ML20154R654

Summary of 980826 Meeting W/Nei in Rockville,Md Re Ultrasonic Exam of Stainless Steel Cask Closure Welds & Inclusion of ASME Code Requirements in Licensing of Spent Fuel Storage & Transportation Casks

ML20154R654
Person / Time
Issue date:	10/19/1998
From:	Reid D NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:	Kane W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
NUDOCS 9810270130
Download: ML20154R654 (21)

Text

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NUCLEAR REGULATORY COMMISSION 5

e WASHINGTON, D.C. 30486 4001 o( 4 ",eT[

October 19, 1998 MEMORANDUM TO: William F. Kane, Director Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards FROM:

Dennis G. Reid, Project Manager

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Spent Fuel Licensing Section kM M

Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards

SUMMARY

OF AUGUST 26,1998, MEETING WITH NUCLEAR ENERGY INSTITUTE AND INDUSTRY On August 26,1998, staff from the Nuclear Regulatory Commission's (NRC's) Spent Fuel Project Office (SFPO) met with industry representatives at a meeting sponsored by the Nuclear Energy Institute (NEI). The meeting followed a workshop format and provided an opportunity for an open technical exchange between NRC and the industry on generic issues relating to the transport and storage of spent nuclear fuel. The meeting, which was noticed and open to the public, was held at NRC headquarters with approximately 60 individuals representing utilities, vendors, and contractors attending. Attachment 1 is a list of attendees. The meeting was noticed on August 6,1998.

The main topics discussed included ultrasonic examination (UT) of stainless steel cask closure welds and the inclusion of The American Society of Mechanical Engineers (ASME) Code requirements in the licensing of spent fuel storage and transportation casks. The industry presentation was made by Robert Nickell of Energy Power Research Institute. The presentation included discussions on the welding of stainless steels; weld defect characterization, flaw tolerance of weld design, and nondestructive examination methods of austenitic stainless steel; and existing ASME Code Section Ill requirements that are pertinent to spent fuel storage cask closure welds. The industry stated that austenitic stainless steels (300 series) possess a high tolerance for hydrogen, maintain their austenitic structure, and are very weldable with conventional techniques, provided that quality practices and materials are used. Tne industry also stated that austenitic stainless steels are ductile, tolerant of very large flaws, and respond very well to the application of both UT and liquid penetrant examination, which can be relied kl/

upon for assurance of adequate structural integrity.

i The staff reminded the industry that the standard review plan explicitly suggests UT as the

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alternative method to radiography and suggested that the industry develop consensus regarding alternative technical methods and propose alternatives to the staff for review. The staff also reaffirmed to the industry that its proposal on alternative examination methods should be limited to closure welds only.

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The ASME Code discussion was considered a follow-up to the NEl workshop held July 1-2, 1998, at which the staff informed the industry that it was considering the full implementation of l

the ASME Code requirements including the services of an authorized nuclear inspector and code stamping. The staff expressed its concern about the industry's seeming inability to come to consensus on this issue and the absence of certain information in NEl's ASME Code presentation. Specifically, at the July 1-2,1998, workshop, NEl reported that the industry committed to augment its inspection program by increasing utility oversight inspection of fabricators and vendors. However, the industry's presentation at the August 26,1998, workshop did not include any reports on this matter. NEl responded that the utility oversight l

group (NUPIC) is developing a final checklist for adoption and will request a meeting with the NRC staff to present NUPIC's inspection approach. NEl proposed to assemble an ASME Code map dowing which requirements apply and how the industry intends to meet them.

A member of the public addressed the audience regarding the use of UT techniques instead of radiography No regulatory decisions were requested or made. No proprietary information was disseminated.

Attachments: 1. Attendance List

2. NEl Slides

3. Public Member Slides Distribution:

NRC File Center PUBLIC NMSS R/F SFPO R/F EEaston CHaughney WHodges LKokajko FSturz PEng WReamer, OGC SGagner, OPA SShankman G:\\DGR\\NElUT826. SUM h

OFC SFPO d

SFPO SFPO

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NAME DReid-dd M VTh EJLeeds DATE 10/d8 /98 10/14/98 10/ N/98 C = COVER E = COVER & ENCLOSURE N = NO COPY OFFiclAL RECORD COPY 10/19/98:dd l

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i August 26,1998, meeting between U. S. Nuclear Regulatory Commission and Nuclear Energy Institute ATTENDANCE LIST

