ML20150E828

Forwards Corrections to Proposed Final Rule Amending 10CFR50.55a,presenting Minor Editorial Changes.Amendatory Instruction Re Authority Citation Will Not Change.Revs to Reg Guide 1.147,re Acceptable Code Cases,Discussed

ML20150E828
Person / Time
Issue date:	11/06/1987
From:	Grimsley D NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
To:	Bosnak R NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
Shared Package
ML20150E547	List: ML20150E543 ML20150E699 ML20150E717 ML20150E745 ML20150E768 ML20150E789 ML20150E799 ML20150E817 ML20150E820 ML20150E825 ML20150E828 ML20151E040 ML20195G742 ML20195G756
References
FRN-52FR24015, RULE-PR-50 AC29-2-15, NUDOCS 8807150310
Download: ML20150E828 (15)

Text

{{#Wiki_filter::. /9C.2 9-2 PM / UNITED STATES E" o*?, ggggO NUCLEAR REGULATORY COMMISSION g

j WASHINGTON, D. C. 20555 k..... p#

Ou 1987

/ZW M / MEMORANDUM FOR: R. J. Bosnak, Deputy Director 1 Division of Engineering Office of Nuclear Regulatory Research FROM: Donnie H. Grimsley, Director Division of Rules and Records Office of Administration and Resources Management

SUBJECT:

DIVISION OF RULES AND RECORDS REVIEW 0F FINA'. RULE TO AMEND 10 CFR 950.55a The Division of Rules and Records has reviewed the final rule, "Codes and Standards for Nuclear Power Plants." We have enclosed a marked copy of the rJie that presents several minor editorial corrections. Please note that in the codified text of this rule, we have inserted the currently effective authority citation for Part 50. This authority citation was recently revised in its entirety. Note that the amendatory instruction regarding the authority citation will not change. In the Supplementary text of this rule, you note that the Regulatory Guide 1.147, which identifies the Code Cases that are acceptable to the NRC staff for implementation in the inservice inspection program, is being revised. If this revision is complete and releaseable to the public, you should note its availability in the ADDRESSES paragraph. As a part of DRR's rulemaking review process, we provided the Records Management Branch, ARM, a copy of this rule to review for compliance with th,r Paperwork Reduction Act. You should consult Brenda Shelton (28132) to ensure that the statement on information collection requirements is appropriate. If you have any questions regarding our coments, please contact Alzonia Shepard of my staff on extension 2-7651. &;qp Y R Donnie H. Grimsley, Director Division of Rules and Records Office of Administration and Resources Management

Enclosure:

As stated 8807150310 880708 $R S2 24015 PDR t .~.

T7590101] Enclos re 1 Federal ster Not' ice j / 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 1984 Addenda, Sumer 1985 Addenda, Winter 1985 Addenda, and 1986 Edition of Section III, Division 1, of the American Society of Mechanical Engineer:; Boiler and Pressure Vcssel Code (ASME Code), and the Winter 1983 Addenda, Sumer 1984 Addenda, Winter 1984 Addenda, Sumer 1985 Addenda, Ninter 1985 Addenda, and 1986 Edition of Section XI, Division 1, of the ASME Code. A limitation is placed on the use of paragraph IWB-36A0 as contained in the Vinter 1983 Addenda and Vinter 1984 Addenda of J

Section XI, Division 1. This limitation requires that for certain types of welds, IWB-3640 when implemented shall be used as modified by the Winter 1985 Addenda. In addition, the modification affecting the inservice inspection of Class 2 piping in residual heat removal systems, emergency \\ core cooling systems, and containment heat removal systems has been revised i tolimititsapplicabilityuptothe1983EditionwithaddendaupthIou~gh 1 THCLOSURE 1 i - I

~ ,[7590-01] the sumer 1983 Addenda. Thesectionsofthe-ASM5-Codebeingincorporated by reference provide rules for the construction of light water-cooled nuclear power plant componente and specify:requiremen.ts fo' inservice. inspection of ~ r those components. Adoption of.these amendments. would pennit the use of improved method for construction and inservice inspection of nuclear power plants. / meHe at%j. a p at e t o/ n 2 w EFFECTIVE 0 ATE: (-Insert sietrS01ays7rftvr puoiit.ai. ion--i; th FR). The Q incorporation by reference of certain publications listed in the reg'ulal < t tions is approved by the Director of the Federal Register as of (! m ert- $wf /M A pa ahi i.gi~ )u date-50 aays af ue r puoi ica c iun nu FR. FOR FURTHER INFORMATION CONTACT: Mr. G. C. Millman, Division of Engineer-ing, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Washington, DC 20555, Telephone: (301)443-7713. 7 SUPPLEMENTARY INFORMATION: OnJuneCS,198f,theNuclearRegulatoryCom-mission published ir the Feds.el P,cptter (52 FR 24015) a proposed amendment to its regulation, 10 CFR Part 50, "Domestic Licensing of Production an'd Utilization Facilities," to update the reference to editions and addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code). This amendment revises % 50.55a to incorporate by reference all editions through the 1986 Edition and all addenda through the Winter 1985 Addenda that modify Division 1 rules of Section III, "Rules for the Construction of Nuclear Plant Components," and Division 1 rules of Sections XI, "Rules for the Inservice Inspection of Nuclear Power.Pl' ant Components," of tie ASME Code. Specifically, this amendr ent to 5 50.55a 2 ENCLOSURE 1 J 4 4

