ML19323H958
| ML19323H958 | |
| Person / Time | |
|---|---|
| Issue date: | 03/21/1980 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-1712, NUDOCS 8006170346 | |
| Download: ML19323H958 (21) | |
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l MINUTES OF THE ACRS SUBCOMMITTEE MEETING ON METAL COMPONENTS WASHINGTON, DC i
l The ACRS Subcomittee on Metal Components met at 11:30 a.m. in Room 1046, to discuss the status 1717 H St., NW, Washington, DC on January 23 and 24,1980 of the steam generator p,oblems with the Steam Generator Owners Group (SG0G) r and the unresolved safety issues concerning pressure vessels, BWR nozzle Also heard at this meet-cracking, and component supports by the NRC Staff.
ing was the problem on Westinghouse low-pressure turbine disc cracking.
There were no written statements or requests for time to make oral statements from any members of the public.
P. G. Shewmon, presiding, The ACRS members present at the meeting were:
M. Bender and H. Etherington. The consultants were:
H. Corten, R. Dillon, and it. Wechsler.
E. G. Igne was the Designated Federal Employee.
Handouts received at the meeting are are attached to the Office Copy of the Minutes.
MEETING OF JANUARY 23, 1980 Mr. 0.Batum, Chaiman of the Steam Generator Owners Group Mr. O. Batum stated in his introduction that (1) the problems associated with steam generators are of primary concern of the utilities because of economic reasons, (2) the utilities have bonded together and fomed a group to share experiences and coordinate a program to resolve the problem expeditiously and efficiently, and (3) there 1s no guarantee that the steam generator degradation will not continue to occur 1n the future.
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Group came into being in 1977, when the utilities The Steam Generator Owners recognized"the importance of the steam generator problems and the needed resea Mr. Batum stated that additional and investigation to cope with the problems.
efforts by the NRC, NSSS, DOE, and EPRI are involved with the resolution of At present, three foreign utilities, Japan, France, and Sweden this problem.
have shown their intent to join the SGOG.
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a' 1/23&24/80 ME'TAL COMP 0No...s EPRI and the SGOG are intertwined in an organization which receives funds EPRI is the program manager, and S. Green from each for one common program.
is the director of the Steam Generator Project Office. At the present time, 17 out of 28 utilities representing operating PWRs are members of the SGOG.
All This number represents 28 out of the 44 units presently in operating.
types of steam generators are represented by the SGOG.
The total funding for research and development is about 52 million dollars; the SGOG portion is 36 million dollars and EPRI's share is 16 million dollars.
This funding expires in 1982. The program will address wastage, denting, High pitting, cracking, erosion, cnd corrosion of steam generator tubes.
cycle fatigue cracking as experienced in B&W-type steam generators will also Jn addition, the problem of improving the carryover design of be addressed.
the steam generator will be studied.
Mr. Batum stated that when all the data from the program are in hand a report recommending modifications, changes in operating specification or redesign of equipment, will be issued to be ultimately incorporated by the effected utili-ties. 'The utilities will not be bound by the recommendations, unless mandated by the NRC.
Mr. Hundis, EPRI Mr. Mundis of EPRI described the Nondestructive Examination (NDE) program of the SG0G. The objectives of the program are:
(1) to identify the precursors of the damage, (2) to find defects that occur in the support plate or the tubes of the steam generators. (3) to determine the effectiveness of possible cor-rIctive measures in a nondestructive way, and (4) to minimize the radiation exposure during NDE.
Flaws in tubes are currently being detected by the following methods or techniques:
Optical Scanner St, rain Gauge Mul'ti-frequency Eddy Current Probe Fiber Optic G
METAL COMPONENTS 1/23&24/80 Flaws in the support plates are detected by the following:
Radiography Magnetic Flux Leakage Fiber Optics Various methods were discussed to detect support plate crevice and tube-to-tube i
support plate crevice blocakge.
Mr. R. Zong, Philadelphia Electric Corporation Mr. Zong discussed the NDE Center that EPRI is having built in North Carolina.
The main objective of the Center is to transfer new development in NDE from the laboratory to the field. At present, there is no organization in the United States t, hat does this. This includes using new equipment in the field and in the training of the people to use this equipment.
The Center will be operated by J.A. Jones Applied Research Company under the direction of T. Nemzek.
The Center will provide the utility industry a dedicated NDE Center.
Mr. S. Green, EPRI Mr. Green is the Director of the Steam Generator Project Office at EPRI.
Mr. Green discussed the chemistry and materials aspect of the program. He stated that the problems and solutions represent a very complex interaction among the various disciplines of chemistry, materials, and thermal hydraulics.
The planned product by the end of 1982 is to provide information in technology to utilities so that each can take actions best suited to their individual Plant to minimize steam generator degradation due to corrosion over the life of the plant.
Mr. Green reviewed the status as of January 1980. He stated that the reasons for corrosion occurring in the steam generator tubes, mainly tube denting and corrosion in tubesheet crevices are understood reasonably well. The effects of impurities and steam generator parameters on tube degradation is understood qualitatively. No quantitative data exist to justify corrective actions for improving feedwater purity.,At the present, they can only state that minimizing the impurity ingress helps, but the ' optimum level is not known, but data exist
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METAL COMPONENTS 1/23&24/80 indicating that a neutralizer, namely boric acid..has shown promise in slowing down tube denting.
