ML20129E698

Forwards Fr Notice Proposing Amend to Update 10CFR50.55a, Incorporating Natl Stds for Design,Fabrication,Testing, Const & Insp of Nuclear Reactor Components & Sys.Section Continually Updated

ML20129E698
Person / Time
Issue date:	04/17/1985
From:	Minogue R NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To:	Dircks W NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
Shared Package
ML20127B699	List: ML20127B694 ML20127C051 ML20127C054 ML20127C070 ML20127C401 ML20127C405 ML20127C440 ML20127C518 ML20129E625 ML20129E663 ML20129E686 ML20129E698 ML20129E717 ML20129F170 ML20129F181
References
FRN-50FR20574, RULE-PR-50 AA83-1, NUDOCS 8507170036
Download: ML20129E698 (3)

Text

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[ 9,, UNITED STATES AA B-l

[ o NUCLEAR REGULATORY COMMISSION ppg e I wasmworow.o. c. mss y*****)

Apg 17 g MEMORANDUM FOR: William J. Dircks _,

Executive Director for Operations .

2 l

4 FROM: Robert B. Minogue, Director Office of Nuclear Regulatory Research

SUBJECT:

PROPOSED AMENDMENT TO 10 CFR 550.55a - CODES AND STANDARDS Enclosed for your signature is a Federal Register Notice proposing an .

amendment to update 150.55a of 10 CFR Part 50 which incorporates by reference national codes and standards for the design, fabrication, construction, testing and inspection of reactor components and systems.

It has been a continuing policy of the Connission to update this section of the regulations to keep the references current. The preamble to the August 24, 1972, final rule amending 550.55a (37 FR 17021) states: "As new or amended editions of applicable codes, code cases, or addenda are issued, the Commission will review them and amend the provisions of l 550.55a . . . as appropriate."

1 This section of the regulations presently references Division 1 rules of Section III, " Rules for the Construction of Nuclear Power Plant Components," of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) and Division I rules of Section XI,

" Rules for Inservice Inspection of Nuclear Power Plant Components" of the ASME Code. The present reference endorses the 1980 Edition and Addenda through the Summer 1982 Addenda for Section III, Division 1, and the 1980 Edition and Addenda through the Winter 1981 Addenda for Section XI, .

I Division 1. The ASME did not publish a Susuner 1982 Addenda to Section XI, Division 1.

ASME procedures provide that editions of the ASME Code be revised every l

three years and that addenda to the editions be issued on a semiannual basis. The 1983 Edition, which was issued July 1983, updates the 1980

Edition by incorporating all addenda from the Sunner 1980 through the j Winter 1982 Addenda. Addenda subsequent to the Winter 1982 Addenda 4 modify the 1983 Edition.

This proposed amendment would incorporate by reference the Winter 1982 Addenda, Sunner 1983 Addenda Winter 1983 Addenda, Summer 1984 Addenda i and 1983 Edition of Section III Division 1, and the Winter 1982 Addenda, Sunner 1983 Addenda, and 1983 Edition of Section XI. Division 1 of the ASME Code. The edition and addenda have been reviewed by the staff and l found to be acceptable and not inconsistent with regulatory criteria. No ,

changes are proposed to previous supplementary requirements included in i i the regulation.

I 8507170036 850710 PDR PR 50 50FR20574 PDR

W. J. Dircks 2 The enclosed notice provides a period of 60 days after publication in the Federal Register for submitting coments on the proposed amendinent.

A note regarding issuance of the proposed amendment will be included in the next Weekly Report to the Comission. The Subcomittee on Energy and the Environment of the House Interior and Insular Affairs Comittee, the Subcomittee on Energy Conservation and Power of the House Comittee on Energy and Comerce, and the Subcomittee on Nuclear Regulation of the Senate Comittee on Environment and Public Works will be informed of this action. No public announcement will be issued.

