ML20215L164
| ML20215L164 | |
| Person / Time | |
|---|---|
| Issue date: | 10/11/1986 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-2449, NUDOCS 8610280508 | |
| Download: ML20215L164 (15) | |
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s CERTIFIED MINUTES DATE ISSUED: October u
11., 1986
SUMMARY
/ MINUTES OF THE ACRS SUBCOMMITTEE ON METAL COMPONENTS AUGUST 4, 1986 RICHLAND, WASHINGTON The ACRS Subcommittee on Metal Components met in the auditorium of Battelle Pacific Northwest Laboratory (PNL) in Richland, Washington on August 4, 1986 to review the status of the research programs being performed on (1) steam generator integrity, (2) SAFT-UT, (3) acoustic emission, (4) eddy current research, (5) tube vibration program and (6) evaluation of welded and repair-welded stainless steel for LWR service.
Notice of the meeting was published in the Federal Register on July 22, 1986(AttachmentA). 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 meeting.
E. Igne was cognizant ACRS Staff member for the meeting.
Principal Attendees ACRS ACRS Staff 7-!Ihewmon, Chairman J. Muscara D. Ward, Member S. Bush, ACRS Consultant Others C. Dodd, ORNL PNL P. Pak, DOE G. Posakony R. Kurtz W. Greenaway, NUS R. Ferris E. Bradley A. Tabatabai R. Clark, PNL Consultant R. Sorenson W. Enderlin P. Hutton S. Bruemmer 0610280508 861011 D. Atteridge A. Roberts PDR ACRS am R. Page J. Spanner PDR T. Taylor
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MINUTES / METAL COMP 0NENTS 2
August 4, 1986, Richland, WA 4
f S. Doctor, PNL, presented an overview of the NDE Reliability for Inser-vice Inspection of Light Water Reactor Program. The major objective was to quantify the reliability of present inservice inspection techniques for LWR primary system components through independent research and to establish means for obtaining improvements in the reliability of inser-vice inspectors.
Not covered at this presentation were topics on cast stainless steel, PISC III autenitic steel task design and modeling of the UT process; these were covered during the last two meetings of the ACRS Subcommittee on Metal Components.
Key regulatory issues addressed by this program are listed as follows:
o Qualification criteria for inservice ultrasonic examination o
Effectiveness and adequacy of current inspection requirements, and o
Technique evaluation and procedure development for IGSCC, weld overlay, cast stainless steel, dissimilar metal welds, for side inspection, nozzles and pressure vessels.
Some of the highlights of the program are as follows:
o Quantification of the national and international ISI perfor-mance tests has been completed, o
ASME code cases N-335 and 409-1 have been upgraded, and o
Development of codes with ASTM on search units and flaw instrument procedures are in progress.
MINUTES / METAL COMPONENTS 3
August 4, 1986, Richland, WA f
T. Taylor, PNL, briefly discussed the work being done on the mini-round robin (MRR) program. The MRR is a limited pipe inspection program dealing with intergranular stress corrosion cracking in austenitic piping.
Some human factors study, was also conducted in conjunction with the MRR program.
EPRI and Dynacon Corp. provided advanced laboratory NT systems which allowed a comparison between manual examination and currently field-ready advanced UT systems. The inspection teams jwere hired by PNL except for the advanced teams to perform the inspection.
Some preliminary conclusions of the MRR program are as listed below:
o No differences in detection capability between short and long cracks; the probability of detection as a function of crack depth was not analysed, o
Requalification results at NDE Center and MRR manual team results are consistent.
o Far side (of weld) inspection is very poor, little better than guessing, and o
A wide variation between best and worst inspectors exists.
J. Spanner, PNL, reported on the impact of human reliability on inser-vice inspection. The objectives of the program were to identify and characterize human factors aspects of UT/ISI and to collect human factors data during the MRR. He stated that significant potential for improving UT/ISI reliability exist, although insufficient data for analysis and recommendations, were obtained from the MRR program.
