Document: NUREG-0800
Document ID: 7c5a6f62-3fbc-4bde-8062-2eb15eeb6d45
Document Type: srp
Title: UNCONTROLLED CONTROL ROD. ASSEMBLY WITHDRAWAL FROM A SUBCRITICAL OR LOW POWER
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350326.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.1
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uct 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 public 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 new Informa- 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. 2Cm. c. Criterion 25, which requires that the reactor protection system be designed to assure that specified acceptable fuel design limits are not exceeded in the event of a single malfunction of the reactivity control system. 2. The requirements of GDC 10, 20, and 25 concerning the specified acceptable fuel design limits are assumed to be met for this event when: a. The thermal margin limits (DNBR for PWRs and MCPR for BWRs) as specified in SRP Section 4.4, subsection II.1 are met. b. Fuel centerline temperatures (for PWRs) as specified in SRP Section 4.2, subsection II.A.2(a) and (b) do not exceed the melting point. c. Uniform cladding strain (for BWRs) as specified in SRP Section 4.2, subsection II.A.2(b) do not exceed 1%. III. REVIEW PROCEDURES The reviewer, in determining whether the acceptance criteria are met, considers the following: 1. Peak conditions for the transient are maximized by low initial power; thus, the power level of the reactor should be at the lowest possible value com- patible with the control rod configuration used for the accident. The postulated initial reactor coolant