Coordination: The Offices of Nuclear Reactor Regulation, Inspection and Enforcement, Administration, and Public Affairs concur in the proposed amendment to 10 CFR fj50.55a. The Office of the Executive Legal Director-has no legal objection to the proposed amendment.

b Robert B. Minogue, Di tor Office of Nuclear Regulatory Research

Enclosures:

1. Federal Register Notice

2. Draft Regulatory Analysis

3. Draft Transmittal Letter to Congressional Comittees

4. Weekly Information Report

W. J. Dircks 3 ApR 171985 1

l Approved for Publication: .

In a final rule published March 19,1982 (47 FR 11816), the Comission delegated and promulgate to therules EDOas(10 defined CFR in 1.40(c) the APA and(5(d))

U.S.C. the 551(4) authority) subject to develop to the limitations in NRC Manual Chapter 0103, Organization and Functions, Office of the Executive Director for Operations, paragraphs 0213, 038, 039, and 0310.

The enclosed proposed rule entitled " Codes and standards" amends 10 CFR 550.55a to incorporate by reference the Winter 1982 Addenda, Sumer 1983 Addenda, Winter 1983 Addenda, Summer 1984 Addenda and 1983 Edition of Section III. Division 1 and the Winter 1982 Addenda, Sumer 1983 Addenda, and 1983 Edition of Section XI, Division 1, of the ASME Code.

This proposed rule does not constitute a significant question of policy, nor does it amend regulations ' contained in 10 CFR Parts 0, 2, 7, 8, 9 Subpart C or 110. I, therefore, find that this rule is within the scope of sy rulemaking authority and am proceeding to issue it.

D M-85 la(

Date Iliam J. Dircks .

E Jtive Director for' 0perations 6

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[7590-01]

Enclosure j Federal Register Notice NUCLEAR REGULATORY COPMISSION 10 CFR Part 50 Codes and Standards for Nuclear Power Plants .

AGENCY: Nuclear Regulatory Connission.

ACTION: Proposed Rule.

o SupMARY: The Commission proposes to amend its regulations to incorporate by reference the Winter 1982 Addenda, Sunner 1983 Addenda Winter 1983 Addenda, Summer 1984 Addenda and 1983 Edition of Section III, Division 1 of the American Society of Mechanical Engineers Boiler and Pressure Yessel Code (ASME Code) , and the Winter 1982 Addenda Sunner 1983 Addenda, and 1983 Edition of Section XI Division '1, of the ASME Code. The sections of the ASME Code being incorpora+.ed 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: Comnent period expires .

Connents received after this date will be considered if it is practical to do so, but assurance of consideration cannot be given except as to connents received on or before this date.

A date will be inserted allowing 60 days for public connent.

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• - ADDRESSES: Written comuments or suggestions may be submitted to the Secre-I tary of the Comission., U.S. Nuclear Regulatory Commission Washington, D.C. 20555, Attention: Docketing and Service Branch. Copies of coments received may be examined in the Comission's Public Document Room at 1717 H Street NW., Washington, D.C.

FOR FURTHER INFORMATION CONTACT: Mr. G. C. Millman, Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S.

I Nuclear Regulatory Comunission. Washington, D.C. 20555 Telephone *

( (301)443-7860.

[ SUPPLEMENTARY INFORMATION: On February 7, 1983, the Nuclear Regulatory Commission 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 550.55a 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 I rules of Section XI, " Rules for Inservice Inspection of Nuclear Power Plant Components " of the ASME Code. On November 4,1993, the Commission published in the Federal Register (48 FR 50878) an amendment to l 550.55a tc incorporate by reference the Summer 1982 Addenda to Section III. Division 1 of the ASME Code. The ASME did not publish a Sumer 1982 l

i 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 f

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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 bywference in 550.55a. the Winter 1982 Addenda, Sumer 1983 Addende 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, Sumer 1981 Addenda, Winter 1981 Addenda Summer 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 Summer 1983 Addenda that modify Section XI. Division 1. of the ASME Code. The Suquner 1983 Addenda for Section XI does not include any technical requirements related to Division l

1 but is being included in the reference to avoid confusion that might I 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 I revisionsarecontainedentirelyin550.55a(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 inspect 15n' interval after September 1,1976. Since this one-third of an inspectioh 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)(iii) be deleted.

