ML20136J399
| ML20136J399 | |
| Person / Time | |
|---|---|
| Issue date: | 08/29/1985 |
| From: | Minogue R NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | Dircks W NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| Shared Package | |
| ML20058J960 | List: |
| References | |
| FRN-50FR38970, RULE-PR-50 AA83-02-07, AA83-2-7, NUDOCS 8511250356 | |
| Download: ML20136J399 (14) | |
Text
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$ # o,, UNITED STATES Certified Original: '(p/m 8[ g NUCLEAR REGULATORY COMMISSION W ASHINGTON, D. C. 20555 D
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AUG 2 91985 MEMORANDUM FOR: William J. Dircks Executive Director for Operations FROM: Robert B. Minogue, Director Office of Nuclear Regulatory Research
SUBJECT:
AMENDMENT TO 10 CFR 550.55a - CODES AND STANDARDS Enclosed for your signature is a Federal Register Notice of a final rule to amend 650.55a 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 Comission to update this section of the regulations to keep the references current. The preamble to the August 24, 1972, final rule amending 650.55a (37 FR 17021) states: "As new or amended editions of applicable codes, code cases, or addenda are issued, the Comission will review them and amend the provisions of
$50.55a . . . as appropriate."
This section of the regulations incorporates by reference - Division I rules of Section III, " Rules for the Construction of Nuclear Power Plant Components," of the American Society of Mechanical Er.gineers 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 Sumer 1982 Addenda for Section III, Divisicn 1, and the 1980 Edition and Addenda through the Winter 1981 Addenda for Section XI, Division 1. The ASME did not publish a Sumer 1982 Addenda to Section XI, Division 1.
ASME procedures provide that editions of the ASME 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, updates the 1980 Edition by incorporating all addenda from the Summer 1980 through the Winter 1982 Addenda. Addenda subsequent to the Winter 1982 Addenda modify the 1983 Edition.
This amendment incorporates by reference 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.
The edition and addenda have been reviewed by the staff and found to be acceptable and not inconsistent with regulatory criteria. No changes are proposed to previous supplementary requirements included in the regulation.
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W. J. Dircks 2 AUG 2 91985 An announcement of the proposed amendment was published in the Federal Register on May 17, 1985. Interested persons were invited to submit written coments for consideration in connection with the proposed amendment and the draft regulatory analysis by July 16, 1985. No adverse comments or significant questions were received in response to the notice of proposed rulemaking.
The enclosed notice of rulemaking will be transmitted to the Office of the Federal Register following your approval. The rule will be effective 30 days after publication in the Federal Register.
A note regarding issuance of the final rule will be included in the next Weekly Information Report to the Commission. The Subcommittee 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 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.
Ccordination: The Offices of Nuclear Reactor Regulation, Inspection and Enforcement, Administration, and Public Affairs concur in the proposed amendment to 10 CFR 550.55a. The Office of the Executive Legal Director has no legal objection to the proposed amendment.
Yb Robert B. Minogue, Director Office of Nuclear Regulatory Research
Enclosures:
- 1. Federal Register Notice
- 2. Regulatory Analysis
- 3. Draft Transmittal Letter to Congressional Comittees
- 4. Weekly Information Report Distribution - see attached page
W. J. Dircks 3 AUG 2 S 1985 P
Approved for Public_a_ti,on:
In a final rule published March 19,1982 (47 FR 11816), the Comission delegated to the E00 (10 CFR 1.40(c) and (d)) the authority to develop and promulgate rules as defined in the APA (5 U.S.C. 551(4)) subject 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 final rule entitled " Codes and standards" amends 10 CFR 550.55a to incorporate by reference the Winter 1982 Addenda, Summer 1983 Addenda, Winter 1983 Addenda, 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.
This final 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 my -
rulemaking authority and am proceeding to issue it.
