Nuclear Services/Field Services - Westinghouse Nuclear

The Internal Core-spray Examination System (ICESys™) was designed to improve the quality of examinations of the core-spray piping system in boiling water reactor (BWR) nuclear power plants, while providing significant critical-path savings and mitigating …

The Materials Initiative

Jun 01, 2015· system components and piping. Other plant events over the last three years involving steam generator tubes, boiling water reactor (BWR) vessel internals and other pressure boundary, vessel internals, and fuel materials suggest that the nuclear industry has not been able to consistently anticipate and manage materials problems as well as it could.

Inspection and Evaluation Guidelines for Light Water ...

Takeuchi, Kimihito, Iizuka, Naoto, Kameyama, Masashi, Fujimori, Haruo, Motora, Yuichi, and Koyama, Koji. "Inspection and Evaluation Guidelines for Light Water Reactor Core Internals in Japan." Proceedings of the ASME 2002 Pressure Vessels and Piping Conference. Service Experience and Failure Assessment Applications. Vancouver, BC, Canada.

REACTOR VESSEL INTERNALS SEGMENTATION EXPERIEN- CE …

6 TECHNOLOGICAL ENGINEERING, Volume X, number 2/2013, ISSN 1336 - 5967 REACTOR VESSEL INTERNALS SEGMENTATION EXPERIEN-CE USING MECHANICAL CUTTING TOOLS Petr Pospíšil, MSc. Received 12 june 2013 ...

Probabilistic safety assessment of BWR shroud-support ...

To assure structural integrity of the shroud-support structure of a BWR in Taiwan, a serial plastic collapse analyses deduced from the EPRI's guidelines have been carried out for two circumferential weldments named H8 and H9 shown in Fig. 2, in which H8 connects the core shroud with a horizontal support plate and H9 connects the support plate with the reactor pressure vessel.

BWR primary coolant pressure boundary license renewal ...

@article{osti_10121103, title = {BWR primary coolant pressure boundary license renewal industry report; revision 1. Final report}, author = {Braden, D and Stancavage, P}, abstractNote = {The U.S. nuclear power industry, through coordination by the Nuclear Management and Resources Council (NUMARC), and sponsorship by the U.S. Department of Energy (DOE) and the Electric Power …

BWR Sparger Replacement Design Criteria (BWRVIP- 1 6NP)

BWR Vessel and Internals Project Internal Core Spray Piping and Sparger Replacement Design Criteria (BWRVIP-16NP) TR-106708NP Research Project B501 Final Report, February 2000 Prepared by: BWRVIP Repair Committee Sargent & Lundy LLC Prepared for BOILING WATER REACTOR VESSEL & INTERNALS PROJECT and EPRI 3412 Hillview Ave.

EPRI's Boiling Water Reactor Vessel and Internals Project ...

EPRI's Boiling Water Reactor Vessel and Internals Project (BWRVIP) is continuing a long-term effort to revise and optimize inspection intervals for BWR internal components. The existing inspection guidelines were written more than 10 years ago based on the best available information at the time.

AMP108 BWR PENETRATIONS - Nucleus

ELECTRIC POWER RESEARCH INSTITUTE, BWRVIP-100, Revision 1-A: BWR Vessel and Internals Project, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Core Shrouds, EPRI Technical Report 3002010541, November 2017

(PDF) Reactor Vessel Internals Segmentation Experience ...

Jun 12, 2013· The BR3 PWR is a small nuclear power plant (thermal power 40.9 MWth, net electrical power output 10.5 MWe), designed in the late fifties and started in 1962.

Ageing Management Program of Reactor Pressure Vessel ...

Ageing Management Program of Reactor Pressure Vessel Internals components in a BWR Nuclear Power Plant. ... BWR ´s Internal Experience LV NPP U1 andU2 RIC ´s Inspections Results. (IVVI) Specific information. ... core spray internal Piping Yes 304L welds 308L 18 304L welds 308L 76 Support ring alloy 600 Shroud Yes BWR VIP

Internal Core-spray Examination System

The Internal Core-spray Examination System (ICESys™) was designed to improve the quality of examinations of the core-spray piping system in boiling water reactor (BWR) nuclear power plants, while providing significant critical-path savings and mitigating radiation exposure during refueling outages. The ICESys performs ultrasonic

IGALL AMP BWR VESSEL INTERNALS - gnssn.iaea.org

[14]ELECTRIC POWER RESEARCH INSTITUTE, BWRVIP-19-A: BWR Vessel and Internals Project, Internal Core Spray Piping and Sparger Repair Design Criteria, EPRI Technical Report 1012114, September 2005 [15]ELECTRIC POWER RESEARCH INSTITUTE, BWRVIP-25, Revision 1: BWR Core Plate Inspection and Flaw Evaluation Guidelines, EPRI Report 3002005594 ...

Boiling Water Reactor Services - Westinghouse Nuclear

Boiling Water Reactor Services U.S. BWR Service Center in Chattanooga, Tennessee (USA) ... BWR vessel internals project (BWRVIP) required needs. Services include: • Standard IVVI (two platform services) ... • Core spray piping automated UT (2011) • Jet pump inside diameter (ID) UT inspection ...