Four
MINUTES / METAL COMP 0NENTS 4
August 4, 1986, Richland, WA 4
performance factors i.e., training variable, procedure variable, task variable and environmental variables, should be further evaluated.
F. Simmonen, PNL, discussed the evaluation of improvement in NDE re-liability. The objective of the program is to use fracture mechanics in order to determine the impact of NDE unreliability on system safety and to determine the level of inspection required to assure a suitably low failure probability for primary system reactor components.
The conclusions reached with respect to BWR stainless piping are as follows:
o "Old" NDE procedures have provided little benefit to systems safety for IGSCC conditions, o
Current improved NDE procedures provide cost effective en-hancement in systems safety, o
Detection of growing cracks prior to leak has been adapted as a working goal for setting criteria for NDE reliabilities and ISI intervals, and o
Current improved NDE procedures are adequate for those systems with leak-before-break characteristics.
With respect to pressure vessels some conclusions of this study are as follows:
MINUTES / METAL COMPONENTS 5
August 4, 1986, Richland, WA 9
o Near surface flaws are of greatest concern for vessels (In reply to a question, it was stated that according to the code no credit is given for the cladding.),
o Prior requirements of minimum code inspections provided little safety benefit, and o
Improved near surface examinations can enhance vessel re-liability, factors of 10 to 100 reductions in calculated failure probabilities, o
State-of-the-art fracture mechanics analysis appears adequate to indicate with some degree of confidence whether a defect will lead to a break or not.
M. S. Good, PNL, discussed weld overlay repaired pipe joints. The objective of this program was to determine the reliability of ultrasonic inspection of weld overlay repaired pipe joints.
Significant con-clusions and recommendations are listed as follows:
o Shear wave examination of a weld overlaid pipe is neither effective nor reliable, o
Longitudinal wave probes provided the best results for detect-ing deep IGSCE, sizing the circumferential extent of the crack and sizing the remaining ligament of the pipe joint, o
The detection and sizing of IGSCC having an original pipe remaining ligament greater than 50 percent is not reliable, o
The detection of unacceptable fabrication flaws contained with the weld overlay has not been demonstrated to be reliable, and
MINUTES / METAL COMP 0NENTS 6
August 4, 1986, Richland, WA f
o Surface preparation (smoothing) of the weld overlay is required to perform meaningful inspections.
S. Doctor, PNL, discussed the development and validation of a real-time SAFT-UT system for inservice inspections of LWRs. This program ad-dressed the improvements in ISI reliability for detecting and sizing defects of IGSCC and for inspection of cast stainless steel. According to PNL, the SAFT technology is proving to be robust, viable and effective in the test performed at Dresden Unit 3, Vermont Yankee and at Commonwealth Edison.
This technology is proving to be equally useful for detection as it is for accurate characterization; although this technology still requires validation in a real-world environment.
Combustion Engineering is under an agreement to validate SAFT-UT.
Transfer of this technology to Sandia National Labs. has also occurred during FY 1986.
P. Hutton, PNL, discussed acoustic emission / flaw relationships for inservice monitoring for LWR's. The obiective of this program is to validate acoustic emission (AE) technology for continuous monitoring of reactor pressure boundaries to detect crack initiation and its growth.
AE has been demonstrated in the laboratory and installed and prepared to monitor Watts Bar Unit I and Peach Bottom Unit 3.
Work on ASME Section VIII AE procedure is in progress and on-reactor validation is the primary remaining step. Some benefits of AE monitoring are as follows:
o Early detection of cracking in primary pressure boundaries, i
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MINUTES / METAL COMP 0NENTS 7
August 4, 1986, Richland, WA 4
o Support leak-before-break concept through crack growth de-tection, and o
Increase operational safety through pressure boundary and/or valve leak detection R. Kurtz, PNL, discussed the steam generator group project. The regu-latory/ safety issues addressed in this program are listed below:
o Determine adequacy of NRC regulation governing frequency, extent and procedure of inservice inspections, o
Determine adequacy of NRC regulation concerning plugging of defective tubes,and o
Determine man-rem exposure for steam generator maintenance, repair and replacement.
