ML20246F730
| ML20246F730 | |
| Person / Time | |
|---|---|
| Issue date: | 12/15/1988 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-2607, NUDOCS 8905150068 | |
| Download: ML20246F730 (17) | |
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DATE ISSUED: Dec.15,1988 i
SUMMARY
/ MINUTES OF THE ACRS SUBCOMMITTEE MEETING ON MECHANICAL COMPONENTS OCTOBER 26-27, 1988 -
BETHESDA, MARYLAND The ACRS Subconraittee on Mechanical Components met on October 26-27, 1988 at Bethesda, Maryland to review the NRC Staff's proposal regarding the draft generic letter requiring that all nuclear power plant owners implement a program to establish, maintain and periodically verify the design basis operability of all safety-related, motor-operated values (MOVs). This was the second meeting of the subcommittee on this sub-ject; the first was held on October 4, 1988.
Notice of the meeting was published in the Federal Register on October 6,1988,(Attachments). The schedule of items covered in the meeting is in Attachment B. A list of handouts kept with the office copy of the minutes is included in Attachment C. There were no written or oral statements received or presented from members of the public at the .
l meeting. E. G. Igne was Cognizant ACRS Staff member for the meeting.
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Principal Attendees
- ta 'o g ACRS NRC
$ C. Michelson, Chairman R. Kiessel e C. Wylie, Member D. Persinko om J. Carroll, Member IL Ornstein 36 P. Wohld, ACRS Consultant 0. Rothberg E. Brown Others R. Baer
- Q Soo J. Jacobson SM J. Edson, INEL R. Van Lear, Babcock & Wilcox G. Weidenhamer S. Tingen ng A i D. Lowry, Liberty Technology
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- Meeting, October 26-27, 1988 R. Bailey, Limitorque R. Slovic, Bechtel KWU R. Carr, M0 VATS R. Elfstrom, Toledo Edison R. McPherson, Southern Cal. Ed.
R. Callaway, NUMARC B. Curry, Philadelphia Electric Co. 1 L. Gifford, General Electric l T. Tipton, NUMARC E. Moore,'INP0 K. DeKall, INEL R. Steele, INEL C. Thibault, Wyle Labs.
J. Hayes, Toledo Edison J. Nadeau, M0 VATS !
J. Lang, EPRI.
i Highlights
- 1. K. DeWall, INEL, discussed test results of gate valve isolation-during high energy BWR line break performed at Wyle Laboratories.
The purpose of'the test program was to provide insights for the technical basis in the resolution of Generic Issue 87, " Failure of HPCI Steam Line Without Isolation." The objective of the program was to determine if isolation valves in BWR process lines will close against the flow resulting from a high energy line break outside of the containment. The valves used in these systems ,
includes 3-10 inch, 900 lb., flexible wedge gate valves with '
Limitorque SMB-type, motor operators, both AC and DC operated.
Two valve assemblies were tested; 1) 6", 900 lb. pressure seal, flex-wedge gate valve and hard faced disc with Limitorque SMB-2-40
_1 motoroperatorand2)6",900lb.boltedbonnet,flexwedgegate valve with hard faced disc and guide with a Limitorque SMB-0-25 motor operator. These M0V valves were diagnostically tested using i
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Meeting, October 26-27, 1988 k
equipment by Liberty Technology Center, Inc. (V0TES), Limitorque Corporation (MAC), MOVATS, Inc. Oak Ridge National Laboratory (MSCA) and Wyle Laboratories (V-MODS). Manufacturers participation was not a competition but rather an attempt to determine what ,
factors need to be considered to provide assurance of valve operability with each device. The results of these diagnostic tests to determine valve operability will be available within the next few months with a NUREG published before the end of the fiscal !
year. A total of 14 hot water blowdown tests were performed at full scale blowdown at 350 to 580 F. and at 600 to 1400 psig.
Flashing with choked flow occurred at the test valves. Preliminary results indicated that the valves successfully isolated flow under all test conditions although some valve assemblies did not fully seat during the highest energy test and that higher than calculated stem forces were observed. In conclusion, he stated that given enough thrust, typical wedge type gate valves will close against the high flow resulting from a line break.