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WiU]/ah J. Dircks Executive Director for Operations
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Enclosure I Federal Register Notice NUCLEAR REGULATORY COMMISSION 10 CFR Part 50 Codes and Standards for Nuclear Power Plants AGENCY: Nuclear Regulatory Commission.
ACTION: Final rule.
SUMMARY
- The Commission is amending its regulations to incorporate by reference the Winter 1982 Addenda, Summer 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 Vessel Code (ASME Code) , and the Winter 1982 Addenda, Summer 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.
EFFECTIVE DATE: (Insert date 30 days after publication in the FR).
The incorporation by reference of certain publications listed in the regulations is approved by the Director of the Federal Register as of (Insert date 30 days after publication in the FR).
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Mr. G. C. Millman, Division of FOR FURTHER INFORMATION CONTACT:
Engineering Technology, Office of Nuclear Regulatory Research, U.S.
Washington, D.C. 20555, Telephone Nuclear Regulatory Commission.
(301)443-7862.
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SUPPLEMENTARY INFORMATION: On May 17, 19ES, the Nuclear Regulatory Commission 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 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.
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This amendment revises $50.55a to incorporate by reference all editions through the 1983 Edition and all addenda through the Sumer 1984 Addenda that modify Division 1 rules of Section III, " Rules for the Construction f'
.of Nuclear Plant Components," and all editions through the 1983 Edition and all addenda through the Summer 1983 Addenda that modify Division I rules of Section XI, " Rules for the Inservice Inspection of Nuclear Power
' Plant Components," of the ASME Code. The Summer 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.
t
! Editorial revisions are included in this amendment" to correct certain L
existing footnote and paragraph references that are inconsistent with the f
' last amendment (49 FR 9711) to this rule and to simplify the language.
These editorial revisions are contained entirely in 950.55a(g).
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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 ir.spection interval has already been completed for all applicable facilities, 650.55a(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 permit 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 permits prior to January 1, 1971. This amendment deletes 550.55a(1) which covers Section 50.55a(c;(4) this provision because it is no longer necessary.
provides that for these and other facilities that received a construction pemit prior to May 14, 1984, the applicable Code Edition and Addenda for l
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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.
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l Interested persons were invited to submit written coments for considera-tion in connection with the proposed amendment and the draft regulatory analysis by July 16, 1985. No adverse coments or significant questions were received in response to the notice of proposed rulemaking.
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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 NF.C 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.
P.'$PERWORK REDUCTION ACT STATEMENT This final rule incorporates by reference information collection requirements that were reviewed by the Office of Management and Budget.
The OMB approval number is 3150-0011.
REGULATORY FLEXIBILITY CERTIFICATION As required by the Regulatory Flexibility Act of 1980, 5 U.S.C.
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.
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LIST OF SUBJECTS IN 10 CFR PART 50
' Antitrust, Classified inforniation Fire prevention, Incorporation by reference, Intergovernmental relations, Nucle 6r power plants and reactors, Penalty, Radiation protection, Reactor siting criteria, Reporting and recordkeeping requirements.
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 adopting the following amendments 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. 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.93-601, sec. 10, 92 Stat. 2951 (42 U.S.C. 5851). Sections 50.57(d), 50.58, 50.91 and 50.92 also issued 5
[7590-01]
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 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), 66 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));
65 50.10(b) and (c) and 50.54 are issued under sec. 1611, 68 Stat. 949, as amended (42 U.S.C 2201(i)); 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; 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)(i) and (iii) are revised; Paragraph (g)(4)(iii) is deleted and reserved; and Paragraph (i) is deleted.
d 550.55a Codes and standards.
(b)
(1) As used in this section, references to Section III of the ASME 6
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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 I, and include 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 examination 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 1 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 4
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6 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 gcgA this 4 day of m ff,u /u, 1985.
For the Nuclear Regulatory Comission.
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W liam J. Dircks, Executive Director for Operations.