The steam generator group project objectives are as follows:
o Develop validated data base to provide recommendation for revision of ISI Reg. Guide 1.83, o
Develop input to provide recommendations for revision of tube plugging Reg. Guide 1.121, and o
Establish performance of eddy current (EC) inspection equip-ment, procedures and training.
Phase I, Tube Integrity Tests, using tubes with simulated defects are completed.
MINUTES / METAL COMPONENTS 8
August 4, 1986, Richland, WA f
Phase II, Tube Integrity Tests, using in-service IGSCC defects are 95 percent complete, and Phase III, evaluation of retired steam generator, is 80 percent complete. A final report is due at the end of FY 1987.
Inspections of the Surry steam generators have resulted in the following observations:
Damage in the Surry steam generator tubes is mostly from o
denting, pitting and wasteage, o
Denting is the primary cause for shortened service life (6 VS.
40 years),
o Sludge at the top of the tube sheet is responsible for most prevalent defects, wastage and pitting, o
Tubes are highly stressed between the support plates due to denting induced by support plate deformation, o
No significant degradation to the tube sheet was observed, and o
Copper deposits may lead to unnecessary radiation exposure.
R. Ferris, PNL, discussed NDE of steam generators tubes. He stated that deposits of copper, magnetite and sludge have a dramatic effect on EC defect signals.
For example, tubes which are coated with copper create a condition of positive and negative defect calls. Pits which contain copper produces a very complex signal and is difficult to analyze.
It also creates a condition of positive and negative defect calls in relation to depth sizing.
MINUTES / METAL COMPONENTS 9
l August 4, 1986, Richland, WA f
He also stated that it is imperative to know the type of defect i.e.,
wastage, fretting, cracking, pitting or intergranular attack, in order to size degradations correctly.
Present bobbin coil techniques as used in ISI testing per codes cannot characterize defect signals.
Defects which lie parallel to the eddy current flow from a bobbin coil such as circumferential cracks can go undetected. Present code changes are necessary to enhance the reliability of ISI testing both in the area of acquisition and analysis.
C. Dodd, ORNL, discussed an improved eddy current inservice inspection of steam generator tubing. He stated that inspection of steam generator is a difficult, changing problem that requires our best effort. The problems did not occur overnight, nor will the solutions be available overnight. As the steam generator continue to deteriorate over the years, the problems are becoming more difficult.
The accuracy of steam generator inspections is much poorer than generally believed.
In spite of all the advances, he stated that, we are less able to inspect them now than a decade ago, and that a long term, broad-based, concentrated research program will be required to solve this very complex problem.
He than described a pulse-amplitude, three frequency instrument with probably a circumferential and pancake coil as a possible next generation ISI equipment.
W. Enderlin, PNL, reviewed the program on vibration and wear in steam generator tubes following chemical cleaning. The objectives of the program are to determine the effect of chemical cleaning on flow induced vibrations and subsequent wear rates of tubes in stean generator and to
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MINUTE',, AETAL COMP 0NENTS 10 August 4, 1986, Richland, WA e
develop recommendations regarding maximum allowable clearance for chemical cleaning of tube crevice. He stated that the regulatory question that needs to be addressed is: Will chemical cleaning of tube crevices lead to high wear rates and unacceptable levels of tube failure as a result of increased amplitude of tube vibration? A full length scale model of the steam generator tube assembly was constructed.
Results from tests indicate the following:
o Even though displacements of the tubes were increased, increased tube wear rate was not indicated, and o
No further wear testing is justified.
