Document: NUREG-0800
Document ID: dcd79479-0633-4d67-ba17-e369513aa55d
Document Type: srp
Title: SPECTRUM4 OF ROD EJECTION ACCIDENTS (PWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350410.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.8
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CFR Title: 

Content:
eview 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 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 nof 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. 2055 Regulatory Positions and specific guidelines necessary to meet the relevant requirements of GDC 28 are in Regulatory Guide 1.77. Regulatory Guide'1.77 (Ref. 2) identifies acceptable analytical methods and assumptions that may be used in evaluating the consequences of a control rod ejection accident. Specific criteria used by CPB in evaluating the control rod ejection accident are: a. Reactivity excursions should not result in a radially averaged enthalpy greater than 280 cal/gm at any axial location in any fuel rod. b. The maximum reactor pressure during any portion of the assumed excursion should be less than the value that will cause stresses to exceed the "Service Limit C" as defined in the ASME Code (Ref. 3). c. The fission product inventory in the fuel rods calculated to experience a departure from nucleate boiling (DNB) condition is an input to the radiological evaluation by AEB. The radiological criteria used in the evaluation of control rod ejection accidents (PWRs) are given in Appendix B of Regulatory Guide 1.77 (Ref. 2). III. REVIEW PROCEDURES 1.