Power reactors for which a notice of hearing on an application for a provi; sional construction pemit or a construction pemit had been published on or

• before December 31, 1970, were permitted to use the rules for construction required by power reactors that had received their construction permits prior to January 1, 1971. Itisproposedthat$50.55a(1)whichcoversthispro-vision be deleted because it is no longer necessary. Section50.55a(c)(4) provides that for these and other facilities that received a construction permit 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 ~

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! the component at the time of issuance of the construction permit.

REGULATORY ANALYSIS The Connission has prepared a draft regulatory analysis on this pro-l 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

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NW., Washington, DC. Singl,e 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,4fashington, D.C.,

20555. Telephone (301)443-7860. ,

The Comission requests public coment on the draft regulatory analysis. Coments 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 Commission 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 ifcensing 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 issued by the Small Business Adninistration at 13 CFR Part 121.

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Since these companies are dominant in their service areas, this proposed rule does not fall within the purview of the Act.

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LIST OF SUBJECTS IN 10 CFR PART 50 I

Antitrust Classified infonnation. Fire prevention. Incorporation by  ;

reference Intergovernmental relations, Nuclear power plants and reactors,

. Penalty. Radiation protection, Reactor siting criteria, Reporting and recordkeeping requirements.

b f Pursuant to the Atomic Energy Act of 1954, as amended, the Energy r

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.

'I PART 50 - DOMESTIC LICENSING 0F PRODUCTION AND UTILIZATION FACILITIES

. 1. The authority citation for Part 50 reads as follows:

ALITHORITY: 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, asamended(42U.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

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under Pub. L.97-415,96 Stat.2071,2073(42U.S.C.2133,2239). 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). Sections 50.100-50.102 also issued under sec. '186, 68 Stat.

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

For the purposes of sec. 223, 68 Stat. 958, as amended (42 U.S.C.

2273),il50.10(a),(b),and(c), 50.44,50.46,50.48,50.54,and50.80(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 (42 U.S.C 2201(1)); and il 50.55(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 follows:

Paragraph (b)(1) and the introductory text of paragraph (b)(2) are revised; Referencetofootnote2inparagraph(g)(1)isdeleted; ,

References to footnote 3 in parag'raph (g)(2) and in paragraphs (g)(3)(ii)and(iv)aredeleted; Paragraphs (g)(3)(1) and (iii) are revised; Paragraph (g)(4)(iii)isdeletedandreserved;and Paragrap'h(1)isdeleted.

650.55a Codes and standards.

(b) ***

(1) As used in this section, references to Section III of the ASME 7

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Boiler and Pressure Vessel Code refer to Section III, Division I, and in-t clude editions through the 1983 Edition and Addenda through the Sunner 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 Sunner 1983  !

Addenda, subject to the following limitations and modifications:

2 (g)*** ,

(3)***

(1) 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. ,

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(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 and 8

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6 Pressure , Vessel 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.

.e For the Nuclear Regulatory Commission.

Jac'k W. Roe -

Acting. Executive Director for Operations.

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ENCLOSURE 2 1

Draft Regulatory Analysis For Current Proposed Amendment Revision of 10 CFR 650.55a Codes and Standards _.

1. Statement of the Problem The General Design Criteria (Appendix A of Part 50) of the NRC Regulations require that structures, systems, and components of light-water-reactors be designed, fabricated, erected, constructed, tested and inspected to quality standards connensurate with the importance of the safety function performed. Without a set of specific rules to implement these quality standards, it would be necessary for each applicant / licensee to develop its own program for submittal to the NRC. Each program would.

have to be reviewed by the staff on a case-by-case basis. This would in-crease significantly the licensing review time and would make inspections by the staff more difficult because of the nonstandard nature of each program.

