ML20202G494
| ML20202G494 | |
| Person / Time | |
|---|---|
| Issue date: | 04/08/1986 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| RTR-NUREG-CR-4302, RTR-NUREG-CR-4380 ACRS-2411, NUDOCS 8607150404 | |
| Download: ML20202G494 (12) | |
Text
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g ISSUED: APR. 8, 1986
SUMMARY
/ MINUTES OF THE APRIL 1, 1986 MEETING OF THE ACRS SUBCOMMITTEE ON RELIABILITY ASSURANCE (VALVES)
WASHINGTON, DC A meeting was held by the ACRS Subcommittee on Reliability Assurance on April 1, 1986. The purpose of the meeting was to discuss the results of EPRI NP-4254, " Improvements in Motor-0perated Valves," dated November 1985. Also to be considered will be NUREG/CR-4380, " Evaluation of the Motor-0perated Valve Analysis and Test System (M0 VATS) to Detect Degradation, Incorrect Adjustments, and Other Abnormalities in Motor-0perated Valves," and NUREG/CR-4302, " Aging and Service Wear of Check Valves Used in Engineered Safety Feature Systems of Nuclear Power Plants." Notice of this meeting was published on Wednesday, March 12, 1986 in the Federal Reaister (Attachment A). Attachment B is a schedule of presentations. Attachment C is a listing of meeting slides and handouts on file in the ACRS Office. The meeting was entirely open to the public. Richard Major was the cognizant staff member for this meeting.
Participants NRC Staff ACRS RES AE0D C. Michelson, Chairman C. Wylie, Member G. Weidenhamer E. Brown G. Reed, Member J. Vora W. Lipinski, Consultant R. Sullivan R. Major, Staff J. Jeffries, Fellow G. Brown, Fellow NRR E
R. Woods R. Kiessel J. Page R. Bosnak
- 0. Rothberg DESIC1MED ORIGIIIAL
$8872=* a' *
- NM 2411 PDR Certified By
4 RELIABILITY AND ASSURANCE (VALVES) 2 April 1,1986 Meeting' Others B. Brooks, EPRI D. Eissenberg, ORNL A. Malinaus Kas, ORNL D. Warsing, Limitorque J. Milito, Philadelphia Electric Co.
B. Curry, Philadelphia Electric Co.
P. Goumer, NUS Corp.
J. Herring, Bechtel W. Craddick, ORNL K. Fleming, B&W A. Charbonneau, M0 VATS Inc.
F. Pimentel, NPC R. Comstock, Wyle Laboratories L. Conner, Doc-Search Associates J. Nurmi, QATEL L. Toth, Gasser Associates Valve Motor Operator Improvements, EPRI Project RP2233 Boyd Brooks, EPRI Project Manager Mr. Brooks explained that the objectives of this project were to:
identify root causes of improper performance of valve motor operators develop means to effectively correct the performance deficiencies, and provide for the technology transfer and commercialization of the developed corrective actions.
Results from a number of industry studies, and especially INP0 Report 83-037 which investigated 644 different licensee event reports, had as a major conclusion that the majority of motor operated valve (MOV) failures analyzed were in some way attributable to the electromechanical switches within the conventional valve motor operator (VMO). Problems discussed centered around the difficulty / uncertainty involved in establishing correct setpoints, especially for torque switches, and the overall reliability of the torque and limit switches. Other discussions in the INP0 report addressed the generally unsatisfactory method of
4 RELIABILITYANDASSURANCE(VALVES) 3 April 1,1986 Meeting providing motor thermal overload protection, and the lack of knowledge as to the mechanical /electromechanical condition of a given MOV.
Beginning in 1984 EPRI began to address the above concerns. The proje.ct has pursued:
1.
Design hardware improvements which can minimize or eliminate the historically documented problems associated with electromechanical components in valve motor actuators. This would include, but not be limited to, improvements in torque switches, limit switches, and motor overload protection devices.
2.
