ML20027C905
| ML20027C905 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/11/1982 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-1999, NUDOCS 8210270410 | |
| Download: ML20027C905 (9) | |
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ACRS SUBCOMMITTEE ON METAL COMPONENTS h g ll i h LE JUNE 7, 1982 CERTIFIED COPY PALO ALTO, CA ISSUED: AUGUST 11, 1982 t
The ACRS Subcommittee on Metal Components met at the Conference Center at Electric Power Research Institute (EPRI), Palo Alto, California on Jure 7,1982, to review the status of the Steam Generator Owners Group (SG0G) program and the TM1-1 steam generator problems and possible modifications.
In addition, the NRC presented a status of steam generator generic reccmmendations based on the Ginna event.
The results of current research programs on steam generators were also discussed.
The meeting was open to the public. There were no written or oral statements received or presented at the meeting. The Federal Register meeting notice, the attendee list and the meeting schedule are shown in Attachments 1, 2 and 3.
respectively.
A set of handouts are on file in the ACRS office.
E. Igne was the Designated Federal Employee.
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Mr. Shewmon, Chairman of the Subcommittee, in his opening remarks stated that there is a lot of discussion within the ACRS about whether degraded steam generator tubes are a safety issue.
Inspections and repairing of steam generators constitute a major source of radiation exposure to workers, and that is a cause of concern.
l P. Santoro, Director of Generation Projects at Northeast Utilities, made a brief pre-sentation on the SG0G organization, budget and programs.
He stated that the SG0G, a utility organization, was formed in 1977 primarily to determine the causes of denting and to provide fixes to this problem.
Since then the program has expanded to include steam generator problems in general.
The SG0G agreed to share the cost of the five-year program with EPRI. EPRI's Steam Generator Program Office (SGPO) was also established in 1977.
The SG0G has committed $38 million through 1982.
EPRI has contributed $16 million. Membership of the SG0G consists 0210270410 820811 PDR ACRS 1999 PDR
METAL COMPONENTS 2
of 23 utilities representing 26 of 47 U.S. operating PWR units.
Four foreign utilities are members of the SG0G.
VEPCO, owner of the first replaced steam generator, does not belong to the SG0G.
A few A/Es belong to the SG0G.
The SGP0 provides the technical capability and program administration of the SG0G.
Some of the SG0G programs are performed by the PWR NSSS vendors.
The SGP0 is directed by S. Green.
The project consists of three main groups:
Chemistry and Materials; Chemical Cleaning, Secondary Systems, and Nondestructive Examination; and Thermal Hydraulic, Structural and Safety.
The development and use of the strain gage profilometer, multifrequency eddy current, and optical profilometer techniques have increased the effectiveness of NDE in characterizing tube flaws and degradation.
Causes of tube denting have been identified from laboratory and plant data.
Preventive and corrective actions are also known.
Causes are ingress of impurities, primarily chlorides and oxygen.
Prevention of tube denting results from controlled feedwater chemistry.
The SG0G has issued secondary water chemistry guidelines to members, in which t
methods are described to achieve feedwater quality.
Utilities are now incorporating the guidelines, which have arrested denting in a couple i
of plants.
Laboratory and plant data support the use of neutralizers (Ca(OH)2 and H (B0 ) to arrest denting.
No undesirable side effects of neutralizer 3
3 additions have been found in model boiler tests.
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METAL COMPONENTS 3
W Mr. Santoro stated that, based on the ongoing work by the SGGG, Millstone-3 has rejected a pre-heater design (Model D) steam generator from Westinghouse because of possible tube wear in the pre-heater section caused by tubes impacting against the tube support plate forced by flow-induced vibration.
Intergranular attack of tubes in the tube-sheet region has been slowed by a combination of reduced primary temperature and tube-sheet crevice flushing by depressurization.
Improved tube-support plate designs which do not concentrate impurities are now in use. Materials for tube-support structures have been changed from carbon steel to ferrite stainless steel which is more resistant to denting.
S. Green, of EPRI, stated in his presentation that, in general, the impact of denting has decreased and the effect of other steam generator problems has not l
l been as severe.
l The utility industry is organizing to continue the steam generator work.
An organizational meeting was held in January 1982, with 41 utilities in attendance.
An initial industry poll indicates that 27 indicated an intention to participate; 11 probably would participate; 2, unlikely; and 1 said no.
Tentative cost of the program would be about $22-27 million for 1983-1986.
The SG0G has initiated work on the problem of vibration-induced tube wear which has occurred at support intersections in preheaters of new steam generators in one U. S. and two foreign units.
