ML20150C193
| ML20150C193 | |
| Person / Time | |
|---|---|
| Issue date: | 04/07/1988 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-2560, NUDOCS 8807120346 | |
| Download: ML20150C193 (18) | |
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i CERTIFIED COPY: l DATE ISSUED: April 7,1938
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SUMMARY
/M!NUTES OF THE MARCH 7-8, 1988 MEETING OF THE ACRS SUBCOMMITTEE ON RELIABILITY ASSllRANCE (VALVES)
WASHINGTON, D.C. 20555 A meeting was held by the ACRS Subconnittee on Reliability Assurance on March 7-8, 1988. The purpose of the meeting was to review current industry and NRC Staff efforts relating to valve reliability. Presen-tations were made by: NUMARC, EPRI, INPO, TVA, Liberty Technology Center, Limiterque Corporation, M0 VATS Inc., Oak Ridge National Lab.,
Idaho National Engineering Lab. and the NRC Staff. Notice of this meeting was published on Tuesdar, February 23, 1988 in the Federal Reoister(AttachmentA). Attachment B is a schedule of presentations.
The meeting was entirely open to the public. Richard Major was the cognizant Staff Engineer for this meeting.
Attendees ACRS NRC Staff C. Michelson, Acting Chairman G. Weidenhamer J. Ebersole, Member M. Vagins C. Siess, Member (8th Only) 0. Rothberg R. Major, Staff R. Woods F. Cherney Others J. Smith R. Hill, EG&G Idaho D. Davidson H. Magleby, EG8G Idaho M. Dey K. DeWall, EG&E Idaho G. Hammer D. Eissenberg, ORNL S. Hoover, Wyle Labs. 8807120346 880407 T. Edwards, Duke. Power P "
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DE01C"ATED ORIGIliAI) s ng . . - . . D ~tIId0d E7 M y l --
Minutes / Reliability Assurance-
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' (Valves) March 7-8, 1988 Mtg.
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. D. Cox, TVA
- 1. Ciaramitaro, Westinghouse
- 3. Bruss, Bechtel S. Priftis, CEC 0 ll. Morgan, CECO A. Maass, Babcock A Wilcox '
D. Warsing, limitorque L. Bailey, limitorque C. Nadeau, M0 VATS A. Charbonneau, MOVATS L. Cannon, NSA B. Curry, Philadelphia Electric Co.
R. Woolley, GA International Service Corp.
R. Schaffstall, KMC Inc.
D~ Ayres, B&W W. Knecht, Anchor / Darling Valve Co.
M. Mancini, Liberty Technology R. Leon, Liberty Tech.
- D. Lowry, Liberty Tech.
J. Terry, Westinghouse R. Keating, MPR Associates A. Nelson, NUMARC J. Calvin, NUMARC T. Tipton, NUMARC T. Marston, EPRI E. Moore, INP0 l R. Van Lear, B&W J. Rose, Heritage K. Boyd, Heritage Chairman's Introduction 1
Mr. C. Michelson, Acting Subcomittee Chairman, explained that the purpose nf the meeting was to bring the subcomittw up to date on l
developments in valve reliability that have occurred over the past year. ,
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He also noted that these Valve Reliability Assurance Subcomittee meetings were an opportunity for the nuclear comunity to educate itself regarding changes and developments that have taken place over the past year.
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- - Minutes / Reliability Assurance 3
, (Valves) March 7-8, 1988 Mtg.
Overview of Industry Efforts on Valve Reliability Improvements - J.
Colvin, NUMARC Mr. Colvin, Chief Operating Officer and Executive Vice President of the Nuclear Managenent and Resource Committee outlined industry initiatives to reduce plant problems caused by failures of valves. Of primary interest to the industry have been the problems with motor operated valves and check valves. NUMARC's role in valve initiatives has been that of a facilitator which attempts to focus industry efforts and resources to try and achieve effective implementation and corrective solutions throughout industry. NUMARC relies primarily on INPO, EPRI, and the Owners Groups, as well as, the utilities themselves to develop and implement solutions to problems.
EPRI Programs - Ted Marston, Director, Nuclear Engineering and Operation I
Mr. Marston described valve related research and development work being performed by EPRI. The industry has tremendous incentive to improve I l
valve reliability on both safety related and economic grounds. j Valve malfunctions result in approximately a 2% loss of U.S. LWR capaci-ty. This translates into a $350 million lost in capacity for the industry. Approximately 10% of the in-plant valve population contrib-utes to this loss. About one-third of the capacity loss is associated with safety related valves.