Identify and evaluate appropriate instruments, or design new ones, which can provide diagnostic information on the electrical and mechanical condition of valve motor actuators.
EPRI decided on a microprocessor system that could be developed to perform the functions of the deficient components and to provide diagnostic information and be readily retrofittable.
Information provided to the microprocessor system includes: motor voltage, motor current, phase angle between current and voltage wave forms, valve stem position, and valve stem load. The microprocessor will calculate / evaluate the control variables and make control decisions. The microprocessor approach to control also allows some assessment of what is likely to occur at some future point. By sensing that a particular set point is about to be reached, the microprocessor control system may be arranged so as to trip the VM0 before the setpoint is reached.
The microprocessor can provide in place diagnostic capability. The microprocessor software functions by continually monitoring parameters such as position limit, stem thrust, and motor load. When a condition
RELIABILITY AND ASSURANCE (VALVES) 4 Apr;l 1, 1986 Meeting requiring motor trip is detected, or predicted, the controller chip can be programmed to provide an auxiliary output telling why the trip occurred.
The next step in this research effort will involve the demonstration of the fully developed microprocessor control / diagnostics systems in an operating nuclear power facility. A final EPRI report (4086) will be issued documenting the entire project. Mr. Brooks also noted a Valve Technology korkshop/ Seminar is scheduled for December 3 and 4, 1986 at MEAC, EPRI NDE Center in Charlotte, N.C.
Nuclear Plant Aging Research Program Activities - D. Eissenberg, Oak Ridge National Laboratory The objective of this program is to provide recommendations for use by NRC regarding the availability and capability of diagnostic methods for assuring the operational readiness of nuclear power plant selected safety systems and components.
A number of activities are under way regarding motor-operated valves.
These include:
identifying and characterizing MOV failure modes and causes, and potential parameters to monitor, identifying and characterizing abnormalities found in a limited number of M0Vs installed in four nuclear plants; evaluating MOVATS as a method for providing useful diagnostic information; and identifying and characterizing diagnostics monitoring methods for assuring operational readiness of MOVs.
The following were listed as characteristics of a good diagnostic monitoring system:
detect and differentiate all significant degradations leading to
- failures,
t RELIABILITYANDASSURANCE(VALVES) 5 April 1, 1986 Meeting provide reproducible and trendable data, provide data during plant operation, provide criteria for maintenance actions based on operational readiness under worst anticipated conditions, be easily or permanently installed, be usable by utility operations and maintenance staff, and be cost effective in terms of risk reduction compared to alternate approaches.
The following conclusions were reached regarding the M0 VATS diagnostic monitoring system.
It can detect and differentiate incorrect adjustments.
It can detect and, to a limited extent, differentiate time dependent degradations under shutdown conditions. Under question were its ability to trend degradation, its ability to obtain data during plant operation, and its criteria for operational readiness.
It is not convenient to install or remove.
The system is relatively expensive.
Based on the ORNL investigations, the following parameters appear the most useful for detecting and trending time dependent M0V degradatic.1s:
motor current, stem thrust, motor stator winding temperature, and motor / gear box vibration. Motor current has been found to be potentially the most valuable diagnostic parameter for monitoring MOVs.
Other activities related to MOV operational readiness include a utility /0RNL informal workshop on M0V diagnostics and ASME 0&M committee efforts. The ASME work includes OM-10, Requirements for Inservice Testing of Valves in Light Water Cooled Nuclear Power Plants, and OM-8, Requirements for Pre-Operational and Periodic Performance Tests of Motor-0perated Valve Assemblies.
The ORNL program is currently studying additional components including:
auxiliary feedwater pumps, solenoid-operated valves, PORVs, concrete structures, and reactor internals.
RELIABILITY AND ASSURANCE (VALVES) 6 April 1, 1986 Meeting Perspective on NRC Valve Related Work - F. Cherny, NRR Mr. Cherr.y described a number of ongoing projects related to valves that are being addressed by the NRC Staff. A large amount of effort is being expended on Generic Issue 2.E.6.1, "In Situ Testing of Valves." It was noted that if this item were prioritized today it would probably be rated high. The Staff also plans to study all efforts relating to signature tracing measurements produced. As a result of the recent San Onofre check valve failures, a task group has been organized to look at all aspects of check valves including design, testing and maintenance.
