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Youngblood, R.W.; Papazoglou, I.A.
Brookhaven National Lab., Upton, NY (USA)1982
Brookhaven National Lab., Upton, NY (USA)1982
AbstractAbstract
[en] The purpose of this paper is to describe the BNL review process applied to the reliability analyses of Auxiliary Feedwater Systems (AFWS) submitted by operating license applicants to NRC in order to satisfy the pertinent Standard Review Plan requirements. Some generic comments on the availability characteristics of the AFWS are also presented. This work represents an application of a quantitative reliability goal to the regulatory process
Primary Subject
Source
1982; 3 p; American Nuclear Society winter meeting; Washington, DC (USA); 14 - 19 Nov 1982; CONF-821103--19; Available from NTIS., PC A02/MF A01 as DE82019452
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AbstractAbstract
No abstract available
Original Title
PWR
Primary Subject
Source
American Nuclear Society annual meeting; Las Vegas, NV, USA; 8 - 13 Jun 1980; CONF-800607--; Published in summary form only.
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Journal Article
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Journal
Transactions of the American Nuclear Society; ISSN 0003-018X;
; v. 34 p. 448-450

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AbstractAbstract
No abstract available
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Israel Nuclear Society, Yavne; Israel Health Physics Society; Radiation Research Society of Israel; Israel Society of Nuclear Medicine; 228 p; 1982; p. 102-103; Nuclear Societies of Israel joint annual meeting; Tel Aviv (Israel); 14-15 Dec 1982; Published in summary form only.
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Miscellaneous
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Nitzel, M.E.
Idaho National Engineering Lab., Idaho Falls (USA)1978
Idaho National Engineering Lab., Idaho Falls (USA)1978
AbstractAbstract
[en] The stress analysis performed on the 1''-PCC-76-A piping system inside containment penetration S-1A is described. Deadweight, thermal expansion, and seismic loads were considered. Results of this analysis show that the subject piping system will meet ASME Boiler and Pressure Vessel Code, Section III, Class 2 requirements provided that supports S8 and S9 are installed as recommended
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Source
11 Dec 1978; 270 p; REA-A--78-172; Available from NTIS., MF A01
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Report
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Turcotte, M.D.S.
Du Pont de Nemours (E.I.) and Co., Aiken, SC (USA). Savannah River Lab1983
Du Pont de Nemours (E.I.) and Co., Aiken, SC (USA). Savannah River Lab1983
AbstractAbstract
[en] Operation of L Reactor will necessitate annual cleaning of the L Area 186 basins. Alternatives are presented for sediment discharge due to 186-basin cleaning activities as a basis for choosing the optimal cleaning method. Current cleaning activities (i.e. removal of accumulated sediments) for the P, C and K-Area 186 basins result in suspended solids concentrations in the effluent waters above the NPDES limits, requiring an exemption from the NPDES permit for these short-term releases. The objective of mitigating the 186-basin cleaning activities is to decrease the suspended solids concentrations to within permit limits while continuing satisfactory operation of the basins
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Source
15 Sep 1983; 5 p; Available from NTIS, PC A02/MF A01 as DE84003028
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Report
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AbstractAbstract
[en] EDF operates 6 km of safety-classified steel cylinder reinforced concrete pipelines spread over 8 PWR nuclear reactors located on the sea coast. These pipelines, placed in galleries, convey approximately 3000 m3/h of sea water under a pressure of 4 bar. They have been in operation since the mid eighties or early nineties. Their service life is limited by different scenarios of corrosion by pitting due to the presence of chlorides from sea water. Pipelines are subjected to frequent visual checks that can lead to immediate temporary reinforcement and subsequent replacement. In addition, a diagnosis methodology was developed in order to better anticipate the maintenance operations and in order to assess the remaining service life of pipelines. This methodology combines autopsies of replaced pipes with periodic campaigns of exhaustive half-cell potential mapping. For exhaustive campaigns, the grid spacing was 30 cm x 30 cm, refined to 10 cm x 10 cm in singular zones, on the entire external concrete surface of pipelines, which represents around 6x105 measurement points for 6 km of pipelines. Robust specifications were drawn up for the measurement method and the interpretation of the results, initially based on RILEM and ASTM recommendations and then significantly reinforced based on operational feedback. These specifications ensure the implementation and the interpretation of half-cell potential mapping can be carried out on a very large scale and enable the comparison of results between successive campaigns. The diagnosis methodology was a decisive factor in the planning of a preventive maintenance strategy which would enable a pipeline service life of 60 years. (authors)