- 2. R. Steele, Jr., INEL, discussed valve testing and its regulatory impact. He stated that generic issues, seismic uncertainty and severe accident concerns resulted in the following four valve test programs:
o Containment Penetration Systems (CPS) (Gate, globe & butterfly valves) o Generic Issue 87 (gate valve) o Purge and Vent (butterfly valve)
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=o HDR (German Decommissioned Nuclear Power Plant) (gate valve)
Each program was planned to investigate as many qualification issues as possible within the scope.of the program.
The results of the CPS program show that the' hardware. had a large margin of' safety for a west coast design basis earthquake and forces resulting.
from 17-inches of containment growth (mainly thermal) in a severe accident. Three items of concern identified were 1) water trapped between isolation valves is not'a sound design practice, 2) valve motor Loperators exhibit amplified seismic response frequencies above 33 HZ,
- and'3) valv'e end loading ' qualification requirements of ANSI B16.41 is not conservative. J
'The results of. Generic Issue 87 reviewed to'date indicate that ANSI .]
B16.41 flow interruption test may not be conservative for all valve.
designs.. Concerns include the correct modelling of the up and down-stream fluid conditions and defining the correct valve position where the maximum torques occur.
The results of the Purge and Vent program are as follows:
o The industry valve operator sizing equations of butterfly valves were not conservative, o Determined that the valve installation orientation and piping i
upstream geometry influenced closing torque requirements up to 150%. -
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1 Minutes / Mechanical-Components 5 m Meeting, October 26-27, 1988 :
The results of the HDR valve test program indicates that structurally the valve assemblies have a large margin of safety in an earthquake loading except.that it confirmed the CPS findings of the motor operated
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response frequencies above 33 Hz. The test also determined that the coil torque springs in SMA operators are subject to aging (permanent set) and that the torque output vs. torque switch setting is lower than specififed. In addition, it.was determined that DC motor heating can significantly reduce output torque in.all DC powered motor operators.-
- 3. G. Weidenhamer, RES, discussed past valve research programs. Major efforts are as follows:
.o .1985 - Butterfly valve tests were performed to confirm safety of purge _ valves in operating plants ,
o 1986 - Earthquake test of typical containment penetration isolation valves were performed. In addition, low level earthquake test on aged valves were run at HDR.
i o 1987 - Accidental tests on typical containment penetration I
isolation valves were performed.
1 0 1988 - A test program in hot water environment and high level earthquake test were performed. ;
o 1989 - Steam blowdown tests are planned, j i
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He stated.that because of decreasing budgets, research in the equipment operability area is being phased out. However, he stated that addition-al work!may be needed.
- 4. C. Thibault, Wyle Laboratories, described the Wyle valve motor operator monitoring system V-MODS. He stated that Wyle's valve diagnostic system consist of two complementary segments as follows:
t MCSA(MotorCurrentSignatureAnalysis)whichhasbeendevelopedby .
ORNL. Wyle is the ORNL licensee for this technology. MSSA consists of one clamp on ammeter, signal conditioning unit, FM
. portable tape recorder and computer / software.
V-MODS'(ValveMotorOperatorDiagnosticSystem)isutilizedto establish base line parameters and was developed entirely by Wyle Labs. [ Note: The use of load washer is the only new hardware; other systems use load cells.]
V-MODS verifies torque switch, torque bypass and limit switched settings,'and stem load on valve motor operators by gathering valve operational data, either during static actuations or under full differ-ential pressure conditions. It also provides information useful for predicting valve condition and for performing failure evaluation.
- 5. J. Hayes, Toledo Edison, discussed the air operated valve program at Davis Besse. He stated that air supply systems are generally non-safety related and therefore must be analyzed in order to l
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assure adequacy. Regulators need to give proper guidance on programmatic air operator valve program; one that is integrated and not piecemeal. He stated that industry and the NRC through a code I group will be providing guidance on this matter soon. ;
- 6. P. Wohld, consultant, discussed the air-operated valve diagnostic testing ~ program beino performed at Davis Besse Nuclear Power Plant.
The diagnostic system consists of two sensors, a 0-100 psig pressure transmitter and a spring loaded lanyard potentiometer to sense valve stem motion. An IBM compatible, portable computer based data acquisition system is used to collect, store and analyze data from the two sensors.
- 7. H. Ornstein, AE0D, discussed solenoid valve failures that have degraded numerous safety system. Failures have been widespread and many appear.to be common mode. The failure frequency also appears to be increasing. Common mode failures have a potential to result in multiple train / system failures which are beyond the plant safety analyses.. He stated'that the primary causes of failures are design and maintenance deficiencies, misapplication, and contaminants in the air system.