Minutes / Reliability Assurance 4 (Valves) March 7-8, 1988 Mtgo Mr. Marston noted that there are active channels for the exchange of international experience related to valve reliability. These channels are both formal and informal.
The methodology EPRI uses in valve related research is to first priori-tize and address problems. The next step is to develop, test, and demonstrate generic corrective actions and guidelines. Finally, results are transferred to the industry through wnrkshops, seminars, and in-plant demonstrations.
To date, some of the root causes of valve problems include: failure to treat as a single entity the valve, its cpetator, and a specific valve i application; failure to focus existing knowledge and problem solving on a case-by-case basis; and a final root cause problem discussed was overly critical design and perfomance requirements, which surpass the !
valves intended operating parameters. .
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Mr. Marston briefly reviewed the published EPRI valve research reports dating back to 1976. Among these efforts is a recently completed ;
applications guide for check valves. This guide was supported by the four HSSS vendor owners groups and EPRI. Also nearing completion is a motorized valve repair guide, which will present a collection of repair experience and good practice. This guide will be available in April 1988.
Minutes / Reliability Assurance 5
.' (Valves) March 7-8, 1988 Mtg.
1 INPO Programs on Plant Maintenance - E. Moore j l
Mr. Moore noted that INP0 became involved in valve reliability following l several significant industry events that included failures or misapplications of motor operated valves and check valves. INP0 responded to these events by disseminating this experience to the industry. INPO then checks to be sure the utilities have responded adequately to the information available.
Mr. Moore explained INPO has a number of programs which strive to improve plant performance through better maintenance. These programs include: NPRDS, the Component Failure Analyses System, Industry Self-Assessment Initiatives, and the accreditation program.
l INP0 Programs on Motor-0perated Valves - G. Peterson l 1
Mr. Peterson discussed INP0 initiatives in the area of motor-operated valves and check valves. I INP0 has created a MOV action plan together with NUMARC and EPRI.
Elements of this action plan include detailed review and analysis of NPRDS for M0V failures, and increased emphasis on M0V maintenance during INP0 evaluations and assistance visits. Visits to plants that have good MOV performance have been conducted to gather information. A number of workshops are planned to inform maintenance managers of the lessons learned from the effort.
Minutes / Reliability Assurance 6
(Valves) March 7-8, 1988 Mtg.
The INP0 check valve activities include the dissemination of various experience reports to the industry. There are also numerous methods for industry interaction through workshops, application guides and an owner's group task force.
Hydrogen Detonation and Damage to Safety Relief Valves in Foreign Boiling Water Reactor - Gary Hammer, NRC-NRR Mr. Hammer discussed a May 6, 1987 event that occurred at the Gundremmingen plant, Unit C in the Federal Republic of Germany. A hydrogen detonation severely damaged three main safety relief valves.
The hydrogen and oxygen that detonated was created by the radiolytic decomposition of water. The hydrogen and oxygen concentrated over a few weeks in high, subcooled, stagnant, pockets. In the SRVs used in Germany, detonation was caused by the fast compression of gas inside the valves pilot lines and inside the SRV when the pilot valve opens to l actuate the SRV. 1 l
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The Staff has reviewed the design of American SRV's used on boiling !
water reactors. The review indicates gases can collect. However, actuation of US valves causes a decompression of gases and therefore, no 1 1
explosion. The water chemistry in a PWR eliminates this problem. The I excess hydrogen present in a PWR causes recombination of hydrogen and ;
l oxygen into water. ,
The Germans are considering twc ,otential solutions to this problem.
One is to install a bypass line around the pilot valve which would sweep 1
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Minutes / Reliability Assurance .7 (Valves) March 7-8, 1988 Mtg. i l
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- the hydrogen gas and prevent its build-up. The second potential so-lution is to install a catalytic material inside the pilot valve to cause the hydrogen and oxygen to recombine into water.
- j Discussion re Valve Actuator Parts Interchangeability - TVA - J..
Ziegler, et.al.