[7590'-01]' incorporates by reference the Winter 1984 Addenda, Sumer 1985 Addenda, Winter 1985 Addenda, and 1986 Edition for Division 1 rules of Section III, and the Winter 1983 Addenda, Sumer 1984-Addenda, W1nter 1984 Addenda, Sumer 1985 Addenda, Winter 1985 Addenda, and 1986' Edition for. Division 1-rules of Section XI of the ASME' Code. The 1986 Edition is equivalent to the 1983 Edition, as modified by the Sumer 1983 Addenda, Winter 1983 Addenda, Sumer 1984 Addenda, Winter 1984 Addenda, Seimer 1985 Addenda, and Winter 1985 Addenda. The Sumer 1984 Addenda and Sumer 1985 Addenda for Section XI do not include technical requirements related to Divis}oh - 1, but are included in the reference to prevent the confusion that might occur with a lack of continuity in the addenda references. Interested persons were invited to submit written coments for con-sideration in connection with the proposed amendment by August 25, 1987. Coments were received from three individuals in response to the notice of proposed rulemaking. Two of the comentors were in favor of the pro-posed rule, and submitted suggestions for editorial clarifications. One of these cementors was concerned that the manner of specifying the endorsed editions and addenda in paraoraphs (b)(1) and (b)(?) was poten-tially confusing for this specific amendment because the latest addenda that is specified does not modify the latest edition that is specified (i.e., the Wirter 1985 Addenda modifies the 1983 Edition). The staff has reviewed the coment and is of the opinion that the proposed wording is not ambigucus to those familiar with the ASME Code and those likely to implement this rule, and that a change to the established fonnat for paragraphs -(b)(1) and (b)(2) could potentially confuse individuals familiar with the rule. Having received no other coments, written or verbal r. re.ative to this item, the staff has e'ected to retain the proposed wording for paragraphs (b)(1) and (b)(2). 3 ENCLOSURE 1 i 4 -

-[7590-01]' The other comentor in, favor'.of the proposed rule &e v6 / .fett-that the pro- ..p V1 p posed additional sentence in pgagraph (b)(2)(1) which' specifies a limitation on the use of IWB-3640 for certain addenda should be specified for clarity.. in a ' separate paragraph. :The staff has. considered and adopted this suggestion. In this final rule, the specified limitation is contained in a new paragraph (b)(2)(v). This comentor also recommended a revision to Footnote 6 to clarify details regarding implementation of the code cases specified in the identified regulatory guides. It is the opinion of the i staff that the rule should not be cluttered with such information. TTiep-fore, the revision has not been incorporated into the final rule.

However, the staff is considering incorporating additional information directly into the regulatory guides to clarify their use. Additionally, this comentor noted that the Winter 1983 Addenda to Section XI included significant inprovements to the inservice inspection of Class 2 piping. This comment is correct.

In particular, the rules specified in that addenda satisfy NRC staff concerns associated with the rules specified in earlier addenda for the inservice inspection of Class 2 piping in residual beat removal systems, emergency core cooling systems, and containment heat removal systems. Thestaffpreviouslyaddressedtheseconcernsbyincorporatinh into & 50.55a the existing modification specified in paragraph (b)(2)(iv)(A). Although the comentor did not make the point specifically, the proposed rule should have recognir d the improvements in the Winter 1983 Addenda by incorporating a revision to limit the applicability of the required existing modification specified in paragraph (b)(2)(iv)(A) to ASME Code editions and addenda up to the 1983 Edition with addenda up through the Summer 1983 Addenda. This final rule incorporates this limitation to.the use of the modification specified in paragraph (b)(2)(iv)(A). 4 ENCLOSURE 1 l _e

[7590-01] )$ bN, tits The third comentordopposed [the' proposed amendmentgk=eC ett that the NRC should not rely nn industry standards, but rather should / develop its own standards based upon NRC experience and-data.. NRC' practice is to-utilize national' standards, such as the ASME' Code, whenever possible- ~ to define acceptable ways.of implementing the _NRC's basic safety regulations. Consistent with this policy, the NRC staff participates actively in the development of many national standards, includ.ing the ASME Code, to ensure that NRC experience and data is part of the.information base used to support development of the standard. Al though the NRC 'staff e is heavily involved in the development of the ASME Code, endorsement of the ASME Code by the NRC without exception is not an automatic action as evidenced by the existing limitations and modifications specified in paragraph (b)(2) and the new limitation specified in paragraph (b)(2)(v) by this final rule. Paragraph IWB-3640 was incorporated into the Winter 19.83 Addenda of Section XI, Division 1, to provide procedures and acceptance criteria for determining the acceptability for continued service of austenitic stain-less steel piping with flaws in excess of the allowable indications spec-ified in IWB-3514.3. Concern was expressed by the NRC staff and otherf that IWB-3640, as presented initially in the Winter 1983 Addenda, did not provide an acceptable level of margin against failure for materials with low toughness, such as might occur in fluxed welds (i.e., submerged arc welds (SAW) or shielded metal arc welds (SMAW)). One concern with low toughness materials was that such materials might fail at load levels below limit load. Additionally, there was concern that secondary stresses, which were not included in the stress analysis procedures, '. 5 ENCLOSURE 1 i _, _. N

[7590h01) required.'by IWB-3640,. might contribute to 'the failure ~ of ' low toughness materials. The ASME established ~ a.special task group 'to' address theiconcerns associated with paragraph IWB-3640 as cor.tained lin the. Winter 1983 Addenda. In the interim, the NRC staff required that licensees utilizing the procedures and acceptance criteria of IWB-3640, as contained in the Winter 1983 Addenda, apply additional safety factors in their analyses to be submitte,d to the staff to account for the above concerns. NRC staff acceptance criteria were provided in Generic Letter 84-11 "Inspectio'ns,';- - of BWR Stainless Steel Piping."* In the opinion of the NRC staff, the concerns associated with material toughness have been adequately addressed by the ASME Code with the modi-fication to paragraph IWB-3640 in the Winter 1985 Addenda. This addenda provides specific acceptance criteria for SAW and SMAW type welds, and these criteria address the concerns associated with limit load and the 1 need to incorporate secondary stresses in the evaluation. This arrendment to 5 50.55a incorporates a limitation in paragraph (b)(2)(v) that allows for the use of paragraph IWB-3640, as contained in the Winter 1983 Addenda and Winter 1984 Addenda, for-al'i applications permitted in that paragraph except those associated with SAW and SMAW type welds. For these weld:,, this amendment spedfies that paragraph IWB-3640, as modified by the Winter 198!,..denda, must be used. Footnote 6 of 6 50.55a provides reference to the NRC Regulatory Guides that denote which ASME Code Cases have been determinad to be acceptable