S. Bruemmer, PNL, discussed the evaluation of welded and repair-welded stainless steel for LWR service. The objective of this program was to develop criteria for selection of material and component fabrication welding procedures to assure adequate resistance to stress corrosion cracking. The regulatory issues should address criteria for evaluating the following:
o Sensitization-induced stress corrosion cracking resistance in welded and repair-welded piping, o
Stress corrosion cracking resistance in replacement piping, and o
Effectiveness of stress reversal techniques.
At present, no guidelines exist or are being developed, to define acceptable fabrication / welding parameters to assure cracking resistance
MINUTES / METAL COMP 0NENTS 11 August 4, 1986, Richland, WA in current or replacement weldments.
Recent work indicates that improp-er fabrication / welding procedures can promote cracking of replacement materials. The fellowing are highlights of this program.
o Weldment thermomechanical history model. This model estab-lished the relationships among pipe size, weld geometry, weld parameters and heat affected zone thermomechanical history, o
Microstructural development model. This model established relationships between thermomechanical history and impurity segregation and between thermomechanical history and deforma-tion characteristics, o
Stress corrosion cracking resistance model. This model established relationship's among sensitization, segregation, deformation and stress corrosion cracking.
o Model integration. This model will (1) enable cracking resistance of components in service to be evaluated based on material and fabrication history and (2) enable welding, repair-welding and stress modification procedures to be evaluated to ensure adequate cracking resistance of components in service.
Future Subcommittee Activities A subcommittee report should be made to the full ACRS at the next meeting, 316th.
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 Reporters, 444 N. Capitol Street, Washington, D. C. 20001(202)347-3700.
ATTACHMENi A
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s-Federal Register / Vol. 51 No.140 / Tuesday. July 22, 1986 / M ilces
. ; > -- - 46317 cn its own motion Institutes review of planning to attend this meeting are are urged to contact one of the above th2 decision within that time.
urged to contact the above named named ind'vidual one or two days Individual one or two days before the.
before the scheduled meeting to be. i.
For the Nuclear Regulatory Commission.
scheduled meeting to be advised of any advised of any changes in schedule,etc.,
Dated at Bethesda, Maryland, this 14th of changes in schedule, etc., which may which may have occurred.. a iw.n..
'b July,1986.
have occurred.
DeMy 17,1986. - '
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N Richard H. Vollmer, Dated: luly 18,1988.
y ar,aa w,u g,yga, Assistant Docuure DimctorforPmjeit' ' '
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Acting Director. Office ofNuclearReactor Morton W.UbarL1a EeSulation.
Assistant becutive Directorfor Pmject Review.
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[nt Doc.86-164s2 Filed 7-21-88;lL45 am}
[Mt Doc. 8616446 FUed 7-21-88; 855'a'm]
Review.
esiseo caos ree>4w
[FR Doc. 86-1645o Filed 7-21-46; 6 45 am]
sausa coes resem e m o coor nas-s m Advisory Committee on Reactor Advisory Committee on Reactor Safeguards; Subcommittee on Advisory Committee on Reactor Safeguarda; Subcommittee on Metal Extreme External Phenomena; Meeting Safeguards; Subcommittee on Componenta; Meeting he ACRS Subcommittee on Extreme improved LWR DesJgna; Meeting
%e ACRS Subcommittee on Metal External Phenomena wiU hold a meeting De ACRS Subcommittee on Improved Components will hold a meeting on en August 6,1986. Room 1048.1717 H LWR Designs will hold a meeting on August 4,1986, at the BatteHe Pacific Street, NW., Washington, DC.
August 5,1986, Room 1046.1717.H Northwest Laboratories (PNL), BatteUe The entire meeting will be open to Street, NW., Washington, DC.
Avenue in the Battelle Auditorium pub!Ic attendance.
The entire meeting willbe open to lobby, Richland, WA.
The agenda for the subject meeting Public attendance.
De entire meeting willbe open to shall be as follows:
Public attendance.
