1、REAFFIRMED June 19, 2015ANSI/ANS-59.51-1997 (R2015) This standard has been reviewed and reaffirmed with the recognition that it may reference other standards and documents that may have been superseded or withdrawn. The requirements of this document will be met by using the version of the standards
2、and documents referenced herein. It is the responsibility of the user to review each of the references and to determine whether the use of the original references or more recent versions is appropriate for the facility. Variations from the standards and documents referenced in this standard should b
3、e evaluated and documented. This standard does not necessarily reflect recent industry initiatives for risk informed decision-making or a graded approach to quality assurance. Users should consider the use of these industry initiatives in the application of this standard. REAFFIRMEDOctober 4, 2007 A
4、NSI/ANS-59.51-1997 (R2007)Secretariat American Nuclear Society Pn:pan:d by 1bc AIDericaa Nuclear Society StaDdards Coauaittee Workia these procedures are accredited by the Amer ican National Standards Institute, Inc., as meeting the criteria for American National Standards. The consensus committee t
5、hat approved the standard was balanced to ensure that competent, concerned, and varied interests have had an opportunity to participate. An American National Standard is intended to aid industry, consumers, governmental agencies, and general interest groups. Its use is entirely volun tary. The exist
6、ence of an American National Standard, in and of itself, does not preclude anyone from manufacturing, marketing, purchasing, or using products, processes, or procedures not conforming to the standard. By publication of this standard, the American Nuclear Society does not insure anyone utilizing the
7、standard against liability allegedly arising from or after its use. The content of this standard reflects acceptable practice at the time of its approval and publication. Changes, if any, occurring through develop ments in the state of the art, may be considered at the time that the standard is subj
8、ected to periodic review. It may be reaffirmed, revised, or withdrawn at any time in accordance with established procedures. Users of this standard are cautioned to determine the validity of copies in their possession and to establish that they are of the latest issue. The American Nuclear Society a
9、ccepts no responsibility for interpretations of this standard made by any individual or by any ad hoc group of individuals. Requests for interpretation should be sent to the Standards Department at Society Headquarters. Action will be taken to provide appropriate response in accordance with establis
10、hed procedures that ensure consensus on the inter pretation. Comments on this standard are encouraged and should be sent to Society Headquarters. Published by American Nuclear Society 555 North Kensington Avenue La Grange Park, IDinois 60526 USA Copyright 1997 by American Nuclear Society. All rights
11、 reserved. Any part of this standard may be quoted. Credit lines should read “Extracted from American National Standard ANSI/ANS-59.51-1997 with permission of the publisher, the American Nuclear Society: Reproduction prohibited under copyright convention unless written permission is granted by the A
12、merican Nuclear Society. Printed in the United States of America Foreword (This Foreword is not a part of American National Standard Fuel Oil Systems for Emergency Diesel Gener ators, ANSI/ANS-59.51-1997.) This standard is applicable to light water reactor nuclear power plants and is one of a series
13、 sponsored by the LWR Criteria Management Subcommittee (MC-1) intended to cover the design of auxiliary systems that support the operation of emergency diesel generator units. Other standards in this series that have been or are being developed by this working group are listed below: Proposed Standa
14、rd ANS-59.52 ANS-59.53 ANS-59.54 ANS-59.55 Subject Lubricating Oil Systems Starting Air Systems Combustion Air Systems Coolant Systems This standard interfaces with American National Standard Criteria for Diesel Generator Units Applied as Standby Power Supplies for Nuclear Power Generating Stations,
15、 ANSI/IEEE 387-1995, the current version of which was revised by the Nuclear Power Engineering Committee (IEEEINPEC). The scope of ANSI/IEEE 387-1995 includes “the fuel oil system from the fuel oil day tank to the engine, including filters and strainers between the day tank and the engine.“ However,
16、 no fluid system or component performance or design criteria are specified in that standard. To address these fluid system requirements, this revision to ANS-59.51 includes in its scope the pumps, tanks, piping and piping components, and instrumentation and control functions, as described herein. Ba
17、sed on discussions with the working group chairman for IEEE 387, it was agreed that the intent of that standard is to address only the overall qualifications and boundaries of the diesel generator auxiliary systems and not the specific performance or design criteria, which are addressed in ANS-59.51
