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Monday, May 11, 2020 | History

2 edition of Regulatory analysis for Generic issue 23, reactor coolant pump seal failure found in the catalog.

Regulatory analysis for Generic issue 23, reactor coolant pump seal failure

S. K. Shaukat

Regulatory analysis for Generic issue 23, reactor coolant pump seal failure

draft report for comment

by S. K. Shaukat

  • 99 Want to read
  • 1 Currently reading

Published by Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission in Washington, DC .
Written in English

    Subjects:
  • Nuclear reactors -- United States -- Cooling -- Safety measures.,
  • Nuclear power plants -- United States -- Equipment and supplies -- Safety measures.,
  • Pumping machinery -- Defects.,
  • Sealing (Technology)

  • Edition Notes

    Other titlesGeneric issue 23, reactor coolant pump seal failure.
    StatementS.K. Shaukat, J.E. Jackson, D.F. Thatcher.
    ContributionsJackson, J. E. 1937-, Thatcher, D. F., U.S. Nuclear Regulatory Commission. Division of Safety Issue Resolution.
    The Physical Object
    Pagination1 v. (various pagings) :
    ID Numbers
    Open LibraryOL15297954M

    Directs excess letdown flow either to the VCT via the seal water return filter or to the Reactor Coolant Drain Tank Describe the function of the Excess Letdown Heat Exchanger Cools letdown flow equivalent to that portion of seal injection that flows into the RCS through the RCP seal labyrinth seals. Generic input for this analysis consist of a 1D representation of the two-loop APR reactor as depicted in Fig. 3 (Ko and Kim, ) modified from one prepared by Korean Institute of Nuclear Safety for regulatory purpose (Bang et al., ). Each loop consists of one hot leg, two cold legs with two reactor coolant pumps and correspondent Cited by: 1.

      According to the fluid hydrodynamic lubrication theory, and the structural characteristics of the convergence gap seal is combined, the effect of differential pressure and centrifugal force should be considered, then the convergent wedge gap mechanical seals flow field numerical model is established and the influence of the leakage factors are researched, including the geometric parameters and Cited by: 1. An independent analysis was performed by ETEC to determine what the seal leakage rates would be for the Westinghouse Reactor Coolant Pump (RCP) during a postulated station blackout resulting from loss of ac electric power. The object of the study was to determine leakage rates for the following conditions: Case 1: All three seals function.

    SUB-CHAPTER – DESCRIPTION OF THE REACTOR COOLANT SYSTEM. Sub-chapter describes the functional role of the reactor coolant system, together with the design assumptions, fluid characteristics and design description of the key components (reactor vessel, pressuriser, reactor coolant pumps and steam generators). System parameters are. Failures of reactor coolant pump (RCP) seals that could result in a significant loss-of-coolant inventory are of current concern to the US Nuclear Regulatory Commission. Particular attention is being focused on seal behavior during station blackout conditions, when failure of on-site emergency diesel generators occurs simultaneously with loss.


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Regulatory analysis for Generic issue 23, reactor coolant pump seal failure by S. K. Shaukat Download PDF EPUB FB2

The U.S. Nuclear Regulatory Commission (NRC) is issuing this regulatory issue summary (RIS) to notify nuclear power reactor licensees about the staff's closure of Generic Safety Issue 23 (GSI), "Reactor Coolant Pump Seal Failure." This RIS transmits no new requirements, and no action or written response is requested.

Comments on Generic Is "Reactor Coolant Pump Seal Failure": and Draft Regulatory Guide; Issuance, Availability EASYLINK +11/'97 59/ S rq Regulatory analysis for Generic issue 23 { aU The NRC solicited comments on Generic Issue (GI), "Reactor Coolant Pump Seal Failures" in the Federal Register (56 FR ) dated Ap Intent The U.S.

Nuclear Regulatory Commission (NRC) is issuing this regulatory issue summary (RIS) to notify nuclear power reactor licensees about the staff’s closure of Generic Safety Issue 23 (GSI), “Reactor Coolant Pump Seal Failure.” This RIS transmits no new requirements, and no action or written response is requested.

Get this from a library. Regulatory analysis for Generic is reactor coolant pump seal failure: draft report for comment.

[S K Shaukat; J E Jackson; D F Thatcher; U.S. Nuclear Regulatory Commission. Division of Safety Issue Resolution.]. Regulatory analysis for Generic is reactor coolant pump seal failure: draft report for comment.

Imprint Washington, DC: Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Physical description 1 v. Generic is reactor coolant pump seal failure.

Librarian. U.S. Nuclear Regulatory Commission, NUREG/CR, "Cost/Benefit Analysis for Generic Issue Reactor Coolant Pump Seal Failure," prepared by SCIENTECH, Inc., dated April WCAP, Revision 2, Excerpts from Westinghouse Owners Group Report, "Reactor Coolant Pump Seal Performance Following a Loss of All AC Power," dated November (Proprietary).