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METAL COMPONENTS 4
R. Wilson, Vice President of Technical Functions, GPU Nuclear, presented a TMI-1 steam generator status report.
Extensive stress corrosion cracking (SCC), with initiation on the ID surface of the tube, has been found.
The SCC is heavily concentrated in the top of the upper tube sheet.
It was probably caused by thiosulfate contamination of the primary coolant and air.
An extensive effort to determine the causes of SCC has been underway.
GPU plans to repair all the steam generator tubes, by expanding the tube if the SCC location is within the tube-sheet region, or by plugging if the SCC is located below the tube sheet.
GPU plans to restart by November 1982.
They would like to discuss this matter again with the ACRS before restart.
P. Shewmon suggested that perhaps the full ACRS should hear this matter when the NRC Staff has l
l reviewed it and formulated a position.
G. Lainas, NRC, presented a report on the status of the generic recom-mendations based on the Ginna event.
The Staff is developing a position which will cover steam generator integrity, plant response, human factors considerations, radiologic consequences, and organizational response to a l
sudden tube failure.
This position will incorporate recommendations from the USI A-3, A-4 and A-5 effort.
The report will be reviewed by CRGR, ACRS and the Commission by mid-or late summer.
J. Muscara, NRC, presented the results of current research programs related to steam generators.
Areas covered were improved eddy current inspection techniques, and development of predictive models for SCC.
Results of the investigation of the removed Surry steam generator were also discussed.
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METAL COMP 0NENTS 5
P. Shewmon stated at the conclusion of the meeting that he will present a Sub-committee report at the next Full ACRS Meeting in July 1982.
I NOTE:
For additional details, a complete transcript of the meeting is available in the NRC Public Document Room,1717 H St. NW, Washington, D.C. 20555 or from Alderson Reporters, 300 Seventh St.,SW, Washington, D.C.
(202) 554-2345.
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Federal Register / Vol. 47, No. 90 / Friday, May 22.1982 L Notices 22265.
h.i erIcbal agendes may obtain theas September 30,1981 (48 FR 47903). o/al or SECURmES AND EXCHANGE '
h
.i? 'cuments'upon request).
written statements may be presented by COMMISSJON
- Comments by Federal. State and local members of the public, recordings will efficials or other members of the pub!!c be pemitted only during those portions. (Release No.18744;(SR-NSCC 42-5)1 received by the Commission wC) be of the meeting when a transcript is being made evallable for pub!!c inspection at ktpt, and questions may be asked only Nationel Securttlee Clearing the Commission's Public Document by members of the Sobmmmittes ks.
Corporation ("NSCC"); Order Room in Washington. D.C. and the co,,sultants, and StaH. Pesons desiring ' APprovbg Proposed Rule Change Eneter Public IJbrary. Comments are to make oral statements abould motify May 171se2.
Se es gnated Fednal Employw as far On March 28,1982.NSCC filed with f e nt sub ed on DES.
in advance as practicable so that
& Comissin pursund k sec6on the Commission's staff wil! prepare a appropriate anangements can be made 19(b)(1)of the Securities F.xchange Act Final Environmental Statement, the tdaUow the necessary time during the
. f 1934.15 USC. 7&s{b)(1). She "Act")
evallability of which wD1be published o
meeting for such statementa.
and Rule 19b-4 thereunder, a proposed l
In the Federal Resister.
Comments on the Drah Environmental ne entire meeting wiU be open to the rule change that amends NSCCa cuerent Statement from interested members of Public attendance except for those rules concerning admisalon.
the public should be addressed to the sessions during which the Subcommittee participants, and issues of securities.
U.S. Nudea(Regulatory Commission.
Ands it necepary to discusa proprietary and specites standards and promdarea Washington. D.C. 20555. Attention: -
infomstion and industrial security. One under those rules.More specificaDy *.
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, Director. Division of IJcensing.
or more dosed sessions may be -
these rules and the standards and necessary to discuss such information.
procedures thereunder indude (1)
Deted at Bethesda. Mary!and, this 14th day l
' of May tea 2.
(Sunshine Act Exemption 4.)To the mintmnm Enandal and operational
.For the Nucear Regu! story Commlesloc.
extent practicabic, these closed session.s standards for applicants to, and l
will be held so as to minimize participants in. NSCC; (ii) guidelines for Frank J. Miraglia.