Also under Staff review is Generic Issue B-55 which deals with the reliability of Target Rock relief valves in BWRs. Regarding relief i
valves on PWRs the Staff is involved in an ASME operations and-maintenance effort in this area. Generic Issue 70 is also addressing PORV and block valve reliability.
PORVs and block valves are being handled as a separate item.
Progress on Check Valve Aging Assessment for the Nuclear Plant Aging Research Program - D. Eissenberg, ORNL The objective for this program is the same as that for the MOV effort.
ORNL has studied failure causes of valves related to aging and service wear.
Diagnostic monitoring options for detection, differentiation, and trending of check valve degradation were discussed. Methods of monitoring include:
visual examination, inspection during maintenance, fastener tightness, disassembly and inspection, obturator movement, acoustic noise due to leakage, and acoustic noise during actuation.
Mr. Reed suggested x-ray inspection as another option.
RELIABILITY AND ASSURANCE (VALVES) 7 April 1, 1986 Meeting Among toe parameters that are being monitored are dimensions of internals subject to erosion, corrosion, or wear. Appearance of internals (roughness, cracks, and deposits of foreign material) are monitored. Acoustic noise intensity could be monitored. Two other parameters that could be monitored are obturator torque / thrust during movement and fastener torque to loosen.
Currently screening tests are under way for leakage monitoring using acoustic leak detection. Also in progress are examinations of worn check valves, and a check valve flow test stand to validate diagnostic monitoring options (acoustic leak detection, acoustic actuation monitor, and other actuation monitor), ORNL is also studying periodic disassembly and inspection reports from nuclear plants.
Licensing Need for Selected Tasks Under Mechanical Equipment Qualification Research Program - G. Weidenhammer, RES Mr. Weidenhammer noted that work was progressing in the containment isolation valve test program in NRC's Office of Research. This project is primarily related to obtaining information on the leakage characteristics of certain kinds of containment isolation valves once subjected to accident environment. Also under review are valve i
qualification standards, j
It was also explained that an effort is under way to review the capability of isolation valves to shut off a high flow system in the event of a downsteam break outside containment that could affect the operation of other safety systems. This was a concern expressed by the ACRS about one year ago. The current effort is surveying previous work in this area. Work is expected to continue into FY-87. The size of this year's (FY-86) effort is about thirty thousand dollars.
RELIABILITY AND ASSURANCE (VALVES) 8 April 1,1986 Meeting Executive Session (0 pen) i During the final half hour of the meeting the Subcommittee planned for future actions.
In April Mr. Michelson will brief the full ACRS on Subcommittee activities related to valves. Approximately thirty minutes has been allotted for this during the April full Committee meeting.
The Subcommittee will not prepare a report but will continue to monitor developments in the industry.
In general the Subcommittee was pleased with the level of effort they have seen and believes programs are moving in the right direction.
Mr. Reed noted one area of concern to him.
He believes more attention could be given in the area of design application and manufacturing of valves which in certain instances are the root cause for valve failures.
Mr. Brown, AEOD, felt there should be more pressure on the industry to encourage adaptation of the new valve test procedures.
He was uncertain as to whether or not the industry perceived a problem in valve performance. Mr. Brown also noted that the cause of many valve failures can not be traced with the new LER system.
Other failure reporting mechanisms, such as NPRDS, do not provide enough detail to determine the root causes of valve failures.
i The meeting was adjourned at 1:15 p.m.
