Document: NUREG-0800
Document ID: eb0ea00d-43e4-45d1-8a5e-4daa4263d2cf
Document Type: srp
Title: EMERGENCY CORE COOLING SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550068.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.3
CFR Part: 
CFR Title: 

Content:
applications, when it is not practicable to achieve design basis differential pressure during ECCS valve testing, a qualification test (under design-basis differential pressure) prior to installation and inservice valve tests conducted under the maximum practicable differential pressure is sufficient. 25. The reviewer determines any special test requirements and confirms that the proposed preoperational test program for the ECCS is in conformance with the intent of Regulatory Guide 1.68. 26. The reviewer evaluates the applicant responses to the following Task Action Plan items: A. III.D.1.1 of NUREG-0737; the reviewer verifies that those portions of the ECCS located outside of containment that contain or may contain radioactive material following an accident are included in a leakage control program. The leakage control program should include periodic leak testing and measures to minimize leakage from the ECCS. B. II.K.3(15) of NUREG-0660; the reviewer should verify that BWR applicants' designs for pipe-break detection circuitry will not cause inadvertent system isolation during pressure spikes resulting from HPCI and RCIC system initiation. For those plants utilizing a time delay relay, the minimum expected response time will be plant specific, the maximum response time should be no greater than seven seconds unless the applicant provides proper justification for using a longer response time. C. II.K.3.21 of NUREG-0737; the reviewer should verify that BWR applicants have studied the design of BWR core spray and low pressure coolant injection systems to ensure that the systems will automatically restart on loss of water level, after having been manually stopped, if an initiation signal is still present. D. II.K.3.16 of NUREG-0737, the reviewer should verify that applicants have evaluated methods to reduce challenges and failures of reactor coolant system relief valves. 27. The reviewer verifies that the applicant has administrative procedures in place that