The program in chemistry and materials are divided as follows:
Effect of plant design and operation on water chemistry of the steam generator.'
Causes of denting and corrosion.
Measures being considered for minimizing corrosion and denting.
New materials and design.
EPRI has visited Japan to gain information in their program in plant operation and chemistry control. The Japanese do not have as much problem with their steam generators as the U.S.
Mr. Green stated that the Japanese experience is factored into the program.
Mr. J. Lang, EPRI Mr. Lang presented t.
aptc of thermal, hydraulics, and structural aspects of the steam generator problem. The status of the problem thus far is as follows:
Tests at prototypical pressures and temperatures have determined that dryout occurs in the drilled holes in the support plates where the tubes touch the drilled holes. A similar' phenomenon is observed in the quatrefoil land design. ' Chemical deposits in the dried out area were found.
Similar tests in prototypical pressures and temperatures have shown that dryout occurs within a half an inch below the top of the sludge pile; corresponding to observed wastage damage.
Present thermal / hydraulic computer codes can predict average conditions in steam generators. More work is required in pre-dicting local phenomena.
Structural studies reveal stresses to be within code allowables.
The utilities then discussed some of the improvements done on the secondary side of the plants.
Mr. L. Lewis, Duke Power Company Highlights of Mr. Lewis' presentation are as follows:
_ The Oconee Station is a B&W, PWR design, with a once-through steam generator.
The plant has always been on-AVT chamistry.
METAL COMPONENTS 1/23&24/80 No copper or copper alloys are used in the system.
Tube degradation is caused by low stress, high cycle fatigue, and erosion.
Feedwater purity was increased by using condensate polishing system.
The forcing function for tube vibration was reduced by i
stopping the daily turbine control valve testing at 96%
power.
Erosion of the steam generator tube is caused by impinge-ment of magnetite pieces on the tube. More study of this phenomenon is being performed by EPRI as part of the SG0G program.
Doses due to steam generator inspection have been showing a downward trend as more experience is gained.
Mr. A. Curtis, Rochester Gas and Electric Company Highlights of M'r. Curtis' presentation are as follows:
The Ginna plant operates _on the shore of Lake Ontario.
RG&E was instrumental in developing multi-frequency Eddy current probe testing in this country.
Significant radiation exposure reduction is obtained by training the maintentance personnel on mock-ups.
Use of multi-frequency testing reduces inspection time by 60%.
AVT chemistry with full flow condensate polishing system is used.
Oxygen ingress is reduced by recycling coolant through con-densate polishing system at stattup.
No change in tube denting and little wastage have beer, observed.
Only about 2-3% of the tubes are plugged after 10 years of operation.
Mr. G. Slifer, Public Service Electric & Gas Company Highlights of Mr. Slifer's presentation are as follows:
To date no primary to secondary. leakage has occurred Condenser inleakage caused Salem to retube with AL6) material.
Cathodic protection has been upgraded by installing additional electrodes and rectifiers on each of the circulating water systems.
Full flow condensate polishing system has been installed.
Salem equipment meets Westinghouse water chemistry specifications.
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METAL COMPONENTS 1/23&24/80 Mr. J. Strosnider, NRC Staff Mr. Strosnider addressed the following three areas.
1.
Problem description including the review of the degradation mechanisms, summary of affected units and a discussion on the safety significance of the degradation that has occurred.
2.
Problem resolution including the status of programs involved and also the potential changes in regulatory requirements.
3.
Expectations from future steam generators that will be coming into service.
Problems in steam generators are wastage, caustic stress corrosion, denting, and intergranular attack which occurred at Point Beach within the tubesheet crevice.
For a tube failure which occurs not concurrent with the MSLB or LOCA, the conclusion is that there is no anomalous or unacceptable system behaviors, no unacceptable offsite doses and only minor procedural and/or training improvements will be identified.
For a tube failure and LOCA there is a potential for steam binding and for the MSLB a potential offsite exposure. These conditions are being addressed by a Task Action Plan. A report by the Reactor Safety Branch should be published in a month or so.
Task Action Plans A-3, -4, and -5 have been rewritten into one write-up.
The Plan includes system analysis of transients and postulated accidents, evaluation of ISI, ISI cost-benefit analysis, and evaluation of steam generator tube integrity.
Steam binding might be a significant problem if leakage rate from the secondary to the primary system is about 1500 gpm concurrrent with a LOCA. About ten
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complete tube failures will give about 1500 gpm leakage.
A discussion on the monitoring program ensued. The committee's concern was the evaluation of the monitoring infonnation that is being submitted by the utilities. Is it going to be compared to the manufacturing specifications?
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e METAL COMPONENTS 1/23&24/80 Will the data provide failure trend for any given set of plant performance and chemistry? Are we going to learn something from it, without being arbitrary and capricious? Will statistical analysis be performed?
It was stated by the committee that the Plan is a good one. tut the schedule for completion should be realistic. It was found during ne discussion that the Plan deals with the p,roblem of tubes having a high rate of failure, and does not resolve the generic problem by itself. Tube failures wit.1 continue in the future but it is hoped that the failure rate will decrease significantly.
