[Federal Register Volume 75, Number 44 (Monday, March 8, 2010)]
[Rules and Regulations]
[Pages 10410-10411]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2010-4846]


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NUCLEAR REGULATORY COMMISSION

10 CFR Part 50

[NRC-2007-0008]
RIN 3150-AI01


Alternate Fracture Toughness Requirements for Protection Against 
Pressurized Thermal Shock Events; Correcting Amendment

AGENCY: Nuclear Regulatory Commission.

ACTION: Final rule; correcting amendment.

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SUMMARY: The Nuclear Regulatory Commission (NRC) is revising its 
regulations to add a table that was inadvertently omitted in a 
correction document published on February 3, 2010 (75 FR 5495). The 
February 3, 2010 document corrected a final rule published on January 
4, 2010 (75 FR 13), that amends the NRC's regulations to provide 
alternate fracture toughness requirements for protection against 
pressurized thermal shock (PTS) events for pressurized water reactor 
(PWR) pressure vessels.

DATES: The correction is effective March 8, 2010, and is applicable to 
February 3, 2010, the date the original rule became effective.

FOR FURTHER INFORMATION CONTACT: Michael T. Lesar, Chief, Rulemaking 
and Directives Branch, Office of Administration, Nuclear Regulatory 
Commission, Washington, DC 20555-0001, telephone 301-492-3663, e-mail 
<a href="/cdn-cgi/l/email-protection#e8a5818b80898d84c6a48d9b899aa8869a8bc68f879e"><span class="__cf_email__" data-cfemail="2964404a41484c4507654c5a485b69475b4a074e465f">[email protected]</span></a>.

SUPPLEMENTARY INFORMATION: This document adds Table 7 to the NRC's 
regulations at 10 CFR 50.61a(g) which was inadvertently omitted in a 
document published on February 3, 2010 (75 FR 5495). Therefore, the NRC 
finds that notice and opportunity for public comment on this corrective 
action is unnecessary.

List of Subjects in 10 CFR Part 50

    Antitrust, Classified information, Criminal penalties, Fire 
protection, Intergovernmental relations, Nuclear power plants and 
reactors, Radiation protection, Reactor siting criteria, Reporting and 
recordkeeping requirements.

    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 amendments to 10 CFR part 50.

[[Page 10411]]

PART 50--DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION 
FACILITIES

0
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); Energy 
policy Act of 2005, Pub. L. No. 109-58, 119 Stat. 194 (2005). 
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).


0
2. In Sec.  50.61a, paragraph (g) is amended by adding Table 7 directly 
after Table 6 to read as follows:


Sec.  50.61a  Alternate fracture toughness requirements for protection 
against pressurized thermal shock events.

* * * * *
    (g) * * *

 Table 7--Threshold Values for the Outlier Deviation Test (Significance
                               Level = 1%)
------------------------------------------------------------------------
                                          Second largest      Largest
                                             allowable       allowable
   Number of available data points (n)      normalized      normalized
                                          residual value  residual value
                                               (r*)            (r*)
------------------------------------------------------------------------
3.......................................            1.55            2.71
4.......................................            1.73            2.81
5.......................................            1.84            2.88
6.......................................            1.93            2.93
7.......................................            2.00            2.98
8.......................................            2.05            3.02
9.......................................            2.11            3.06
10......................................            2.16            3.09
11......................................            2.19            3.12
12......................................            2.23            3.14
13......................................            2.26            3.17
14......................................            2.29            3.19
15......................................            2.32            3.21
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    Dated at Rockville, Maryland, this 2nd day of March 2010.

    For the Nuclear Regulatory Commission.
Michael T. Lesar,
Chief, Rulemaking and Directives Branch, Division of Administrative 
Services, Office of Administration.
[FR Doc. 2010-4846 Filed 3-5-10; 8:45 am]
BILLING CODE 7590-01-P


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