter, Aging Rescatch on liigh Pressure injection Sys.

" Current Applicationsof Vibration Monitoringand tems," Idaho National Engineering Iaboratory, Neutron Noise Analysis: Detection and Analysis of EGO-2514, August 1989.

Structural Degradation of Reactor Vessellnternals from Operational Aging," Gak Ridge National

62. NUREG/CR-4977. R. Steele, Jr, and J. G.

laboratory, ORN1/PM-ll398, February 1990.

Arendts, "Sil AG Test Series: Seismic Research on an Aged United States Gate Vah>e and on a Piping 71.

NUREG/CR-5404, D. A. Casada, " Auxiliary System in the Decommissioned lleissdampfreaktor Feedwater System Aging Study,"Vol,1 Oak Ridp (llDR): Summary," Vol.1, Idaho National Engi.

National Laboratory, ORNie6566/V1, March necting 121mratory, EGO-2505, August 1989, 1990.

63. NUREG/CR-4977, R. Steele, Jr and J. G.

72.

NUREG/CR-5181, I C, Meyer and J. L. Edson, Arendts, "SiI AG Test Series: Seismic Research on

" Nuclear Plant Aging Research:The IE Power Sys-an Aged United States Gate Valve and on a Piping tem," Idaho National Engineering laturatory, System in the Decommissioned lielssdampfreaktor EGO-2545, May 1990.

NUREG-1377 56

1 senj,'c.nu 336 u.s. Nuctt an mE out Alon y coumissioN i.>

yin E'I2E BIBLIOGRAPHIC DATA SHEET

~

<s we,-,

.,i es.' ""'"'

NUREG-1377 7,1ti tt AND bub 1116 4 Rev. 1 NRC Research Program on Plant Aging: Listings and Summaries oAn MtPOa1 Puntis to Of Reports Issued Through May 1990 j

-u m

'taa July 1990 4 IIN OH GM ANT NUMBLR b AU1HOhth 61TPE Of MLPOft1 N.N. Londic, E.L. Hill Technical 7 Pt R 10D COV t fit D parw.e Demas 1981-1990 e Pyeggo, Api AiiON - AME ANu Avont ss

.,,..c.,,. c-o.,.

us --.

m c-Di.ssion of Engineering Office of Nuclear Regulatory Research b.S. Nuclear Regulatory Research waching;nn_ n _ r.

2ntu 9 EP0 NG ANil A110N N AML & ND ADOR t 55 t## 4me,.ves h m.aew. er e s,.

,,, ase.vac p per., a.,

u a ap.,w a e,, c Same as above 1

,0. $UPPtt elt NI AftY NOtt 5

11. ABS 1 h ACI (Np es,e., has The U.S. Nuclear Regulatory Commission is conducting the Nuclear Plant Aging Research (NPAR) Program. This is a comprehensive hardware-oriented engineering research.orogram focused on understanding the aging mechanisms of components arid systems in nuclear plants. The NPAR program also focuses on methods for simulating and monitoring the aging-related degradation of these components and systems.

In addition, it provides recommendations for effective maintenance to manage aging and for the implementation of the research results in, the regulatory process.

This document contains a listing and index of reports generated in the NPAR program that were issued through May 1990 and summaries of those reports. Each summary describes the elements of the research covered in the report and outlines the significant results. For the convenience of the user, the reports are indexed by personal author, corporate author, and subject.

is. At v wOnovok sen:eions a..

....~,

is av.sa 60. o *u um Unlimited Aging Mechanisms

,,,, m,,,, c,..,,,c.,,o,,

Aging Mitigation Compilation Unclassified Nuclear Plant Aging Research Life Extension Unclassified 16 NUM6th 06 PAGt 5 16 PHICt NHC f OHU 3M N 998 -

8

o I

I-UNITED STATES senciateova n ctass mat NUCLEAR C EOULATORY COMMISSION "0"'jdy'*

WASHINGTON, D.C. 20555 i

0FFICIAL BUSINESS PENALTY FOR PRIVATE USE 6300

!?Cb$5139531 1 ]Aq]py I

US NPC-0Anu DIV F0la

f. U4L! CATIONS 'Vce c

T P ;.

p r a.N in t 9 P ppt

'4 b bbIOh

]{

• )

rr I

k I

?

'f t

een i

..