• A copy of Generic Letter 84-11 is available for inspection or copyirIg for

< fee at the NRC Public Document Room 1717 H Street NW., Washington, DC. 6 . ENCLOSURE 1 L

c ~[7590.01]J to the'NRC staff -for' implementation..Previously, this footnot'e provided?' reference to only Reguiatory Guides-1.84.and 1.85, which denote acceptability-of Section III,' Division 1, Code Cases on design and fabrication, and or) materials, respectively.,This amendment revises Footnote 6 to incorporate a reference to Regul.atory Guide 1.147, "Inservice Inspection Code.C'ase Acceptability -- ASME Section XI Division 1," which identifies the Code' wO. Cases acceptable to the NRC staff for implementation in the inservice $L %N inspection (ISI) program of light-water-cooled nuclear power. plants. At present, the Implementation section of. Regulatory Guide 1.147 specif ths[' - Ih that applicants should make a specific requesp to the NRC to use Code Cases.endorsedJn..the reculatory guide. The next revision of Regulatory m 5{ 5 ide1.147(i.e., Revision 6)willreflectthhropose ge in ~ Footnote 6 of the regulit It will permit the use of Code Cases endorsed in the regulatory guide without a specific request to the NRC for approval. In the interim, it is the intent of.the NRC that Code Cases. listed in Regulatory Guide 1.147 be used without specific application to the NRC. This amendment further revises Footnote 6 to correct the referenced titles for Regulatory Guides 1.84 and 1.85. Subsection IWE, "Requirements for Class MC Components of light-Wat'er Cooled Power Plants," was added to Section XI, Division 1, in the Winter 1981 Addenda. However, 10 CFR 6 50.55a presently incorporates only those portions of Section XI that address the ISI requirements for Class 1, 2, and 3 components and their supports. The regulation does not currently address the ISI of containments. Since this amendment is only intended to update current regulatory requirements to include the latest ASME. Code edition and addenda, the requirements of Subsection IWE would not be. imposed 7 ENCLOSURE 1 i 4

((7590-01] upon Comission lihensees by this amendment. The c.pplicability of Subsection IWE'is being considered separately. ENVIRONMENTAL IMPACT: CATEGORICAL EXCLUSION-The NRC has determined that this final rule is the type of action described in categorical exclusion 10 CFR 51.22(c)(3). Therefore, neither an environmental impact statement-nor an environmental assessment has been prepared for this final rule. [' - REGULATORY ANALYSIS The Comission has prepared a regulatory analysis for this amendn.ent to the regulations. 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 fi St. NW., Washington, DC. Singic copies of the analysis may be obtained from Mr. G. C. Millman, Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Comission, Washington, DC, 20555, Telephone (301)443-7713. PAPERWORK REDUCTION ACT STATEMENT This final rule incorporates by reference information collection requirements that were reviewed by the office of Management and Budget (OMB). The OMB approval number is 3150-0011. 8 ENCLOSURE 1 i ___________3

' ' D590-01] REGULATORY FLEXIBILIT.Y CERTIFICATION - As required by the Regul'atory 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 enti, ties" set forth in the Regulatory Flexibility Act or the Small BusinessSizeStanderdssetoutinregulationsissuedbytheSmallB'usif.es's Administration at 13 CFR Part 121. LIST OF SUBJECTS IN 10 CFR PART 50 Antitrust, Classified information, Fire protection, Incorporation by reference, Intergovernmental relatior.s, Nuclear power plants and reactors, Penalty, Radiation protection, Reactor siting criteria, Reporting and recordkeeping requirenents. l Pursuant to the Atomic Energy Act of 1954, as amended, the Energy l Reorganization Act of 1974, as amended, and 5 U.S.C. 553, the NRC is- 'e adopting the following amendments to 10 CFR Part 50. PART 50 - DOMESTIC LICEllSING 0F PRODUCTION AND UTILIZATION FACILITIES 1 1. Theauthorityci)ationforPart50continuestoreadasfollows: ,47u % sed VA s ia i;f e AUTHORITY: Secs.p103,104,161,182,183,186,189, 60 Stat. 936, 93])(JJ) 948, 953, 954, 955, 956, as amended, sec. 2: 4, 83 Stat.1244, as amended 9 Ef; CLOSURE 1 i A_________________________._____