To provide a consistent set of rules, which the industry has participated in developing,150.55a rendates use of Section III of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) for construction of Class 1, 2, 3 components, and Section XI of the ASME Code for inservice inspection of those components.Section III and Section XI are implemented by applicants / licensees of all light-water-cooled reactors. The NRC first endorsed the ASME Code by reference in 10 CFR 550.55a in 1971. The ASME publishes a new edition of the Code every three years and new addenda every 6 months. It has been a continuing policy of the Commission to update this section of the regulations to keep the references current. In those cases where an item in the ASME Code is inconsistent with NRC criteria, an' exception may be taken to endorsing that portion of the Code, or supplementary criteria may be incorporated to make the item consistent with staff requirements. -

Section 50.55a last endorsed the 1980 Edition and addenda through the Summer 1982 Addenda. Since then, the Winter 1982 Addenda, Summer 1983 Addenda, Winter 1983 Addenda, Summer 1984 Addenda, and 1983 Edition have been published by the ASME. The purpose of this proposed rule is to incorporate the new edition and addenda into the regulations.

The ASME Code is developed by the consensus process, which ensures that the various industry sectors (e.g., utility, NSSS suppliers, regula-tory) are represented on the standards writing committees and that their viewpoints are considered in the standards writing process. Endorsement of the ASME Code by the NRC provides a method of incorporating rules into the regulatory process that are acceptable to the NRC and have received j industry participation in their development.

I If the NRC did not take action to endorse the ASME Code, the NRC position on the methods for construction and inservice inspection would have to be established on a case-by-case basis. If the NRC did not take action to update the ASME Code references, improved methods for construction and inservice inspection might not be implemented.

2. Objectives The proposed rule would:

o Incorporate by reference into 550.55a of the NRC's ' regulations the Winter 1982 Addenda, Sumer 1983 Addenda, Winter 1983 Addenda, Sumer 1984 Addenda, and 1983 Edition of Section III, Division 1, and the Winter 1982 Addenda, Sumer 1983 Addenda, and 1983 Edition of Section XI, Division 1 of the ASME Code, o Incorporate revisions to correct certain existing footnote and paragraph references; to simplify the language of the rule; and to delete two obsolete provisions.

3. Alternatives An alternative to incorporating by reference into NRC's regulations the latest requirements of Section III, Division 1 and Section XI, Division 1, and making certain editorial revisions would be to take no action. This would mean that the NRC position on the methods for construction and inservice inspection contained in the latest edition and addenda of the ASME Code would have to be provided on a case-by-case basis; certain incorrect footnote and paragraph references would remain in the present rule; and obsolete provisions would remain to clutter the rule.

A second alternative to incorporating by reference the latest requirements of Section III, Division 1, and Section XI, Division 1, is to incorporate the entire text of these sections of the ASME Code into the NRC regulations. Because of the volume of these sections, this approach is not practicable.

4. Consequences Incorporating by reference the latest edition and addenda of the ASME-Code will establish the NRC staff position on these Code rules on a generic basis for applicants / licensees thereby minimizing the need for -

case-by-case evaluations and reducing the time and effort required for submittal preparations and license reviews.

The cost / benefit of ASME Code revisions is balanced by the manner in which these revisions are achieved through the American National Standards Institute (ANSI) consensus process. The ANSI consensus process ensures that participation in ASME Code development is open to all persons and organizations that might reasonably be expected to be directly and materially affected by the activity, and ensures that such persons and organizations shall have the opportunity for fair and equitable participation without dominance by any single interest. Consensus is established when substantial agreement has been achieved by the interests involved. Consensus requires that all views and objectives be considered, and.that a concerted effort be made toward resolution. ASME Code proposed revisions are published for public comment in the ASME Mechanical Engineering and ANSI Reporter publications prior to being submitted for final ASME and ANSI approval. Adverse public coments are referred to the

. appropriate technical comittee for resolution.

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The consensus process ensures a proper balance between utility, regulatory and other interests concerned with revisions to the ASME Code, and ensures that the cost of any Code revision is consistent with its benefit.

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Implementation of the new ASME Code rules requires certain additional information collection requirements. The Supporting Statement for Information Collection Requirements in 10 CFR 950.55a is provided in Appendix A.

The 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 in the Small Business Size Standards set out in regula-tions issued by the Small Business Administration at 13 CFR Part 121.