Memorandum for W. Travers from A. Thadani, "Closeout of Generic Safety Is 'Reactor Coolant Pump Seal Failure,'" November 8, [ML] Regulatory Issue Summary"Closure of Generic Safety Is Reactor Coolant Pump Seal Failure," U.S.

Nuclear Regulatory Commission, Febru [ML]. Commission decision on the resolution of generic issue 23 " Reactor coolant pump seal failure.".

Generic Assessment of Delayed Reactor Coolant Pump Trip during SmalI Break Loss-of-Coolant Accidents in Pressurized rs Manuscript Completed: November Date Published: November B.

Sharon Bulletins and Orders Task Force Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. Intent The U.S. Nuclear Regulatory Commission (NRC) is issuing this regulatory issue summary (RIS) to notify nuclear power reactor licensees about the staff’s closure of Generic Safety Issue 23 (GSI), “Reactor Coolant Pump Seal Failure.

” This RIS transmits no new requirements, and no action or written response is requested. As a result, ''Reactor Coolant Pump Seal Failure,'' Generic Issue 23 was established. This report summarizes the findings of a technical investigation generated as part of the program to resolve this issue.

Intent The U.S. Nuclear Regulatory Commission (NRC) is issuing this regulatory issue summary (RIS) to notify nuclear power reactor licensees about the staff’s closure of Generic Safety Issue 23 (GSI), “Reactor Coolant Pump Seal Failure. ” This RIS transmits no new requirements, and no action or written response is : United States.

Generic is reactor coolant pump seal failures, Task action plan, US Nuclear Regulatory Commission (Oc- tober ). [7] Peter Lain, Overpessurization of emergency core cooling systems in boiling water reactors, Preliminary Case Study Report, Office for Analysis and Evaluation of Operational Data, US Nuclear Regulatory Commission Cited by: 1.

A hydraulically controllable mechanical seal for a nuclear reactor coolant pump (RCP) is under development. Its purpose is to correct excessive or insufficient leakage through RCP seals, a current expensive problem. The non-rotating seal face contains an annular cavity, filled with pressurized by: 1.

Regulatory Analysis for Generic Issue Reactor Coolant Pump Seal Failure", NUREG/, Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S SK Shaukat.

Abstract. MODEL FOR WESTINGHOUSE PWRS, ” DECEMBER The purpose of this memorandum is to inform the Standardized Plant Analysis Risk (SPAR) model users and other agency risk analysts about the implications of using the “Rhodes Model” to model reactor coolant pump (RCP) seal loss-of-coolant accidents (LOCAs).

Int. Pres. Ves. & Piping 27 () Investigation of a Reactor Coolant Pump Seal from Indian Point Unit No. 2* Carl J.

Czajkowski Materials Technology Division, Department of Nuclear Energy, Brookhaven National Laboratory, Upton, NYUSA (Received 2 September ; accepted 6 September ) ABSTRACT A failure investigation was performed on a Westinghouse reactor coolant pump Author: Carl J.

Czajkowski. As a result, ''Reactor Coolant Pump Seal Failure,'' Generic Issue 23 was established. This report summarizes the [Show full abstract] findings of a technical investigation generated as part of. The objective of the study presented here is to develop and demonstrate the benefits of employing a combined safety-security risk evaluation methodology as compared to the current method of calculating R SAF and R SEC independently as described in section demonstrate the methodology a typical nuclear Spent Fuel Storage Pool (SFSP) facility design shown in Fig.

1 is : Mohammad A. Hawila, Sunil S. Chirayath. A new generation reactor coolant pump (RCP) seal that can endure and continue to perform under the severe conditions present during a station blackout was developed and tested in response to NRC Author: Gerard Van Loenhout.

Safety Analysis of WWER Type Reactors Against Pump Failure Accident in 2 and 4 Loops if one or more of the reactor coolant pump sets fail. A loss and the final safety analysis report Author: Yashar Rahmani.Reactor Coolant Pumps Advanced Sealing Technology: Pure Hydrodynamic Seals Ensuring the primary circuit leaktightness to guarantee plant operation and safety The challenge In case of Station Black-Out, Reactor Coolant Pumps (RCP) stop, leading to the leakage of signifi - cant quantities of water through the seals (typically several cubic File Size: KB.Generic assessment of delayed reactor coolant pump trip during small break loss-of-coolant accidents in pressurized water reactors [Sheron, B.] on *FREE* shipping on qualifying offers.

Generic assessment of delayed reactor coolant pump trip during small break loss-of-coolant accidents in pressurized water reactorsAuthor: B. Sheron.