Document: NUREG-0800
Document ID: a650b8f2-b0fa-4f0f-bc8f-55bb3f6ec603
Document Type: srp
Title: INADVERTENT OPENING OF A PWR PRESSURIZER PRESSURE RELIEF VALVE
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0708/ML070820094.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.6.1
CFR Part: 
CFR Title: 

Content:
model previously reviewed and accepted by the staff. The input parameters for this model were reviewed and found suitably conservative. In addition, we have determined further that the positions of RG 1.53 on single failure criterion and RG 1.105 for instrument setpoints also are satisfied. 6. The applicant has shown that this AOO would not develop into a postulated accident without other faults occurring independently. 7. The applicant has met 10 CFR 50.34(f)(1)(vi) and (iii) by [describe means used by the applicant to implement the action plan item].” 8. For DC and COL reviews, the findings will also summarize the staff’s evaluation of requirements and restrictions (e.g., interface requirements and site parameters) and COL action items relevant to this SRP section. V. IMPLEMENTATION The staff will use this SRP section in performing safety evaluations of DC applications and license applications submitted by applicants pursuant to 10 CFR Part 50 or 10 CFR Part 52. Except when the applicant proposes an acceptable alternative method for complying with specified portions of the Commission’s regulations, the staff will use the method described herein to evaluate conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision. VI. REFERENCES 1. 10 CFR Part 50, Appendix A 2. NUREG-0718, "Licensing Requirements for Pending Applications for Construction Permits and Manufacturing Licenses." 3. NUREG-0737, "Clarification of TMI Action Plan Requirements." 4. NRC Generic Letter 85-12, "Implementation of TMI Action Item II.K.3.5, 'Automatic Trip of Reactor Coolant Pumps,' for Westinghouse-Designed Nuclear Steam Supply Systems." 5. NRC Generic Letter 86-05, "Implementation of TMI Action Item II.K.3.5, 'Automatic Trip of Reactor Coolant Pumps,' for Babcock and Wilcox-Designed Nuclear Steam Supply Systems." 15.6.1-11