ML070650583

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E-mail: (PA) Cap Reduction Factor Issue
ML070650583
Person / Time
Site: Oyster Creek
Issue date: 02/05/2007
From: Webster R
Rutgers Environmental Law Clinic
To: Ashar H, Ashley D, Junge M, Modes M
Division of Engineering
References
TAC 8261
Download: ML070650583 (6)


Text

D.AhlyCa edction factor issue Pg From:

"Richard Webster" <rwebster@ kinoy.rutgers.edu>

To:

"D. Ashley" <DJA1 @nrc.gov>, <hga@nrc.gov>, <MCM@nrc.gov>, "Michael Junge"

<MXJ2 @ nrc.gov>

Date:

02/05/2007 11:03:27 AM

Subject:

Cap reduction factor issue Gentlemen, I managed to consult with my engineers. They point out that we could avoid the argument about the capacity reduction factor completely if Amergen measured the shape of the vessel and then modeled it using the measured shape and conservative thickness values. If a realistic finite element analysis came out with good margins in terms of thickness, we feel that this would be much more reassuring that a study relying on a modified capacity reduction factor. Sandia's refusal to use the modified capacity reduction factor is still a huge concern.

For your information, I attach the report from Stress Engineering stating that a realistic analysis would be the most accurate and would be state of the art. Please carefully consider requiring the new analysis by AmerGen to be a state of the art study that includes measurement of the shape of the vessel.

Regards Richard Webster Staff Attorney Rutgers Environmental Law Clinic 123 Washington Street Newark, NJ 07102 Phone: 973-353-5695 Fax: 973-353-5537 CONFIDENTIAL LEGAL COMMUNICATION/WORK PRODUCT This e-mail may contain privileged and confidential attorney-client communications and/or attorney work product. If you receive this e-mail inadvertently, please reply to the sender and delete all versions on your system.

Thank you.

CC:

"Paul Gunter" <pgunter@nirs.org>, <may@ nrc.gov>

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Cap reduction factor issue 02/05/2007 11:02:23 AM "Richard Webster" <rwebster@kinov.rutgers.edu>

rwebster@kinov.rutgers.edu Recipients nrc.gov OWGWPO01.HQGWDO01 DJAI (D. Ashley)

HGA (Hansraj Ashar) nrc.gov TWGWPO04.HQGWDOO1 MAY CC (Mitzi Young) nrc.gov kpl-po.KPDO MCM (Michael Modes) nrc.gov OWGWPO04.HQGWDO01 MXJ2 (Michael Junge) nirs.org pgunter CC (Paul Gunter)

Post Office OWGWPOOI.HQGWDOOI TWGWPO04.HQGWDO01 kpl-po.KPIDO OWGWPO04.HQGWDO01 Files MESSAGE Stress Final Report.pdf Mime.822 Options Expiration Date:

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[D. Ashley-strDinal

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STRESS ENGINEERING SERVICES INC.

13800 Westfair East Drive, Houston, Texas 77041-1101 Phone: (281) 955-2900 Fax: (281) 955-2638 Website: www.stress.com HOUSTON CINCINNATI NEW ORLEANS CHICAGO SENIOR PRINCIPALS President Joe R, FrOIwl, PhD., PE, Senorr Vice Pr-e,,t W ThoMa-AWbdI P E Vice Presidents Rorld O Yong Ph, D 1

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Robert E Wolk. PE July 15, 2006 Mr. Richard Webster Staff Attorney Rutgers Environmental Law Clinic 123 Washington Street Newark, NJ 07102 Tel: 973 353-5695 rwebster@kinoy.r utqers.com SES Project No.: 131377

Subject:

CursoryCheck of Structural Analyses, Oyster Creek Drywell Vessel

Dear Mr. Webster:

Recently, you requested that Stress Engineering Services, Inc. consider several documents that you provided and others that were made available to us through internet link references from the U.S. Nuclear Regulatory Commission.

These documents concern the license renewal of the Oyster Creek Nuclear Generating Station.

One issue of contention in the license renewal at hand is whether the corroded drywell shell retains adequate strength for continued service.

Your specific instructions were to review the structural analyses and comment on the approach used to assess their adequacy. Thus, we did not address any issues related to either the preexisting corrosion damage or potential ongoing corrosion of the vessel, unless it was salient to our review of the structural analysis work.

This report contains two sections.

The first section addresses the general structural analysis methods and results.

The second section addresses the ASME Code provisions. In both sections, it is important to note that our comments and opinions are based on a severely limited review that only touches the highlights of the respective subjects. A mere detailed review is needed to address these subjects with the depth of study necessary to uncover the fundamental differences between the work that was done in support of the license and the state-of-the-art in structural analysis.

Structural Analyses At issue is the structural adequacy of the drywell shell, which has the shape of an inverted light bulb. The primary structural concern is the drywell shell's ability to resist buckling with an adequate margin for continued safe operation.

The structural analysis results offered by AmerGen were obtained using typical techniques for the 'period of time in which the analyses were performed.

