Alternate fracture toughness requirements for protection against pressurized thermal shock events.

CFR · 2024-01-01 · US · Title 10

(a) (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (b) (c) (1) Each licensee shall have projected values of RT (2) Each licensee shall perform an examination and an assessment of flaws in the reactor vessel beltline as required by paragraph (e) of this section. The licensee shall verify that the requirements of paragraphs (e), (e)(1), (e)(2), and (e)(3) of this section have been met. The licensee must submit to the Director, in its application to use § 50.61a, the adjustments made to the volumetric test data to account for NDE-related uncertainties as described in paragraph (e)(1) of this section, all information required by paragraph (e)(1)(iii) of this section, and, if applicable, analyses performed under paragraphs (e)(4), (e)(5) and (e)(6) of this section. (3) Each licensee shall compare the projected RT (d) (1) Whenever there is a significant change in projected values of RT (2) The licensee shall verify that the requirements of paragraphs (e), (e)(1), (e)(2), and (e)(3) of this section have been met. The licensee must submit, within 120 days after completing a volumetric examination of reactor vessel beltline materials as required by ASME Code, Section XI, the adjustments made to the volumetric test data to account for NDE-related uncertainties as described in paragraph (e)(1) of this section and all information required by paragraph (e)(1)(iii) of this section in the form of a license amendment for review and approval by the Director. If a licensee is required

official document · source cfr-2024 · id 10:§ 50.61a