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2015; 37 p; Fontevraud 8: Conference on Contribution of Materials Investigations and Operating Experience to LWRs' Safety, Performance and Reliability; Avignon (France); 15-18 Sep 2014; 7 refs.; Available from the INIS Liaison Officer for France, see the 'INIS contacts' section of the INIS website for current contact and E-mail addresses: http://www.iaea.org/INIS/contacts/
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Miscellaneous
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[en] The Service Water Assistance Program was developed to provide utility service water system engineers with a mechanism to quickly and efficiently address service water issues. Since its inception, its ability to assist utilities has resulted in a reduction in the operations and maintenance costs associated with service water systems and has provided a medium for EPRI awareness of industry service water issues
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Source
Anon; 874 p; ISSN 0097-2126;
; 1995; p. 511-513; American Power Conference; Chicago, IL (United States); 57. annual American power conference; Chicago, IL (United States); 18-20 Apr 1995; American Power Conference, Illinois Inst. of Technology, Technology Center, Chicago, IL 60616 (United States)

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Book
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AbstractAbstract
[en] It has been known that drain pumps in nuclear power plants may suffer cavitation under transient turbine load reductions. Although increasing the size and height of the drain tank can prevent it, such provisions are often not practical, and in some instances even not possible. The paper presented explores some conceptual protective methods, and briefly discusses their pros and cons as applied to both drain pumping forward and backward systems. The method of quantitative determination of design parameters required for each protective method is either referred to or derived. Based on simplicity, economy, and reliability, it is concluded that the drain tank pressure decay control system appears to be the most promising protective method for the drain pumping forward system, whereas either the continuous feedwater injection system or the continuous drain subcooling system is the optimum method for the drain pumping backward system
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Source
ASME Winter annual meeting; Houston, TX, USA; 30 Nov 1975
Record Type
Journal Article
Literature Type
Conference
Journal
Journal of Engineering for Power; v. 98(3); p. 401-410
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McKay, T.K.; Fors, R.M.
Idaho National Engineering Lab., Idaho Falls (USA)1978
Idaho National Engineering Lab., Idaho Falls (USA)1978
AbstractAbstract
[en] The purpose of the review was to examine all remaining lines of the LOFT emergency core coolant facility piping outside of containment and with a diameter of less than two inches, not analyzed by ITT Grinnell Corporation. Because of a discrepancy on the Grinnell analysis, lines 3''-ECCV-10-A, 2''-ECCV-10-A and 2''-ECCV-11-A were included in this review. In addition, some lines from other systems which connected to the ECC piping were also examined, as listed on the isometric sketches in this report. An on-site ''walk-through'' was made first to verify existing restraint and valve locations. Very short stub lines were eliminated by inspection. All remaining lines, together with the lines analyzed by Grinnell and lines being currently analyzed by R. M. Fors of the Applied Mechanics Branch constitute a complete analysis of the ECC facility piping as now listed in LOFT Specification P-1, Line Designation Tables
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31 Aug 1978; 38 p; Available from NTIS., PC A03/MF A01
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Report
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AbstractAbstract
No abstract available
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Canadian Nuclear Association, Toronto, Ontario; p. 12; nd; p. 12; 17. annual international conference of the Canadian Nuclear Association; Montreal, Canada; Jun 1977; Available from Canadian Nuclear Association, Toronto; Published in summary form only.
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