Document: NUREG-0800
Document ID: 01d33a9e-6474-4916-b4b9-6fe8a75f04c6
Document Type: srp
Title: -
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0622/ML062210398.pdf
Revision Date: 2023-06
Chapter: 14
Section ID: 14.2.1
CFR Part: 
CFR Title: 

Content:
f. Guidance Contained in Vendor Topical Reports The NRC previously reviewed and accepted General Electric (GE) Company Licensing Topical Report, “Generic Guidelines for General Electric Boiling Water Reactor Extended Power Uprate” (referred to as ELTR-1), NEDC- 32424P-A, Class III, February 1999, as a basis for reviewing EPU LARs. This topical report provided specific guidance on integrated system transient testing at EPU conditions. As described in Section 5.11.9.d and Appendix L.2.4 of ELTR-1, the generator load rejection and the main steam isolation valve (MSIV) closure tests verify that the plant performance is as predicted and projected from previous test data. On March 31, 2003, the NRC approved the use of GE Licensing Topical Report NEDC-33004P, “Constant Pressure Power Uprate,” for constant pressure power uprate (CPPU) EPU LARs. However, as noted in the staff’s safety evaluation (SE), the staff did not accept the elimination of large- transient testing (e.g., the MSIV closure and turbine generator load rejection described in NEDC-32424P-A) from the scope of the CPPU test program. The staff noted that the need to conduct large-transient testing for a CPPU would be considered on a plant-specific basis. For pressurized water reactors (PWRs), Westinghouse report WCAP-10263, “A Review Plan for Uprating the Licensed Power of a Pressurized Water Reactor Plant,” provides limited guidance for power uprate testing. Specifically, the document states that the recommended test program for the nuclear steam supply system and the interfacing BOP systems should be developed on a plant-specific basis depending on the magnitude of hardware modifications and the magnitude of the power uprate. Although the NRC has previously approved certain exceptions to EPU test program requirements, the applicability of these exceptions to a particular plant must be considered and justified on a plant-specific basis as discussed above in Section III.C.2.a. g. Risk Implications