ML20010J378
| ML20010J378 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 08/26/1981 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-1872A, NUDOCS 8109300391 | |
| Download: ML20010J378 (12) | |
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TI I klA6- / 8'/f2)Q Issue Date: 8/26/81 fI MINUTES OF THE ACRS SUBCOMMITTEE MEETING ON g, yU g
METAL COMPONENTS RICHLAND, WA JUNE 30, 1981 The ACRS Subcommittee on the Metal Components met in Richland, WA on June 30, 1981 to discuss the research programs being conducted by Battelle Pacific Northwest Laboratory (PNL) for the NRC in the areas of Integration of NDE and Fracture Mechanics, cortinuous acoustic emission monitoring, and the Surry steam generator program.
Notice of this meeting was published in the Federal Register on June 11, 1981 (Attachment A).
A copy of the detailed schedule of presentations is shown in Attachment B.
A list of documents and presentation handouts provided to the Subcommittee during the meeting is contained in Attachment C.
A If st of attendees is contained in Attachment D.
Mr. Elpidio Igne was the Designated Federal Employee for this meeting. The entire meeting was open to thqps\\
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Steam Generator Program Review, Dr. R. A. Clark, PNL T
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The Surry 2,kh Dr. R. A. Clark reviewed the steam generator program.
house Model 51 steam generator has been received by PNL and is presentiy' stored in its shipping cast in a remote area. A steam generator examination facility is currently under construction and is scheduled for completion by November, 1981. The characteristics of the facility allow destructive as well as nondestructive assays of a large amount of samples. The facility is equipped for handling the radiological aspects of this work. The facility is a high bay structure which allows vertical positioning of the steam generator.
The vertical positioning of the generator allows NDE tests to be perf arined in k
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r METAL COMPONENTS 6/30/81 their in-service orientation. The facility is triple, HEPA filtered for cutting operations.
Cranes are provided for removal of samples and adjacent laboratory facilities are available to conduct metallurgical examinations.
It is a unique facility for doing a destructive assay of a large radioactive component.
Dr. Clark discussed the pre-shipment examination performed to ensure that storage had not degraded the unit and that transportatioq of the steam generator would not damage it so that useful research would be precluded.
The steam generator was shipped over a year ago (May,1980) to Hanford, WA.
The types of degradation in the steam generator, including tube denting and flow hole blockage'from service at North Anna, were reviewed.
Major research areas of this program include validation of nondestructive examination, tube integrity determinations, primary side decontamination and secondary side cleaning, ALARA control of radiation exposure and statistics of degradation and nondestructive testing characterization of degradation.
Dr. Clark emphasized the fact that the cleaning and decontamination studies are not research studies, in so far as the NDE program is concerned. The purpose of these studies is to determine whether or not a unit that has been cleaned or decontaminated can be returned to safe, long-terni operation.
Al so of interest are the effects of cleaning on NDE ability to characterized defects in the unit following cleaning. The steam generator examination facilities and efforts to date have cost 55 million which represents 25% of the total project funding.
Another $10 million will be spent over the next 5 years. Validation of nondestructive examination techniques will represent
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METAL COMPONENTS 6/30/81 35% of the budget, and tube integrity determinations represent 10% of the budget. Together, the secondary side cleaning and primary side decontamin-ation represent another 10% of the budget. Health physics considerations will account for 10% of the budget. Finally, the experimental as well as analytical process involves 10% of the cost. Dr. Clark felt that there was a good possibility that over half of this project could be funded by or-ganizations other than NRC.
Dr. Clark discussed the NDT "round robin" which will consist o,f all sponsors, on the order of 8-10 groups, who will participate in using single and multi-frequency eddy type testing. Other NDT devices under development will also be used. EPRI is bxpected to join the groups and validate the devices that they have developed. The real crux of the validation testing is to determine how much inspection is necessary and if it is possible to do other than 100%
inspection. The base line inspection of all unplugged tubes using accepted state-of-the-art instrumentation will be conducted. The base line inspection plus analysis of historical in-service inspection data will be used to deter-mine which plugged tubes will be unplugged for an optimum defect matrix. A statistical selection will then be made to determine a subset of tubes for round robin NDT inspection.
