ML20128E543
| ML20128E543 | |
| Person / Time | |
|---|---|
| Issue date: | 04/19/1985 |
| From: | Roe J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| FRN-50FR20574, RULE-PR-50 NUDOCS 8505290411 | |
| Download: ML20128E543 (9) | |
Text
$ Joca s allt W ER M10000E0 RULE
[7590-01]
[SBFRotaP7Ajr
' Federal Register Notice NUCLEAR REGULATORY COMMISSION 10 CFR Part 50 Codes and Standards for Nuclear Power Plants AGENCY: Nuclear Regulatory Comission.
ACTION: Proposed Rule.
SUMMARY
- The Comission proposes to amend its regulations to incorporate by reference the Winter 1982 Addenda, Sumer 1983 Addenda, Winter 1983
- _ Addenda, Sumer 1984 Addenda and 1983 Edition of Section III, Division 1, of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) , and the Winter 1982 Addenda, Sumer 1983 Addenda, and 1983 Edition of Section XI, Division 1, of the ASME Code. The sections of the ASME Code being incorporated provide rules for the construction of light-water-cooled nuclear power plant components and specify requirements for inservice inspection of those components. Adoption of these amendments would permit the use of improved methods for construction and inservice inspection of nuclear power plants.
DATES: Coment period expires Jt!L 161985 ,
Coments received after this date will be considered if it is practical to do so, but assurance of consideration cannot be given except as to coments received on or before this date.
J A date will be inserted allowing 60 days for public comment. 45 0
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ADDRESSES: Written comments or suggestions may be submitted to the Secre-I tary of the Comission, U.S. Nuclear Regulatory Comission, Washington, D.C. 20555, Attention: Docketing and Service Branch. Copies of coments received may be examined in the Commission's Public Document Room at 1717 H Street NW., Washington, D.C.
e FOR FURTHER INFORMATION CONTACT: Mr. G. C. Millman, Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S.
< Nuclear Regulatory Conmission, Washington, D.C. 20555, Telephone -
(301)443-7860.
SUPPLEMENTARY INFORMATION: On February 7, 1983, the Nuclear Regulatory Comission published in the Federal Register (48 FR 5532) amendments to its regulation, 10 CFR Part 50, " Domestic Licensing of Production and Utilization Facilities," which incorporated by reference new addenda to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code). The amendment revised 650.55a to incorporate by reference the Winter 1981 Addenda to Division 1 rules of Section III,
" Rules for. the Construction of Nuclear Power Plant Components," and Division 1 rules of Section XI, " Rules for Inservice Inspection of Nuclear Power Plant Components," of the ASME Code. On November 4, 1983, the Comission published in the Federal Register (48 FR 50878) an amendment to
$50.55a to incorporate by reference the Sumer 1982 Addenda to Section III, Division 1, of the ASME Code. The ASME did not publish a Sumer 1982 Addenda to Section XI. On March 15, 1984, the Comission published in the Federal Register (49 FR 9711) an amendment to 550.55a to, among other 2
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things, incorporate by reference those subsections of Section III which apply to the construction of Class 2 and Class 3 components.
Since publication of the last ASME Code addenda incorporated by reference in 550.55a. the Winter 1982 Addenda, Summer 1983~ Addenda, Winter 1983 Addenda, Sumer 1984 Addenda, and 1983 Edition, to the ASME Code have been issued. The 1983 Edition is equivalent to the 1980 Edition, as modified by the Summer 1980 Addenda, Winter 1980 Addenda, Summer 1981 Addenda, Winter 1981 Addenda, Sununer 1982 Addenda, and Winter 1982 Addenda. The-Comission proposes to amend $50.55a to incorporate by ' reference all editions through the 1983 Edition and all addenda through the Summer 1984 Addenda that modify Section III, Division 1, and all editions through the 1983 Edition and all addenda through the Sumer 1983 Addenda that modify Section XI, Division 1, of the ASME Code. The Sumer 1983 Addenda for Section XI does not include any technical requirements related to Division 1, but is being included in the reference to avoid confusion that might occur with a lack of continuity in the addenda references.
Editorial revisions are proposed to correct certain existing footnote and paragraph references that are inconsistent with the last amendment (49 FR 9711) to this rule and to simplify the language. These editorial revisions are contained entirely in 550.55a(g).
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For facilities whose operating licenses were issued prior to March 1,1976, this rule provides the effective date for implementing the inservice inspec-tion requirements and for defining the effective edition and addenda of the Code for the start of the next one-third of a 120-month inspection interval after September:1,1976. Since this one-third of an inspection interval has already been completed for all applicable facilities, it is proposed that the part of the rule addressing it in 550.55a(g)(4)(fii) be deleted.
Power reactors for which a notice of hearing on an application for a provi ,
sional construction pemit or a construction permit had been published on or before December 31, 1970, were pemitted to use the rules for construction required by power reactors that had received their construction permits prior l t
to January 1, 1971. It is proposed that $50.55a(i) which covers this pro-vision be deleted because it is no longer necessary. Section50.55a(c)(4) provides that for these and other facilities that received a construction perinit prior to May 14, 1984, the applicable Code Edition and Addenda for a component of the reactor coolant pressure boundary continue to be that Code Edition and Addenda that were required by Comission regulations for the component at the time of issuance of the construction permit.
i REGULATORY ANALYSIS The Comission has prepared a draft regulatory analysis on this pro-posed regulation. The analysis examines the costs and benefits of the alternatives considered by the Commission. The draft analysis is available for inspection in the NRC Public Document Room,1717 H Street 4
_ _ _ _ -.~ _. _ ,_.-_ . _ __ __ _ _ _ _ _ _ _ . , _ _ _ _ . _ _ __ l
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NW., Washington, DC. Single copies of the analysis may be obtained from Mr. G. C. Millman, Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Comission, Washington, D.C.,
20555, Telephone (301)443-7860.