NOTE: A transcript of the meeting is available in the NRC Public Document Room,1717 H Street, N.W., Washington, D.C., or can be purchased from ACE-Federal Reports, 444 North Capitol Street, Washington, D.C. 20001 [(202) 347-3700]
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8S80 Feder:1 Regist:r / Vol. 51, No. 48 / Widn:s' day, March 12, 1986 / Notices
,a proposed NRC quantitative safety goals only during those portions of the the status of technical development and which are to be discussed during the meeting when a transcript is being kept, support available to Fort St. Vrain.
meeting with the NRC Commissioners, and questions may be a=ked only by Oral statements may be presented by Procedures for the conduct of and members of the Subcommittee,its members of the public with the participation in ACRS meetings were
. consultants, and Staff. Persons desiring concurrence of the Subcommittee in the Federal Register on to make oral statements should notify Chainaan: written statements will be 2,1965 (50 FR 191) and apply to the ACRS staff member named below as accepted and made available to the this portion of the meeting.
far in advance as is practicable so that Committee. Recordings will be permitted Ja2 A.M-JJ:30 A.Mr(Room 1130-appropriate arrangements can be made.
only, duri those portions of the H)LMeeting with NRCCommissioners During the initial portion of the meeting en a transcript is be
- kept, (Open)-Discuss items noted above.
meeting, the Subcommittee, along with
- i In view of the possibility that the any ofits consultants who may be and questions may be asked only y members of the Subcommittee,its g 's schedule for ACRS meetings may be present, may exchange preliminary consultants, and Staff. Persons desiring adjusted as necessary to facilitate the views re arding matters to be conduct of the meeting persons consider d during the Wance of the to make oral statements should notify
]
the ACRS staff member named below n s planning to attend should check with'the meeting.
{
ACRS Executive Directorif such he Subcommittee will then hear far in advance as is practicable so that l)
.i rescheduling would result in major presentations by and hold discussions appropriate arrangements can be made.
Dum einiualporuon of ee
'I e
{-
inconvenience.
with representatives of the NRC Staff, l
Further information regarding topics its consultants, and other interested meet ' 6 S bc I
wie to be discussed, whether the meeting persons regarding this review.
Yo ts consultan w a be I
has been cancelled or rescheduled. the Further information regarding topics present, may exchange preliminary t
g, Chairman's ruling on requests for the to be discussed, whether the meet views regarding mattus to be considered during the balance of the opportunity to present oral statements has been cancelled or rescheduled, e and the time allotted can be obtained by Chairman's mling on requests for the
""U"8-a prepaid telephone call to the ACRS opportunity to resent oral statements The Subcommittee will then h~ ear i!
Executive Director, Mr. Raymond F.
and the time al otted therefor can be presentations by and hold discussions l
Fraley (telephone 202/634-3265).
obtained by a prepaid telephone call to with representatives of the NRC Staff, h
between 8.15 A.M. and 540 P.M.
the cognizant ACRS staff member, Mr.
Public Service Company of Colorado, Dated; March 7,1986 Paul Boehnert (telphone 202/634-3267) their consultants, and other interested -
1 John C. Hoyle, between 8:15 A.M. and 5:00 P.M. Persons Persons regarding this review.
9' A dvisory CommitteeManagement Officer.
planning to attend this meeting are Furtherinformationregardir: topics (FR Doc. 86-53e1 Filed 3-11-a6 tes am) urged to contact the above named to be discussed. whether the meeting individual one or two days before the has been cancelled or rescheduh d, the
- I
" " * "8 "**'*
- scheduled meeting to be advised of any Chairman's ruling on requests for the changes in schedule, etc which may opportunity to present oral r, tate nents Advisory Committee on Reactor have occurred.
and the time allotted therefor can be Safes tards; Subcommittee on Dated; March 7.1986.
obtained by a prepaid telephone call to Emergency Core Cooling Systems; Morton W. Ihrkin, the cognizant ACRS staff member, Mr.
Meettng
' A ssistant Executive Directorfor Project lohn C.MMey or to Mr. Richard K Review..
