Document: NUREG-0800
Document ID: 7aef037f-a817-4377-a41f-be2c1006a20b
Document Type: srp
Title: STATION SERVICE WATER SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350543.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.2.1
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of the Office of Nuclear Reactor Regulation staff responsible for the review of applications to construct and operate nuclear power plants. These documents are made available to the public as part of the Commission's policy to Inform the nuclear Industry and the general pubflc of regulatory procedures and policies. Standard review plans are not substitutes for regulatory guides or the Commission's regulations and compliance with them is not required. The standard review plan sections are keyed to the Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants. Not all sections of the Standard Format have a corresponding review plan. Published standard review plans will be revised periodically, as appropriate, to accommodate comments and to reflect now inf orma- tion and experience. Comments and suggestions for Improvement will be considered and should be sent to the U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Washington. D.C. 2OS 2. The PSB also reviews the design of the SWS with respect to: a. The capability for detection, control, and isolation of system leakage including the capability for detection and control of radioactive leakage into and out of the system and prevention of accidental releases to the environment. b. Measures to preclude long-term corrosion and organic fouling that would tend to degrade system performance. c. Provisions for system and component operational testing, including the instrumentation and control features that determine and verify that the system is operating in a correct mode (i.e., valve position, pressure and temperature indication). d. The effects of the failure of nonseismic Category I equipment, struc- tures or components of safety-related portions of the SWS are taken into account in the design. 3. The PSB reviews the SWS capability to flood the reactor containment should this be required in a post-accident recovery situation. 4. The PSB reviews the system to determine that a