Representatives from TVA discussed a valve actuator parts inter-changeability problem that arose at the Watts Bar Nuclear Plant. During a lubriacation process, it was discovered that the internal parts of the limitorque valve actuator differed even among the same actuator model number. TVA has instituted an extensive program to assure that the appropriate actuator is installed on a particular valve, for a specific function. The current program, at all TVA plants, controls the valve !
actuator configuraction to ensure it is functionally appropriate. l l
l Tuesday, March 8, 1988:
Presentation by the NRC Office of Research - Introduction.
o - M. Vagins, NRC, RES Mr. Vagins noted the substantial effort the Office of Research has in the area of valve research. Among the ongoing projects is an effort to i test actually aged valves from the Shippingport Reactor. Programs to test feedwater and isolation valves are underway. Most of this research is aimed at general support of generic issue 87. The total expenditures for this year are on the order of $800,000.
Minutes / Reliability Assurance 8 (Valves) March 7-8, 1988 Mtg.
Containment Penetration System Behavior During Design Basis and Severe Accidents - R. C. Hill, INEL This work was designed to characterize the performance of containment penetration systems during design basis and severe accidents through experimental investigation. Three systems were picked for study: an 8-inch containment spray pipe penetration, an 8-inch purge and vent system, and a 2-inch small bore support system which is typical of the majority of containment penetrations. The test configuration was de-signed to accurately represent a actual system, actual nuclear grade components were used in the test apparatus.
The systems were tested during simulated operating basis and safe shutdown earthquake conditions. The valve leak integrity, valve operability, and piping systen responses were tonitored. Results indicated that structural integrity of systems was not impaired, valve leakage was not increased by seismic excitation, and valve operability 1
was not degraded by seismic excitation. l Three full-scale containment penetrating systems configuration were also tested under accident loading conditions. It was found that leak i
integrity and valve operability will be maintained during design basis l
and severe accident loading. Double valve penetration systems will l maintain leak integrity after severe accident loading. There was deformation of pipe clamps, pipe supports, and pipe walls, but no pipe wall collapse.
1 Minutes / Reliability Assurance 9
, (Valves) March 7-8, 1988 Mtga i
Gate Valve Isolation During High Energy BWR Line Breaks - K. G. DeWill, INEL
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The aim of this research.is to demonstrate the ability of isolation -
valves in Boiling Water Reactor process lines to close against the flow resulting from a high energy line break outside containment. Con- l clusions from this program which drew on previous test data include the fact that valves have failed to close in test programs where they were specifically designed for the test conditions. The actual stem thrust needed to close some valves is greater than calculated. The available )
test data is not sufficient to answer flow interruption concerns. l (There has been very little testing using large valves; valves have >een te_ted with steam, without the effect of flashing hot water; and there have been no direct stem thrust measurements.) Testing at actual BWR pipe break flow conditions is recommended.
l In the future, plans are being made to conduct hot water blowdown tests l l
to provide insights into gate valve stem loadings and their effort on functionality during high energy pipe breaks. Separate effects eval-uations are also planned for the future. The purpose for this testing will be to assess the likely effects of deposition, erosion, and corro-sion on valve performance for BWR plant conditions.
Valve Anomaly Identified From HDR Testing - H. L. Magleby, INEL During the seismic simulation tests that were done at the decommissioned HDR in Germany, an anomaly in a MOV's performance was observed. Tho
Minutes / Reliability Assurance 10
.- (Valves) March 7-8,~1988 Mtga anomaly observed was the failure of the torque switch to stop motor current, once stall conditions were reached. Conclusions from this incident seen to indicate: torque switch settings may need to be monitored to compensate for permanent spring deformation due to aging.
Motors should be sized to close without apptoaching stall to avoid degraded performance due to heating of windings. Additional evaluations are still underway.
Generic Issue II.E.6.1 In Situ Testing Of Valves - 0. Rothberg, NRC -
RES This task was one of the TMI Action plan items. Its original objective was to evaluate whether current requirements for valve testing provide adequate assurance of performance under design conditions. The current work scope is to identify performance requirements that are not ade-quately verified by current in situ tests, evaluate alternate in situ tests to verify performance, and develop staff positions for additional periodic valve in situ tests. Current areas of concern include motor operated valves (MOVs), pressure isolation valves (PIVs), check valves, and thermal overload devices (TOLs) for MOVs.
Prediction of Check Valve Performance and Degradation - M. Vagins, NRC - I RES l
The objective of this research is to develop a technical basis for predicting check velve failures and an assessment of their perfonnance.