Malor (telephone 202/634-1414) between ne ACRS Subcommittee on Emergency Core Cooli Systems will p Doc. 86-5392 Filed 3-1165 am]
8:15 A.M. and 5:00 P.M. Persons planning i
w hold a meeting on Ma 26,1986, Room = = coon nos.e w to attend this meeting are urged to contact one of the above named l
1048,1717 H Street NW. Washington.
G DC.
Individuals one or two days before the To the extent practical the meetin Ady'sory Committee on Reactor scheduled meeting to be advised of any f
will be open to public attendance. g Safeguards; Subcommittee on Fort St.
changes in schedule, etc., which may.
'l However, portions of the meeting may Vraln; Meeting have occurred.
be closed to discuss proprietary ne ACRS Subcommitee on Fort St.
DetMarch 8,1988.
infomation related to Westinghouse Vrain will hold a meeting on April 2 and Morton W.thrMa, 4
ECCS codes.
3.1988, at the Visitors Center of the Fort Assistant Kxecutire Directorfbr Project The agenda for the subject meeting St.Vrain Power Plant at 16805 WCR Review.
shall be as follows:
19%. Platteville. CO.
p Doc. 5303 Filed 3-11-48; 4.45 am]
Wednesday. Man ~h 26,1986-8:30 ne entire meetin same ooon reas*w A.M. untilthe conclusion of business.
public attendance. g will be open to 1
The Subcommittee will:(1) Continue The agenda for the subject meeting [ Advisory Committee on Reactor review of the Duke Power Company's shall be as follows:
request to delete use of the ECCS Ul0 Wednesday, April 2,1986.-8:30 A.M.
Safeguards; Subcommittee on system at McGuire, and (2) discuss the until the conclusion of business.
Reliability Assurance; Meeting proposed NRR resolution position for nursday, April 3,1986-8:30 A.M.
Generic fasue 124, Auxiliary Feedwater until the conclusion of business.
%e ACRS Subcommittee on System Reliability (tentative).
He Subcommittee will explore Reliability Assurance willhold a
. Oral statements may be presented by technical problems addressed during the meeting on Aprill,1986 Room 1046, members of the public with the recent extended outage, discuss 1717 H Street, NW Washington, DC.
concurrenceof theSubcommittee management changes made as a result ne entire meeting will be open to Chairman: written statements will be of thelicensee'sindependent
' public attendancel accepted and made available to the assessment of management controls, The agenda for the subject meeting, Committee. Recordings will be permitted discuss regulatory issues, and review shall be as follows:
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N ATTACHMENT A g--e-
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4581 IIderal Register / Vol. 51 No. 48 / Wednesday, March 12, 1986 / Notices'
.{
Appendix to Gris Order,the Director,,.
m.
I
. Tuesday. April 1,1986-400 o.m. until Dated March e, ases-Office ofInspection andEnforcement f
the conclusion of business.
Morton W. Ubarkin.
has determined that the SixtyTour.
4 The purpose of the meeting will be to Assistant sceutire Dimdorfor Awicet nousand Dollar ($64,000) penalty C
Review-discuss the results of EPRI NP-4254, (W Doc. as-5394 Filed 3-19aet ads am) -
proposed for the violation designated in the Notice of Violation and Proposed
" Improvements in Motor-Operated Valves," dated November 1985. Also to awwa cooe ***as '
imposition of Civil Penal,ty is'prqper,and be considered will be NUREG/CR-4380,
.should beimposed..,
c (.
" Evaluation of the Motor. Operated IDocket ito. 50-330; uoenee No. Deut-73;
' N 'i c
Valve Analysis and Test System EA 84 1371 gy 7
Jn view of the foregoug and pursuant (MOVATS) to Detect Degradation.