On the order of two to three hundred tubes has been suggested.
NDE Pipe Reliability Program, F. L. Becker, PNL Mr. Becker discussed the status of the integration of NDE reliability and fracture mechanics program.
The licensing issues that are addressed in the program include the effectiveness of current NDE inspection practices and the adequacy of current requirements; this includes inspection techniques,
METAL COMPONENTS 6/30/81 the extent and frequency of inspection, the allowable flaw size, and the required detection probabilities. These items are fed back to NRC so ef-fective requirements for the industry can be produced. The basic objective of the program is to determine the reliability of ultrasonic, in-service inspection (151) and using fracture mechanics to determine what impact the unreliability of the ISI technique can have. Major accomplishments thus far are as follows:
Developed fatigue and IGSCC flaw growth characterization techniques.
Implemented procedures for search unit and instrument characterization.
Initiated RPV under clad crack program.
A round robin program to detect and characterize similar metal welds in piping systems has been started.
It is scheduled to be completed by mid-1982.
The objective of the round robin inpsection is to measure the current level of inspection reliability, determine the source and magnitude of inspection errors, and provide information for inspection reliability models which can be used to expand the data base to other piping applications.
Representative materials from PWRs and BWRs have been selected for examination. The flaws that the participants will try to discover will be intergrannular stress corrosion cracks, which are among the more difficult defects to discover.
Attempts will be made to simulate the environment found in actual practice.
J coustic Emission, Flaw Characteristic Program, P. Hutton, PNL i
P. H. Hutton, discussed the status of the acoustic emission ( AE) flaw char-acterization program. The objectives of the program are to evaluate, on
r METAL COMPONENTS 6/30/81 an experimental basis, the feasibility of flaw detection and evaluation using acoustic emission information (during both in-service inspection and during hydro-testing) that is derived on a continuous basis. The licensing and safety issues being addressed are to provide a continuous surveillance.ech-nique for the reactor pressure boundaries to assure structural integrity by detecting, locating, and performing some evaluations of active flaws that are detected by AE.
In older reactors, the vessel inspection due to the construc-tion features is quite difficult with normal methods.
The application of AE would not only be for detection and evaluation of defects, but.to localize and choose shielding penetrations at optimum points for follow-up or con-firmatory inspection by conventional methods.
This The first phase (laboratory study) of this program has been completed.
study has produced a method of identifying AE signals from crack growth by pattern recognition and AE/ fracture mechanics relationship for the estimation of flaw severity. The second and third phases of the program remain to be completed. These are (1) perform a vessel test and analyze the results and (2) instrument a reactor and perform continuous AE monitoring to demonstrate program results. This will be done on TVA's Watts Bar Unit I reactor.
The AE program has successfully accomplished a demonstration of an NRC-The test used a developed AE weld monitoring system on a test in Germany.
ten-inch thick plate. The test was successful ;n detecting small and large cracking, slag inclusion, and porosity.
For additional details, a complete transcript of the meeting is avail-NOTE:
able in the NRC Public Document Room,1717 H St., NW, Washington, DC 20555 or from Alderson Reporters, 300 7th St., SW, Washington, DC, (202) 554-2345.
Fcderal Rrgister / Vol. 46. No.112 / Thursday. June 11. 1981 / Notices 30923 pa.senger sessels operating under its contro!
(49 U.S C.1903(a)(2).1906) with representatives of the NRC Staff.
their consultants, and other interested serification program.1960 SOLAS adequate!) Margaret L Fishr*
persons regarding this review.
, proudes for safe's des:gn of such doers FederalRegisterLsaison O'fscer.
y g
M-ao-10e USCG has neither su!!icnent fund.ng nor personnel to condact June 4.1981 g
sC s i
1e t ng J
unannounced boardings of foreign ;.ssenger tFR Doc el-1W Find a-10-at s es em}
vessels to insure that spnni!er system control espo com mo-sa-as Chairman.a ruling on requests for the
~
sahes are full > open opportunity to present oral statements M-40-tot SOLAS requirements for hofdmg and the time allotted therefor can be 3
and logging regular dnlis are adequate to NUCLEAR REGULATORY obtained by a prepaid telephone call to y
insure crew famihanty with the sessel and its COMMISSION the cognizant Designated Federal is Rrefighting s> s'em and equipment M-aa-los it is not necessar> to mod.f> the Advisory Committee on Reactor Employee. Mr. Elpidio Igne (telephone intent of current SOLAS consention fire Safeguards, Subcommittee on Metal 202/634-1414) between B 15 a.m. and 5 watch standards Components; Meeting p.m., EDT.