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- Date:
Enclosure 2 Regulatory Analysis Amendment to 10 CFR 650.55a i Codes and Standards 1.- Statement of the_, Pro,blem
< The General Design Criteria (Appendix A of 10 CFR Part 50) require that structures, systems, and components of light-water-reactors be designed, fabricated, erected, constructed, tested and inspected to
' quality standards commensurate 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
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-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 increase 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, 650.55a mandates use of Section III, Division
- 1. .1, 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, Division 1 of the ASME Code for inservice inspection of those 1 components.Section III and Section XI are implemented by applicants and 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 l' new edition of the Code every three years and new. addenda every 6 months, i 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 Sunener 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 amendment is to incorporate by reference the new edition and addenda into the regulations.
The ASME Code is developed through the consensus process, which
- ensures that the various technical interests (e.g., utility,
- manufacturers, regulatory) 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 l
method of incorporating rules into the regulatory process that are acceptable to the NRC and have received industry participation in their development.
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 i
construction and inservice inspection might not be implemented.
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- 2. Objectives This amendment will:
o Incorporate by reference into 10 CFR 550.55a 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 updated 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 recent 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 these later 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 recent addenda of the ASME Code will establish the NRC staff position on these Code rules on a generic basis for applicants / licensees. This will minimize the need for case-by-case evaluations and will reduce the time and effort required for submittal preparations and license reviews.
The cost / benefit of ASME Code revisions is balanced by the manner in
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which these revisions are achieved through the American National Standards Institute (ANSI) consensus process. The ANSI consensus process ensures I 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 l
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 coment 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.
Implementation of the new ASME Code rules requires certain ade cional information collection requirements. The Supporting Statement for Information Collection Requirements in 10 CFR 550.55a is provided in Appendix A.
This amendment to 650.55a 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 regulations issued by the Small Business Administration at 13 CFR Part 121._ Since these cospanies are dominant in their service areas, this amendment does not fall in the province of this Act. The final rule will have no significant effect on a substantial number of small companies.
- 5. Decision Rationa_le From the above analysis it is concluded that this arciendment to 10 CFR 550.55a to update the reference to incorporate the latest edition and recent addenda of the ASME Code will save applicants / licensees and the NRC staff both tic.e and effort by providing uniform detailed criteria against which the_ stafi un 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 Infonnation Collection Requirements in 10 CFR 650.55a
- 1. Justification
- a. Need for the Information Collection NRC Regulations in 10 CFR 950.55a incorporate by reference Division I rules of Section III, " Rules for 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). These sections of the ASME Ccde set forth the requirements to which nuclear power plant components are designed, constructed, tested and inspec-ted. Inherent in these requirements are certain recordkeeping functions.
4 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 adds 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 componer.t Design Documents.
o Summer 1984 Addenda NB/NC-7240, Review of (0verpressure 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 over-pressure 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
%50.55a.
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, Summer 1983 Addenda, and the 1983 Edition of Section XI, Division 1, of the ASME Code adds the following recordkeeping requirements.
Section XI o Winter 1982 Addenda IWA-6220(b W Weparation jof Records and Reports) - Requires preparation of Owner's R'epoFtTor Yehalrs'orTeFacements (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
$50.55a.
The Winter 1982 Addenda of the ASME Code references ANSI /ASME NQA-1-1979,
" Quality Assurance Program Requirements for Nuclear Power Plants."
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_ th_e Information 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 to determine, for example, if proper inservice examination test methods were utilized.
- c. Duplication,With Other Collections of Informa_ti_on ASME requirements are incorporated to avoid the need for writing equivalent NRC requirements. This amendment 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 Supp gti,ng, Info _rma, tion 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 Rest.ondents In general, the information collection requirements incurred by 650.55a through endorsement of the ASME 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 Secticn XI, the class and type of components involved, the date of the 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 _Schedu_le for Collec_ ting I_nicmation 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.
- c. Method of Collec_ ting _the Informat_i_on See Item 2(b).