GPU Nuclear Corp (Three Mlle Island, to Section 234 af the Atomic Enetgy Act Incorrect Adjustments,and Other Unit 2); Order imposing Civil of t954, as amended (42 US.C.zza2, Abnormalities in Motor Operated Monetary Penalty
' Pob. L.96-295), and 10 TR 2.205Jt is Valves," and NUREG-CR-4302. " Aging and Service Wear of Plants," both g~
hereby ordered that:.
reports were prepared by the Oak Ridge General Public Utilities Nuclear Helicenece pay the civilpenalty in National Laboratory for the Office of Corporation (GPU Nuclear or licensee),
the emownt of Sixty.Four%ousand Nucleat Regulatory Research.The
. Parsippany, New Jersey is the holder of DoMars ($64D00) within thirty days of Subcommittee will also plan the format 12 cense No. DpR-73 issued by the the date of this Order by check, draft,or for a report which will encompass its ar Regdat@%skn @RQ money order. payable to the Treasurer of the United States and mailed to the considerations over the past year.
Oral statements may be presented by fpe*r t theIhre le d
ear Director, OEice ounspecuon and members of the public with the Station. Unit 2 in Middletown, Enforcyment DS.NuclearReguhtory concurrence of the Subcommittee Pennsylvania,in accordance with Commissson Wu%n, DC 20555.
Chairman; written statements will be conditions specified therein. The license accepted and made available to the was issued on February 8,1978 and y
Committee. Recordings will be permitted modific'l by Order en July 20,1979.
,The licensee may request a hearmg within thirty days of the date of this only during those portions of the U.
. Order. A request for a bearing shall be meeting when a transcript is beir.g kept.
During the period between February addressed to the Director Offim of and questions may be asked only by 23,1983 and March 24,1983, Richard D.
members of the Subcommittee,its Parks, a Bechtel employee, was Inspection and Enforcement US.
consultants, and Staff. Persons desiring discriminated against for engaging in Nuclear Regulatory Comminaion, to make oral stateme.its should nohfy protected activities in reporting safety Washington, DC 20555. A cory M the the ACRS staff member nar ted below as concerns to his management. requesting hearing request also shall be seet td the
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far in advance as is practicable so that assistance from the NRC, and Executive legal Diredor. US. Nuclear appropriate arrangements can be made.
c mmencing a proceeding with the U.S.
Regulatory Commission, Washington, During the initial portion of the D, epa,rtment of Labor (DOL).The acts ofDC 20555.
meeting. the Subcommittee, along with disenmmauon were described in a DOL If a hearing is requested. the any of its consultants who may be inusugauon M. Case 834RA-y that Commission willissue an Order 8
designating the time and place of the,
present.may exchange preliminary
- '#* '$*n
- 2) anif heanng. If the hansee fails to request a views regarding matters to be g.est h
po considered dunng the balance of the discussed in Section 10 of NUREG-0680, hearing withb thirty days of the date of meeting-Supplement 5. As p result of the NRC this Order, the provieions of this Order
' The Subcommittee will then hear staff's review of these reports, an shallbe effective without further presentations by and hold discussions apparent violation of NRC requirements Proceedings. If payment has not been with representatives of the NRC Staff.
was identified. Consequently, a written made by that time, the matter may be its consultants, and other interested Notice of Violation and Proposed seferred to the Attorney Generalfor Imposition of Civil Penalty (NOV) was persons regarding this review.
served upon the licensee by letter dated collection.
in the event the hcensee requests a Further information regarding topics August 12,1985. The Notice stated the to be discussed, whether the meeting nature of the violation. the NRC hearing as provided above, the issues to has been cancelled or rescheduled, the requirement that the licensee had be considered at such bearing shall be:
Chairman's ruling on requests for the vi lated. and the amount of civil penalty (a) Whether the licensee violated NRC opportunity to present oral statements proposed for the violauon. An answer requirements as set forth in the Notice and the time allotted therefor can be
- dated October 21,1985 to the Notice of of V olation and Proposed Imposition of obtained by a prepaid telephone call to Vi lation and Proposed imposiuon of Civil Penalty referenced in Section H
~
.[
the cognizant ACRS staff member, Mr.