Wednesday, August 6,1966-o.30 a.m.
sh 11be as follo a*
The agenda for sub}ect meeting shall Unulthe Conclusion ofBusiness sd. AugusM, JWWR unul be as foHows:
The Subccmmittee will conduct a p
bionday, August 4.1996-&30 A.M. Until workshop to review the importance of De Subcommittee will discuss the the Conclusion ofBusiness ; -
I seismic risk to nuclear power plants.
StandardizaUon Policy Statement.
-%e Subcommittee will review the Seismic hazard will be the principal Oral statements may be presented by steam generator integrity program. In topic to be discussed.
members of the public with the addition, the integrated Fracture Oral statements may be presented by concurrence of the Subcommittee Mechanics / Nondestructive Examination members of the ublic with the Chairman; written statements will be and other PN1, programs will be concurrence of t e Subcommittee accepted and made available to the discussed.
Chairman; written statements will be Committee. Recordings will be permitted Oral statements may be presented by cceepted and made available to the only during those portions of the members of the public with concurrence Committee. Recordings will be permitted. meeting when a transcript is being kept, of the Subcommittee Chairman; written Cnly during those portions of the and questions may be asked only by statements will be accepted and made meeting when a transcript is being kept, members of the Subcommittee,its available to the Committee. Recordings cnd questions may be asked only by consultants, and Staff. Persons desiring will be permitted only during those members of the Subcommittee,its to make oral statements should notify Portions of the meeting when a consultants, and Staff. Persons desiring the ACRS staff member named below as transcript is being kept, and questions to make oral statements should notify far in advance as is practicable so that may be asked only by members of the l
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the ACRS staff member named below as appropriate arrangements can be made.
Subcommittee,its consultants, and Staff.
far in advance as is practicable so that During the initial portion of the Persons desiring to make oral appropriate arrangements can be made.
meeting, the Subcommittee, along with statements should notify the ACRS staff During the initial portion of the meeting the Subcommittee, along with any ofits consuhants who may be members as farin advance as any of its consultants who may be present, may exchange preliminary practicable so that appropriate views regarding matters to be present, may exchange preliminary considered during the balance of the arrangements can be made.
views regarding matters to be During the initial portion of the considered during the balance of the meeting.
meeting, the Subcommittee, along with The Subcommittee will then hear 9
The Subcommittee will then hear presentations by and hold discussions any ofits consultants who may be meeting.
d presentations by and hold discussfons with representatives of the NRC Staff, present, may exchange preliminary with representatives of the NRC Staff, its consultants, and other laterested views regarding matters to be considered during the balance of the -
n-its consultants, and other interested persons regarding this review.
Further information regarding topics meeting.
4 persons regarding this review.
to be discussed, whether the meeting ne Subcommittee willthen bear Further information regarding topics to be discussed, whether the meeting has been cancelled or rescheduled, the presentations by and hold discussions
, 'I has been cancelled or rescheduled, the Chairman's ruling on requests for the with representatives of the NRC Staff.
its consultants, and other interested.
P Chairman's ruling on requests for the opportunity to present oral statements persons regarding this review.
and the time allotted therefor can be iS opportunity to present oral statements obtained by a prepaid telephone call to Further information regarding topics and the time allotted therefor can be the cognizant ACRS staff member,Mr.
to be discussed,whether the meeting obtained by a prepaid telephone call to Herman Alderman (telephone 202/634-has been cancelled or rescheduled. the the cognizant ACRS staff member, Dr.
1413) between 8:15 A.M. and 5.00 P.M.
Chairman's ruling on requests for the Richard Sado (telephone 202/634-3267) between 8.15 A.M. and 5 00 P.M. Persons Persons planning to attend this meeting opportunity to present oral statements i
1 4
- 22. 1988 / Notice 3 Federal Register / Vol. 51, No.140 / Tuesday, July 26318 Chairman's ruling on requests for the.