2 M-ao-109 USCG does not concur; 1948 and The ACRS Subcommittee on Metal I have determined,in accordance wit!1 19m sot.AS Consentions teamre Components will hold a meeting on June Subsection 10(d) of the Federal 3a 1982 at the BatteDe Memoria) msg Gmmh Act. Wat H ma3 k I assenger sh ps s t a fire 3 Institute, Pacific Northwcst necessary to close some portions of this I
promptly detected Additional unilateral fire Laboratories. Richland. WA 99352. The meeting The authority for such closure t
I safet) requirements can be mandated aboard Subcommittee will review NRC's fiscal is Exemption 9(B) to the Sunshine Act. 5 foreign-flag sessels on!) if a thorough basis for name is Erst estabbshed year 1983 Reactor Safety Research U.S C. 55:b(c)(9)(B).
I M-80-110 A copy of USCG Marine Board Program Budget concerning Inservice Dated. June 8.1981.
ofInvestigation and Commandant's Action Inspection and Steam Generator John C. Ro>le, Advisory Committee Afono,< ment Off,cer.
on its recommendations will be made programs-In accordance with the procedures 1
'atuable to sessel operators and mas'ers through their local agents. The case will be outlines in the Federal Register on offered at IMCO through USCG haison with October 7.1980. (45 B 66535), oral or that body.
wTitten statements may be presented by a bmit a members of the public, recordings will (Docket Nos. 50-416 and 50.-417]
, d,,
,,s n of be perTnitted only during those portions P, e k
dis of the meeting when a transcript is being Availability of the Draft Environmental ss r.
he A Cl t R kept, and questions may be asked only Statement for the Grand Gulf Nuclear l
casuait) and h:ghhghtirg lessons teamed in by members of the Subccmmittee. its Station, Unita 1 and 2 investigation Owners and operators of should notif 8
Notice is hereby given that the Draft UllEuSghto o na e oral e aterne t Environmental Statement (NUREG-spect t r ga e ex a st system for cleanhness. Ic, esaluate spnnkler the Designated Federal Employee as far 0777) related to the operation of the systems for proper memtenance. ready is advance as practicable so that.
Grand Gulf Nuclear Station. Units 1 and asailabiht) of mater. and completeness of appropriate arrangements can b6 made
- 2. by the Mississippi Power & Light coserage. and. further, to esaluate the need to allow the necessary time during the Company, has been prepared by the ge for addationalinsulation and f sed meeting for such statements.
Commission's Office of Nuclear Reactor extinguishmg sy stems in ga!!ey exhaust The majority of the meeting will be Regulation. The Grand Gulf Nuclear a
ducts. volunta*> insta!!ation of fire and open to public attendance.The Station is located on the Mississippi smoke detection systems wdl be Subcommittee will be considering some River in Claiborne County, %ssissippl.
predecisional budget information The Draft Environmental Statement la I
s, commended 440-111 USCG concurs in training a!!
associated with the NRC Safety E
eerdor and safety officers at an approved Research Program Budget for fiscal year available for inspection by the public in and$rds of 1983 In order to perform this review, the the Commission's Public Do,cument Room at 1717 H Street, N.M..
te ao 1 n ention on ACRS must be able to engage in frank Training Certification and Watchkeeping for discussion with members of the NRC
% ashington. D.C. 20555. and at the M-ao-114 USCC has contacted the Federal Staff.Therefore it may be necessary to Hinds Jr. College. George M. McLendor Seafarers.19?8. addresses this rnatter.
Emngency Management Agency, offering to close portions of this meeting (Sunshine Library, Raymond. Mississippi 39154.