~ .n ..~... .a PART 50 - DCMESTIC LICENSING OF PRODUCTION AND UTILIEATION FACILITIES AUTHORITY: Secs. 102, '03, 104, 105, 161, 182, 183, 186, 189, 6G Stat. 936, 937, 938, 948, 953, 954, 955, 956, as amanded, sec. 234, 83 Stat. 1244, as amended (42 U.S.C. 2132, 2133, 2134, 2135, 2201, 2232, 2233, 2236, 2239, 2282); secs. 201, as amend'ed, 202, 206, 88 Stat. 1242, as amended, 1244, 1246 (42 U.S.C. 5841, 5F42, 5846). Section 50.7 also issued unde! Pub. L. 95-601, sec. 10, 92 Stat. 2951 (42 U.S.C. 5851).I Section 50.10 also issued under secs. 101, 185, 68 Stat. 936, 955, as amended (42 U.S,C. 2131, 2235); s'ec. 102, Pub. L. 91-190, 83 Stat. 853 (42 U.S.C. 4332).' Sections 50.23, 50.35, 50.55, and 50.56 also issued under sec. 185, 68 Stat. 955 (42 U.S.C. 2235). Sections 50.33a, 50.55a and Appendix Q also issued under sec. 102, Pub. L. 91-190, 83 Stat. 853 (42 U.S.C. 4332). Sections 50.34 and 50.54 also issued under sec. 204, 88 Stat 1245 (42 U.S.C. 5844)./ Sections 50.58, 50.91, and 50.92 also issued umier Pub. L. 97-415, 96 Stat. 2073 (42 U.S.C. 2239). Section 50.78 also iscued 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). Section 50.103 also issued under sec. 108, 68 Stats 939, as amended (42 U.S.C. 2138). Appendix F also issued under sec. s 187, 68 Stat. 955 (42 U.S.C. 2237). For the purposes of sec. 223, 68 Stat. 958, as amended (42 U.S.C. 2273); SS50.10(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)); SS50.10(b) and (::), and 50.54 are issued under sec. 1611, 68 Stat. 949, as amended (42 U.S.C. 2201(1)); and SS50.55(e), 50.59(b), 50.70, 50.71, 50.72, 50.73, and 50.78 are issued under sec. 161o, 68 Stat. 950, as amended (42 U.S.C. 2201(o)). 4 L

'. [7590-0'1] ' 53L) AW (42U.S.C.A2133,'2134,32201;-2232,2233,2236,2239', '" '$ecs. 20'., dJ 4,3 4ck 6 1244, 1246, as ?-aded. (42 U.S.C. 8'41,:58 c, N 202, 206, '88 Stat. 1242,l a s 6 a,ehded - 5846), en1=es ethensise'actdg Section 50.7 also. issued under Pub..L. 95-601,-

c. 10, 92 Stat'. 2951

/ (42U.S.C.-5851). Sections 50.58,-50.91and50.p2alsoissuedunder Pub. L. 97-415, 96 Stat. 2073 (42 U.S.C. 2239 { Section 50.78 also issued under sec. '122, 68 Stat. 939 (42 lf.S.C. 2 2). ' Sections 50.80-50.81 also issued under sec. 154, 68 Stat. 954, amended (42U.S.C.2234). Sec-tions 50.100-50.102 al'soissuedup/ersec.186,68 Stat.955(42U.S . [-- ~ 2236). For trie purpo u i of ec. 223, 68 Stat. 958, as amended (42 U.S.C. 2273), $! 50.10(~a), (b), an c), 50.44, 50.46, 50.48, 50.54, and 50.80(a) are issued under 'ec. 161b, Stat. 948, as amended (42 U.S.C. 2201(b)); 69 50.10(b) anJ (c) and 50.54 are issued under sec. 1611, 68 Stat. 949, as amended (42 U.S.C. 2201(1), en6 66 50.55(e), 50.59(b), 50.70, 50.71, 50.72, 5.0.73 and 50.'78 are iss d under sec. 1610, 68 Stat. 950, as amended-(42 U.S.C. 2201(o)). 2. For 5 50.55a, paragraph (b)(1), the introductory tcxt of para-graph (b)(2), paragroph (b)(2)(iv), and Footnote 6 are revised and para-oraph (b)(2)(v) is added to read as follws: 650.55 Codes and standards ? (b) * * * (1) Asusedinthissection,referencestoSectionIIIofthe-ASHI Boiler and Pressure Vessel Code reter to Section III, Division t. and 10 ENCLOSURE 1

[759.0-01]' include editions through the 1986 Edition and Addenda-through the Winter-1985 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, dr.d include editions through the 1986 Edition and Addenda through the Winter 1985 Addenda, subject to the folloying limitations and modifications: (iv) Pressure-retaining welds in ASME Code Class 2 piping (applies to Tables IWC-2520 or IWC-2520-1, Category C-F). '( A) ' Appropriate Coifi ['- Class 2 pipe welds in Res'. dual Heat Removal Systems, Emergency Core Cool-ing Systems and Containment Heat Removal Systems, shall be examined. When applying editinns and addenda up to the 1983 Edition through the Sumer 1983 /cdenda of Section XI of the ASME Code, the extent of examination for these systems shall be determined by the requirements of paragraph IWC-1220, Table IWC-2520 Category C-F and C-G, ard paragraph IWC-2411 fn the 1974 Edition and Adder.da through the Sumer 1975 Addenda. + + (v) Evaluation precedures and acceptance criteria for austenitic piping (applies to IWB-3640). When applying the Winter 1983 Addenda and Winte'r 19E4 Adaer:da, the rules of paragraph IFB. 36d0 may be used for all appiica-tions permitted in that paragraph, except those associated with submerged arc welds (SAW) or shielded metal arc welds (SMAW}. For SAW ce SMAW, use paragraph IWB '1640, as modified by the Winter 1985 Addenda. Footnatesth!50.55a: 11 ENCLOSURE 1 1 4