- 8. O. Rothberg, RES, discussed the comments received on the proposed M0V generic letter by CRGR and industry. The ma,ior CRGR comments are as follows:
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Meeting, October 26-27, 1988-
- o. Thel program in the generic letter is for-safety and it should be sent.
o The 1etter should clearly indicate that documentation of the-design bases includes consideration of degraded voltage, wiring line losses and power supply to the extent indicated in the owners commitment.-
o The implementation schedule was questioned.
o The list of degraded conditions should be clarified.
o That owners should consider augmented surveillance of the balance-of-plant MOVs.
o Owners should be given credit for work done to comply with Bulletin 85-03.
The major industry (NUMARC, EPRI). comments are as follows:
o The industry disagreed with the NRC estimates of the cost (too low) and implementation schedules (not enough time),
o Suggested that testing schedule be prioritized based on the importance of the specific MOVs contribution to avoid a core melt accident.
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- Meeting, October 26-27, 1988 o Differential pressure testing in-situ was considered to be difficult and expensive, especially for some valves, o Detailed test information on butterfly valve operators may.be
' difficult to:obtain.
Questions from a member of the subcommittee and the NRC Staff's response on the draft generic letter are as follows:
o Question: Regarding pipe break design criteria; What size pipe breaks are used in.the design criteria?
Answer: Owners are to use-the pipe break criteria committed to in the FSAR Comments: It was stated that the leak-before-break criteria shall be used only for pipe whip restraint consideration only, except for equipment qualification if justified and not other ECCS and I containment sizing. If valve operability falls under "the umbrella" of the leak-before-break I L
criteria, the differential pressure across the valve l
assembly may be smaller and less conservative than a !
design basis accident.
i o Question: Are new plants covered under your implementation plans?
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Answer: No 1
l Comment: NRR and not the Research is responsible for plant applicability.
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- 9. T. Tipton, NUMARC,' led the industry presentation on its comments on j the draft generic letter. The first speaker was E. Moore of INP0. I He stated that INPO is continuing its efforts to upgrade MOV performance industrywide. A review of NPRDS reveals that 1) limitorque models SMB-000 and 00 account for nearly 60% of all installed MOVs and experience about 37% higher failure rate than do-other operators, and 2) torque switches, limit switches'and motors ;
account for about 70% of all M0V failures. DC motors do not track closely with the overall MOV Jailure rate trend. This indicates failure mechanisms other than torque switches and limit switches may be the cause of some DC motor failures.
EPRI's Nuclear Maintenance Assistance. Center (NMAC) is addressing the below M0V issues: '
.o Technical repair guidelines. These guidelines will include detailed recommendations on topics such as preventive maintenance, testing, equipment overhauls and common industry problems.
o Initial guidelines for the SMB-000 operator is expected to be available this fall (1988).
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'. Meeting, October 26-27,'1988 o INPO is working closely with EPRI in the development of these- i repair standards.
'i, INP0 is continuing to evaluate and provide recommendations concerning check valve performance. A review of NPRDS reveals the following:
1 o Larger check valves (greater than 4 inches) are subject to more failures. Service water, main steam feed system check valves are'particularly prone to failure.
o Most frequent failure is stuck open valve exhibiting gross leakage.
i INP0 has evaluated the progress of the industry's check valve efforts with increased attention during 1988. Focus has been on recommendations of SOER 86-03: Establishment of a preventative maintenance program and performance of. design reviews (size type, and orientation).
IllP0 is'also involved in instrument air / air operated valve evaluation l
program. Many pneumatic valve failures are directly attributed to-1 instrument air system problems. Some air-operated valves have been installed with failure modes opposite to that assumed in safety analysis and some supply and exhaust lines have been found reversed. In addi-l tion, training and SOER 88-01 evaluation guidelines have been provided to evaluators.
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,' . " Meeting,-October-26-27, 1988 In summary, he stated that valve performance is improving, overall industry response has been positive and that evaluations are focusing on I
valve maintenance, design and operability issues.
. 10.. J. Lang, EPRI, discussed its activities on MOVs. .Their efforts.are directed by Nuclear Maintenance Assistance Center (NMAC) and are concentrated on technical repair and application guidelines which-will be published about November 1988. Future activities will include extensive MOV testing in order to predict its performance.
