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in subjects: "In-Service Inspection"

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Reviews of ASME Section 11 pump and valve relief requests: Post Generic Letter 89-04

This paper presents a discussion of ASME Section 11 Pump and Valve Inservice Testing relief request reviews by the NRC and their contractors. Topics that will be discussed include the scope of USNRC reviews in Technical Evaluation Reports (TERs) (and Safety Evaluation, SEs); including the basis for granting relief requests, the status of relief requests in IST Program updates, and the Generic Letter 89-04 approval process; and the level of technical detail required in submitted programs. This p… more

Date: January 1, 1992

Creator: DiBiasio, A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Evaluation of Inservice Inspection Examinatiions

In order to evaluate the effectiveness of Section 11, Division 1, Rules for Inservice Inspection of Nuclear Power Plant Components,'' of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code examinations, 26 inservice inspection (ISI) summary reports from 24 facilities were reviewed. It was found that these ASME Code examinations and tests are instrumental in revealing indications and defects in welds and plant components. In addition, this study uncovered that fac… more

Date: May 1990

Creator: Aldrich, D. A. & Cook, J. F.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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The development of code inservice inspection (ISI) requirements for Low Temperature Heavy Water Reactors (LTHWR)

DOE Savannah River Field office requested that the American Society of Mechanical Engineers (ASME) develop rules for inservice inspection (ISI) of Savannah River Site (SRS) Low Temperature Heavy Water Reactors (LTHWR's) in January 1990. The request is part of the SRS Reactor Safety Improvement Program (RSIP). RSIP will implement an ASME B PV Code Section XI based ISI program after restart of K Reactor. The establishment of a Code based ISI program at SRS will affect a transition from a standing… more

Date: January 1, 1992

Creator: Cowfer, C.D.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Application of ultrasonic waves to assess grain structure in cast stainless steel

Although the ASME code requires the inspection of cast stainless steel (CSS) piping in nuclear reactors, it has not been possible to demonstrate unambiguously that current inspection techniques are adequate. Ultrasonic inspection is difficult because the microstructure of CSS can vary considerably, from elastically isotropic with equiaxed, relatively small grains to elastically anisotropic with a columnar grain structure to a combination of the two. For the near term, improvements that may incr… more

Date: April 1, 1985

Creator: Kupperman, D.S.; Reimann, K.J. & Abrego-Lopez, J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Impact of inservice inspection on the reliability of nuclear piping

The reliability of nuclear piping is a function of piping quality as fabricated, service loadings and environments, plus programs of continuing inspection during operation. This report presents the results of a study of the impact of inservice inspection (ISI) programs on the reliability of specific nuclear piping systems that have actually failed in service. Two major factors are considered in the ISI programs: one is the capability of detecting flaws; the other is the frequency of performing … more

Date: December 1, 1983

Creator: Woo, H.H.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Automatic ultrasonic testing and the LOFT in-service inspection program

An automatic ultrasonic testing system has been developed which significantly improves the flaw indication detection and characterization capability over the capability of conventional volumetric examination techniques. The system utilizes an accurately located ultrasonic sensor to generate the examination data. A small computer performs and integrates control and data input/output functions. Computer software has been developed to provide a rigorous method for data analysis and ultrasonic imag… more

Date: January 1, 1980

Creator: Hunter, J.A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Regulatory analysis for the resolution of Generic Safety Issue 29: Bolting degradation or failure in nuclear power plants

Generic Safety Issue (GSI)-29 deals with staff concerns about public risk due to degradation or failure of safety-related bolting in nuclear power plants. The issue was initiated in November 1982. Value-impact studies of a mandatory program on safety-related bolting for operating plants were inconclusive: therefore, additional regulatory requirements for operating plants could not be justified in accordance with provisions of 10 CFR 50.109. In addition, based on operating experience with boltin… more

Date: September 1, 1991

Creator: Chang, T.Y.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Acoustic monitoring systems tests at Indian Point Unit 1. Final report

This report describes the results of a program to test acoustic monitoring systems on Indian Point Unit No. 1 under actual plant operating conditions, less the reactor core. The two types of systems evaluated were the monitoring of acoustic emissions generated by growing flaws and the monitoring of acoustic signals from leaks.