- d. Adequacy o_f 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 Table NCA-4134.17-1 of the ASME Code. The retention periods for recordkeeping requirements specified in Item 1.a above are:
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Information Retention Period (3)
Design document for appurtenances Lifetime Overpressure protection report Lifetime Reports for repair and replacement Lifetime Final nondestructive examination report Lifetirre Lifetime retention of the above records is necessary to ensure adequate historical information on the design and examination of components and systems to provide a basis for evaluating degra-dation of these components and systems at any time during their service lifetime.
- 3. Estinate of Buroen
- a. Estimated Hours The additional 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 c.bove. 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 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. Section 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 determined by the provisions of paragraph NCA-1140 of Subsection NCA of Section III of the ASME Code. NCA-1140 specifies that the owner (or his designee) shall establish the ASME Code edition and addenda to be included in the Design Specifications, but that in no case shall the Code edition and addenda dates established in the Design Specifications be earlier than three years prior to the date that the nuclear power plant construction permit is docketed. NCA-1140 further states that later ASME Code editions and addenda may be used by mutual consent of the Owner (or his designee)andCertificateHolder. The earliest Section III addenda that is addressed in the amendmen+. is the Winter 1982 Addenda. Since the last plant to be docketed that is still under construction was docketed in October 1974 (Palo Verde Units 1, 2, 3), there is no plant under construction for which implementation of the Section III edition and addenda specified in the final rule is a requirement. Plants may implement these improved rules on a voluntary basis, but unless they make that choice, there is no additional recordkeeping burden associated with incorporating the proposed Section III edition and addenda.
3 Service lifetime of the component or system.
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I -The additional Section XI requirements incur a burden associated with the docunentation of component repairs and replacements.
To facilitate this documentation,Section XI provides Fom NIS-2, " Owners' Report for Repairs or Replacements."
Information required by this fom relates to identifying the owner and facility; identifying the components repaired or replaced, and replacement components; identifying the type of work, the repeir 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 Fom NIS-1,
" Owners'-Data Report for Inservice Inspections," (Form NIS-1 was l part of an addenda previously incorporated by reference into 1 650.55a). 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 i 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 t
plantsunderconstruction).
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 F 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 fors = 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 ,
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the period noted in Item 2.e is estimated to be I hour / year for each plant. Thus, the total time required by all utilities to complete and maintain the NIS-2 form is approximately 2517 hours0.0291 days <br />0.699 hours <br />0.00416 weeks <br />9.577185e-4 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 this amendment to $50.55a is a total of $211,020/ year (3517 hrs x $60/hr) for 127 plants.
- c. Source of Burden Data and Method for Estimating,B,urden Estimates of the number of NIS-2 forms that are completed during a year and the time required to collect the necessary information and to ccmplete the forms, were obtained from utility staff inservice inspection specialists, and NRC staff in the Office of Inspection and Enforcement (regional and headquarters)engagedininserviceinspectionactivities.
- 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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O Enclosure 3 Draft Transmittal letter to Congressional Committees The Honorable Alan Simpson, Chairman Subcommittee on Nuclear Regulation Committee on Environment and Public Works United States Senate Washington, DC 20510
Dear Mr. Chairman:
Enclosed for the information of the Subcommittee are copies of a notice of a final rule that amends 650.55a of the Commission's regulations codified in 10 CFR Part 50. Section 50.55a requires holders of construction permits and licenses to conform to the requirements 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 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 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 Sunner 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 Summer 1980 through the Winter 1982 Addenda. Addenda subsequent to the Winter 1982 Addenda modify the 1983 Edition.
This amendment incorporates 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 regulatory criteria. No changes are proposed to previous supplementary requirements included in the regulation.
. ?-
r The Honorabia Edward J. Markey 2 An announcement of the proposed amendment was published in the Federal Register on May 17, 1985. Interested persons were invited to submit written comments within 60 days for consideration in connection with the proposed amendment and the draft regulatory analysis. No adverse comments or significant questions were received in response to the notice of proposed rulemaking.
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: The Honorable Carlos Moorhead
,