[f590-01] E 6ASME Code. ca'ses that'are authorized for use,by'the Comission staff are listed in NRC Regu'latory Guide l'.84, "Design and Code Case Accep-s tability -- ASME Section III Division 1," NRC Regulatory: Guide 1.85,' "Materials Code Case Acceptabi.lity -- ASME Section III Division 1," and NRC Regulatory Guide 1.147, "Inservice Inspection Code Case Acceptability -- ASME Section XI Division 1." The use of other Code casu may be authorized by tFe Director of the Office of Nuclear Reactor Regulation upon request pur,suant to 6 50.5Sa(a)(3). ' : i. *,- o,... Dated at .this day of 1988. For the Nuclear Regulatory Comission. Victor Stello, Jr., Executive Director for Operations. 12 ENCLOSURE ' i ^ , _ _ - _ _ _ _ _ _, -., -.. _ _.., _ _. _ _ ~ ~,. _,, _. _ _... - _ _ _ _ _

/$C ' 2$ M. c ~ ' pg 4 OCT 2 2 W MEMORANDUM FOR: L. C. Shao, Director, DEST, NRR J.' G. Partlow. Director, DRIS, NRR T.'M.'Novak, Director, DSP, AE0D J. G. Keppler, Director, OSP L D. H..Grimsley, Director, DRR, ARM W. A. Hagee, Acting Director, DISS, ARM S. A. Treby, Asst. General Counsel, 0GC FROM: R. J. Bosnak, Deputy Director Division of Engineering Office of Nuclear Regulatory Research

SUBJECT:

INTEROFFICE REVIEW 0F FINAL RULE FOR 10 CFR 50.55a TO... UPDATE REFERENCES ~ TO EDITI0h5 AND ADDENDA 0F SECTION Ill,' I DIVISION 1, AND 3ECTION XI, DIVISION 1, 0F.THE ASME BOILER AND PRESSURE VESSEL CODE Please review the enclosed final rule (Enclosure 1), including regulatory analysis (Enclosure 2), and provic'e written coments to the RES task lea.Jer before the reouested completion date. The followino sumarizes this technical review iequest. 1. Ti tle: Section 50.55e (10 CFR 50), "Codes and standards" ?. RES Task Leader: G. C. Millman, DE:EMEB, x37713 3. RES Task No.: MS 503-1 4. Cocnizant Individuals: C. Y. Cheng, NRR; l.. B. Marsh, NRR 5. Requested Action: Review, coment and make recomerdations 6. Requested Ccmpletion Date: November 5, 1987 7.

Background:

This final rule amends ! 50.5M to incorporate by reference the Vinter 1984 Addenda, Sumer 1985 Addenda, Winter 1935 Addenda and 1986 Edition cf Section III, Division 1, and the Winter 1903 Addenda, Sumer 1984 Addenda, Winter 1934 Addenda, Sumer 1985 Addenda. Wirter 1985 Addenda and 1c86 Edition cf Section .I, Division 1, of the ASME Code. The 60-day public coment period for the ornposed rule closed on August 25, 1987. Coments were received from three individuals Enclosure 3). i The public coments resulted in two revisions to paragraph (b)(2) that OFFC: NAME: j DATE: f ~6 f p( x

i i s ... OCT 2 21937 - l have been incorporated into the final rule. The resoluticn of public comments is provided in the "Supplementary Infonnation" section of the final rule. In addition to updating the references to Section !!I, Division 1, and Section XI, Division 1, editions and addenda, the final rule includes: o A limitation in paragraph (b)(2)(v) on the use of paragraph IWB-3640, "Evaluation Procedures and Acceptance Criteria for Austenitic Piping," as contained in the Winter 1983 Addenda and Winter 1984 Addenda. (The limitation reouires that the rules of IWB-3640, as modified by the Winter 1985 Addenda, be used for submerged arc welds and shielded metal atc welds.) o An applicability statement in paragraph (b)(2)(iv)(A) to limit the *- need to apply the existing modification for the inservice inspection of Class 2 piping welds in residual heat removal systems, emergency core cooling systems, and containment heat removal systems. (This revision acknowledges the improved rules for Class 2 inspections that are containe ' in the Wir.ter 1983 Addenda. The applicability statement ) limits the need to apply the existing modification up to the 1983 Edition with addenda up through the Summer 1983 Addenda.) o A revision to Footnote 6 to include reference to R.G. 1.147 to indicate that code cases contained therein have been determined by the NRC staff to be suitable for use, and to correct the referenced titles for R.G. 1.84 and R.G. 1.85. Q** ,pJ lyf R J, [pj;gj," 'M R. J. Bosnak, Deputy Director Division of Engineering Office of Nuclear Regulatory Research

Enclosures:

1. Final Rule 2. Regulatory Analysis 3. Public Comments n OrFC:EVEb~ dco-

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DE/h/

NAME:GMillmin/:b

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R80srnak

~ DAT E:/v i A' // 87

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1 l

/ '{j59001] 2 Federal. Register Notice hUCLErlR 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 1984 Addenda, Sumer 1985 Addenda, Winter 1985 Addenda, and 1986 Edition of Section III, Division 1, of the America'n' Society of Mechanical Engineers Boiler and Pressure Vessel Ccde (ASPE Code), and the Winter 1983 Addenda, Sumer 1984 Addenda, Winter 1984 Addenda, Sumer 1985 Addendr., Winter 1985 Addenda, and 1986 Edition of Section XI, Division 1, of the ASME Code.