C il Penalty was received from the above and '
Richard Major (telephone 202/634-1414)
(b) Whether, on the basis ofsuch
~
between 8:15 a.m. and 500 p.m. Persons
~violaticn, this Order should be HI planning to attend this meeting are sustained.
urged to contact the above named
'After consideration of GPU Nuclear's Individual one or two days before the response and the statements of fact. -
beted et Estheede Mary 4end,61s 4th day scheduled meeting to be advised of any explanation. and denial of the violation af March nee.
changes in schedule, etc., which may contained therein,as set forthin the o
.M-have occurn d.
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8 TENTATIVE SCHEDULE FOR THE APRIL 1, 1986 [8:00 A.M.] MEETING 0F THE ACRS SUBCOMMITTEE ON RELIABILITY ASSURANCE (VALVES)
ROOM 1046 1717 H STREET, N.W.
WASHINGTON, D.C.
8:00 a.m.
A. Chairman's Introduction - C. Michelson 8:05 a.m.
B. Discussion of EPRI NP-4254, " Improvements in Motor-Operated Valves" (Interim Report) - B. Brooks, EPRI 10:00 a.m.
BREAK 10:30 a.m. C.
Update by RES/0ak Ridge, NUREG/CR-4380, " Evaluation of the Motor-0perated Valve Analysis and Test System (M0 VATS) to Detect Degradation, Incorrect Adjustments, and Other Abnormalities in Motor-0perated Valves" 11:30 a.m. D.
Discussion of NUREG/CR-4302, " Aging and Service Wear of Check Valves Used in Engineered Safety-Feature Systems of Nuclear Power Plants" - RES/0ak Ridge 12:30 p.m.
E. Summary Session Discussion by Subcommittee of the Format for a Final Report on Subcommittee Considerations 1:30 p.m.
F.
ADJOURN l
ATTACHMENT B 1
6 m
,e
-e
4 SLIDES / HAND 0UTS ACRS SUBCOMMITTEE ON RELIABILITY ASSURANCE APRIL 1, 1986 WASHINGTON, D.C.
1.
. Valve Motor Operator Improvements, EPRI Project RP2233-2, Project Status Report, presented to the ACRS Subcommittee on Reliability Assurance (Valves), Washington DC, April 1,1986, from Boyd Brooks, EPRI, 10 slides.
2.
Microprocessor-Based Control and Diagnostic System for Valve Motor Operators by Robert A. S. Lee, Foster-Miller, Inc., 350 Second Ave., Waltham, MA 02254, from Boyd Brooks, EPRI - handout paper.
3.
Nuclear Plant Aging Research Program Activities Presentation for Advisory Committee on Reactor Safeguards, Subcommittee on Reliability Assurance (Valves) - David M. Eissenberg, Oak Ridge National Laboratory, 25 slides.
4.
Progress on Check Valve Aging Assessment for the Nuclear Plant Aging Research Program, D. Eissenberg, ORNL, 14 slides.
5.
Memorandum for Robert Minogue, Director, Office of Nuclear Regulatory Research, from H. Denton, Director, Office of Nuclear Reactor Regulation,
Subject:
Licensing Need for Selected Tasks Under Mechanical Equipment Qualification Research Program (A-6322) from G. Weidenhammer, NRC/RES, dated March 11, 1986.
6.
DET/RES Programs Related to Valve Operability and Reliability -
G. Weidenhammer, NRC/RES, 1 slide.
7.
ASME Working Group OM-8, Startup and Periodic Performance Testing of Electric Motor-0perated Valve Assemblies in Nuclear Power Plants, Draft D, dated August 28, 1985. Handout from D.
Eissenberg, ORNL, with date of March 25, 1986.
1 8.
Memorandum for C. Michelson, Chairman, ACRS Subcommittee on Reliability Assurance (Valves) from P. Wohld, Reactor Inspector, R. III,
Subject:
Review Comments on Interim EPRI Report, EPRI NP-4254, November 1985. Meeting handout dated March 27, 1986.
9.
ASME Operations and Maintenance Committee - Project Status Form.
Handout from D. Eissenberg, ORNL.
ATTACHMENT C
.