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NAME ORGANIZATION l

I William Kane NRC/NMSS/SFPO Wayne Hodges NRC/NMSS/SFPO Susan Shankman NRC/NMSS/SFPO Dennis Reid NRC/NMSS/SFPO Fritz Sturz NRC/NMSS/SFPO Kimberly Gruss NRC/NMSS/SFPO Henry Lee NRC/NMSS/SFPO Charles Interrante NRC/NMSS/SFPO Chris Brown NRC/NMSS/SFPO Ken Battige NRC/NMSS/SFPO David Tang NRC/NMSS/SFPO Ron Parkhill NRC/NMSS/SFPO Michael Raddatz NRC/NMSS/SFPO Alan Nelson NEl Lynette Hendricks NEl Robert E. Nickell EPRI Frank Ammirato EPRI Frank Machiels EPRI Shane Findian EPRI E. Kim Keitzman EPRI Greg Selby EPRI Bill Lee NAC International Bill McConaghy NAC International Len Tremblay DE&S/NAC Owners Group Jim Nestell MPR Associates for BNFL Alan Redley BNFL Wayne Massie BNFL/ Sierra Nuclear Walter Bak Transnuclear West Tara Neider

'Transnuclear Inc.

Ray Kellar Entergy (ANO)

David Williamson SAIC John A. Vincent GPUNG & Private Fuel Storage Kenneth A. Phy New York Power Authority - FitzPatrick Christen Howard Southern Nuclear Gary Tjersland Holtec intemational Ted Gado Foster Wheeler Pete Riccardella StructuralIntegrity Assoc.

Jerry Delezenski Rancho Seco Don J. Green TVA ATTACHMENT 1

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August 26,1998, meeting between t

U. S. Nuclear Regulatory Commission and Nuclear Enugy Institute l

I ATTENDANCE LIST (continued) l NAME ORGANIZATION l

l Andrea Jenneta Washington Nuclear Corp.

Dan Gildow Portland General Electric John Vesik Portland Geenral Electric Bob Hardies BG&E Stephen Dunn Naval Reactors - DOE Barry Miles Naval Reactors - DOE Brian Hallett Bettis Marv Doman Bettis John Clark Bettis Joe Kramer NNS Bob Quinn Westinghouse Electric Co.

Emil Zernick Comsumers Energy James Doman Booz-Allen (DOE-OCRIUM)

Kenneth Ainger Commonwealth Edison Maureen Conley Washington Nuclear Corp.

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CANISTER CLOSURE WELD PRESERVICE EXAMINATION ISSUE

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Nuclear Energy Institute /U. S. Nuclear Regu atory Commission j

Rockville, MD 1

August 26,1998 5

EPRI Technical Team n

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AUSTENITIC STAINLESS STEEL CLOSURE WELDS Both UT and PT (Root Pass and Intermediate / Final Pass) Can Provide Assurance of Adequate StructuralIntegrity Adequacy Depends on Weld Defect Characteristics, and on the j

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Flaw Tolerance of the Weld Design 9

Weld Defects Characterized as: (1) Lack of Fusion; (2) Slag 1

Inclusions; (3) HAZ Defects from Stabilizer Carbide Precipitation; and (4) Weld Defects from Excessive Residual Elements, Excessive Joint Restraint, Ferrite Content Outside l

Range, and Rapid Cooling l

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FLAW EVALUATION ROAD MAP 1

S.

Material is Ductile, Even for Worst-Case (SAW and j

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SMAW) Properties c

Flaw Stability, as Opposed to Crack Initiation, Must Be Demonstrated 1

In Addition, Resistance to Global Plastic Collapse (Limit Load) Must Be Demonstrated y

Very Large Flaws Can Be Tolerated by Stainless Steel

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Closure Welds Under Design-Basis Loads

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Flaw Tolerance Examples Can Be Developed l

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FLAW TOLERANCE EXAMPLES

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Flaw Completely Around Circumference (2c/W :

1),

i Penetrating Part-Through the Weld (a/t = 0.3 to 0.5);

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Applied J is Less Than 1,000 in-Ib/in as Compared to 2

1430 in-lb/in for J-R Curve at 0.1 Inches of Crack l

Extension Plastic Collapse Load May Be More Limiting Flaw Completely Through-Wall (a/t = 1), -10 Inches Around Circumference (2c/W = 0.1); Applied J is Less 2

2 Than 1,000 in-Ib/in as Compared to 1430 in-lb/in for J-R Curve at 0.1 Inches of Crack Extension i

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ASME CODE ISSUE NRC Concerns Vendor Commitments and Utility Oversight During Fabrication AreInconsistently Applied Provisions of the ASME Code Are Not Applied Uniformly to Dry Storage System Casks and Canisters Question Should Full Compliance With Code Requirements,

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Including Third-Party Inspection and Code Stamping, Be Imposed?