The first phase of this study is using 3 inch and 6 inch instrumented
Minutes / Reliability Assurance 11
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check valves to evaluate the effects of upstream flow disturbances (elbows and pipe reducers), flow velocity and valve disc backstop angle on disc oscillations, and backstop impacting; and determine minimum velocity for stable valve disc behavior. !
Conclusions reached to date indicate check valves have been improperly selected for service conditions in many cases leading to disc hinge pin failures from disc oscillations and wear and back stop failure from disc impacting. Upstream flow disturbances in close coupled nuclear plant piping systems must be considered in v61ve selection. Yalve selec+, ion must censider disc angle and hence backstop position required for stable disc behavior over the operating flow range.
Plans for future research will combine the results from this first phase research with additional research to provide a basis for determining the need for valve replacement or scheduling maintenance, and a basis for evaluating plant life extension regarding check valves.
Liberty Technoloay Center's - Votes System - R. Leon Mr. Leon described a new system that has been developed for testing and diagnosing motor operated valves. A key feature of this system is its stem force measurement concept. (This concept is also applicable to hydraulic and air operated valves.) Valve stem forces cause equal and opposite yoke reaction forces, with the resulting yoke deflections being measurable as an accurate indicator of stem force over the entire valve stroke. A special sensor is applied to the valve yoke to measure the l
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Minutes / Reliability Assurance 12 (Valves) March 7-8, 1988 Mtge
- stem force. This stem force measurement can be used as a diagnostic aid. It can give indications of too little or too mucn seating force, packing force degradation, damaged stem threads, poor lubrication, spring packing condition, torque and limit switch settings and other ,'
indications of the M0V's servicability.
Limitorque's Motor Actuator Characterizer (MAC) - R. Bailey Mr. Bailey described a portable, computer controlled test system for diagnostic testing of Limitorque valve actuators while they are in service. This system through various sensors measures torque, thrust, motor current, worm gear displacement, limit and torque switch settings.
Among the diagnostic information that can be gleaned from this product are: stem lubrication, spring pack performance, worm gear wear, a damaged or worn valve stem, unbalanced torque switch, motor degradation, and excessive packing load.
M0 VATS Incorporated - A. Charbonneau Mr. Charbonneau went through a listing of approximately 32 types of l valve degradations in which signature analysis can provide some insight.
He noted that 99% of the valves tested by M0 VATS have been in nuclear plants although there is valve test experience at fossil plants, refin-1 eries, and chemical process plants, l Future concern discussed by Mr. Charbonneau were the adequacy of histor-ical thrust prediction ecuations. These traditional handbook equations
' Minutes / Reliability Assurance 13 (Valves) March 7-8, 1988 M29
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are receiving renewed attention and conservative new equations are being developed for use with the MOVATs product. The adequacy of ASME section XI for MOVs may be modified or expanded to consider valve operability.
MOVATs also believes the NRC will require more valve signature testing in the future. M0 VATS has high and low pressure flow loops under construction. These experimental loops will be used for resea ch and development projects and for educational purposes.
MOVATs has a number of new devices on the market. A new motor load unit has been developed that can from the motor control center and a data base predict whether or not a valve will operate against a given differ-ential pressure. These units incorporate stem strain transducers when measuring valve stem loads. Diagnostic testing equipment is being applied to different types of valve actuators and different types of valves.
To date, M0 VATS has tested over 9,000 valves. I l
I The checkmate system, used to test check valves was reviewed. This is a portable system that uses two externally mounted ultrasonic probes and a processing unit to test check valves. The system can verify valve disc position to within 4 degrees, and whether or not the valve disc is fluttering.
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' Minutes /Reliebility Assurance 14 (Valves) March 7-8, 1988 Mtgo T
Valve Diagnostic Equipment - ORNL - D. Eissenberg l I
A motor current based equipment diagnostic system has been developed as a result of motor-operated valve (MOV) research at Oak Ridge. This approach was selected because it is capable of non-intrusive and remote monitoring, measurements may be performed rapidly using portable equip-ment, and it offers high sensitivity and selectivity to M0V disorders.
The focus of the testing at Oak Ridge was to discover aging degradation. )
The technical basis for the notor current signature analysis that has been developed is that an electric motor driving a mechanical load acts as a transducer, converting the load variations of the driven device into electrical signals transmitted through the power cable. The signals are sensed and processed using state of the art technology. The resulting signatures are compared, and trends related to degradation and other defects.
l Oak Ridge is working on check valve diagnostics to identify aging degradatien. Radiography, ultrasonic testing, and noise analysis are .
l being considered. The current check valve being tested at Oak Ridge is instrumented to detect disc position and motion as well as to permit spectral analysis of pressure noise and acoustic signals.