[
The Draft Environmental Statement,si assist the Virgin Islands Gosemment in Act Exemption 9(B]). To the extent ia revising contingency plane USCG practicable, these closed sessions will also being made available at the State contingency plans for ports in the Greater be held so as to minimize inconvenience Clearinghouse. Coordinator Federal-Antilles Section will be updated by Dec.1.
to members of the public in attendance.
State Programs. Office of the Governor, ten The agenda for subject meeting shall 1503 Sillers Building Jackson.
6 Note-Single copies cf Board reports are be as follows:
Mississippi 39201, and the Southwest available without charge as long as limited Tuesday, fune M, 1961,8:30 o.m. until Mississippi Planning and Development aire supphes last Copies of recommendation the conclusion of business.
District, Post Office Box 636. Meadville.
letters, responses and reisted correspondence During the initial portion of the Mississippi 39653. Requests for copies of meetirq. tne Subcommittee, along with NUREG-0777 should be addressed to the any of its consultants who may be U.S. Nuclear Regulatory Commission.
in ident d ecom er da io
]
report number. Address requests to: Pubhc present, may exchange preliminary Washington.D.C. 20555. Attent,on:
i Inquiries Section. National Transportation views retarding matters to be Director,TechnicalInformation and DI Sah ty Board. Washington. D C. 20594 considered during the balance of the Document Control.
,4 Mattiple copies of Board reports may be Pursuant to 10 CFR Part 51, interested 4
purchased from the National Technical meeting.
- I j
Information Service. U.S Department of The Subcommittee will then hear persons may submit comments on this u
Commerce. Spnngfield. V A. 22161.
presentations by and hold discussions Statement for the Commission's N
//
s ATTEIWNT ~A 1
REVISED 6/26/81 TENTATIVE SCHEDULE SITE TOUR AND ACRS SUBCOMMITTEE MEETING ON METAL COMPONENTS HANFORD, RICHLAND, WA JUNE 29 & 30,1981 JUNE 29,1981 SITE TOUR Pick Up At Hotel 8:30 a.m.
Tour N-Reactor 9:15 a.m. - 11:15 a.m.
Lunch, BNW, NW Room 1:30 p.m. - 3:00 p.m.
Tour FFTF 3:30 p.m. - 4:00 p.m.
Return to Hotel NOTE:
A Shuttle Van will be provided by PNL for the tour.
JUNE 30,1981 METAL COMPONENTS SUBCOMMITTEE MEETING Steam Generator Program Review 8:00 a.m. - 10:00 a.m.
(R. Clark)
NDE Pipe Reliability Program 10:00 a.m. - 11:00 a.m.
(F. Larry Becker)
Continuous A/E Monitor 11:00 a.m. - 12:00 noon (P. Hutton)
LUNCH 12:UO noon - 1:00 p.m.
NDE Lab. Tour 1:00 p.m. - 3:00 p.m.
(T. Posakony)
Tour Steam Generator Storage Site 3:00 p.m. - 4:30 p.m.
Tour Steam Generator Exam Facility Unde-Construction Tour Steam Generator 314 Bldg. Pipe Crack and Burst Test
/tTrAsMM7 T Tour Steam Generator 30S Bldg. Survivability Test Bed in large Pipe
r ATTACHMENT C LIST OF HAND 0UTS PROVIDED TO SUBCOMMITTEE DURING MEETING ACRS SUBCOMMITTEE MEETING ON METAL COMPONENTS RICHLAND, WA JUNE 30, 1981
- 1.. Photographs from an examination conducted on the Surry 2A steam generator about 1-li years ago after its removal from service.
(Provided by R. A. Clark, -38 photographs) 2.
Surry Generator Research Program Plan, Steam Generator Group Project.
(Provided by R. A. Clark, Battelle Project Manager &
J. Muscara, NRC Program Manager, 61 pages) 3.
Integration of NDE Reliability and Fracture Mechanics (NDE/FM).
(Provided by F. Larry Becker, PNL,-G0 slides) 4.
Acoustic Emission - Flaw Relationship for In-Service Monitoring of Nuclear Pressure Vessels.
(Provided by P. H. Hutton, PNL, 10 pages)
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