A limitation is placed on the use of paragraph IWB-3640 as contained in the Vinter 1983 Addenda and Vinter 1984 Addenda of j Section XI, Division 1. This limitation requires that for certain types j of welds, IWB-3640 when implemented shall be used as modified by the Winter 1985 Addenda. In addit wn, the modification affecting the inservice inspection of Class 2 piping in residual heat removal systams, emergency core cooling systems, and containment heat removal systems has been revised to limit its applicability up to the 1983 Edition with addenda up through l 1 ENCLOSURE 1 i

s [7590-01] the sumer 1983 Addenda. The sections of the ASME Code being incorporated-by reference provide rules for the construction of light-water-cooled nuclear power plant co,ponents and specify requiraments 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 0 ATE: (Insert date 30 days after publication in the FR). The incorporation by reference of certain publications listed in the regu af- - tions is approved by the Director of the Federal Register as of (Insert date 30 days after publication in the FR). FOR FURTHER INFORMATION CONTACT: Mr. G. C. Millman, Division of Engineer-ing, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Washington, DC 20555, Telephone: (301)443-7713. SUPPLEMENTARY INFORMATI0h: On June 26, 1986, the huclear Regulatory Com-mission published ir the Federal Register (52 FR 24015) a proposed amendment to its regulation, 10 CFR Part 50, "Domestic Licensing of Production an'd ) l'tilization Faci!itiet " to update the reference to editions and addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code). This amendment revises 6 50.55a to incorporate by reference all editions through the 1986 Edition and all addenda through the Winter 1985 Addenda that modify Division 1 rules of Section III, "Rules for the Construction of Nuclear Plant Components," and Division 1 rules of Sections XI, "Rules for the Inservice Inspection of Nuclear Power,Pl' ant Components," o'.he ASME Code. Specifically, this amenenent to 5 50.55a 2 ENCLOSUPE 1 i 4

I '.[7590-01] -incorporates by reference the Winter 1984 Addenda, Sumer 1985 Addenda, Winter 1985 Addenda, and 1986 Edition for Division 1 rules of Section'III, ~ and the -Winter 1983 Addenda, Sumer 1984 Addenda. Wint'er 1984 Addenda, Sumer 1985 Addenda. Winter 1985 Addenda, and 1986 Edition for Division 1 rules of Section XI of the ASME Code. The 1986 Edition is equivalent to the 1983 Edition, as modified by the Summer 1983 Addenda, Winter 1983 Addenda, Sumer 1984 Addenda, Winter 1984 Addenda, Sumer 1985 Addenda, and Winter 1985 Addenda. The Sumer 1984 Addenda and Sumer 1985 Addenda for Section XI do not include technical requirements related to Div'is'iof; - 1, but are included in the reference to prevent the confusion that might occur with a lack of continuity in the addenda references. Interested persons were invited to submit written comments for ccn-sideration in connection with the proposed amendment by August 25, 1987. Coments were received from three individuals in response to the notice of proposed rulemaking. Two of the comentors were in favor of the pro-posed rule, and submitted suggestions for editorial clarifications. One of these comentors was concerned that the manner of specifying the endorsed editions and addenda in paraaraphs (b)(1) and (b)(?) was poten-tially confusing for this specific amendment because the latest addenda that is specified does not modify the latest edition that is specified (i.e., the Wirter 1985 Addenda modifies the 1983 Edition). The staff has reviewed the comment and is of the opinion that the propcsed wording is not ambiguous to those familiar with the,ASME Code and those likely to implement this rule, and that a change to the established format for paragraphs ib)(1) and (b)(2) could potentially confuse individuals f amiliar with the rule. Having received no other coments, written or verbal,. '. I relative to this item, the staff has electe : to retain the proposed wording for paragraphs (b)(1) and (b)(2). 3 JNCLOSURE 1 s 4 m,

'[7590-01]- The other comentor in' favor of. the proposed rule felt:that the pro-posed additional sentence in pragraph (b)(2)(1) which specifies ~ a limitation on the use of IWB-3640 for certain addenda should be specif,iy for clarity in a separate paragraph. The staff has considered and adopted this ~ suggestion. In this final rule, the specified limitation is contained in a new paragraph (b)(2)(v). This commentor also recomended a revision to Footnote 6 to clarify details regarding implementation of the code cases specified in the identified regulatory guides. It is the opinion of the staff that the' rule should not be cluttered with such inforination. Teep fore, the revision has not been incorporated into the final rule.

However, the staff is considering incorporating additional information directly into the regulatory guides to clarify their use. Additionally, this comirentor noted that the Winter 1983 Addenda to Section XI included sigt;ificant inprovements to the inservice inspection of Class 2 piping. This comment is correct.

In particular, the rules specified in that addenda satisfy NRC staff concerns associated with the rules specified in earlier addenda for the inservice inspection of Class 2 piping in residual heat removal systems, emergency core cooling systems, and containment heat removal systems. The staff previously addressed these concerns by incorporatinh into S 50.55a the existing modification specified in paragraph (b)(2)(iv)(A). Although the comentor did not make the point specifically, the p*oposed rule should have recognized the improvements in the Winter 1983 Addenda by incorporating a revision to limit the applicability of the required existing modification specified in paragraph (b)(2)(iv)(A) to ASME Code editions and addenda up to the 1983 Edition with addenda up through the Sumer 1983 Addenda. This final rule incorporates this limitation to the use of the modification specified in paragraph (b)(2)(iv)(A). 4 ENCLOSURE 1 L 4

'[7590-01]- ~ The third commentor was opposed to the proposed ~ amendment because he.. felt that the NRC should not rely on industry standards, but rather should develop its own standards based upon NRC experience-and da'ta. NRC practice is to utilize national standards, such as the ASME Code, whenever possible todefineaccehtablewaysofimplementingtheNRC'sbasicsafety regulations. Consistent with this policy, the NRC staff participates actively in the development of many national standards,. including the ASME Code, to ensure that NRC experience and data is part of the information base used to support development of the standard. AlthoughtheNRCItEffs is heavily involved in the development of the ASME Code, endorsement of the ASME Code by the NRC without exception is not an automatic action as evidenced by the existing limitations and modifications specified in paragraph (b)(2) and the new limitation specified in paragraph (b)(2)(v) by this final rule. Paragraph IWB-3640 was incorporated into the Winter 19.83 Addenda of Section XI, Division 1, to provide procedures and acceptance criteria for determining the acceptability for continued service of austenitic stain-less steel piping with flaws in excess of the allowable indications spec-ified in IWB-3314.3. Concern was expressed by the NRC staff and otherF that IWB-3640, as presented initially in the Winter 1983 Addenda, did not provide an acceptable level of margin against failure for materials M th low toughness, such as might occur in fluxed welds (i.e., submerged arc welds (SAW) or shielded metal arc welds (SMAW)). One concern with low toughness materials was that such materials might fail at load levels below limit load. Additionally, there was concern that secondary stresses, which were not included in the stress analysis procedures._ ! 5 ENCLOSURE 1 i