CNef Ucwing Smrd h1Diviaam of inconvenience to memhers of the public requiring applicants and participants ucensh;g in attendance.
that do not meet those minimum gra pw. es-wuo md wwt use==4 He agenda for subject meeting abaB standards to provide NSCC with
, saum coce rusoms be as foUows:Mondoy, June 7,1982-specified further assurances: and (Hi)
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8:30 c.in. untilthe conclusion of guidelinea for monitoring securities hu8m888-
!ssues that NSCC believes are volatile
[ W No.50-334)
During the initial portion of the or otherwise present greater than bquesne Ught Co., et af. (Besvor meeting, the Subcommittee along with normal financial risk to NSCC and its
]h-h!!ey Power Station,IJrdt No.1);
any of its consultants who may be participants. NSCC made minor editorial
{ Exemption present, will exchange prehminary changes to the proposalin a letter dated
. N views regarding matters to be May 14,1982.
considered during the balance of the Notice of the proposed rule change.
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- In FR Doc. 82-12783 appearing on meeting.
together with the tenns of substance of g
c't Further infomation regarding topics the proposed rule change,was given by C
$1.1 ms e the fo o g cor publicat on of a ammins on Release r
to be discussed. whether the meeting I
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has been cance!!ed or rescheduled, the (Securities Exchange Act Release No.
h co p! e pa th li e F
"will relieve" should have read "will not Chaiman's ruling on requests for the 18619. April 5.1982) and by publication 8
opportunity to present oral statements
- in the Federal Register (47 FR 15471.
d relieve-q
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and the time allotted therefor can be April 9.1982). No letters of commeni obtained by a prepaid telephone cab to were received by the Commission.
l the cognizant Designated Federal De Commission finds that the
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Advisory' Committee on Reactor %_.. Employee. Mr. Elpidio Igne (tplephone proposed rule change is consistent with
. Safeguards, Subcommittee on MetalJ 202/634-1414) between 8:15 a.m. and the requirements of the Act and the C
3 500 p.m, DST..
rules and regulations theretmder k* Components; Meeting g' 'e on Metal De ACRS Subiommitte I have determined,in accordance with applicable to registered desring Components will hold a meeting on June Subsection 10(d) of the Federal agencies. and in particular, the 7.1982 at EPRI(Elecide Power Advisory Committee Act, that it may be requirement: of Section 17A of the Act.
i Research Institute). 3412 HiUview necesssary to close some portions of It is therefore ordered. pursuant to 3
Avenue. Palo Alto, CA in the this meeting to protect proprietary Section19(b)(2)of the Act that the,
Information and industrial secudty.De proposed rule change be, and it hereby
] Conference Center behind Building No.
A 1.De Subcorhmittee will review the authority for such dosure is Exemption is, approved.
status of the steam generstor problems (4) to the Sunshine Act. 5 U.S.C.
For the Comm!ssion.by the Didston of 3( end its probable resolutions with the 552b(c)(4).
a uthority*
Madet Re'gdetion. pursuant to delegated 2 Steam Generators Owners Croup and Dated. May ta. tos2.
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Industry.In addition.the Subcommities, J ha C.Hoyla.
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Cooge A.F1tuimmons.
wiU review the dim steam generator A drh ory Committee Stanchement Offiar.
Secretary.
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'IEhTATIVE SCHEDULE METAL C04PONENTS StBC01MITIEE MEETING JUNE 7, 1982 (EPRI Conference Room)
PAID ALTO, CA I. Olairman's Opening Statement 8:30 - 8:45 P. G. Shewmon II. Steam Generator Owners Group (SGOG) Presentation Introduction and Organization 8:45 - 9:00 D. Noble or representative EPRI's Presentation 9:00 - 11:00 S. Green, Project Manager (includes a 15-min. break)
- Elements of Program, chemical & mechanical
- Results of Program
- Implementation
- Summary and Conclusion III. NRC Presentatiori
- Status of NRR actions relative to generic recom-11:00 - 12:00 mendation. Ref. Ginna Steam Generator Event G. Iainas LUNCH
- Steam Generator Research Programs; results, 1:00 - 2:00 schedule, etc.
C. Serpan/J. Muscara IV. GPU Briefing to ACRS Subcommittee on Status of 2:00 - 4:15
'IMI-l Steam Generator (includes a 15-min. break)
M. J. Graham, etc.
- Introduction
- Steam Generator Degradation Failure mechanism, causes
- Possible Repair or fixes
- Lessons learned V. Other Matters
- Steam generator industry /NRC/ACRS Task Force 4:15 - 4:45 VI. Executive Session (open) 4:45 - 5:00 and Adjournment ATTACHi4ENT 3
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