73 FR 107 pgs. 31607-31608 - Licenses, Certifications, and Approvals for Nuclear Power Plants; Correction
Type: RULEVolume: 73Number: 107Pages: 31607 - 31608
Docket number: [NRC-2001-0010]
FR document: [FR Doc. E8-12345 Filed 6-2-08; 8:45 am]
Agency: Nuclear Regulatory Commission
Official PDF Version: PDF Version
NUCLEAR REGULATORY COMMISSION
10 CFR Part 50
[NRC-2001-0010]
RIN 3150-AG24
Licenses, Certifications, and Approvals for Nuclear Power Plants; Correction
AGENCY:
Nuclear Regulatory Commission.
ACTION:
Final rule: correcting amendment.
SUMMARY:
On August 28, 2007 (72 FR 49352), the Nuclear Regulatory Commission (NRC) published a final rule revising the provisions applicable to the licensing and approval processes for nuclear power plants (i.e., early site permit, standard design approval, standard design certification, combined license, and manufacturing license). These amendments clarify the applicability of various requirements to each of the licensing processes by making necessary conforming amendments throughout the NRC's regulations to enhance the NRC's regulatory effectiveness and efficiency in implementing its licensing and approval processes. This document is necessary to include a paragraph that was inadvertently omitted in that final rule.
DATES:
The correction is effective June 3, 2008, and is applicable to September 27, 2007.
FOR FURTHER INFORMATION CONTACT:
Michael T. Lesar, Chief, Rulemaking, Directives, and Editing Branch, Division of Administrative Services, Office of Administrative Services, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, telephone 301-415-7163, e-mail Michael.Lesar@nrc.gov.
SUPPLEMENTARY INFORMATION:
This document corrects an inadvertent omission in the Code of Federal Regulations by adding 10 CFR 50.55a(f)(3)(iv)(B).
For the reasons set out in the preamble and under the authority of the Atomic Energy Act of 1954, as amended; the Energy Reorganization Act of 1974, as amended; and 5 U.S.C. 552 and 553, the NRC is adopting the following amendment to 10 CFR part 50.
PART 50-DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES
1. The authority citation for part 50 continues to read as follows:
Authority:
Secs. 102, 103, 104, 105, 161, 182, 183, 186, 189, 68 Stat. 936, 937, 938, 948, 953, 954, 955, 956, as amended, sec. 234, 83 Stat. 444, as amended (42 U.S.C. 2132, 2133, 2134, 2135, 2201, 2232, 2233, 2236, 2239, 2282); secs. 201, as amended, 202, 206, 88 Stat. 1242, as amended, 1244, 1246 (42 U.S.C. 5841, 5842, 5846); sec. 1704, 112 Stat. 2750 (44 U.S.C. 3504 note); sec. 651(e), Pub. L. 109-58, 119 Stat. 806-810 (42 U.S.C. 2014, 2021, 2021b, 2111).
Section 50.7 also issued under Pub. L. 95-601, sec. 10, 92 Stat. 2951 as amended by Pub. L. 102-486, sec. 2902, 106 Stat. 3123 (42 U.S.C. 5841). Section 50.10 also issued under secs. 101, 185, 68 Stat. 955, as amended (42 U.S.C. 2131, 2235); sec. 102, Pub. L. 91-190, 83 Stat. 853 (42 U.S.C. 4332). Sections 50.13, 50.54(dd), and 50.103 also issued under sec. 108, 68 Stat. 939, as amended (42 U.S.C. 2138). Sections 50.23, 50.35, 50.55, and 50.56 also issued under sec. 185, 68 Stat. 955 (42 U.S.C. 2235). Sections 50.33a, 50.55a and appendix Q also issued under sec. 102, Pub. L. 91-190, 83 Stat. 853 (42 U.S.C. 4332). Sections 50.34 and 50.54 also issued under sec. 204, 88 Stat. 1245 (42 U.S.C. 5844). Sections 50.58, 50.91, and 50.92 also issued under Pub. L. 97-415, 96 Stat. 2073 (42 U.S.C. 2239). Section 50.78 also issued under sec. 122, 68 Stat. 939 (42 U.S.C. 2152). Sections 50.80-50.81 also issued under sec. 184, 68 Stat. 954, as amended (42 U.S.C. 2234). Appendix F also issued under sec. 187, 68 Stat. 955 (42 U.S.C. 2237).
2. In § 50.55a, paragraph (f)(3)(iv)(B) is added to read as follows:
§ 50.55a Codes and standards.
(f) * * *
(3) * * *
(iv) * * *
(B) Pumps and valves, in facilities whose construction permit under this part or design certification or combined license under part 52 of this chapter is issued on or after November 22, 1999, which are classified as ASME Code Class 2 and 3 must be designed and be provided with access to enable the performance of inservice testing of the pumps and valves for assessing operational readiness set forth in editions and addenda of the ASME OM Code (or the optional ASME Code cases listed in the NRC Regulatory Guide 1.192 that is incorporated by reference in paragraph (b) of this section) referenced in paragraph (b)(3) of this section at the time the construction permit, combined license, or design certification is issued.
Dated at Rockville, Maryland, this 28th day of May 2008.
For the Nuclear Regulatory Commission.
Annette L. Vietti-Cook,
Secretary of the Commission.
[FR Doc. E8-12345 Filed 6-2-08; 8:45 am]
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