Document: NUREG-0800
Document ID: d5a274a9-ea29-4a99-9cbe-73eefa2e90f4
Document Type: srp
Title: REACTOR CORE ISOLATION COOLING SYSTEM (BWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340631.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.4.6
CFR Part: 
CFR Title: 

Content:
eismic Category I standards (discussed in SRP Section 3.2.1) and must not be shared among nuclear power units except as permitted by General Design Criterion 5 (Ref. 7). 5. The RCIC and HPCS (or HPCI) systems must be protected against natural phenomena, external or internal missiles, pipe whip, and jet impingement forces so that such events cannot fail both systems simultaneously. Acceptance criteria for these are discussed in SRP Sections 3.3.1 through 3.6.2. Acceptance criteria for RCIC instrumentation are described in SRP Section 7.4. 6. The RCIC system must meet the requirements of General Design Criterion 54 (Ref. 8) with regard to leak detection and isolation provisions for lines passing through the primary containment. Other containment isolation criteria for RCIC are described in SRP Sections 6.2.4 and 6.2.6. 7. The RCIC system must meet the recommendations of Task Action Plan items II.K.1.22, II.K.3.13, II.K.3.15, II.K.3.22, II.K.3.24, and III.D.1.1 of NUREG-0737 (Ref. 1) and NUREG-0718 (Ref. 11) with regard to actions needed for operation, system initiation setpoint and automatic restart capability, break detection provisions, automatic suction switchover to the suppression pool, adequacy of space cooling, and leakage minimization, respectively. 8. If the RCIC system is used to control or mitigate the consequences of an accident, either by itself or as a backup to another system, it must meet the requirements of an engineered safety feature. The RCIC system must 5.4.6-4 Rev. 3 - April 1984 meet the guidelines of Regulatory Guide 1.1 (Ref. 9) regarding net positive suction head. 9. In order to meet the requirements of General Design criterion 4 (Ref. 12) design features and operating procedures, designed to prevent damaging water hammer due-to such mechanisms as voided discharge lines, steam bubble collapse and water entrainment in steam lines, shall be provided. III. REVIEW PROCEDURES The procedures below are used during the construction permit (CP) review