- 11. R..McPherson, Southern California Edison, R. Elfstrom, Toledo Edison and B. Curry, Philadelphia Electric, discussed the-industry- i I
comments on the generic letter in the areas of cost impact, testing at design basis conditions, and implementation schedule respectively. Industry stated that the cost of this program is about 100 times the BNL report and that design basis testing is at best very difficult. Industry proposed to prioritize the testing of its safety-related valves on the basis of pRA methodology or valves contributing to high core melt frequency be tested first.
Industry also stated that because of external and internal restraints, the testing schedule should be relaxed.
Subcommittee Action:
The Subcommittee in its deliberation stated that the proposed generic letter is not yet available for full ACRS review and comments because significant changes are being proposed by the NRC Staff. The proposed
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- f. . I..g . final / draft of the generici1etter should be available for our planned
- 1. ,P subcommittee meeting on December 12, 1938. Full ACRS review and-concents are ' planned l for the' December._ meeting.
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>> NOTE ::, A transcript of the meeting 'is available' at the NRC Pbblic Document, Gelman Bldg., 2120 "1." St. NW., Washington, D.C.
Telephone (202) 534-3383 or'can be purchased from Heritage Reporting Corporation, 1220 L Street,1NW., Washington, D.C..
20005. Telephone ~(202).6284888~
'I
i ATTACHMENT A I
b' ., Federal Register / Vol. 53, No.194 / Thursday, October 6,1988 / Notic:s 89383
, exemption will have either no Wednesday, October S.19ss--B.30 a.m. been developed to describe and make
- - significantly different environmental Untilthe Conclusion ofBusiness . available to the public such information
,1 impact or Creater environmental impact. as methods acceptable to the NRC staff Thursday, October 27,19sS-B:30 a.m.
i The principal alternative would be to f r implementing specific parts of the Untilthe Conclusion ofBusiness Commission a regulations, techniques
.. deny the requested exemption. This The Subcommittee will discuss recent used by the staff in evaluating specific would not reduce environmental w rk related to valve reliability, impacts as a result of plant operations- problems or postulated accidents, and including: isolating high energy line tests data needed by the staffin its review of Alternofive Use o/ Resources at Wyle Labs.. compressed air systrms applications for permits andlicenses.
and valves, seismic tests on an aged The draft, temporarily identified by its Th.is action does not ins,olve the use of Shippingport valve, etc.
resources not previously considered in task number MS 804-4 (which should be Oral statements may be presented by mentioned fri all correspondence connection with the Fmal members of the pubhc with the concerning this draft guide),is the Env.ironmental Statement Related tn the concurrence of the Subcommittee second propmed Revision 1 to Operation of the Sequoyah Nuclear Chairman; written statements will be Regulatory Guide 7.8, %ad Plant, Units 1 and .t," dated July 3974. accepted and made avabble to the Combinations for the Structural
- " Analysis of Shipping Casks for A
Agencies andPersons Consulted c hfh those p rN o f e Radioactive Matenal. This guide is j The NRC staff has reviewed the meeting when a transcript is being kept, being developed to present the initial licenseis request that supports the and questions mey be asked only by l membus of tht Subcommittee,its corelitions that are considered proposed exemption.The NRC staff did acceptable by the NRC staff for use in and a , e so s j not censult other agencies or persons. co s a d
8 "8 the structural analysis of Type B Finding of No Significant Impact the ACRS staff memberidcntified below to ans '"
Packagjsjs
,e5 , d a as far in advance as practicable sc that l The Commission has determined not This drsit guide f a being issued to
- to prepare an environmantalimpact 'Ehurfn ei it alpertion I e inv Ive the public la the early stages of I statement for the proposed exemption. meeting, the SubcomtrJttee, along with the development of a regulatory position Based upon the foregoing any of its consultants who may be in this area. it has not received complete L ,
b environmental assessment, we conclude present, may exchange preliminary staff review and does not represent au 1 l that the proposed actior' will not have a views regarding matters to be official NRC staff positlen.
i significant effect on the quality of the considered during the balance of the Public comments are being solicited
, human environment. meeting. en the guide, including any The Subcommittee will then hear implementation schedu:e. Comments for details with respect to this action. should be accompanied by su porting see the licensee's request for an presentations by and hold discussions
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a"vadle$'"$}S"cbn r[sY fy" e{fauons at the Commission,s Public Document fu'1 Information and Publications Services, Further information regarding topics Room, Gleman Building,2120 L Street, Office of Administration and Resources to be discussed, whether the meeting NW., Nshington, DC., and at the has been cancelled or rescheduled, the Management, U.S. Nuclear Regulatory Chattanooga. Hamilton County Commission, Washington, DC 20555.