He man Alderman (telephone 202/634-opportunity to present oral statements
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and the time allotted therefor can be cnd the time allotted therefor can becbtrined by a prepaid telephone call to-l 1414) between 815 A.M. and 500, Persons planning to attend this me P Mc f
the cognizant ACRS staff member,Mr.:
the cogniz:nt ACRS staff mernber.Mr.-
are urged to contact the above named -
Richard Majer (telephone 202/634-1414) -
% idio Igne (telephone 202/834-1414) d before the
! individual one or two ays ceen 8:15 A.M. and $20 P.M. Persons' scheduled meeting to be advised of any - between 8:15 A.M. and 5:00 P.M. Persons, nning to attend this meeting are changes in schedule, etc., which may planning to attend this meeting are,
urged to contact the above named urged to contact the above named have occurred.
individual one or two days before the individual one or two days before the Dated. July 16.1988, schtduled meeting to be advised of any f Morton w.Ubarum, scheduled meeting to be advised of any.
changes in schedule, etc., which may Assisent hive DirectforPmject changes in schedule, etc., which may h:ve occurred.
have occurred.
- Review, D; tid: July 17,1986,
[FR Doc. a6-16451 Filed 7-21 8e: 8:45 am)
Dated: july 17,1988. -
Morton W. U5arMn, seaseo coon rouw.ae--
Morton W.UbeAln, Assistant D ecu tive Directorfor Pmject Assistant. Evecutive DirectorforPmject A rview.
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lFR Doc. 86-16447 nled 7-Zhak ses am)
Advisory Committee on Reactor
[FR Doc. 86-16449 Filed 7-21-a0: &45 am) asumo coes rsoo.m Safeguards; Subcommittee on -
Reilability Anurance; Meeting
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He ACRS Subcommq. tee on Advisory Committee on Reactor Reliability Assurance will hold a
! Docket No.50-373 and 50-374)
Safeguards; Subcommittee on Reactor.meeting on August 5,1986, Room 1046, Commonwealth Edison Co.; La SaBe O
tions-Meeting 1717 H Street, NW., Washington. DC.
%s ACRS Subcommittee on ReactorThe entire meeting will be open to County Station, Units 1 and 2; Denial of Amendments to Facittty Operating Operztions will hold a meeting on.
public attendance.The agenda for the subject meeting Ucense and Opportunity for Heartng August 4.1988. Room 1048,1717 H Street. NW., Washington. DC.
shall be as follows:
The U.S. Nuclear Regulatory The entire meeting will be open to Tuesday, August 5,1986-&30 A.M.
Comnussion (the Commission) has e a enda0$the subject meeting Until the Conclusion of Business denied in part requests by the licensee ne Subcommittee will review the for amendments to Facility Operating final resolution of USI A-46 " Seismic Ucense Nos. NPF-11 and NPF-18, issued
. shril b2 as follows:
Monday, August 4.1968-Im P.M. until to the Commonwealth Edison Company Qualification of Equipment in Operating(licensee) for operation of the La Salle the conclusion of business Plants." ne Subcommittee will also County Station, Units 1 and 2 located in ne Subcommittee will review recent hear a briefing by the Vendor Program Branch NRC's Office of Inspection and La Salle County.11iinois.The Notice of ants at operating plants.
'rd statements may be presented by Enforcement on the status of a generic Consideration ofIssuance of Amendments was published in the
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.nbers of the public with the concurrence of the Subcommittee Oral statements may be presented by Federal Register on April 9,1986 (51 FR check valve program.
Ch:frman: written statements will be members of the public with the 12247).
concurrenceof theSubcommittee The amendments proposed by the ccc:pted and made available to theCommittee. Recordings will be permitted Chairman; licensee would change the Technical Specifications: (a) To add fire detectors accepted and made available to theCommittee. Recordings wi enly during those portions of the meeting when a transcript is being kept, cod questions may be asked only by only during those portions of the Unit 1 to demonstrate compliance with members of the Subcon mittee,its meeting when a transcript is being kept, Operating Ucense NPF-11 Ucense c:nsultants, and Staff. Pe.4ons desiring and questions may be asked only by Condition 2.C.(25)(c}: and (b) for Units 1 to mike oral statements should notify members of the Subcommittee,its and 2 to delete u.e Action Statement th2 ACRS staff member named below as consultants, and Staff. Persons desiring3.3.7.9b.The licensee's reason for this proposed item b change is that a) they fa lo advance as is practicable so that to make oral statements should notify willhave the required special fire watch cppropriate arrangements can be made.