That should be the goal of the Plan.
The Task Action Plan should be completed by May,1980..
Mr. R. Emch, NRC Environmental Evaluation Branch Mr. Emch discussed ALARA as applied to steam generators. The ALARA concept is set forth in 10 CFR Part 20. ALARA means that your dose should be as low and reasonably achievably (ALARA) taking into account cost and socio-economic benefits. For example, steam generator tube inspection and plugging should be weighed against exposure and benefits.
Mr. Emch then discussed steam generator tube inspection and the doses received at various plants. He stated that the limit of 5 man-rems per' year is safe and is used for both inside and outside the plant.
The meeting was adjourned at 5:36 p.m.
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0 METAL COMPONENTS 1/23&24/80 MEETING OF JANUARY 24, 1980 Mr. W. Hazelton, NRC Staff Mr. Hazelton, as a spokesman for the Staff, presented an introduction of the status of the unresolved generic item on the integrity of the reactor pressure vessel. The developments in this area are being performed by various industry groups; vendors, and the HSST program.
Mr. K. Hoge, NRC Staff Mr. Hoge discussed the subject relating to tne low upper shelf life of pressure vessel materials in a program called Integrated Surveillance Program. Mr. Hoge stated that the purpose of the program is to ensure that a wide safety margin against failure during normal cperation exist.
In addition, these margins should be large enough to ensure vessel integrity during transient and accident conditions and to provide the flexibility of operation during emergency opera-tio n. Mr. Hoga then presented a~ brief history in pressure vessel evaluation and regulatory requirements.
The results of the Staff's Systematic Evaluation Program on the Integrity of the Pressure Vessel is documented in NUREG-0569, dated December,1979.
The lower upper shelf energy problem may affect about 21 reactor vessels by the end of its life. The regulation requires that if the energy value is less than 50 ft-lbs, (1) augmented inservice inspection of the reactor vessel beltline area be instituted, (2) additional fracture toughness informa-tion be acquired, and (3) fracture mechanics analysis be performed to deter-mine that sufficient safety margin exists.
The original 50 f t-lb energy limit first appeared in the Appendix G 1971 ver-One reason this value was chosen was that the Staff felt that if they sion.
values (about 150,000 psi-1Rn) had 50 ft-1bs they had good correlation with Kg which would provide adequate toughness for normal operating conditions and that calculation indicates that the pressure vessel will leak before break.
Another reason was that a good quality vessel material should have about 50 ft-lb energy. Yankee Rowe pressure vessel had a start-of-life Charpy L _.
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- 1/23&24/80 METAL COMPONENTS Energy of 55 ft-lbs. It is now at a level of 50 ft-lbs and projected
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to 42 ft-lb at the end-of-life. The Yankee Rowe pressure vessel material is 302-B.
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Saturation effect will tend to extend the life of some vessels.
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Mr. Hoge stated that linear elastic fracture mechanic (LEFM) is not suf-ficient to deal with the low upper shelf problem. An elastic-plastic type i
analysis, ifr. Hoge stated, should provide an approach to the low upper shelf energy.
This Mr. Hoge next discussed the B&W integrated surveillance program.
concern arose because the ca;eule holder on B&W plants failed by fatigue.
Because of di'ficulties in replacing these capsule in their original vessels, it was proposer that these capsule be placed instead in reactors not yet on line, or in host reactors. There are three host reactors. Calculations have shown that all of these vessels will be exposed to very similar fluence and neutron spectrums, both in the capsule location and vessel walls.
The Staff concurs with the evaluation and have issued a safety evaluation report.
Mr. Hoge next discussed the B&W atypical weld problem.
In this concern the silicon content was higher than normal and the nickel content lower than normal in the weld material. Even with lower Charpy Energy values, the stresses in the region of the atypical welds are low as to cause no Residual stresses according to the Staff pose no problems. To concern.
be conservative the Staff has requested that utilities with the affected 6 typic 61 nelds te spa ai.e with pressure-temperature limits that reflect
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a conservative approach using 120 for the RTNDT-l Mr. Hoge next discussed pressure vessel fluence. He mentioned that GE fluence calculations were low by factors of 6 or 8.
GE has now recal-culated the fluence based on new computer codes. The new calculations now correlate with the surveillance specimen pulled-from the operating plants. Combustion Engineering (CE) also had problems with their one dimensional code. The Staff has stated that only Ft. Calhoun is affected
' by the.CE error. No reasons were given for this discrepancy. All pressure
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1/24&24/80 METAL COMPONENTS vessels have surveillance capsules that can be removed and checked for dosimetry.
Mr. Hoge next di: cussed the evaluation of the integrity of the SEP vessels as reported in NUREG-0569. In conclusion, Mr. Hoge stated that:
(1) all the pressure vessels were acceptable, and (2) tne vessels designed according to ASME Section I and Section VIII are approximately equal to those designed by Section III. The material surveillance program of all the vessels was found to be acceptable although in all cases it did not meet' Appendix H l
requirements.
j The Subcommittee deferred until a later date a discussion on the philosophy and practices o.f in-service inspections of pressure vessels. Also deferred was the topic of acoustic emission methodologies. Both of these topics will be covered at a later meeting on ISI.
i Mr. R. Johnson, NRC Staff
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Mr. Johnson discussed Task Action Plan A-11, Reactor Vessel Material Toughness.
