ML20136J381

From kanterella
Jump to navigation Jump to search
Codes & Stds for Nuclear Power Plants, 10CFR50 Final Rule. Regulations Amended to Incorporate Revised ASME Boiler & Pressure Vessel Code Re Const of LWR Components & Requirements for Inservice Insp of Components
ML20136J381
Person / Time
Issue date: 09/04/1985
From: Dircks W
NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To:
Shared Package
ML20058J960 List:
References
FRN-50FR38970, RULE-PR-50 AA83-02-05, AA83-2-5, NUDOCS 8511250353
Download: ML20136J381 (8)


Text

- .

' ' [7590-01)

Federal Register Notice NUCLEAR REGULATORY COMMISSION 10 CFR Part 50 Codes and Standards for Nuclear Power Plants AGENCY: Nuclear Regulatory Comission.

ACTION: Final rule.

SUMMARY

The Comission is amending 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, a The sections of 1983 Edition of Section XI. Division 1, of the ASME Code.

the ASME Code being incorporated provide rules for the construction of light-water-cooled nuclear power plant components and specify requireme for inservice inspection of those corr.ponents. Adoption of these amendments would permit the use of improved methods for construction and inservice inspection of nuclear power plants.

I EFFECTIVE DATE:

(Insert date 30 days after publication in the FR).

incorporation by reference of certain publications listed in the The regulations is approved by the Director of the Federal Register as of (Insert date 30 days after publication in the FR).

jjjl2l 353 851119 50 50FR38970 PDR 1

[7590-01)

Mr. G. C. Millman, Division of FOR FURTHER INFORMATION CONTACT:

Engineering Technology, Office of Nuclear Regulatory Research, U.S.

Conunission. Washington, D.C. 20555 Telephone Nuclear Regulatory (301)443-7862.

SUPPLEMENTARY INFORMATION: On May 17, 1985, the Nuclear Regulatory Comission published in the Federal Register (50 FR 20574) a proposed amendment to its regulation, 10 CFR Part 50, " Domestic Licensing of

- Production and Utilization Facilities," to update ' existing references .

i to specific editions and addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code); to make editorial corrections to the existing rule; to simplify the language of the rule; and to delete two obsolete provisions.

This amendment revises $50.55a to incorporate by reference all editions P through the 1983 Edition and all addenda through the Sumer 1984 Addenda that modify Division 1 rules of Section III, " Rules for the Construction of Nuclear Plant Components " and all editions through the 1983 Edition .

and all addenda through the Sumer 1983 Addenda that modify Division 1 rules of Section XI, " Rules for the Inservice Inspection of Nuclear Power Plant Components," of the ASME Code. The Sumer 1983 Addenda for Section XI does not include technical requirements related to Division 1, but is

^

included in the reference to prevent the confusion that might occur with a lack of continuity in the addenda references.

f y Editorial revisions are included in this amendment 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 650.55a(g).

2

[7590-01]

For facilities whose operating licenses were issued prior to March 1,1976, this rule provided the effective date for implementing the inservice inspection 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 4 interval has already been completed for all applicable facilities.

4 550.55a(g)(4)(iii) which addresses the implementation of that inspection

' is unnecessary and is deleted by this amendment.

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 for power reactors that had received their construction pemits prior to January 1, 1971. This amendment deletes 150.55a(1) which covers this provision because it is no longer necessary. Section 50.55a(c)(4) provides that for these and other facilities that received a construction pemit 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 Connission regulations for the component at the tim of issuance of the construction pemit.

i Interested persons were invited to submit written connents for considera-tion in connection with the proposed amendment and the draft regulatory analysis by July 16, 1985. No adverse connents or significant questions were received in response to the notice of proposed rulemaking.

3

, w ,. -

[7590-Ol]

REGULATORY ANALYSIS The Comission has prepared a regulatory analysis on this regulation.

The analysis examines the costs and benefits of the alternatives considered by the Comission. Interested persons may examine a copy of the regulatory analysis at the NRC Public Document Room,1717 H St. NW.,

Washington, D.C. 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)443-7862.