Just starting is a test progran for solenoid valves. Several diagnostic approaches are being considered including: solenoid temperatures, inrush current transient analysis, and vibration.
Minutes / Reliability Assurance 15 (Valves) March 7-8, 1988 Mtg.
The meeting was adjourned at 5:30 p.m.
NOTE: A transcript of the meeting is available at the NRC Public '
Document Room, 1717 H Street, NW., Washington, D.C., or can be purchased from Heritage Reporting Corporation,1220 L Street, NW., Washington, D.C. 20005, Telephone: (202) 628-4888 f
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5332 ' Federd R:,gister / Vol. 23, No. 35 / Tuesday, February 23, 1988 / Notices l 1
offsite which have not already been meeting on htarch 7 and 8,1988, Room Da te: Febru ary 17,1988, evaluated and approved in the FES (as 1No.1717 H Street NW., Washingtott Gary Quitts6teiber, amended) for a NSSS power rating of DC. Acting A ssistant Lecutive Director /Or 3579 N1Wt. Similarly, as ens eloped by The entire meeting will be open to Project Review.
the FES (e,s amended). there would be public attendance. IFR Doc. 86-3821 Filed 2-22-88,8.45 am) no significant increase in individual of The agenda foi the subject meeting sumo coot mo-et-u cumulative occupational radiation Uall be as follows:
" P ' * "' Afonday. Afarch 7,1998--1Mp.m. until Advisory Committee on Reactor \
Alternatives to the Proposed Action the conclusion of business. Saf eguards, Sut>committte on i The principal alternative to the Tuesday. Afarch s.19ss--430 a.m. until Auxiliary Systems; Meeting I proposed action would be to deny the the conclusion of business.
ne ACRS Subcommittee on Auxiliary requested amendment. %is alternative The Subcommittee will hass:(1) Systems will hold a meeting on March 9, l would be in contradiction to the fact Valve reliabibty, including valve testing 1988, Room 104e,1717 H Street NW.,
that the NRC. approved F'ES. as schemes by Liberty Technic al Center, amended, has already addressed Washington, DC.
Limitorque,hiOVATS, and Oak Ridge hiost of the meeting will be open to operation up to a stre'tch power rating of National Laboratory;(2) RES plans for htOV and check valve related work;(3) pubFc attendance. Ilowever, a portion 3579 htWt.
of the meeting will be closed to discuss valve testing insights from Peter Wohld; Ahernative Use o/ Resources proprietary information relating to fire (4) incidents alated to valves (German protection provisions at foreign nuclear This action does not involve the use of hydrogen explosion in PORV and TVA resources not considered previously in h10V interchangeability problem); and power plants.
the FES (as amended) for Callaway (5) status reports from indu stry The agenda for the subject meeting Plant Unit No.1. organizations on valve rela ted shall be as follows:
programs. Wednesday, hfarch 9, :983--s.30 a.m.
Agencies and Persons Consultai Oral statemeMs may h I meded h WWmh@h The NRC staff reviewed the licensee's .
members of the public with .he The Subcommittee will discuss the request and did not consult other results of the Fire Risk Scoping Study concurrence of the Subcommi tee agencies or persons. Chairman: written statemen,s vill be performed by Sandia National Finding of No Sigmficant impact accepted and made available to be .t.aboratories for the NRC.
Committee. Recordings will be pencitted Oral statements may be presented b, The Commission has deterrnined not only during those portions of the members of the public with the to prepare an environmentalimpact statement for the proposed amendment.
meeting when a transcript is being kept, concurrence of the Subcommittee Based upon the foregoing environmental and questions may be asked only by Chairman, written statements will be assessment, the NRC staff concludes members of the Subcommittee,its accepted and made available to the consultants, and Staff. Persons desiring Committee. Recordings will be permitted that the proposed action will not have a significant effect on the quahty of the to make oral statements should i.otify only during those portions of the human environment, the ACRS staff member named below as meeting when a transcript is being kept, For further details with respect to this far in ads ance as is practicable so that and questions may be asked only by action, see the request for amendment appropriate arrangements can be made, members of the Subcommittee,its dated March 31,1987, as supplemented Dunng the ini*ial portion of the consultants, and Staff. Persons desiring Apnl 21 September 18. October 2. meeting. the Subcommittee, along with to make oral statements should notify October 23. and November 13,1987, any of its consultants who may be the ACRS Staff member named below which is available for public inspection present, may exchange preliminary as far in advance as is practicable so at the Commission's Public Document views regarding matters to be that appropriate arrangements can be Room.171711 Street NW., Washington, considered danng the balance of the made.