Strong contributors to embrittlement sensitivity are:
(1) relatively high levels of residual elements such as copper and phosphorous, and (2) factors in weld parameters such as weld heat input and flux composition.
Some beltline welds exhibit low values of absorbed energy at the Charpy upper shelf temperatures. With neutron radiation these marginal welds could fall to energies less than the 50 ft-lb level required by 10 CFR 50. Should this happen, the licensee is offered at least three options. They are:
(1) show by calculation that the steel has enough toughness to maintain an adequate safety margin, (2) anneal the vessel to restore toughness, or (3) perform a 100% volumetric nondestructive tospection to shw the largest flaw present is too small to initiate failure.
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METAL COMPONENTS 1/23824/80 Current linear-elastic fracture mechanics (LEFM) techniques are inadequate to predict the behavior for a steel with 50 ft-lb energy levels because the assume crack plastic deformation violates the LEFM boundary conditions.
Therefore NRC sponsored work on elastic-plastic fracture mechanics (EPFM).
The goal is to provide the analytic basis for a more meaningful assessment of the safety margin in p.ressure vessels at operating temperatures. This work has lead to some fav'orable results. This work is detailed in NUREG-0311, dated August 1977. The approach uses the J-Ingetral method developed by Rice of Piown University and Hutchinson of Harvard. Their method'may be used to reduce fracture experiment data and provide fracture resistance curves commonly known as J-R curves.
Subtask of A-11. are listed below:
Identify and measure the mechanical properties which control tearing and stability type of failures.
Develop a method for analyzing structural members that incor-porates postulated flaws under conditions which could lead to tearing and stabilizing fractures.
Define reactor vessel safety criteria to avoid failure.
Evaluate the feasibility of in-place reactor vessel annealing to regain toughness.
Evaluate actions which might lessen the severity of actual neutron radiation damage or improve accuracy of calculation of such damage.
Establish a computer information system for storage and retrieval of reactor pressure vessel material data.
Problems concerning the use of the J-Integral methodology was explored by j
the Subcommittee. One of the main concern was obtaining data from older vessels so that the J-Integral method can be used. The Staff stated that they will use similar material, i.e., chemistry and fabrication process to obtain the material characteristics need to use the J-Integral approach.
Other fracture mechanic specimen like the WOL specimen can be used to characterize the material. Another problem was the use of new technology in solving problems today with no " aging" experience to determine the validity of the method.
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METAL COMPONENTS 1/23&24/80 Yankee Rowe pressure vessel has according to the Staff low upper shelf life. The logic for accepting the adequacy of this vessel without material properties from this vessel was difficult to understand.
Mr. Johnson stated that at a meeting of the Committee on Safety of Nuclear Installations, the folloding conclusions were reached:
(1) a single parameter can adequately characterize the crack instability conditions and crack extensions, (2) the J-Integral is the most general parameter for that purpose, and (3)
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recognized that the J-Integral could be related to crack opening displace-ment and other fracture parameters. The...eeting transcript as well as other information in this area, will be available in NUREG reports.
The Task Action Plan A-11 will be completed by the end of December 1980.
Mr. Johnson next covered the subject of thermal shock on pressure vessels.
This area has been renamed.
It is now called faulted condition evaluation.
He stated that if a crack of sufficient length is present in the vessel a thermal shock as a result of injecting cold water into the vessel could propagate the crack. Presupposing that a crack is present, analysis leads to the following conclusions:
Total stresses under thermal shock can cause crack extension.
Relatively small cracks are more likely to grow because stresses are higher near the inside surface.
Crack growth would arrest within the wall thickness.
Mr. R. Snaider, NRC Staff Mr. Snaider addressed the generic activ'ity on'BWR feedwater nozzles and control rod drive nozzle cracking. Both of these problems were caused by high cycle thermal fatigue by fluctuating water flow.
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METAL C0!iPONENTS 1/23&24/80 General Elect'ric has redesigned the feedwater nozzle configuration so that the thermal fluctuation caused by water flow is minimized. Modifications are being made in some plants. Resolution of this generic item is scheduled for the end of 1985.
In the control rod drive, nozzle cracking problem thermal fatigue is the probable cause. A fix for this problem has been approved by the Staff and will be implemented by December 31, 1981.
In a brief open caucus, the Subcommittee was concerned about:
(1) low upper shelf energy of some pressure vessels, and (2) the resolution of generic items. Concerning the first item, the Subcommittee decided to meet again after the documents on this matter have been studied. Concerning the latter item, the Subcommittee will discuss tne criteria for the resolu; tion of the generic matters during a full ACRS meeting.
Concerning Task Action Plan A-10, the Subcommittee would like J. Ebersole to study the proposed fix to determine if it is acceptable.
. r. Snaider next covered Task Action Plan A-12 concerning the problem on steam generator and reactor coolant pump supports. The question on these supports hinges on the potential for low fracture toughness caused by lamellar tearing. This problem was discovered in 1975 and 1976. This case was resolved by heating the supports to a level where this phenomenon does not occur.