PAPERWORK REDUCTION ACT STATEMENT This final rule incorporates by reference information collection requirements that were reviewed by the Office of Management and Budget, l

The OMB approval number is 3150-0011.

f i

REGULATORY FLEXIBILITY CERTIFICATION As required by the Regulatory Flexibility Act of 1980, 5 U.S.C.

l 605(b), the Comission hereby certifies that this rule does not have a significant economic impact on a substantial number of small entities.

This 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 regula-tions issued by the Small Business Administration at 13 CFR Part 121.

4

L,, -

[7590-011 LIST OF SUBJECTS IN 10 CFR PART 50 Antitrust, Classified information, Fire prevention, Incorporation by reference, Intergovernmental relations, Nuclear power plants and reactors, Reactor siting criteria, Reporting and Penalty, Radiation protection, recordkeeping requirements.

Pursuant to the Atomic Energy Act of 1954, as amended, the Energy 553, the NRC is Reorganization Act of 1974, as amended, and 5 U.S.C.

adopting the following amendments to 10 CFR Part 50.

l PART 50 - DOMESTIC LICENSING OF PRODUCTION AND F

1. The authority citation for Part 50 continces to read as follows:

AUTHORITY:

Secs. 103, 104, 161, 182, 183, 186, 189, 68 Stat. 936, 937, as amended, sec. 234, 83 Stat. 1244, as amended 948, 953, 954, 955, 956, (42 U.S.C. 2133, 2134, 2201, 2232, 2233, 2236, 2239, 2282); secs. 201 t as amended (42 U.S.C. 5841, 5842, 5846),

206, 88 Stat. 1242, 1244, 1246,

[-

unless otherwise noted.

i Section 50.7 also issued under Pub. L.95-601, sec. 10, 92 Stat. 2951 Sections 50.57(d), 50.58, 50.91 ar.d 50.92 also issued (42 U.S.C. 5851).

(

i 5

[7590-01]

under Pub. L.97-415, 96 Stat. 2071, 2073 (42 U.S.C. 2133, 2239). Section Sections 50.78 also issued under sec.122, 68 Stat. 939 (42 U.S.C. 2152).

50.80-50.81 also issued under sec.184, 68 Stat. 954, as amended (42 U.S.C. 2234). Sections 50.100-50.102 also issued under sec. 186, 68 Stat.

955(42U.S.C.2236).

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));

1611, 68 Stat. 949, as li 50.10(b) and (c) and 50.54 are issued under sec.

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.1610, 68 Stat. 950, as amended (42 U.S.C.2201(o)).

2. Section 50.55a is amended as follcws:

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) are deleted; Paragraphs (g)(3)(1)and(iii)arerevised; Paragraph (g)(4)(iii)isdeletedandreserved;and Paragraph (i) is deleted.

150.55a Codes and standards._

(b)

(1)

As used in this section, references to Section III of the ASME 6

[7590-01)

Boiler and Pressure Vessel Code refer to Section III, Division 1, and in-clude editions through the 1983 Edition and Addenda through the Sumer 1984 Addenda.

(2) As used in this section, references to Section XI of the ASME Boiler and Pressure Vessel Code refer to Section XI, Division 1, and include i

editions through the 1983 Edition and Addenda through the Sumer 1983 Addenda, subject to the following limitations and modifications:

(g) * * *

(3) * * *

(1) Components which are classified as ASME Code Class I shall be designed and be provided with access to enable the performance of inservice examinatior. of such components and shall meet the preservice examination requirements set forth in Section XI of editions of the ASME 6 applied to the construction Boiler and Pressure Vessel Code and Addenda of the particular component.

(iii) Pumps and valves which are classified as ASME Code Class I 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 7

e*

[7590-01) 0 Pressure Vessel Code and Addenda applied to the construction of the particular pump or valve or the Sumer 1973 Addenda, whichever is later.

(4) * * *

(iii)[ Reserved]

Dated at- M, , MA, I this Y day of dw 1985.

y, For the Nuclear Regulatory Comission.

4 ( _

W liam J. Dircks.

Executive Director for Operations.

G 8