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INDUSTRY OPTIONS t

Support and Endorse the Activity in ASME Code Section III, Division 3, to Incorporate Subsection WC to Cover Storage System Containment Boundary Construction t

Support and Endorse the Interim Application ofASME Code Section VIII, Either Division 1 or Division 2, to Cover Storage System Containment Boundary Fabrication andExamination AdoptInterim Position of Utility Oversight in Lieu of Third-Party Inspection; Certification; and TP (SP) l Stamping i

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INDUSTRY RECOMMENDATIONS Adopt the ASME Code Section III, Division 1, as a materials, design, fabrication, examination, and testing standard, documented in each Safety Analysis Report.

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Recognize that the ultimate responsibilityfor ensuring t

regulatory compliancefalls upon the cask vendor and utility

-l owner.

Defer implementation ofASME Code third-party inspection procedures and Code stamping ofitems covered by ASME Code rules.

Commitfurther development of consensus codes and standards.

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BACKGROUND ON ASME SECTION XI FLAW EVALUATION APPROACH

- Fracture Mechonk:s thect Elas8c Elastic-Rostic UmR Load Fracture Mechanics Fracture Mechanics (Net SecRon (LEFM)

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• Bdffle Malerlois

• SemIOuctie Malertals

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• Moderale Toughness

• Hgh Toughness low Toughness a

• CerdMc Steels d

• Stainless SW h

• Ferdtic Steels d Hgh Temperature Meld cmd GTAW Low Temperature Weidments

• Stainless Steels and Weidments (SAW cnd SMAw)

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OueStionS for NRC meeting: August 26,1998 1.

Intro a) Robert Moss, consultant to Bio-Imaging Research, Inc. (BIR) b) BIR: Since 1980, a research and development company that solves unique imaging problems for industry. 50 man staff thoroughly familiar with xray, ultrasound, mri, nuclear imaging, etc. Clients include DOE, Navy, Boeing, NASA, as well as SKB, the Swedish Nuclear Agency.

c) Just recently shipped a high-energy digital xray system to SKB in Sweden for radiographic inspection of containment welds on nuclear fuel dry casks. Resolution proved to be greater than 1 millimeter through 100 millimeters of copper (which is the equivalent to 120 mm. or about 5 inches of steel).

2.

Why hasn't the industry thoroughly explored the use of RT (radiographic) instead of UT:

a) Much greater resolution possible b) Not dependent on type of steel used; works on other materials also. Solely dependent on density c) Less dependent on operator technique d) Own guidelines call for and mandate its use: Chapter 9 of your own publication NUREG 1536 calls for: " Confinement boundary welds and welds for components associated with redundant sealing must meet the requirements of ASNE Code,Section III, Article NB/NC-5200 ' xequired Examination of Welds." This section generallv requires RT for volumetric examination and either PT or MT for surface examination. The ASNE-approved specifications for RT, PT, and MT are detailed in AShE Code,Section V, Articles 2,6, and 7, respectively."

e) UT only appears acceptable according to NUREG 1536 if RT is not feasible: "For confinement welds that cannot be volumetrically examined using RT, the licensee may use 100-percent UT."

3.

Why does NRC allow any voids or cracks of any length (referring to communications and graph in Sierra Nuclear files regarding allowable crack size) when Chapter 9 of NUREG 1536 appears to preclude this: " Acceptance criteria should be defined in accordance with NB/NC-5330, " Ultrasonic Acceptance Standards." Cracks, lack of fusion, or inccmplete penetration are unacceptable, regardless oflength."?

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4.

Why has the NRC and industry been reluctant to evea explcre this technology when brought to its attention ATTACHMENT 3

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- j big 11Ac-Defective welds have been a problem with some dry cask systems and, until recently, there were no fully satisfactory solutions to the prob'em of ensuring the integrity of critical confmement l

welds. Now, Bio-Imaging Research, Inc. has a solution.

Recently, Bio-Imaging Research, Inc. delivered a sophisticated imaging system to SKB (the Swedish Nuclear Agency) for radiographic analysis cf confinement welds on nuclear fuel dry storage casks (see attached press release, photo, and schematic). This system, which we call HEDR (High-Energy Digital Radiography), is the first practical system to allow for the high-resolution discovery and visual display of defe

'n the critical confinement welds which have been an industry concern in the U.S. and elsewhere.

