Document: NUREG-0800
Document ID: bec1a8e3-20ad-4900-900c-0c7c0628e8d5
Document Type: srp
Title: INSERVICE TESTING OF PUMPS AND VALVES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340651.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.6
CFR Part: 
CFR Title: 

Content:
ry procedures and polci Standard review plans are not ubsttts for regulatory guide or the Commson's regulations and compican with tem not requied. T standard reiw pln setons ked to the Standard Format and Cont of Safety Anal Reports for Nudcer Power Plants. Not all sectons o the Stanrd Fomt hea 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. ?; 2. Inservice Testing of Valves The descriptive information in the SAR covering the inservice test program is reviewed for those ASME Code Class 1, 2, and 3 valves whose function is required for safety. This review does not include those nonsafety-related valves exempted by the Code. 3. Relief Requests 10 CFR Part 50, §50.55a(g) requires a nuclear power facility to periodically update its inservice testing program to meet the requirements of future revisions of Section XI of the ASME Code. However, if it proves impractical to implement these criteria, the applicant is allowed to submit requests for relief from Section XI requirements on a case-by-case basis. Accord- ingly, any requests for relief are reviewed by the staff to determine if the proposed exceptions to Section XI will degrade the overall plant safety. Due consideration is given to the burden upon the applicant that could result if the criteria of Section XI were imposed on the facility. II. ACCEPTANCE CRITERIA The acceptance criteria is based on meeting the relevant requirements set forth in General Design Criteria 37, 40, 43, 46, 54, and 10 CFR Part 50, §50.55a(g). The relevant requirements are as follows: A. General Design Criterion 37, as it relates to periodic functional testing of the emergency core cooling system to assure the leak tight integrity and