BWR/PWR IN-VESSEL INSPECTION WORKSHOP

BWR/PWR IN-VESSEL INSPECTION ... –Core shrouds –Core spray piping –Jet pump beams –Jet pump inlet piping –Jet pump restrainer brackets –Top guides –Steam dryers ... boiling water reactor (BWR) vessel internals and other pressure boundary, vessel internals, and fuel materials suggest that the ...

BWR Vessel and Internals Project, Internal Core Spray ...

BWR Vessel and Internals Project Internal Core Spray Piping and Sparger Repair Design Criteria (BWRVIP-19NP) TR-1 06893NP Research Project B501 Final Report, February 2000 Prepared by: BOILING WATER REACTOR VESSEL AND INTERNALS PROJECT REPAIR COMMITTEE GE NUCLEAR ENERGY Prepared for BOILING WATER REACTOR VESSEL & INTERNALS PROJECT …

GE BWR - Wikipedia

History. The progenitor of the BWR line was the 5 MW Vallecitos Boiling Water Reactor (VBWR), brought online in October 1957.. BWR-1. BWR Type 1 (BWR-1, BWR/1): In 1955 GE developed their original VBWR design into the 197 MW Dresden 1 (6×6, 7×7) reactor, embodying the first iteration of GE's BWR/1 design. Dresden 1 used forced circulation (via external recirculation pumps) and a …

BWR Vessel and Internals Project Update

Jun 02, 2015· address BWR reactor vessel and internals material condition issues • The goal was to lead industry toward proactive generic resolution of vessel and internals material condition issues with generic, cost-effective strategies • Intergranular Stress Corrosion Cracking (IGSCC) in austenitic piping was a major issue

DISTRIBUTION for NRR Director's Quarterly Status Report ...

A special industry review group (Boiling Water Reactor Vessels and Internals Project - BWRVIP) was formed to focus on resolution of reactor vessel and internals degradation. This group was instrumental in facilitating licensee responses to NRC's GL 94-03. The NRC evaluated the review group's reports,

Age-related degradation of boiling water reactor vessel ...

A.G. Ware and V.N. Shah ~Age-related degradation of BWR internals Table 2 History of IGSCC in BWR reactor internals 55 Location Date detected Material Contributing factors Jet pump hold-down beam 1970 Alloy X-750 Core spray sparger 1978 Stainless steel Supply junction box between 1982 Stainless steel vessel wall and shroud Core spray sparger ...

IASCC Evaluation Method for Irradiated Core Internal ...

Jan 10, 2011· "IASCC Evaluation Method for Irradiated Core Internal Structures in BWR Power Plants." Proceedings of the ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference . ASME 2010 Pressure Vessels and Piping Conference: Volume 6, Parts A and B .

BWRVIP-34NP-A: BWR Vessel and Internals Project

Weld Overlay Repair of Vessel Internal Core Spray Piping. EPRI, Palo Alto, CA: 2008. 1016377NP. This report is based on the following previously published report: BWR Vessel and Internals Project, Technical Basis for Part Circumference Weld Overlay Repair of Vessel Internal Core Spray Piping (BWRVIP-34). EPRI, Palo Alto, CA: 1997. TR-108198,

Repair and replacement of reactor internals for plant life ...

A number of internals were repaired or replaced including the core shroud support which was welded to the bottom of the reactor pressure vessel. The project verifies that it is fully possible to carry out complicated inspection and repair work inside a nuclear pressure vessel which has been in operation for more than 20 years.

Turn-key Reactor Internals Segmentation Services

Turn-key Reactor Internals Segmentation Services GE Nuclear Energy Capabilities ... BWR Components Dismantled and Segmented • Steam dryer and separators • Shroud • Guide rods • Feedwater spargers • Core spray piping • Top guide • Shroud • Core Plate • ICM (Incore Monitor Housing) guide tubes and stabilizers

2014 Portfolio: Boiling Water Reactor Vessel and Internals ...

Boiling Water Reactor Vessel and Internals Project (QA) Program Overview . Program Description . As boiling water reactors have aged, various forms of operation-limiting stress corrosion cracking have appeared, first in the recirculation piping, then in the reactor pressure vessel internals. Typically, poor …

BWRVIP-1 8NP, Revision 2: BWR Vessel and Internals Project

BWRVIP-18NP, Revision 2: BWR Vessel and Internals Project BWR Core Spray Internals Inspection and Flaw Evaluation Guidelines 1025059NP Final Report, April 2012 EPRI Project Manager K. Wolfe This document does NOT meet the requirements of 1 OCFR50 Appendix B, 1 OCFR Part 21, ANSI N45.2-1977 and/or the intent of ISO-9001 (1994).

Assessment and management of ageing of major nuclear …

structural integrity of these reactor pressure vessel internals throughout NPP service life, in spite of several ageing mechanisms, is essential for plant safety. The work of all contributors to the drafting and review of this publication, identified

BWR core internals replacement - ScienceDirect

In addition to the core shroud, the majority of the internal components made of 304 SS were replaced. These included (1) core shroud, (2) top guide, (3) core plate, (4) core spray spargers, (5) feed water spargers, (6) jet pumps, (7) DP/LC pipe, (8) ICM guide tubes (9) internal pipes and (10) nozzle safe end which is connected to these components, as shown in Fig. 1.