i Chairman's ruling on requests for the Bicentennial Library,1001 Broad Street' opportunity to present oral statements Copies of comments received may be j Chattanooga, Tennessee 37402. and the time allotted therefor can be examined at the NRC Public Document Room,2120 L Street NW., Washington, '
! Dated at p.ockville, Maryland, this 30th day obtaind by a prepaid telephone call to s of September 1988. the cognizant ACRS staff member, Mr. DC. Comments will be most helpfulif Elpidio Igne (telephone 301/492-8192) received by November 25,1988.
, For the Nac! ear Regulatory Commission.
between 7.30 a.m. and 4:15 p..n. persons Although a time limit is given for Suzanne Black' commente on these drafts, comments b planning to attend this meeting are r AssistentD rectorforProjects. 7VA Projects and suggestions in connection with (1) urged to contect the above named a Division. Office o/Specic/ Projects. items for inclusion in guides currently individual one or two days before the
') (FR Doc. 88-:'.3059 Tded 1>5-88. 8 45 amj
- com '6m scheduled meeting to be advisded of any being developed or (2) improvements in all published guides are encouraged at changes in schedule, etc., which may have occurred. any time.
b / Dated: September 29,1988.
Regulatory guides are available for
- / Advisory Committee on Reactor Wrton Wharkin, inspection at the Commission's Public 6 F Safeguards, Subcommittee on Document Room,2120 L Street NW.,
Mechanical Components; Meeting Assistant Executive DirectorforProject Washington, DC. Requests for single h' ##"'" copies of draft Fuldes (which may be The ACRS Subcommittee on (FR Doc. 88-23o5o Filed 105-88,8.45 sm) reproduced) or for placement on an
, Mechanical Components will hold a suo com ree6c" automatic distribution list for single
[ meeting on October 26-27,1988, Room P-114,7920 Norfolk Avenue, Bethesda, '
enples of future draft guides in specific l divisione should be made in writing to ]
Draft Regutatory Gulde; ts.uance, MD. the U.S. Nuclear Regulatory
'j Availability Commission. Washington, DC 20555, l
The entire meeting will be open to I public attendance. The Nuclear Regulatory Commission Attention: Director, Division of j The agenda for subject meeting shall has issued for public comment a draft of Information Suppon Services, j f be as follows: a proposed revision to a guide in its Telephone requests can' tot be <
f Regulatory Guide Series. This series has acconanodated. Regulatory guides are l 1
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d% V k4. r - Q ,F ~ idi(, w y CE5 ) T 'i LS '? ATTACHMENT B Ng v.
REVISION 2 - 10/25/88 Tentative Agenda r
ACRS SUBCOMMITTEE MEETING ON MECHANICAL COMPONENTS OCTOBER 26-27, 1988 L
L 7920 NORFOLK AVENUE, ROOM P-114 BETHESDA, MD c
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(M30 - 4 45 A.M. I. CHAIRMAN'S OPENING STATEMENTS (C. Michelson, ACRS Subcommittee Chairman)
II. MOV TESTING AND OPERATING EXPERIENCE
- 1. Blowdown Tests at Wyle Laboratories h g Ao - V. 4-f
&&5 - 9dt A.M. - Introduction s ',45 - touto (G. Weidenhamer, RES)
,9t n - 19 46 A.M. - . Test Set-up and Results (K. DeWall, INEL) i o'. CV - 10 ' 15 140vtn -----------
, ledt 30 a.m. ----------- BREAK W Vs seaf n.e 10.-30 e 11:30 a.m. - Regulatory Impacts (R. Stelle, INEL)
(bow
- 2. Overview of Current MOV Operating Experience
\p: 10
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H+40 - 1& OO a.m.* - Current Activities of the Office of ..
Analysis and Evaluation of Operational Data Q f(E. Brown, AE00, will be available for U13 cnswering questions from subcommittee.)
tin o C,O
-lh00 -hte p.m. ----------- LUNCH t :23 G e o 2.'.0~7
-1HKL ;.30 p.m. - Plans for Valve-Related Research (G. Weidenhamer, RES)
'2_.'c ? t 4+40-.- 690 p.m. 3.