As an example of the system capabilities, also attached is an image taken with the system which illustrates its ability to detect 1 mm. voids through 100 mm. of solid copper. Since copper is denser than steel, this is the equivalent to penetrating 120 mm. of steel. This is substantially better resolution than can be achieved with ultrasound technology. Greater distances can be penetrated if necessary

, corresponding results. Also attached is an image of the operator's display screen showing a continuous weld.

BIR feels that this represents the highest and best safety technology for weld examination now available and should completely eliminate any doubts about weld integrity. This will, of course, substantially strengthen the quality assurcnce program of both cask manufacturer and utility and virtually eliminate the risk of substantial costs and program delays attributable to this source.

For more information, please contact Mr. Chuck Smith of BIR at 847-634-6425 ext.110.

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Charles R. Smith, Vice President Marketing Bio-Imaging Research, Inc.

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. Lincolnshire, IL 60069 USA TEL: 847/634-6425 FAX: 847/634-6440 E-MAIL: marketing @birinc.com Att: Dr. Lars O. Werme SKB Project Manager, Canister SKB Encapsulation Plant Project TEL: (Stockholm) 011-46-8-459-8525 FAX:(Stockholm) 011-46-8-667-3645 E-Mail: skbiw@skb.se 6/26/98

Enclosures:

BIR System Photo, SKB Schematic Site / Canister Illustration Page1of3 FOR IMMEDIATE RELEASE Stockholm, Sweden-SKB adds advanced imaging technology to its encapsulation project for i

storing nuclear waste safely up to one million years.

SKB, Swedish Nuclear Fuel and Waste Management Co. (SVENSK KARNBRdNSLEHAN-TERING AB), Stockholm, Sweden, has taken delivery of an advanced High-Energy Digital l

Radiography (HEDR) imaging system developed by Bio-Imaging Research, Inc. (BIR, d

Lincolnshire, IL) which will be utilized by its nuclear waste Encapsulation Plant Project. The BIR system will be installed at SKB's Canister Laboratory located in Oskarshamn, Sweden, on the 1

j Baltic Coast some 220 miles (350 km) south of Stockholm.

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Page 2 of 3 The SKB project was staned to demonstrate that spent nuclear fuel can safely be encapsulated end disposed ofin copper canisters. A canister is some 16-feet (5 meters) tall and approximately 40-inches (1 meter) in diameter; each weighs about 27 tons (24,660 kilograms). Begun in 1992, SKB will be applying for licensing the encapsulation process at the earliest in 2001. The encapsulation plant will be operated for at least 40 years, the time necessary to encapsulate all accumulated spent Swedish nuclear fuel. During an initial four-year period,10% of spent fuel, filling some 400 canisters, will be encapsulated. The total cost of the encapsulation plant has been preliminarily estimated at some $250 million (US).

SKB's process includes encapsulatis; s;ient nuclear fuel pellet assemblies in cylindrical copper canisters with inner steel containers. Copper was chosen for the canister outer shdl because it provides resistance to corrosion. The steel inner container was chosen for its mechanical strength.

Studies have shown that these copper canisters will probably remain intact for at least one million years, considerably longer than the 100,000 years during which spent nuclear fuel is more hazardous than natural rich uranium ore.

Copper corrodes very slowly in oxygen-free groundwater present in Swedish bedrock. Canisters will be placed in deep repositories, deposited in venical holes (one canister in each) bored into the floors of a tunnel system within a repository, which is built into bedrock to a depth of some 1,640+ feet (500 meters). When all canisters are in place, the deep repository will be scaled by i

backfilling its tunnels and shafts with a mixture of bentonite and sand.

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Page 3 of 3 Each copper canister lid will be sealed by electron-beam welding. The BIR High-Energy Digital f

- Radiography (HEDR) System will inspect these critical lid weldments to make absolutely sure there are no leaks in the final structure. SKB required that the BIR we'id inspection system should resolve 1 mm spherical we:dment void in 100 mm of copper weldment with a probability of 99.97%. BIR's HEDR System has exceeded all SKB functional requirements.

BIR is a worldwide leader in next-generation (nor.-medical) x-ray imaging systems for industrial applications, including computed tomography and digital radiography scanners. BIR has installed over 60 industrial x-ray scanner systems over the past 18 years for research and nondestructive testing worldwide, more than any other company. Bio-Imaging Research, Inc.,425 Barclay Boulevard, Lincolnshire, IL 60069;'i lL: 847/634 6425; FAX: 847/634-6440: E-MAIL:

marketing @birinc.com; WEB: www. bio-imaging.com.

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SKB schematic drawing of deep repository for spent nuclear fuel built to a depth of 1,640+ feet /500 meters.

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