.[7590-01'] required by' IWB-3640,.might contribute to the failure of low toughness materials. ~ The ASME established a special task group to address the concerns associated with paragraph IWB-3640 a~s contained in the Winter -1983 Addenda. In the interim, the NRC staff required that licensees utilizing the procedures and acceptance criteria of IWB-3640, as contained in the Winter 1983 Addenda, apply additional safety factors in their analyses to be submitte,d to th staff to account for the above concerns. NRC staff acceptance criteria were provided in Generic Letter 84-11. "Inspect 1'onsh- ~ of BWR Stainless Steel Piping."* In the opinion of tha NRC staff, the concerns associated with material toughness have been adequately addressed by the ASME Code with the modi-fication to paragraph IWB-3640 in the Winter 1985 Addenda. This addenda provides specific acceptance criteria for SAW and SMAW type welds, and these criteria address the concerns associated with limit load and the need to incorporate secondary stresses in the evaluation. This arrendment to s 50.55a incorporates a limitation in paragraph (b)(2)(v) that allows for the use of paragraph IWB-3640, as contained in the Winter 1983 Addenda and Winter 1984 Addenda, for afi applications pemitted in that paragraph except those associated with SAW and SMAW type welds. For these s ids, this amendment specifies that paragraph IWP-3640, as modifieo oy the Winter 1985 Addenda, must be used. Fnotnote 6 of 6 50.55a provides reference to the NRC Regulatory Guides that denote which ASME Code Cases have been determined to be acceptable

• A copy of Generic' Tetter 84-11 is available for inspection or copyi g for a fee at the NRC Public Document Room 171*. H Street NW., Washington, DC.

6 ENCLOSURE 1 .i 4

'[7590-01] ~ to the'NRC staff for implementation; Previously, this footnote.provided reference to only Regulatory Guide's 1.84 and 1.85, which denote acceptability of Se'ction III, Division 1, Code Cases'on design and fabrication, and on materials, respectively. This amendment revises Footnote-6 to incorporate a reference to Regulatory Guide 1.147, "Inservice Inspection Code Case Acceptability -- ASME Section XI Division 1," which identifies the Code Cases acceptaM e to the NRC staff for implementation in the inservice inspection (ISI) program of light-wter-cooled nuclear power plants. At present, the Implementation section of Regulatory Guide 1.147 speciff5s['y - that applicants should make a specific request to the NRC to use Code Cases endorsed in the regulatory guide. The next revision of Regulatory Guide I.147 (i.e., Revision 6) will reflect the proposed change in Footnote 6 of the regulation. It will pemit the use of Code Cases endorsed in the regulatory guide without a specific request to the NRC for approval. In the interim, it is the intent of the NRC that Code Cases. listed in Regulatory Guide 1.147 be used without specific application to the NRC. This amendment further revises Footnote 6 to correct the referenced titles for Regulatory Guides 1.84 and 1.85. Subsection IWE, "Requirements for Class MC Components of Light-Wafer Cooled Power Plants," was added to Section XI, Division 1, in the Winter 1981 Addenda. However, 10 CFR % 50.55a presently incorporates only those portions of Section XI that address the ISI requirements for Class 1, 2, and 3 components and their supports. The regulation does not currently address the ISI of containments. Since this amendment is only intended to update current regulatory requirements to include the latest ASME. Code edition and addenda, the requirements of Subsection IWE would not,be imposed 7 . ENCLOSURE 1 \\ 4

~ ~ [7590-01] 4 upon Comission licensees by this amendment. The applicability of Subsection IWE is being considered separately. ENVIRONMENTAL IMPACT: CATEG0kiCAL EXCLUSION The liRC has determined that this final rule is the type of action described in categorical exclusion 10 CFR 51.22(c)(3). Therefore, neither an environmental impact statement.nor an environmental assessment has been prepared for this final rule. [';- - REGULATORY ANALYSIS The Commission has prepared a regulatory analysis for this amendment to the regulations. 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 li St. !!W., Washington, DC. Single copies of the analysis may be obtained from Mr. G. C. Millman, Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Comission, Washington, DC, 20555, Telephone (301)443-7713. PAPERWORK REDUCTION ACT STATEMENT This final rule incorporates by reference information cellection requirements that were reviewed by the office of Management and Budget (0MB). The OMB approval number is 3150,0011, 8 ENCLOSURE 1 i 4

,7590-01) ~ [ ,c REGULATORY FLEXIBILITY CERTIFICATION As required by.the Regulatory Flex'ibility.Act'of 1980, 5 U.S.C. 605(b), the Commission 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 BusinessSizeStandardssetoutinregulationsissuedbytt.2SmallB'usi[hess ~ Administration at 13 CFR Part 121. LIST OF SUBJECTS IN 10 CFR PART 50 Antitrust, Classified inforniation, Fire protection, Incorporation by reference, Intergovernmental relations, Nuclear power plants and reactors, Penalty, Radiation protection, Reactor siting criteria, Reporting and recordkeeping requirerents. Pursuant to the Atc.mic Energy Act of 1954, as amended, the Energy Reorgar.ization Act of 1974, as amended, and 5 U.S.C. 553, t.e NRC is adopting the following amendirents to 10 CFR Part 50. PART 50 - DOMESTIC LICEllSING 0F PRODUCTION AND UTILIZATION FACILITIES 1. The authority citation for Part 50 continues to read as follows: AUTHORITY: Secs.103,104,161,182,103,186,189, 68 Stat. 936,-947,'- 948. 953, 954, 955, 956, as amended, sec. *!34, 83 Stat. 1244, as amended 9 ENCLOSURE 1 i