After inspection of other plants, it was viewed by the Staff to be a generic The material problem because similar materials were uted in the supports.
that is susceptible to lamel _lar tearing is maraging steel of 300-350 ksi yield strength. The result of the Staff's review indicates that Six plants are satisfactory, eleven plants may need further review, and twenty-one plants require in-depth plant specific review.
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METAL COMPONENTS 1/23&24/80 The acceptance criteris is documented in NUREG-0577. The licensee is cur-rently reviewing the affected plants.
Mr. Snaider next discussed the radiation effects on the reactor vessel supports.
The problem here is the effect of low energy or less than 1 Mev neutron radia-tion on the support materials and the resulting NDT shift. The problem was brought out on North Anna by VEPC0 in discussing the effect of the impact of low energy neutron on the neutron shield tank. Damage potential to the support by analysis performed by NRL indicates a definite possibility of excessive NDT shift for the particular material used. NRC Staff review of operating plants indicates that 13 plants could be affected. Calculation by the Staff indicates that a transition to a brittle state could occur with-in 20 years. The Staff is currently investigating the problem, which may take four years before it is resolved because of test restraint.
Mr. W. Hazelton next presented the status of the low pressure turMne disc cracking problem that is currently affecting only Westinghouse turbines.
The problem was found on the Surry 2 turbine during inspection of the tur-bine assembly during refurbishing at the Westinghouse Charlotte plant. Cracks have been found in the core and keyway regions of the disc. These cracks are attributed to stress corrosion cracking phenomenon.
i Westinghouse developed a UT method where a probe could be located at the outside diameter of the disc to detect bore region cracks. This method was developed in order to check for cracks in the bore region without disassembling the disc from the shaft.
Cracks have been detected in a number of plants. Crack depth up to a Bore area little over half an inch has been found in the keyway area.
cracks have also been found.
In one case, Zion 1, the crack was about 1.2 inches deep by 2.5 inches long.
The critical crack size for most discs is about 1 - 1.5 inches.
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METAL COMPONENTS. 1/23&24/80 The Staff has. issued a letter to the utilities with Westinghouse turbines to address the turbine missile problems at their plants.
NOTE: A complete transcript of the open sessions of this meeting is on file in the NRC Public Document Room at 1717 H St., NW, Washington, DC, or can be obtained from International Verbatim Reporters. Inc.,
499 S. Capitol Stret Suite 107, Washington, DC (202-) 484-3550.
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Federal Register / Vol. 44, N:. 250 / Pridiy,RMRTMM muym---_-
intirfirence with cperation cf the HumanitiesPanet AhyCommittoo; Committle.
Endowment for the Humanities for projecta Slotice of Changes it is suggested that those d: siring l
beginning after June 1.19so.
J:nuary 18.1980. Time: 9'oo em to This is to announce changes in tw more specific information contact the
. s.30 pm Room:307.
Purpose:
To review meetings of the Humanities Panel Advisory Committee Management
- 6. Datz:
Officer, Mr. Stephen J. McCleary, 806 NDt Fellowships in Category C Advisory Committee.
1.The meeting to be held onIanuary 15th Street NW., Washington,DC 20506, applications in Sociology and uteraturesubmitted to the National Endowment for 3-4,1980 in Room 897, National or call area code 202-724-0367.
the Humanities for projects beginning after Endowment for the Humanities. 80615th St*P enJ.McCleary, h
I J:nuary 18,19e0 'nme: eso a.m. to St., N.W., Washington.D.C. to review AdrisoryCommittee.Managemen officer.
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June 1,1981 a 30 p m. Room: 500.
Purpose:
To review Museums and Historical Organizations gruk.mmeerw szea se m]
s Dste:
j Humanities Projects Program salaso coos isss as.es j
I catione s t to ational applications submitted to the National Endowment for the Humanities for projects Eadowment for the Humanities for beginning after May 1,1980.
projeets beginning after April 1,1980 haa NUCLEAR REGUL.ATORY 7.Date: January 19,19e0
- lime: 9:00 aa to been changed.It will be held in Room COMMISSION 314.
Purpose:
To review 807 of the National Endowment for the 5.30 p.m. Room:
NDI Summer Stipend applications in Humanities on january 9-10,1980.
Advisory Committee on Reactor Contampory uterature, and Uterary 2.The meeting to be held January 10.
Safeguards Sut committee on Tbsory and Criticism submitted to the 1979 in the 5th Floor Conference Room, Anticipated Tranelents Without Scram; National Endowment for the HurnanitiesNational Endowment for the Meeting for projects bes'nning after lune 1,1980.
- s. Data: lar.uary 21,1980. Time. 9:00 am t Humanities,80615th St., N.W.,
The ACRS Subcommittee on Washington,D.C. to review NEH Anticipated Transients Without Scram
$t$nowabps C
Libraries Humanities Projects Program (ATWS) willhold an open meeting on applications submitted to the National January 25,1980,in Room 1046,1717 H appbcations in llumanities for Two. Year Coll 2 e Teachers submitted to the National Endowment for the Humanities for St., NW., Washington, DC 20555. Notice Endowment for the Humanities for projects projects beginninh after April 1,1980 has of this meeting was publithed December
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besinning after June 1,19ea been changed. It willbe held in Room 900 a.m. to 5.30 p.m. Room: 807.
