Document: NUREG-0800
Document ID: 7e9d3620-7a94-488e-b2d5-992282113080
Document Type: srp
Title: NUREG408OO
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350480.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
perator action based solely on the bypass indications. 5. The indication system should be designed and installed in a manner which precludes the possibility of adverse effects on plant safety systems. Failure or bypass of a protective function -should not be a credible consequence of failures occurring in the indication equipment, and the bypass indication should not reduce the required independence between redundant safety systems. 6. The indication system should include a capability of assuring its operable status during normal plant operation to the extent that/ he indicating and annunciating function can be verified. C. REFERENCES 1. Regulatory Guide 1.47, "Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety Systems." 7A-15 Rev. 2 - July 1981 BRANCH TECHNICAL POSITION ICSB 22 GUIDANCE FOR APPLICATION OF REGULATORY GUIDE 1.22 A. BACKGROUND A recent application listed eight functions that are not tested while the reactor is operating at power. The applicant claimed that the periodic testing complied with Regulatory Guide 1.?2. -Regulatory Guide 1.22 does make provisions for actuated equipment that is not tested during reactor operation but it does not have provisions for excluding any portion of the protection system from the requirements of paragraphs 4.9 and 4.10 of IEEE Std 279. B. BRANCH TECHNICAL POSITION All portions of the protection systems should be designed in accordance with IEEE Std 279, as required by 10 CFR Part 50, §50.55a(h). All actuated equipment that is-not tested during reactor operation should be identified and a discussion of. how each conforms to the provisions of paragraph D.4 of Regulatory Guide 1.22 should be submitted. C. REFERENCES 1. Regulatory Guide 1.22, "Periodic Testing of Protection System Actuation Functions." 2. IEEE Std 279, "Criteria for Protection Systems for Nuclear Power Generating Stations." 7A-16 Rev. 2 - July 1981 BRANCH TECHNICAL POSITION ICSB 25 GUIDANCE FOR THE INTERPRETATION OF GENERAL.DESIGN