Date: December 1, 1979

Creator: Smith, J. R.; Rao, G. V. & Craig, J.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Transactions of the nineteenth water reactor safety information meeting

This report contains summaries of papers on reactor safety research to be presented at the 19th Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel in Bethesda, Maryland, October 28--30, 1991. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, USNRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the Electric Power Res… more

Date: October 1, 1991

Creator: Weiss, A. J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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State-of-practice review of ultrasonic in-service inspection of Class I system piping in commercial nuclear power plants

The Pacific Northwest Laboratory conducted a survey to determine the state of practice of ultrasonic in-service inspection of primary system piping in light water reactors. Personnel at four utilities, five inspection organizations, and three domestic reactor manufacturers were interviewed. The intention of the study was to provide a better understanding of the actual practices employed in in-service inspection of primary system piping and of the difficulties encountered.

Date: August 1, 1982

Creator: Morris, C. J. & Becker, F. L.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Evaluation of a hanging core support concept for LMR application

The paper describes an innovative design concept for a liquid metal reactor (LMR) core support structure (CSS). A hanging core support structure is described and analyzed. The design offers inherent safety features, constructability advantages, and potential cost reductions. Some safety considerations are examined which include the in-service inspection (ISI), the backup support system and the structural behavior in a hypothetical case of a broken beam in the core support structure.

Date: January 1, 1985

Creator: Burelbach, J. P.; Cha, B. K.; Huebotter, P. R.; Kann, W. J.; Pan, Y. C.; Saiveau, J. G. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Surveillance and in-service inspection (SISI) program at FFTF

Assurance of the integrity of the sodium coolant pressure boundaries of the Fast Flux Test Facility systems and components is essential for safe operation. A program has been developed to monitor the integrity of the coolant boundaries and certain plant conditions. Specific equipment and features have been designed into the plant for monitoring. The purpose of SISI is to prevent failures or minimize their consequences through early detection. The program which administers the requirements for m… more

Date: January 1, 1980

Creator: Conrads, T. J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Results of LWR snubber aging research

This report describes the aging research results and recommendations for snubbers used in commercial nuclear power plants. Snubbers are safety-related devices used to restrain undesirable dynamic loads at various piping and equipment locations in nuclear power plants (NPPs). Each snubber must accommodate a plant's normal thermal movements and must be capable of restraining the maximum off-normal dynamic loads, such as a seismic event or a transient, postulated for its specific location. Th… more

Date: May 1, 1992

Creator: Brown, D P; Werry, E V & Blahnik, D E

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Evaluation of flaw characteristics and their influence on inservice inspection reliability. [PWR; BWR]

This report describes the results of the first year's effort of a five year program which is being conducted by Battelle, Pacific Northwest Laboratories, on behalf of the US Nuclear Regulatory Commission. This initial effort was directed toward identification and quantification of inspection uncertainties, which are likely to occur during inservice inspection of LWR primary piping systems, and their influence on inspection reliability. These experiments were conducted on 304 stainless steel sam… more

Date: January 1, 1980

Creator: Becker, F. L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Reactor safety research programs. Quarterly report, July 1-September 30, 1979

The programs include: ultimate heat sink performance measurement; experimental verification of steady state codes: Task A - irradiation results and Task C - code development; graphite nondestructive testing; acoustic emission-flaw relationship for in-service monitoring of nuclear pressure vessels; fuel subassembly procurement and irradiation test program; report of resident engineer at Cadarache, France; core thermal model development; integration of nondestructive examination reliability and f… more

Date: March 1, 1980

Creator: Hooper, J.L. (comp.)

Item Type: Report

Partner: UNT Libraries Government Documents Department

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In-service filter testing

This report contains the observations, test results, and conclusions of three separate in-service tests beginning in November 1979 and concluding in September 1983. The in-service tests described in this report produced encouraging results on filters constructed with fiberglass medium containing 5% Nomex and separators of aluminum foil coated with a thin film of vinyl-epoxy polymer. Filters containing medium with Kevlar fiber additives demonstrated they merited further evaluation. Other types o… more

Date: April 29, 1985

Creator: Terada, K.; Woodard, R.W. & Jensen, R.T.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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A STRUCTURAL IMPACT ASSESSMENT OF FLAWS DETECTED DURING ULTRASONIC EXAMINATION OF TANK 15

Ultrasonic (UT) inspection of Tank 15 was conducted between April and July 2007 in accordance with the Tank 15 UT inspection plan. This was a planned re-inspection of this tank, the previous one was performed in 2002. Ten cracks were characterized in the previous examination. The re-inspection was performed to verify the present models and understanding for stress corrosion cracking. During this re-examination, one indication that was initially reported as a 'possible perpendicular crack <25… more