OetailsConcerning(DevelopmentofMOV Testing Technique V-MODS)
JC.Thibault,WyleLabs.)
af 2:45- VDQ 4ggq ----------- BREAK -----------
6 30 - 2:45 p.m. i III. AIR-0 PEP.ATED VALVE TESTING AND OPERATING EXPERIENCE 3 .t 4 - W , 1. Program on Air-0perated Valves g"g g 4+45'- 3:30 p.m. I 4 M J. Hayes, Toledo Edison) T do.s. wtg
- NOTE:
If E. Brown is not present et the meeting, the 30 minutes time will '
4'0} bh'\5distributed Jo e.to(00.60.8#
C. Thibault j l and J. Ha es.06) "' @ ;
3:00 - 4.CC p.m. IV. SUBC0W41TTEE DISCUSSION AND RECESS 46 4.
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AGENDA - MECHANICAL COMPONENTS .2 - October 26-27, 1988 I
l OCTOBER 27, 1988
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V. RESUMPTION OF MEETING g ,, g g,g h30 - &45 A.M. 1. Chairman's Remarks (C. Michelson)
VI. AIR-0PERATED VALVE TESTING AND OPERATING EXPERIENCE (CONT'D)
&45 - 9:45 A.M. 2. - Diagnostic Testing Techniques (P. Wohld, ACr4 Cuisuitant)
A'at, - t0;40 \$ 1HRTN %W' Operating Experience of Air and Hydraulic 4 - Mt45- A.M. 3.
Valves / Systems
\5 (H. Ornstein, AE0D) l D',4 - (O'.30 -
10:15 1& Stb A.M. ----------- BREAK -----------
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M - 8 40 A.M. Vll. NRC STAFF'S REPORT ON CRGR'S AND INDUSTRY'S W.
10 'i55 - 11' B COMMENTS ON THE GENERIC LETTER (O. Rothberg, NRR) i TN
- 14L i40, P .M. ----------- LUNCH -----------
c.w s. - lus5 12:30 - 3:45 P.li. Vill. INDUSTRY PRESENTATION (includes 15 min.
.brea k) The industry (T. Tipton, NUMARC, lead
/ ,, ' f - 1. presenter) will discuss the valve problems, arid in particular, the scope of implementing the-
/ NRC Staff's generic letter in terms of re-sources, equipment, and cost and schedule.
EPRI, INPO, and utilities are expected to participate.
3:45 - 4:00 P.M. IX. SUBCOMMITTEE DISCUSSION AND ADJOURNMENT L%dux3New (3 wg 3 Q.wdod ) O l .' 6- l'. You a ~Uh eJ w2m - w we, es morte sc> mm
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i L.. L' ATTACHMENT C LIST OF HANDOUTS FOR MECHANICAL COMPONENTS SUBCOMMITTEE MEETING
. OCTOBER 26-27, 1988 l.
- 1. Gate Valve Isolation During High Energy BWR Line. Breaks presented-by K. G. DeWall, Idaho National Engineering Laboratory
- 2. Valve Testing and Regulatory Impact presented by R. Steele, Jr.,
Dr. G,'H. Weidenhamer, NRC Technical Monitor, Idaho National Engineering Laboratory
- 3. Equipment Operability FIN A6857 - INEL
- 4. Past Valve Research - G. Weidenhamer 4a. Wyle Valve Motor Operator Monitoring System - Claude Thibault,'Wyle Scientific Services & Systems Group
- 5. Presentation to CRS Subcommittee on Air Operated Valve Program by John H. Hayes, Toledo Edison
- 6. Air-Operated Valve Diagnostic Testing - P. R. Wohld
- 7. Solenoid Valves --Hal Ornstein, NRC/AEOD
- 8. Memo for R. L. Baer, Chief Engineering Issue Branch, thru Frank Cherny from Owen Rothberg dated October 26, 1988,
Subject:
Summary-of Meeting Between NRC Staff and Industry Representatives on 10/19/88 to Discuss in Situ Testing of Motor Operated Valves (MOVS)
- 9. Industry Initiatives to Upgrade Valve Performance - Ed Moore, Institute of Nuclear Power Operations, Oct. 27, 1988
- 11. Nuclear Management and Resources Council Meeting with ACRS Subcom-mittee on Mechanical Components on Industry Activities and Draft Generic letter on MOVs, October 27, 1988 l i
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