Since these companies are dominant in their service areas, this proposed rule does not fall in the province of this Act. The proposed rule will' have no significant effect on a substantial number of small companies.

5. Decision Rationale From the ab'ove analysis it is concluded that the proposed revision to incorporate the latest edition and addenda of the ASME Code will save applicants / licensees and the NRC staff both time and effort by providing uniform detailed criteria against 'which the staff can review any single submission. No significant additional cost to the applicants / licensees is expected as a result of NRC endorsement of the new ASME Code edition and addenda.

6. Implementation No implementation problems are anticipated. The framework for imple-mentation is already established in both the industry and the NRC.

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Appendix A Supporting Statement for Infomation Collection Requirements in 10 CFR 950.55a

1. Justification

a. Need for the Information Collection NRC Regulations in 10 CFR 550.55a incorporate by reference Section III, Division 1, and Section XI, Division 1,.cf the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code). These sections of the ASME Code set forth the requirements to which nuclear power plant components are designed, constructed, tested and inspected. Inherent in these requirements are certain recordkeeping functions.

Incorporation of the Winter 1982 Addenda, Sumer 1983 Addenda, Winter 1983 Addenda, Sumer 1984 Addenda, and 1983 Edition for Section III, Division 1 of the ASME Code would add the following recordkeeping requirements. .

Section III o Winter 1982 Addenda NB-2125, Fabricated Hubbed Flanges - New provision for surface examination requires documentation of examination results.

o Summer 1983 Addenda No additional recordkeeping o Winter 1983 Addenda NCA-3650, Design Documents for A>purtenances -

Requires Design Document for eac1 appurtenance that is to be attached to a component unless it is already included in the component Design Documents.

o Sumer 1984 Addenda NB/NC-7240, Review of (Overpressure Protection) Report .

After Installation - Addendum to report required to document any modification of the installation from that used for preparation of the Overpressure Pro-tection Report.

ND-7200, Overpressure Protection Re;) ort - Requires overpressure protection report for Class 3 components to define the protected systems and the integrated overpressure protection provided, and (ND-7240) documentation of any modification of the installation from that used for preparation of the Overpressure Protection Report.

I o 1983 Edition All requirements, except those for Winter 1982 Addenda, previously incorporated in separate amendments to 10 CFR 550.55a.

IThe 1983 Edition of Section III is equivalent to the 1980 Edition, as modified by the Summer 1980 Addenda, Winter 1980 Addenda, Sumer 1981 Addenda, Winter 1981 Addenda, Sumer 1982 Addenda, and the Winter 1982 Addenda.

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Incorporation of the Winter 1982 Addenda, Sumer 1983 Addenda, and the 1983 Edition of Section XI, Division 1, of the ASME Code would add the following recordkeeping requirements.

Section XI '

o Winter 1982 Addenda IWA-6220(b), Preparation (of Records and Reports) - Requires preparation of Owner's Report for Repairs or Replacements (Form NIS-2).

o Summer 1983 Addenda No additional recordkeeping 2

o 1983 Edition -

All requirements, except those for Winter 1982 Addenda.

previously incorporated in separate amendments to 10 CFR 550.55a.

The Winter 1982 Addenda of the ASME Code references ANSI /ASME NQA-1-1979,

" Quality Assurance Program Requirements for Nuclear Power Plants."

l NQA-1-1979 is based upon the contents of ANSI /ASME N45.2-1979, " Quality Assurance Program Requirements for Nuclear Facilities" and seven daughter standards. These standards are referenced in Regulatory Guides 1.28, 1.58, 1.64, 1.74, 1.88, 1.123, 1.144, and 1.146 as providing methods acceptable for implementing certain NRC quality assurance program requirements. NQA-1-1979 incorporates no recordkeeping beyond that originally required by the N45 standards upon which it is based. There is, therefore, no additional recordkeeping burden associated with the endorsement of NQA-1-1979.

b. Practical Utility of the Infonnation Collection These records are used by the licensees, National Board inspectors, insurance companies, and the NRC in the review of a -

variety of activities, many of which affect safety. The records are generally historical in nature and provide data on which future activities can be based. NRC Inspection and Enforcement personnel can spot check the records required by the ASME Code i to determine, for example, if proper inservice examination test methods were utilized.

c. Duplication With Other Collections of Information ASME requirements are incorporated to avoid the need for writing equivalent NRC requirements. The final rule will not duplicate the information collection requirements contained in any other -

generic regulatory requirement.

d. Consultations Outside the NRC

> No consultations.