18、. The purpose of this standard and the related standards is to provide guidance to nuclear plant owners, designers, manufacturers, regulatory authorities, and operators in the design of reliable, safety-related, onsite power systems for light water reactors. The reliability of the fuel oil system mu
19、st be considered when one attempts to satisfy the overall reliability requirements of the diesel generator units. This is particularly important if fuel oil systems have components that are shared between reactor units, and if the single failure criterion is applied. This standard can also be used f
20、or non-safety-related onsite power systems, with several changes to eliminate those requirements which would not normally apply to such equipment. For example, non-safety-related equipment would not normally have to meet American National Standard Single Failure Criteria for Light Water Reactor Safe
21、ty-Related Fluid Systems, ANSIIANS-58.9-1981 (R1987), the Class 1E Power Systems requirements of American National Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations, ANSI/IEEE 308-1992, and several of the requirements described in American National Standard Nuclear S
22、afety Criteria for Design of Stationary Pressurized WaterReactorPlants,ANSI/ANS-51.1-1983(R1988)andAmericanNationalStandardNuclear Safety Criteria for Design of Stationary Boiling Water Reactor Plants, ANSI/ANS-52.1-1983 (R1988), for safety related equipment, such as Seismic Category I. Other requir
23、ements referenced herein-such as American National Standard ASME Boiler and Pressure Vessel Code-1995, Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, and American National Standard Quality Assurance Program Requirements for Nuclear Facilities, ANSIIASME NQA-1-1994-whic
24、h normally apply to safety-related equipment but which are considered to enhance reliability, as well as the seven day fuel oil supply requirement, could be optional or modified to suit a particular application. This standard was initially issued by the American Nuclear Society in April 1976. It was
25、 revised in 1989 to conform to the latest revisions of ANS-51.1 and ANS-52.1, and to resolve -i-comments from previous ballots issued in 1982 for reaffirmation, in 1985 for withdrawal, and in 1986 for reaffirmation. This revision agrees with the definitions and requirements of American National Stan
26、dard Safety and Pressure Integrity Classification Criteria for Light Water Reactors, ANSIIANS-58.14-1993; ANS-51.1 ; ANS-52.1 ; cDTellt technology and practices; and information available from industry reports. U.S. Nuclear Regulatory Commission Regulatory Guide 1.137 endorsed ANSI Nl95-1976/ANS-59.
27、51 as providing an acceptable method for complying with the pertinent requirements of Title 10, “Energy,“ Code of Federal Regulations, Part 50, Appendix A, General Design Criterion 17, subject to some clarifications and additional requirements. This revision bas considered and incorporated these cla
28、rifications and requirements where appropriate. This revision to the standard has been prepared by Working Group ANS-59.51 of the American Nuclear Society Standards Committee, which had the following membership: S. A Shuman, Chairman, Connltant J. M. Home. Cr Cameron Corporation W. J. McFarland, PEC
29、O Energy Company T. O Brien, Commonweahh the word “should“ denotes a recommendation; and the word “may“ denotes permission, neither a requirement nor a recom mendation. tanks. All tanks used to support diesel genera tor operation; where used without modifiers, the 1 Numbers in brackets refer to corr
30、esponding numbers in Section 7, References. word covers day, integral, and supply tanks. 1 American National Standard ANSI/ANS-59.51-1997 day tank. A fuel oil tank or tanks which pro vides fuel directly to its associated diesel genera tor or integral tank. integral tank. A fuel oil tank which may be
31、 furnished by the diesel generator manufacturer and mounted on the diesel engine. supply tank. A separate fuel oil tank for stor age of fuel, which supplies a day tank or integral tank. vital area. An area that contains safety-related equipment. 3. System Function The fuel oil system shall be capabl
32、e of supplying an adequate supply of suitable fuel oil to the emergency diesel generators under all Plant Con ditions that are defined in American National Standard Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants, ANSI/ANS-51.1-1983 (R1988) 6, and American Natio
33、nal Standard Nuclear Safety Criteria for the Design of Stationary Boiling Water Reactor Plants, ANSI/ANS-52.1-1983 (R1988) 7. 4. System Description The fuel oil system consists of independent fuel oil subsystems, each dedicated to supplying fuel to a single emergency diesel generator unit. Each subs
