Table 1 to Paragraph (b)(1)(ii)-Prohibited Code Provisions
Editions and addenda | Code provision |
1989 Addenda through the latest edition and addenda incorporated by reference in paragraph (a)(1)(i) of this section | Subparagraph NB-3683.4(c)(1); Subparagraph NB-3683.4(c)(2). |
1989 Addenda through 2003 Addenda | Footnote 11 to Figure NC-3673.2(b)-1; Note 11 to Figure ND-3673.2(b)-1. |
2004 Edition through 2010 Edition | Footnote 13 to Figure NC-3673.2(b)-1; Note 13 to Figure ND-3673.2(b)-1. |
2011 Addenda through the latest edition and addenda incorporated by reference in paragraph (a)(1)(i) of this section | Footnote 11 to Table NC-3673.2(b)-1; Note 11 to Table ND-3673.2(b)-1. |
Table 2 to Paragraph (b)(2)(xv)(K)(4)-Table VIII: S7-1-Modified
[Flaw locations and orientations]
Parallel to weld | Perpendicular to weld | |
Inner 15 percent | X | X |
Outside Diameter Surface | X | |
Subsurface | X |
For R [LESS THAN] 0, [DELTA]KI depends on the crack depth (a), and the flow stress (Af). The flow stress is defined by Af = 1/2(Ays + Ault), where Ays is the yield strength and Ault is the ultimate tensilestrength in units ksi (MPa) and (a) is in units in. (mm). For -2 [LESS THAN EQUAL TO] R [LESS THAN EQUAL TO] 0 and Kmax- Kmin [LESS THAN EQUAL TO] 0.8 * 1.12 Af[RADIC]([PI]a), S = 1 and [DELTA]KI = Kmax. For R [LESS THAN] -2 and Kmax- Kmin [LESS THAN EQUAL TO] 0.8 * 1.12 Af[RADIC]([PI]a), S = 1 and [DELTA]KI = (1 - R) Kmax/3. For R [LESS THAN] 0 and Kmax - Kmin [GREATER THAN] 0.8 * 1.12Af[RADIC]([PI]a), S = 1 and [DELTA]KI = Kmax-Kmin.
Table 3 to Paragraph (b)(3)(iv)-Maximum Intervals for Use When Applying Interval Extensions
Group size | Maximum interval between activities of member valves in the groups (years) | Maximum interval between activities of each valve in the group (years) |
[GREATER THAN EQUAL TO]4 | 4.5 | 16 |
3 | 4.5 | 12 |
2 | 6 | 12 |
1 | Not applicable | 10 |
1 USAS and ASME Code addenda issued prior to the winter 1977 Addenda are considered to be "in effect" or "effective" 6 months after their date of issuance and after they are incorporated by reference in paragraph (a) of this section. Addenda to the ASME Code issued after the summer 1977 Addenda are considered to be "in effect" or "effective" after the date of publication of the addenda and after they are incorporated by reference in paragraph (a) of this section.
2-3 [Reserved]
4 For ASME Code editions and addenda issued prior to the winter 1977 Addenda, the Code edition and addenda applicable to the component is governed by the order or contract date for the component, not the contract date for the nuclear energy system. For the winter 1977 Addenda and subsequent editions and addenda the method for determining the applicable Code editions and addenda is contained in Paragraph NCA 1140 of Section III of the ASME Code.
5-6 [Reserved]
7 Guidance for quality group classifications of components that are to be included in the safety analysis reports pursuant to § 50.34(a) and § 50.34(b) may be found in Regulatory Guide 1.26, "Quality Group Classifications and Standards for Water-, Steam-, and Radiological-Waste-Containing Components of Nuclear Power Plants," and in Section 3.2.2 of NUREG-0800, "Standard Review Plan for Review of Safety Analysis Reports for Nuclear Power Plants."
8-9 [Reserved]
10 For inspections to be conducted once per interval, the inspections must be performed in accordance with the schedule in Section XI, paragraph IWB-2400, except for plants with inservice inspection programs based on a Section XI edition or addenda prior to the 1994 Addenda. For plants with inservice inspection programs based on a Section XI edition or addenda prior to the 1994 Addenda, the inspection must be performed in accordance with the schedule in Section XI, paragraph IWB-2400, of the 1994 Addenda.
10 C.F.R. §50.55a