the ACRS staff member named below as patrol at least once per hour in each During the initial portion of the far in advance as is practicable so that such area with a deficient number of fire appropriate arrangements can be made.
meeting, the Subcommittee may exchange preliminary views regarding During the initial portion of the detection instruments, and b) this m:tters to be considered during the meeting, the Subcommittee, along with change is consistent with the General.
b ltnce of the meeting.%e any of its consultants who may be Electric (CE) Standard Technical Subcommittee will then hear present, may exchange preliminary Specifications (STS). However, the views regarding matters to be presence of the required special fire presentations by and hold discussionswith representatives of the NRC Staff +
considered during the balance of the watch (3.3.7.9a) does not address the requh'ement for returning instruments to tnd other interested persons regarding meeting.
%e Subcommittee will then bear operable status or submitting a Special this review, Further Information regarding topics presentations by and hold discussionsReport to describe the actions taken to with representatives of the NRC Staff, restore the operability, the cause of the to be discussed, whether the meeting and plans and schedule h:s been cancelled or rescheduled the its consultants, and other interested Inoperability,he instruments status if Chairman's ruling on requests for the persons regarding this review.Further information regarding topics instruments are not operable after 14 for restoring t cpportunity to present oral statements -
cnd the time allotted therefor can be to be discussed. whether the meeting days. In addition. the proposed change cbtained by s'pfepaid telephone call to has been cancelled or rescheduled, the Ae cx>gnizant ACRS staff rnember, Mr.
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Agenda
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for METAL COMPONENTS ACRS SUBCOM4ITTEE MEETING sa AUGUST 4, 1986 BATTELLE AUDITORIUM LOBBY (0 pen Meetings) 8:00 NDE Reliability Nrr $b SR Doctor I i<g n I
"4 40:45 irlo " SAFT (Discussion)
SR Doctor 11:15 Acoustic Emission PH Hutton 12:00 m.30 Lunch Break 1:00 Facilities Tours (Tours Closed to General Public),
SAFT System SR Doctor a
e Steam Generator RJ Kurtz RETURN TO BATTELLE AUDITORIUM LOBBY (0 pen Meetings)
/
~3TOO' 9 D Steam Generator RJ Kurtz 5:15 Break - with refreshments l'A.gEddy Current Research CD [oerris M0 g
s.ng L'.\\S Tube Vibration Program WI Enderlin l
-enT'MM Welding Program SM Bruemmer 4t45 Jter4als -Integration-Center JTA Rchert:
-7:30 T.D 5 Wrap up l
ATTACHMENT C LIST OF HAND 0UT MATERIALS August 4, 1986, Presented to Metal Components ACRS Subcommittee Meeting at Battelle, Pacific Northwest Laboratories, Richland, Washington 1.
Program Review - Acoustic Emission / Flaw Relationships for Inservice Monitoring of LWRs 2.
Program Review - Development and Validation of a Real-Time SAFT-UT System for Inservice Inspection of LWRs 3.
Program Review - Evaluation and Improvement in NDE Reliability for Inservice Inspection of Light Water Reactors 4.
Steam Generator Group Project 5.
Task 9 and 13 Evaluation of NDE - R. Ferris 6.
Improved Eddy-Current In-Service Inspection of Steam Generator Tubing - Cass V. Dodd, Oak Ridge National Lab. Oak Ridge, Tennessee
- ORNL 7.
Vibration and Wear in Steam Generator Tubes Following Chemical Cleaning 8.
Evaluation of Welded and Repair-Welded Stainless Steel for LWR Service l
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