DC. and at the Callaway County Public meeting. Dunng the initial portion of the Library,710 Court Street Fulton. The Subcommittee will then hear meeting, the Subcommittee, along with Missouri 65251 and the John M. Olin presentations by and hold discussions any of its consultants who may be .
Library, Washington University, Skinker with representatives of the NRC Staff, present. may exchange preliminary )
and Lindell Boulevards, St. Louis, its consultants and otherinterested views regarding matters to be Mis souri 63130. persons regarding this review. considered dunng the balance of the Further information regarding topics meeting.
Dated at Bethesda. Maryland. this 17th day ,
of February.1988. to be discussed. whether the meeting The Subcommittee will then hear has been cancell?d or rescheduled, the presentations by and hold discussions 1 For the Nuclear Regulatory Commission.
Chairman's ruling on requests for the with representatives of he NRC Staff, l Kenneth E. Perkins. its consultants. and other interested pp rtursity to present oral statement ]
Director. Pro /cct Duveto ote ll/-J. Dinision of and the time allotted therefor can be persons regarding this review.
btained by a prepaid telephone call to Further information regarding topics FR .
Filed 2-22-ea 8.45 am] the cognizant ACRS staff member, Mr. to be discussed, whether the meeting l m mo coes n n. " Richard Major (telephone 202/6M-1414) has been cancelled or rescheduled, the h etween 7.30 a.m. and 415 p.m. Persons Chairman's ruling on requests 'or the ,
planning to attend this meeting are opportunity to present oral statements l Advloory Committee on Reactor urged to contact the above named and the time allotted therefor can be Safeguards, Subcommittee on indisidual one or two days before the obtamed by a prepaid telephone call to Re!M Amurong MW scheduled meeting to be advised cf any the cognizant ACRS Staff member. Mr.
The ACRS Subcommittee on changes in schedule, etc., wh.ch may Sam Duraiswamy (telephone 202/634-Reliability Assurance will hold a have occurred. 3267) between 7.30 a.m. and 4:30 p m.
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- Monday, March 7, 1938 1:00 p.m. 1. Chairman's Introduction 1:10 p.m. 2. Overview of Industry Efforts on Valve Reliability +
Improvements - NUMARC 1:PO p.m. 3. EPRI Programs 2:20 p.m. 4 INP0 Precrams 3:20 p.m. ****** PPEAK '****
3:30 p.m. 5. Discussion of Operations Experience
- a. Hydrogen Detonation and Damage to Safety Relief Valves in foreign Boiling Water Reaeter - G.
Hamer
- b. TVA - Discussion re Limitorqe motor actuator corrperent interchangeability problem Tuesday March 8, 1986 8::0 a,n. 6. Reconvene 6:35 a.n. 7. Presentation by HRC Office of Research - G.
k'eidenherer
- a. Containmert Isolation Valves - (i Hour)
- b. Isolation of High Energy Line Breaks - (i Hour)
- c. Seismic Testing of an Aged Shippingport Valve -
(1/2 Hour)
- d. Status of Generic Item II. E 6.1 Inservice ,
Testing of Valves (1/2 Hours). - O. Rothberg l
- e. Prediction of Check Valve Performance and degradation- (15 Min.) - M. Vagins
- BREAK 10:45 a.m. 8. Valve Diagnostic Enuipment: Liberty Technology Cento - P. Leon !
- LUNCH 12:00 NOON 1:00 p.m. 9. Valve Diagnostic Equipment: Limitorque Corporation - l
- 0. Warsing/R. Bailey ,
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l 2:15 p.m. 10. Yalve Diagnostic Equipment: Movats Inc. - S.
Charbonneau
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3:30 p.m. BREAK 3:45 p.m. 11. Valve Diagnostic Equipment: Oak Ridge National Laboratory - D. Eissenberg 5:00 p.n. ADJOUoN l
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