Purpose:
To review 911 on January 18,1980-20.1979'genda for subject muting shall January 22.1980. Time:
- 8. Date:
The a Both of these meetings were ND1 Summer Stipend applications in announced on page 70937 of the Federal be as follows-'
Unguistics. Speech, Communications.
Register dated December 10,1979 Friday, January 25,1980; 8:30 a.m. Until Composition. Rhetoric, and Thester sebmitted to the National Endowment for tepben J. McCIeary, Conclusion of Business the Humanities for projects beginning after Advisory Committee Management Officer.
The Subcommittee will discuss
- 10. Dste: [anuary 23,1980. Time: 9:00 am to A massas rwis.47-re au al proposed resolution of ATWS with Mry 1.1980.
6.30 pm Room: 314.
Purpose:
To review messo occa tsas.es es representatives of the NRC Staff.
Further information regarding topics NDi Summer Stipends applications in to be discussed, whether the meeting English uterature: Restoration to the Humanities Panel Advisory Committee; Present submitted to the National has been cancelled or rescheduled, the ties for projects Notice of Meeting Chairman *a ruling on requests for the
",t f her December 28,1979.
opportunity to present oral statements Because the proposed meetings will Pursuant to the provisions of the and the time allotted therefor can be consider financialinformation and Federal Advisory Committee Act (Public obtained by a prepaid telephone call to disclose information of a personal Law 92-364 as amended.) notice is the colmhant Designated Federal l
nature the disclosure of which would hereby given that a meeting of the Employee Mr. Paul A.Boehnert cons"tute a clearly unwarranted Humanities Panel will be held at 806 (telephone 202/634-3267) between 8:15 j
invr alon of personal privacy, pursuant 15th Street, NW., Wa shington, DC 20506, a.m. and 5:00 p.m., EST.
to authority granted,me by the in room 314, from 9 am to 5:30 pm on Dated: December 20,1979.
Chzirman s Delegation of Authority t Sa.turday, Januab12.1980.i Close Advisory Committee Meetings, fh
- Q A is rycomou\\teeManogementOfficer.
D l'"* " " '*#* ** "I edYatheme gs would fall n
e, within exemptions (4) and (6) of 5 U.S.C.
Endowment for the Humanities for
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te projects begmning after May 1,1980.
552b(c) and that it is essential to close Because the proposed meeting will these meetings to protect the free V
rfe nce ope ationo the disc se orma of p so 1 88 UT' E' dI8CI 8" 8 I hICh
- d Components; Meeting Ifyou site more specific constitute a clearly unwarranted
%e ACRS Subcommittee onMetal infctmatiori, contact the Advisory invasion of personal privacy, pursuant Components willhold an open meeting Committee Management Officer, Mr.
to authority granted me by the on January 23-24,1980,in Room 1046, Step en J.McCleary,80615th Street, Chairman's Delegation of Authority to 1717 H St., NW., Washington, DC 20555.
NW., Washington, D.C. 20506, or call Close Advisory Committee Meetings, Notice of this meeting was published dated January 15,1978 Ihave December 20,1979.
202-724-0367 determined that the meeting would fall He agenda for subject meeting shall kephen J.McCleary, within exemptions (4) and (6) of 5 U.S.C.
be as follows:
AdvisoryCommittee MonogementOfficer.
552b(c) and that it is essential to close Wednesday, January 23. Approximately 11:00 i
Puommsesseru.dtsease i the meeting to protect the free exchange a.m. (following the ACRS Subcommittee I
sume caos rssa.et.as of internalviews and to avoid I
J-
j Federal Ret ster / Vcl. 44, Ns. 250 / Friday, December 28, 1979 / Nstices t
- 76000,
meetins an the surry stron1until presentations by and hold discussions cbtdned by a prepaid telephoni call to th2 cognizint Designated Federal conclusion of business.hrsday. january with represent:tivss cf the NRC Stdf, Employee, Dr. Andrew L Bates
- 24. 8.30 a.m. until the conclusion o the Virginia Power and Electric (telephone 202/634-3267) between 8:15 bustnus.
Company, and their consultants, and The Subcommittee will review the other interested persons.
a.m. and 5:00 p.m., EST.
status of unresolved generic safety items In addition,it may be necessary for Dated: December 20,1979.
involving pressre vessels, steam the Subcommittee to hold one or mere I* ' '
generators, and other pressure boundary closed sessions for the purpose of Advisory Committee Management Oficer.
components in its cognizant area of exploring matters involving proprietary
[n Da Me W M-m ad el Information. I have determined,in e m ocaosts m us
[
review.
accordance with Subsection 20(d) of the Further information regarding topics to be discussed. whether the meeting Federal Advisory Committee Act (Pub.
has been cancelled or rescheduled, the L 92-463), that, should such sessions be Advisory Committee on Reactor Chairman a ruling on requests for the required,it is necessary to close these Safeguards Nuclear Regu! story opportunity to present oral statements sessions to protect proprietary Commission; Meetin8
[
and the time allotted therefor can be information. See 5 U.S.C. 552b(c)(4).