Due to the limited computational power that was readily available at the time, the computer-aided analysis performed by General Electric (GE) utilized relatively small slices of DESIGN

  • TESTING
  • ANALYSIS

D. As hley - Sýtress Final Report.pdf Pa-ge 21 Mr. Rdchad WebstEr Iagers Envi ronmental Law Ci nic July 15, 2006 the vessel, idealized geometries (perfect spheres, cylinders, etc.), and required computationally efficient calculation techniques. Calculated buckling load behaviors for the idealized geometries were subsequently adjusted using assumptions or "capacity reduction factors" for surface irregularities, plasticity, and local buckling; and the resulting adjusted values were taken as representative of the actual buckling load.

GE compared the calculated buckling loads with the imposed loads, and safety margins were determined for comparison to ASME Code mininum requirerments.

Primarily because of these computational limitations, the finite element analysis performed by GE on the drywall vessel may not be adequate to capture its global behavior, which may be sorre combination of symmetrical and anti-symmetrical buckling.

The state-of-the-art has progressed far beyond the methods available to structural analysts in the early 1 990s. Today, when reconstructing or reverse engineering existing structures, it is routine to use laser devices to generate "point clouds" that fully define the surfaces of pressure vessels, including any irregularities.

The point clouds are digitalized, and the digitized information is converted into a mathematical representation of the actual surface shape, which is subsequently utilized for full three-dimensional modeling.

Since the resulting models account for actual surface waviness, unevenness, bulges, facets, and other potentially deleterious geometric surface conditions, there is no longer any need to resort to the use of "capacity reduction factors" to determine buckling loads, as the GE analysts were forced to do.

The digitized surface is converted into a form suitable for meshing and further processing using finite elerment analysis (FEA). The mesh areas are then assigned the corroded thicknesses at the specific areas where they actually occur, and any future corrosion allowance is subtracted from the thickness at this time. The FEA mesh density would then be generated as fine as needed to capture the stiffness that resists buckling. The simulated loads are then applied and the buckling load and shape are directly calculated without needing imposed perturbations or anything except the measured geometry and thicknesses.

Utilization of point cloud surface mapping techniques along with measurements that represent the actual wall thickness is thought to give the most accurate structural analysis results possible, with the fewest assumptions, using current technology. Three-dimension al thin shell analyses can be done today with few assumptions concerning stiffness and in a way that complies with Case N-284-1-1 320.

ASMIE Code1 Provisions At issue is whether the Code is the best tool available for determining the drywell's fitness for continued service.

In general, the Code establishes rules of safety relating only to pressure integrity and governing the construction2 of boilers, pressure vessels, transport tanks, and nuclear components.

Its

' ASIA E BoilEr aid Ressure Vesse Code, Sectiion Ill, Nudear Corrponents, and Section VIll, Rilesfor Construction of Pressre Vessds, Amei can Sod ety of M echanica Engineers, Three Park Avenuea New York, NY 10016 2 Construction, as used in the Code, isai dl-indusivetermcomprising materias, design, faebtclion, exanination, inspection, testing, certification, and pressure rdief.

Stress Engineering Services, Inc.

Page 2 SES Project No.: 131377

Pftý.D AýSley -S-tre--s-s Final Report.pdfP Mr. Rc:ad Webster Rutgers Environmenta LaN Clinic July 15, 2006 wording allows for some latitude in design and analysis methods, anticipates that deterioration of pressure vessels, will occur, requires the use of engineering judgment, and recognizes the inevitability of technological progress in design and analysis methods.

The following statements, which we excerpted from the FOREWORD of the current edition of the ASME Boiler and Pressure Vessel Code, support this contention.

"The Committee's function is to establish rules of safety, relating only to pressure integrity, governing the construction of boilers, pressure vessels, transport tanks and nuclear components, and inservice inspection for pressure integrity of nuclear components and transport tanks, and to interpret these rules when questions arise regarding their intent...

With few exceptions, these rules do not, of practical necessity, reflect the likelihood and consequences of deterioration in service relating to specific service fluids or external operating environments. Recognizing this, the Committee has approved a wide variety of construction rules in this Section to allow the user or his designee to select those which will provide a pressure vessel having a margin for deterioration in service so as to give a reasonably long, safe period of usefulness. Accordingly, it is not intended that this Section be used as a design handbook; rather, engineering judgment must be employed in the selection of those sets of Code rules suitable to any specific service or need...

The Committee recognizes that tools and techniques used for design and analysis change as technology progresses and expects engineers to use good judgment in the application of these tools."

Clearly, the authors of the Code never intended that its rules be used as the only arbiter of pressure vessel structural integrity.

Neither did the authors intend the rules be used to extend, possibly unreasonably, the useful life a significantly corroded nuclear pressure vessel such as the drywell.

Nonetheless, sorm continue to rely on Code construction rules for these purposes.

They continue to do so despite the existence of tools such as three-dimensional thin shell analysis that have proven to be more than adequate for nuclear applications when applied in the presence of seasoned engineering judgment.

Respectfully Submitted, Richard C. Biel, P. E.

Staff Consultant Stress Engineering Services, Inc.

J. Kirk Brownlee, P. E.

Staff Consultant Stress Engineering Services, Inc.

Stress Engineering Sevices, Inc.

Page 3 SIES Project No.: 131377