2The 1983 Edition of Section XI is equivalent to the 1980 Edition, as modified by the Winter 1980 Addenda Winter 1981 Addenda, and the Winter 1982 Addenda.

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. e. Other Supporting Information NRC applicants and licensees have been complying with the information collection requirements of the ASME Code since 1971.

No problems with these information collection requirements have been identified to the NRC by the applicants or licensees.,

2. Description of the Information Collection -

a. Number and Type of Respondents In general, the information collection requirements incurred by 650.55a through endorsement of the Code apply to the owners of the 34 nuclear power plants under construction and to the owners of the 93 nuclear power plants in operation. The actual number of plants that would implement the edition and addenda addressed '

by the proposed revision, and thereby be affected by their information collection requirements, is dependent on a variety of factors. These factors include whether the application is for Section III or Section XI, the class and type of components

- involved, the dates of the construction permit and construction permit application, the schedule of the inservice inspection program, and whether the plant voluntarily elects to implement updated editions and addenda of the ASME Code.

b. Reasonableness of the Schedule for Collecting Information The information is generally not collected, but is retained by the licensee to be made available to the NRC in the event of an NRC inspection or audit. The preservice and inservice  ;

inspection plans are, however, submitted to the NRC for review l as part of the application for an operating license.

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c. Method of Collecting the Information

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See Item 2(b).

'd. Adequacy of the Description of the Information The ASME Code provides listings of information required and specific forms to assist, where necessary, in documenting required information.

e. Record Retention Period The retention period for information is in accordance with a schedule provided in the ASME Code. The retention periods for the more significant information keeping requirements specified in Item 1.a above are:

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Information Retention Period (3) l Design document for appurtenances Lifetime Overpressure protection report Lifetime Reports for repair and replacement Lifetime'

, 3. Estimate of Burden .

a. Estimated Hours 1 The information collection requirements inherent in incorporating by reference the latest edition and addenda of Section III, Division 1, and Section XI, Division 1, of the ASME Code are identified in Item 1.a above. These requirements may be categorized in terms of Section III requirements that document component / system design and the results of construction -

examinations, and Section XI requirements that document repairs l and replacements.

The additional Section III requirements incur a one-time burden on plants under construction. The information collection requirements associated with the proposed edition and addenda are generation of the design documents for appurtenances and the overpressure protection report. Se: tion 50.55a specifies that the Code Edition, Addenda, and optional Code Cases to be applied to reactor coolant pressure boundary, and Quality Group B and Quality Group C components must be deter-mined by the provisions of paragraph NCA-ll40 of Subsection NCA ,

of Section III of the ASME Code. NCA-ll40 specifies that the i owner (ot' his designee) shall establish the ASME Code edition and addenda to be included in the Design Specifications, but that in nc case shall the Code edition and addenda dates establishemi in the Design Specifications be earlier than three years prior to the date that the nuclear power plant ,

construction permit is docketed. NCA-ll40 further states that - l later ASME Code editions and addenda may be used by mutual i

consent of the Owner (or his designee) and Certificate Holder.

i The earliest Section III addenda being addressed in the proposed rule is the Winter 1982 Addenda. Since the last plant to be

, docketed that is still under construction was docketed in <

l October 1974 (Palo Verde Units 1, 2, 3), there is no plant under l construction for which implementation of the Section III edition l and addenda specified in the proposed rule is a requirement. '

Pla'nts may implement these improved rules on a voluntary basis, but unless they make that choice, there is no additional paperwork burden associated with incorporating the proposed Section III edition and addenda.