34、ystem consists of tanks, pumps, filters, strainers, flame arresters, valves, piping, piping components, instruments, and controls.2 The fuel oil subsystem starts at the fill connection, and terminates at the connections to the diesel engine. This standard assumes the use ofactive compo nents to tran
35、sfer the oil from a storage tank to the diesel generator day tank. A gravity drain system may be used if potential system leakage and its consequences are evaluated. 5. System Performance Require ments 5.1 General. Fuel oil systems shall be designed to maintain their integrity and to remain func tio
36、nal during and after all design basis events. The reliability of the fuel oil system shall be addressed when the overall reliability require-2 Refer to Appendix A and Figure A1 for a typical fueloil subsystem description and flow diagram respectively. 2 ments of the diesel generator units are satisf
37、ied. 5.2 Single Reactor Unit Nuclear Stations. The fuel oil system of single reactor unit nuclear stations shall be designed to applicable require ments of3.2.1, “Application of the Single Failure Criterion,“ and 4.20, “Multi-Unit Stations,“ of ANS-51.1 6 and ANS-52.1 7. The onsite fuel oil storage
38、for each diesel generator shall be sufficient to operate the diesel generator follow ing any design basis event either for seven days, or for the time required to replenish the fuel from sources outside the plant site following any design basis event without interruption of the operation of the dies
39、el generator, whichever is longer. During this period it shall be assumed that no offsite ac power is available. Storage capacity shall be calculated in accordance with 5.4. 5.3 Multiple Reactor Unit Nuclear Stations. Multiple reactor unit nuclear stations should be designed with completely independ
40、ent fuel oil systems for each unit. In this case, the fuel oil system for each reactor unit shall meet the re quirements of 5.2. In the event that the fuel oil systems have components that are shared be tween reactor units, the fuel oil storage capacity shall be based on all of the following: (1) Op
41、eration of the safety-related systems and components required to accommodate any design basis event in any one unit. (2) Operation of equipment necessary to shut down safely all reactor units at the site to cold shutdown status, and to maintain the cold shutdown condition of all reactor units. (3) N
42、o availability of offsite ac power. The fuel oil system of multiple reactor unit nu clear stations shall be designed to applicable re quirements of 3.2.3, “Single Failure Criterion,“ and 4.0, “Primary Design Function,“ of ANS-51.1 6 and ANS-52.1 7. Based on the minimum diesel generator capacity dete
43、rmined through the use of the above criteria, sufficient on-site fuel oil storage for each diesel generator shall be provided to operate the required number of diesel generators either for seven days, or for the time required to replenish the fuel from sources out side the plant site following any d
44、esign basis event without interruption of the operation of the diesel or diesels, whichever is longer. Storage capacity shall be calculated in accordance with 5.4. 5.4 Calculation of Usable Fuel Oil Storage Requirements. The fuel oil storage capacity re quirements should be conservatively calculated
45、, with the assumption that each of the required diesel generators operates continuously for the time period determined in 5.2 or 5.3 at its rated capacity. The calculation shall include an explicit allowance for fuel consumption required by peri odic testing. A conservative calculation is expressed
46、as: C = (Fa) (7 days) (1440 min/day)+ T where: C = Minimum storage capacity (liter or gal). Fa = Fuel consumption rate associated with the continuous rating based on the min imum quality fuel oil that is acceptable and the most adverse operating condi tions (liter/min or gallmin).3 T = Fuel capacity
47、 to be added to the min imum capacity required for 5.2, to ac commodate site-specific testing prac tices. An alternative calculation of the required storage capacity that takes into account the time depend ence of diesel generator loads may be used in place of the previous equation. Note: The fuel o
48、il storage requirements listed in 5.2, 5.3, and 5.4 are consistent with ANSI!IEEE 308-1995 4. 5.5 Component Performance Requirements 5.5.1 Tanks. Each diesel shall be equipped with one or more day or integral tanks whose capacity is sufficient to maintain at least 60 min utes of operation after reac
49、hing the low level alarm setpoint. The integral and day tanks may be combined in establishing the available capa city. This capacity shall assume the fuel con sumption with the diesel running at 100 percent continuous rated load plus a minimum additional The minimum quality fuel oil that is acceptable is specified by the ASTM standards discussed in Appendix C. 4 Appendix B provides guidance for an alternative calculation. American National Standard ANSIIANS-59.51-1997 margin of 10 percent based on the minimum quality fuel oil that is acceptable and the most adv