In accordance with the purposes of Further information regarding topics obtained by a prepaid telephone call to to be discussed, whether the meeting Sections 29 and 182b. of the Atomic the cognizant Designated Federal has been cancelled or rescheduled, the Energy Act (42 U.S.C. 2039,2232b.), the Employee.Mr. Elpidio C. Igne Chairman's ruling on requests for the Advisory Committee on Reactor
[ telephone 202/634-3314) between 8:15 opportunity to present oral statements Safeguards will hold a meeting on a.m. and 5.00 p.m., EST.
and the time allotted therefor can be January lu-12.1980, in Room 1046,1717 l
Dated: December 20,1979.
obtained by a prepaid telephone call to H Street, NW., Washington, DC. Notice l
John C. Hoyle, the cognizant Designated Federal of this meeting was published in the Advisory Committee Management 0)/icer.
Employee, Mr. Gary Quittschreiber Federal Register on December 20,1979.
II" Q* 7* * * "I (telphene 202/634-3267) between 8:15 ne agenda for the subject meeting a.m. and 5:00 p.m., EST.
will be as follows:
i Background information concerning Thursday, January 10,1m items to be discussed at this meeting Advisory Comnuttee on Reactor can be found in documents on 111e and 8:30 A.M-12:30RM Executive Safeguards Subcommittee on the available for public inspection at the Session (OpenJ--The Committee will I
Surry Nuclear Station; Meeting NRC Public Document Room.1717 H hear and discuss the report of the ACRS The ACRS Subcommittee on the. Surry Street, NW, Washington. DC 20555 and Chairman regarding miscellaneous Nuclear Station will hold a meeting on ai the Swem 1.ibrary, College of Wi!!iam matters relating to ACRS activities.
Roo 1 1717 H and Mary, Williamsburg, VA 23185.
The Committee will discuss proposed hanuy231900 ACRS comments and recommendations Dated. December 2o,1979.
to the U.0 Congress regarding the NRC continue its review of the Surry Station John C. Hoyle, Safety Research Program.
steam generator replacement program.
AdVi80t7 o3'mitterManagementOfficer Portions of this session will be closed C
Notice of this meeting was published tra ow neas m tw-m au mi as necessary to discuss infonnation the December 20,1979.
premature disclosure of which would in accordance with the procedures sea coot tseo-ows outlined in the Federal Register on frustrate the ACRS ability to perfonn its October 1,1979, (44 FR 5M08), oral or Advisory Committee on Reactor statutory function, 1:30 RM.-5:30 RM.: Meeting with written statements may be presented by Safeguards Subcommittee on NRCStaff(OpenJ-The Committee will members of the public, recordings will Licensee Event Reports (LERs);
hear and discuss reports from be permitted enly during those portions Meeting of the meeting when a transcript is being representatives of the NRC Staff kept, and questions may be asked only The ACRS Subcommittee on Licensee regarding proposed NRC action plans to by members of the Subcommittee,its Event Reports (LERs) will hold an open implement recommendations of the consultants, and Staff, Persons desiring meeting on January 23,1980, in Room President's Commission and other to make oral statements should notify 1167,1717 H St., NW., Washington. DC studies of the Three Mile Island, Unit 2 l
the Designated FederalEmplovee as far 20555. Nctice of this meeting was accident.
in advance as practicable so tfiat published December 20,1979 Portions of this session will be closed appropriate arrangements can be made The agenda for subject meeting shall as necessary to discuss Proprietary to allow the necessary time denng the be as follows:
Information applicable to these items.
j meeting for such statements.
Wednesday, January 23,1980; 11:30 a.m.
5:30RM-6:30RM ExecutiveSession The agenda for subject meeting shall Until Conclusion of Business (OpenJ-The Committee will discuss be as follon The Subcommittee will discuss the proposed methods to strengthen the role Wednesday, January 23,1900; 8:30 a.m.
evaluation of LER information with of the ACRS in accordance with the Until the Conclusion of Business representatives of NRC's newly formed recommendations of the President's The Subommittee may meet in Office of Analysis and Evaluation of Commission on the accident at Three Mile Island.
Executae Seeston, with any ofits Operational Da:a.
consultants who may be present, to Further information regarding topics Friday, January 11.1980 4
to be discussed, whether the meeting explore and exchange their preliminart has been cancelled or rescheduled, the 8:30 A.M-1030 A.M.: Meeting with opialons regarding matters which should i
be considered during the meeting.
Chairman's ruling on requests for the NRCStaff(OpenJ-The Committee will At the conclusion of the Executive opportunity to present oral statements hear reports and will discuss proposed Session, the Subcommittee willhear and the time allotted therefor can be plans for NRCImplementation of the 5
h A
REVISED:
1 /16/80 TENTATIVE SCHEDULE ACRS SUBCCMMITTEE MEETING ON METAL COMPONENTS WASHINGTON, DC JANUARY 23&24, 1980 (NOTE: Meeting will commence immediately after the conclusion of the Surry 2 Subcommittee meetina. Surry 2 Subcommittee meeting is scheduled to be adjourned about 11:00 a.m.)
JANUARY 23, 1980 APPROXIMATE TIME 11:30 a.m.
I.
EXCLTTIVE SESSION (OPEN) - P. Shewmon II.
STEAY GENERATOR OWNERS GRctP - Ozen Batum, Chairman, So. Company Services 1.
Steam Generator Owners Group -
11:40 a.m.