3 Service lifetime of the component or system.

A-4

.' . The additional Section XI requirements incur a burden associated with the documentation of component repairs and replacements.

To facilitate this documentation,Section XI provides Form NIS-2, "0wners' Report for Repairs or Replacements."

Information required by this form relates to identifying the owner and facility; identifying the components repaired or replaced and replacement components; identifying the type of work, the repair organization and by whom the work was performed; and identifying the type of tests conducted. A portion of this information, such as that to identify the owner, facility and components is already required by Form NIS-1, "0wners' Data Report for Inservice Inspections," (Form NIS-1 was part of an addenda previously incorporated by reference into 50.55a). Most of the remaining information required by Form NIS-2 can be obtained from the previously prepared component work / repair order. It is estimated that the time required to ,

complete the required documentation on Form NIS-2 is ten hours.

Nuclear power plants are required to update their inservice inspection programs by incorporating into their initial 120-month inspection interval requirements of the latest edition and addenda of Section XI, Division 1, that have been incorporated by reference into 50.55a as of 12 months prior to the date of issuance of the operating license; and by incorporating into successive 120-month inspection intervals requirements of the latest edition and addenda of Section XI that have been incorporated by reference as of 12 months prior to the start of a 120-month inspection interval. On this basis, many plants will at one time be required to implement the Section XI, Division 1, edition and addenda specified in the proposed rule. The number of plants that will be implementing the specified edition and addenda will grow gradually as each plant updates its inservice inspection program at the 10-year interval. Therefore, conservatively, the total number of plants that may ultimately be required to implement the specified ,  !

edition and addenda is 127 (i.e., 93 operating plants and 34 p.lants under construction). .

Inservice inspections are typically performed at the time of refueling (i.e., approximately every 18 months). The need to complete an NIS-2 form would occur as a result of a repair required by the results of an inservice inspection, or as a result of an unanticipated repair between refuelings. It is estimated that 2 NIS-2 forms are completed for repairs resulting from the inspection and 2 for repairs required during operation.

Assuming applicability to 127 plants, and the completion of 4 NIS-2 forms by each plant every 18 months, with ten hours required to collect information and complete each form, it is estimated that the total time required by all utilities to complete the NIS-2 form is approximately 3400 hours0.0394 days <br />0.944 hours <br />0.00562 weeks <br />0.00129 months <br /> / year (i.e.,

4 forms x 127 plants = 508 forms per 18 months, 508 forms x 2 =

1016 forms per 3 years, 1016 forms / 3 = 339 forms per year, 339 forms x 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> per form = 3390 hours0.0392 days <br />0.942 hours <br />0.00561 weeks <br />0.00129 months <br /> per year). The time required to maintain these repair and replacement records for A-5

the period noted in Item 2.e is estimated to be 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> / year for each plant. Thus, the total time required by all utilities to complete and maintain the NIS-2 form is approximately 3517 hours0.0407 days <br />0.977 hours <br />0.00582 weeks <br />0.00134 months <br /> / year.

b. Estimated Cost Required to Respond to the Collection Based upon the hours specified in Item 3.a. it is estimated that the cost of responding to the information collection required by the Section III, Division 1, and Section XI, Division 1, edition and addenda specified in the

%50.55a is a total of $211,020/ year3517 (proposed amendment hrs x $60/hr) for to

, 127 plants.

c. Source of Burden Data and Method for Estimating Burden Estimates of the number of NIS-2 forms that are completed during a year and the time required to collect the necessary i information a1d to complete the forms, were obtained from -

utility staf! inservice inspection specialists and NRC staff in the Office of Inspection and Enforcement (regional and headquarters) engaged in inservice inspection activities.

d. Reasonableness of Burden Estimate The estimate of the burden is considered reasonable because of the reliable source of the burden data.

4. Estimate of Cost to the Federal Government NRC inspection personnel who audit plant quality assurance records would include in their audit verification of the proper implementation of the NIS-2 form. The time associated with NRC inspectors verifying use of the NIS-2 form would be extremely small when the activity is performed as part of a normal quality assurance audit.