The Comission requests public coment on the draft regulatory analysis. Comments on the draft analysis may be submitted to the NRC as indicated under the ADDRESSES heading.
PAPERWORK REDUCTION ACT STATEMENT This proposed rule amends information collection requirements that are subject to the Paperwork Reduction Act of 1980 (44 U.S.C. 3501 et seq.). This rule has been submitted to the Office of Management and Budget for review and approval of the paperwork requirements.
REGULATORY FLEXIBILITY CERTIFICATION
.In accordance with the Regulatory Flexibility Act of 1980, 5 U.S.C.
605(b), the Comission hereby certifies that this rule will not, if pro-mulgated, have a significant economic impact on a substantial number of small entities. This proposed rule affects only the licensing and operation of nuclear power plants. The companies that own these plants do not fall within the scope of the definition' of "small entities" set forth in the Regulatory Flexibility Act or the Small Business Size Standards set out in regulations issn:d by the Small Business Aoministration at 13 CFR Part 121.
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Since these companies are dominant in their service areas, this proposed j rule does not fall within the purview of the Act.
LIST OF SUBJECTS IN 10 CFR PART 50 l
Antitrust, Classified information, Fire prevention, Incorporation by reference, Intergovernmental relations, Nuclear power plan'ts and reactors,
< Penalty, Radiation protection, Reactor siting criteria, Reporting and recordkeeping requirements.
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Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974, as amended, and 5 U.S.C. 553, the NRC is proposing to adopt the following amendments to 10 CFR Part 50.
PART 50 - DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES 4
- 1. The authority citation for Part 50 reads as follows:
AUTHORITY: Secs. 103, 104, 161, 182, 183, 186, 189, 68 Stat. 936, 937, 948.,953, 954, 955, 956, as amended, sec. 234, 83 Stat. 1244, as amended (42 U.S.C. 2133, 2134, 2201, 2232, 2233, 2236, 2239, 2282); secs. 201, 202, 206, 88 Stat. 1242, 1244, 1246, as amended (42 U.S.C. 5841, 5842, 5846),
unless otherwise noted.
Section 50.7 also issued under Pub. L.95-601, sec. 10, 92 Stat. 2951 (42 U.S.C. 5851). Sections 50.57(d), 50.58, 50.91 and 50.92 also issued 6
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under Pub. L.97-415, 96 Stat. 2071, 2073 (42 U.S.C. 2133, 2239). Section 50.78 also issued under sec. 122, 68 Stat. 939 (42 U.S.C. 2152). Sections 4
50.80-50.81 also issued under sec. 184, 68 Stat. 954, as 4 mended (42
~
U.S.C.2234). Sections 50.100-50.102 also issued under sec. 186r 68 Stat.
955 (42 U.S.C. 2236).
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For. the purposes of sec. 223, 68 Stat. 958, as amended (42 U.S.C.
2273), il 50.10(a), (b), and (c), 50.44, 50.46, 50.48, 50.54, and 50.80(a) are issued under sec.161b, 68 Stat. 948, as amended (42 U.S.C. 2201(b)); -
il 50.10(b) and (c) and 50.54 are issued under sec. 1611, 68 Stat. 949, as amended (42U.S.C2201(1));andil50.55(e),50.59(b),50.70,50.71,50.72, 50.73 and 50.78 are issued under sec.161o, 68 Stat. 950, as amended (42 U.S.C.2201(o)).
- 2. Section 50.55a is amended as follows:
Paragraph (b)(1) and the introductory text of paragraph (b)(2) are revised; Reference to footnote 2 in paragraph (g)(1) is deleted; References to footnote 3 in paragraph (g)(2) and in paragraphs (g)(3)(ii)and(iv)aredeleted; Paragraphs (g)(3)(i)and(iii)arerevised; Paragraph (g)(4)(iii) is deleted and reserved; and Paragraph (1) is deleted.
650.55a Codes and standards.
i
- i (b)
- (1) As used in this section, references to Section III of the ASME 4
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. .. . _ . -.: = = . = ; - . .... - - - _-_.- - _ - . . - . - - - - . . - . - . - . . . .
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, 1 Boiler and Pressure Vessel Code refer to Section III, Division 1, and in-t clude editions through the 1983 Edition and Addenda through the Summer l
1984 Addenda.
l l (2) As used in this section, references to Section XI of the ASME i ~ Boiler and Pressure Vessel Code refer to Section XI, Division 1, and include j editions through the 1983 Edition and Addenda through the Sumer 1983 Addenda, subject to the following limitations and modifications:
~
-(g)*** .
(3) * *
- s (i) Components which are classified as ASME Code Class 1. shall be designed and be provided with access to enable the performance of inservice examination of such components and shall meet the preservice examination requirements set forth in Section XI of editions of the ASME 6
Boiler and Pressure Vessel Code and Addenda applied to the construction of the particular component.
(iii) Pumps and valves which are classified as ASME Code Class I l shall 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 Section XI of editions of the ASME Boiler and 8
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' 0 Pressure Dssel Code and Addenda applied to the construction of the particular pump or valve or the Summer 1973 Addenda, whichever is later.
)
(4) * * * ;
(iii) [ Reserved]
Dated at Bethesda, MD this 19th day of April 1985.
For the Nuclear Regulatory Commission.
-Jack W. Roe Acting: Executive Director for Operations.
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