Organization and Activities - O. Batum 11:55 a.m.
2.
Description of Technical Programs - O. Batum 12:00 noon 3.
Chemistry and Materials - Stanley Green, EPRI 12:45 p.m. - 1:45 p.m.
LUNCH 4.
'lhermal Hydraulics and Structures - Jim Long, EPRI 1:45 p.m.
5.
NDE - John Mudis 2:00 p.m.
6.
Examples of various field applications 2:15 p.m.
2:45 p.m. - 2:55 p.m.
BREAK III. NRC PRESENTATION CN STEAM GENERATORS 1.
Description of Problem 2:55 p.m.
2.
Status of TAP A-3, A-4, A-5 3:10 p.m.
IV.
AIARA APPLIED TO STEAM GENERA'IORS 1.
leC Presentation 3:55 p.m.
4:30 p.m.
'2.
Olmers Group Comments V.
CHAIRMAN'S
SUMMARY
AND AIUOURM4ENT 5:00 p.m.
~
. JANUARY 24, 1980 APPROXIMATE TIME 8:30 a.m.
I.
EXCtJTIVE SESSION (OPEN) - P. Shewmon II.
LNRESOLVED SAEETY ISSUES (ACRS GENERIC ITEMS) 1.
Pressure Vessel 8:40 a.m.
a.
NDT Shift (NURD3 in by end of 1/80) 9:20 a.m.
b.
Fluence Nil-ductility properties (TAP A-ll) 9:50 a.m.
c.
(background material NUREG-0569) 10:30 a.m. - 10:40 a.m.
BREAK 10:40 a.m.
d.
'Ihermal Shock 2.
WR Nozzle Cracking (TAP A-10) 11:30 a.m.
(background material NUREG-0619) l 12: 30 p.m. - 1:30 p.m.
LUNCH 3.
Steam Generator and Reactor Coolant Pressure Supports (TAP A-12)
(background material NUREG-0577) 1:30 p.m.
4.
Disc Cracking 2:15 p.m.
k\\(
III. OTHER QUESTIONS BY THE SUBCOMMITTEE ON REIATED ITDiS 2:30 p.m.
3:00 p.m.
IV.
CAUCUS 3:15 p.m.
V.
Ab)0URNMENT
~
NOTES:
1.
At the discretion of the Subcommittee Chairman, scheduled items on 1/23 may be on 1/24 or vice versa.
. 2.
'Ihe NRC Staff should prepare for each generic items in the following manner:
a.
A short history of each item. Discuss any recognized shortcomings in the regulatory requirements or guidance.
ACRS SUBCOMMITTEE MEETING ON METAL COMPONENTS WASHINGTON, DC JANUARY 23 & 24, 1980 ATTENDEE LIST ACRS NRC STAFF P. Shewmon, Chairman ;
R. Emch M. Bender A. Schwencer H. Etherington J. Neighbcrs R. Dillon, ACRS Consultant B. Liaw H. Corten, ACRS Consultant M. Grotenhuis M. Wechsler, ACRS Consultant R. LaGrange E. Epler, ACRS Consultant C. Serpen E. Igne, Designated Federal Employee S. Goldberg J. Strosnider ELECTRIC POWER RESEARC4 INSTITUTE J. Rayan K. Hoge J. Mundis D. van Rooyen S. Green K. Parczewski J. Lang R. Gustafson J. P. Paine G. Georgiev G. Knighton SOUTHERN COMPANY SERVICES, INC.
PHILADELPHIA ELECTRIC COMPANY
- 0. Batum R, Zong DUKE POWER COMPANY COMBUSTION ENGINEERING CORP.
L. Lewis J. Hall A. Sudduth D. Kreps VIRGINIA ELECTRIC & POWER COMPANY WESTINGHOUSE ELECTRIC CORP.
H. McKay W. Fletcher J. Benton C. Hirst E. Rivas M. Haley T. Stenzel F. Beldecos CONSUMERS POWER COMPANY STONE & WEBSTER ENGINEERING CORP.
S. Frost R. Rosenberg J. Lewis C. Grochmal 1
a...
WISCONSIN ELECTP.IC CONSOLIDATED EDISON G. Frieling P. Silliman B. Bennett BABC0CK & UILCOX tiAGRAW-LILL U. Speight J. Gutzwiller J. Dann POTOPAC ALLIANCE NORTHEAST UTILITIES
- F. Millar R. Laudenst J. Fackelmann CENTRAL ELECTRIC GENERATING BOARD POWER AUTHORITY OF THE STATE OF NY (UNITED KINGDOM)
B.f'ukherji R. Garnsey PUBLIC SERVICE ELECTRIC & GAS CO.
ROCHESTER GAS A ELECTRIC G. Slifer A. Curtis, III G. Schnabel CAROLINA POWER & LIGHT CO.
EMPIRE STATE ELECTRIC ENERGY RESEARCH CORP.
W. Way
~
J. Burger KMC fiEMBERS OF THE PUBLIC D. Knuth E. Roby, United Press International S. Kest, Washington Star M. Crutsinger, Associated Press TENNESSEE VALLEY AUT4ORITY B. Miller, Richmond Times G. Olaya E. Harwell B. Byrne D. Martin
~
S. Clocker S. Corsanico
,_