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Enclosure 3 -

Draft Transmittal Letter To Congressional Committees .

The Honorable Morris K. Udall, Chairman Subcommittee on Energy and the Environment

{

Committee on Interior and Insular Affairs United States House of Representatives Washington, DC 20515

Dear Mr. Chairman:

Enclosed for the information of the Subcommittee are copies of a notice of proposed rulemaking to amend 150.55a of the Commission's regula-tions codified in 10 CFR Part 50. Section 50.55a presently requires holders of construction permits and licenses to conform to the require-ments of certain national codes in the design, fabrication, construction, testing and inspection of specified reactor components and systems.

This section of the regulation presently references Division I 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 American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) through the 1980 Edition and Addenda through the Summer 1982 Addenda. The ASME has since issued the Winter 1982 Addenda, 1983 Edition, Summer 1983 Addenda, Winter 1983 Addenda and the Summer 1984 Addenda to the ASME Code.

ASME procedures provide that editions of the Boiler and Pressure . Vessel Code'be revised every three years and that addenda to the editions be issued on a semiannual basis. The 1983 Edition, which was issued July 1983, updated the 1980 Edition by incorporating all addenda from the l

Summer 1980 through the Winter 1982 Addenda. Addenda subsequent to the Winter 1982 Addenda modify the 1983 Edition.

The proposed amendment would incorporate by reference the Winter 1982 Addenda, Summer 1983 Addenda. Winter 1983 Addenda, and the Summer 1984 Addenda and 1983 Edition of Section III, Division 1, and the Winter 1982 Addenda, Summer 1983 Addenda, and 1983 Edition of Section XI, Division 1, of the ASME Code. The edition and addenda have been reviewed by the staff and found to be acceptable and not inconsistent with regulator; critria.

No changes are proposed to previous supplementary requirements included in the regulation.

i i

r

The Honorable Morris K. Udall 2

. . g In view of the routine nature of the amendment, we do not consider that a public announcement is warranted. _ ,

Sincerely. -

Robert B. Minogue, Director Office of Nuclear Regulatory Research

Enclosures:

As stated .

cc: Rep. Manuel Lujan e

W e

, - - - _ _ - - , . , . _ __ _ . _ . . . - . _ . , ._m___. . - _ , - - , _ , , , - -- --

- - Enclosure 4 WEEKLY INFORMATION REPORT Proposed Rule to be Signed by EDO On , 1985, the Executive Director for Operations approved a proposed rule which revises 10 CFR 650.55a, Codes and standards. This rule proposes to update the references incorporating the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) to include the Winter 1982 Addenda, Sumer 1983 Addenda, Winter 1983 Addenda, Sumer 1984 Addenda and 1983 Edition of Section III, Division 1, and the Winter 1982 Addenda, Sumer 1983 Addenda, and 1983 Edition of Section XI, Division 1, of the ASME Code.

+

l 1 l

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W. J. Dircks 2 gpg y 7 g The enclosed notice provides a period of 60 days after publica' tion in the Federal Register for submitting comments on the proposed amendment.

A note regarding issuance of the proposed amendment will be included in the next Weekly Report to the Commission. The Subcommittee on Energy and the Environment of the House Interior and Insular Affairs Comittee, the Subcommittee on Energy Conservation and Power of the House Committee on Energy and Comerce, and the Subcommittee on Nuclear Regulation of the Senate Comittee on Environment and Public Works will be informed of this action. No public announcement will be issued.

Coordination: The Offices of Nuclear Reactor Regulation, Inspection and -

Enforcement. Administration, and Public Affairs concur in the proposed amendment to 10 CFR 650.55a. The Office of the Executive Legal Director has no legal objection to the proposed amendment.

Original signed 97 ROBERTB. m unsuun Robert B. Minogue, Director Office of Nuclear Regulatory Research

Enclosures:

1. Federal Register Notice

2. Draft Regulatory Analysis

3. Draft Transmittal Letter to Congressional Comittees

4. Weekly Information Report Distribution - see attached page

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