Date: August 21, 2008

Creator: Wiersma, B & James Elder, J

Item Type: Report

Partner: UNT Libraries Government Documents Department

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ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM- 2007

Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. The 2007 inspection program revealed that the structural integrity and waste confinement capability of the Savannah River Site waste tanks were maintained. A very small amount of material had seeped from Tank 12 from a previously identified leaksite. The material observed had dried on the tank wall and did not reach the annulus floor. A total o… more

Date: June 5, 2008

Creator: West, B & Ruel Waltz, R

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Innovative Electromagnetic Sensors for Pipeline Crawlers Progress Report: October 2005 - March 2006

Internal inspection of pipelines is an important tool for ensuring safe and reliable delivery of fossil energy products. Current inspection systems that are propelled through the pipeline by the product flow cannot be used to inspect all pipelines because of the various physical barriers they encounter. Recent development efforts include a new generation of powered inspection platforms that crawl slowly inside a pipeline and are able to maneuver past the physical barriers that can limit inspect… more

Date: May 4, 2006

Creator: Nestleroth, J. Bruce

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Nondestructive and Destructive Examination Studies on Removed-from-Service Control Rod Drive Mechanism Penetrations

Studies conducted at the Pacific Northwest National Laboratory (PNNL) in Richland, Washington, focused on assessing the effectiveness of nondestructive examination (NDE) techniques for inspecting control rod drive mechanism (CRDM) nozzles and J-groove weldments. The primary objectives of this work are to provide information to the U.S. Nuclear Regulatory Commission (NRC) on the effectiveness of NDE methods as related to the in-service inspection of CRDM nozzles and J-groove weldments and to enh… more

Date: June 7, 2007

Creator: Cumblidge, Stephen E.; Crawford, Susan L.; Doctor, Steven R.; Seffens, Rob J.; Schuster, George J.; Toloczko, Mychailo B. et al.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Initial acceptance test experience with FFTF plant equipment

The purpose of this paper is to examine the initial acceptance test experience of certain pieces of auxiliary equipment of the Fast Flux Test Facility (FFTF). The scope focuses on the DHX blowers and drive train, inert gas blowers, H and V containment isolation valves, and the Surveillance and In-service Inspection (SISI) transporter and trolley. For each type of equipment, the discussion includes a summary of the design and system function, installation history, preoperational acceptance testi… more

Date: September 1, 1978

Creator: Brown, R. K.; Coleman, K. A.; Mahaffey, M. K.; McCargar, C. G. & Young, M. W.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Aging management of safety-related concrete structures in nuclear power plants

The Structural Aging Program has the overall objective of providing the US Nuclear Regulatory Commission with an improved basis for evaluating nuclear power plants for continued service. In meeting this objective, a materials property data base is being developed as well as an aging assessment methodology for concrete structures in nuclear power plants. Furthermore, studies are well under way to review and assess inservice inspection techniques for concrete structures and to develop a methodolo… more

Date: January 1, 1990

Creator: Naus, D.J.; Oland, C.B. (Oak Ridge National Lab., TN (USA)) & Arndt, E.G. (Nuclear Regulatory Commission, Washington, DC (USA))

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Reactor safety research programs. Quarterly report, January 1--March 31, 1979. [BWR; PWR]

Progress is summarized in the following LWR safety-related studies: (1) ultimate heat sink performance; (2) verification of steady-state fuel performance computer codes; (3) acoustic emission-flow relationship for pressure vessel monitoring; (4) fuel subassembly procurement and irradiation; (5) steam generator tube integrity prediction; (6) core thermal model development; and (7) integration of nondestructive examination reliability and fracture mechanics. (HDR)

Date: May 1, 1979

Creator: Hooper, J.L. (comp.)

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Summary report for 1990 inservice inspection (ISI) of SRS 100-K reactor tank

The integrity of the SRS reactor tanks is a key factor affecting their suitability for continued service since, unlike the external piping system and components, the tanks are virtually irreplaceable. Cracking in various areas of the process water piping systems has occurred beginning in about 1960 as a result of several degradation mechanisms, chiefly intergranular stress corrosion cracking (IGSCC) and chloride-induced transgranular cracking. The purpose of this inspection was to determine if … more

Date: May 15, 1990

Creator: Morrison, J. M. & Loibl, M. W.

Item Type: Report

Partner: UNT Libraries Government Documents Department