A pilot application of risk-informed methods to establish inservice inspection priorities for nuclear components at Surry Unit 1 Nuclear Power Station. Revision 1 Metadata

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Title

  • Main Title A pilot application of risk-informed methods to establish inservice inspection priorities for nuclear components at Surry Unit 1 Nuclear Power Station. Revision 1

Creator

  • Author: Vo, T. V.
    Creator Type: Personal
  • Author: Phan, H. K.
    Creator Type: Personal
  • Author: Gore, B. F.
    Creator Type: Personal
  • Author: Simonen, F. A.
    Creator Type: Personal
  • Author: Doctor, S. R.
    Creator Type: Personal
    Creator Info: Pacific Northwest National Lab., Richland, WA (United States)

Contributor

  • Sponsor: U.S. Nuclear Regulatory Commission
    Contributor Type: Organization
    Contributor Info: Nuclear Regulatory Commission, Washington, DC (United States)

Publisher

  • Name: U.S. Nuclear Regulatory Commission
    Place of Publication: Washington D.C.
    Additional Info: Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering Technology
  • Name: Pacific Northwest National Laboratory (U.S.)
    Place of Publication: Richland, Washington
    Additional Info: Pacific Northwest National Lab., Richland, WA (United States)

Date

  • Creation: 1997-02-01

Language

  • English

Description

  • Content Description: As part of the Nondestructive Evaluation Reliability Program sponsored by the US Nuclear Regulatory Commission, the Pacific Northwest National Laboratory has developed risk-informed approaches for inservice inspection plans of nuclear power plants. This method uses probabilistic risk assessment (PRA) results to identify and prioritize the most risk-important components for inspection. The Surry Nuclear Power Station Unit 1 was selected for pilot application of this methodology. This report, which incorporates more recent plant-specific information and improved risk-informed methodology and tools, is Revision 1 of the earlier report (NUREG/CR-6181). The methodology discussed in the original report is no longer current and a preferred methodology is presented in this Revision. This report, NUREG/CR-6181, Rev. 1, therefore supersedes the earlier NUREG/CR-6181 published in August 1994. The specific systems addressed in this report are the auxiliary feedwater, the low-pressure injection, and the reactor coolant systems. The results provide a risk-informed ranking of components within these systems.
  • Physical Description: 72 p.

Subject

  • Keyword: Low Pressure Coolant Injection
  • STI Subject Categories: 21 Nuclear Power Reactors And Associated Plants
  • Keyword: Reactor Cooling Systems
  • Keyword: Surry-1 Reactor
  • Keyword: Reactor Components
  • Keyword: Planning
  • Keyword: Risk Assessment
  • Keyword: Auxiliary Water Systems
  • Keyword: In-Service Inspection

Source

  • Other Information: PBD: Feb 1997

Collection

  • Name: Office of Scientific & Technical Information Technical Reports
    Code: OSTI

Institution

  • Name: UNT Libraries Government Documents Department
    Code: UNTGD

Resource Type

  • Report

Format

  • Text

Identifier

  • Other: TI97004344
  • Report No.: NUREG/CR--6181-Rev.1
  • Report No.: PNNL--9020-Rev.1
  • Grant Number: AC06-76RL01830
  • DOI: 10.2172/446366
  • Office of Scientific & Technical Information Report Number: 446366
  • Archival Resource Key: ark:/67531/metadc681080

Note

  • Display Note: INIS; OSTI as TI97004344
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