~ [7590-01). - i (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. S841, 5842, 5846), unless o' herwise notd.- t Section 50.7 also' issued under Pub. L.-95-601, sec. 10, 92. Stat. 2951 f ~ (42 U.S.C. 5851). Sections 50.58,~50.91 and 50.92'also issued under Pub.L.97-415,96 Stat.2073(42U.S.C.2239). Section 50.78 also issued. under sec. 122, 68 Stat. 939 (42 U.S.C. 2152). Sections 50.80-50.81 also issued under sec. 184, 68 Stat. 95.4, as amended (42 U.S.C. 2234). Sec-tions 50.100-50.102 also issued 'under sec.186, 68 Stat. 955 (42 U.S'.[';- - 2236). For the purposes of sec. 223, 68 Stat. 958, as amended (42 U.S.C. 2273), 1 $! 50.10(a), (b), and (c), 50.1* 50.45, 50.48, 50.54, and 50.80(a) are issued undersec.161b,68 Stat.948,asamended(42U.S.C.2201(b));il50.10(b)and (c) and 50.54 are issued under sec. 1611, 68 Stat. 949, as amended (42 U.S.C. 2201(1));andil50.55(e),50.59(b),50.70,50.71,50.72,50.73and50.78are issued under sec. 161o, 68 Stat. 950, as amended (42 U.S.C. 2201(o)). 2. For 5 50.55a, paragraph (b)(1), the introductory text o' para- ) graph (b)(2), paragraph (b)(2)(iv), and Footnote 6 are revised and para-graph (b)(2)(v) is added to read as follows: 5 650.55 Codes and standards (b) * * * (1) Asusedinthissection,referencestoSectionIIIcaftheASIE Boiler and Pressure Vessel Code re'er to Section III, Division 1,.and 10 ENCLOSURE 1 t

-{7590-01]' inc1'ude editions through the 1986 Edition and Addenda'through.the Winter 1985~ Addenda. ,(2) As used 'in.this section, r~eferences to Section:XI of t.he ;ASME Boiler and Pressure Vesse1 Code refer to Section'XI, Division 1. and include editions through the 1986 Edition and Addenda through the Winter 1985 Addenda, subject to the following limitations and modifications: (iv) Pressure-retaining welds in ASME Code Class 2. piping (applies. to Tables WC-2520 or IWC-2520-1, Category C-F). (A)AppropriateCodh[';- Class 2 pig welds in Residual Heat Removal Systems, Emergency Core Cool-ing Syster.s and Containment Heat Removal Systems, shall be examined. When applying editions and addenda up to the 1983 Edition through the Sumer 1983 Addenda of Section XI of the ASME Code, the extent of examination for these systems shall be detennined by the requirements of paragraph IWC-1220, Table IWC-2520 Category.C-F and C-G, and paragraph IWC-2411 in the 1974 rdition and Adder.da through the $umer 1975 Addenda. + f (v) Evaluation procedures and acceptance criteria for austenitic piping (applies to IWB-3640). When applying the Winter 1983 Addenda and Winte'r I !984 Adaenda, the rules of paragraph IW8-3640 may be used for all applica-tiens permitted in that paragraph, except those associated with submerged arc welds (SAW) or shielded metal arc welds (SMAW). For SAW or SMAW, use paragraph IWB-3640, as modified by ;he Winter 1985 Addenda. Footnotes to 5 50.55a: 11 ENCLOSURE 1 i 4

c[7590-01) ' t 6ASME Code cases that are' authorized for' use by the ' Commission 'sta'ff are listed in NRC Regulatory Guide 1.84, "Design and Code Case ~Accep-t'bility -- ASME Section III Division 1," NRC Regulatory.Guida'1.85, a "Materials Code Case Acceptability -- ASME Section III. Division l'," and NRC Regulatory Guide 1.147, "Inservice Inspection Code Case Acceptability -- ASME Section XI Division 1." The use of other Code cases may be authorized'by the Director of the Office of Nuclear Reactor Regulation upon reauest pur,suant to 6 50.55a(a)(3). i.s c Dated at this day of-1988. 'For tne Nuclear Regulatory Connission. Victor Stello, Jr., Executive Director for Operations. .~ 12 ENCLOSURE 1 4 b

PDR s Certified Original: Date: Regulatory Analysis Amendment to 10 CFR $ 50.55a Codes and Standards Executive Sumaty' Section 50.55a of the NRC regulations requires that nuclear power plant owne'rs construct Class 1, 2, and 3 components in accordance with the rules pro-vided in Section III, Division 1, of the ASME Boiler and Pressure Yessel Code (ASME Code) and that they provide for and perform an inservice inspection of those components in accordance with the rules provided in Section XI, Division 1, of the ASME Code. NRC has been mandating this requirement since shortly after initial publication of Section Ill and Section XI of the ASME Code in 1971. The preamble to the August 24, 1972, final rule amending 6 50.55a (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 6 50.55a... as appropriate." The mechanism for endorsement, which has been used since the first endorsement 4 in 1971, has been to incorporate by reference the ASME Code into 6 50.55a. The regulation identifies which edition and addenda of the ASME Code have been approved by the NRC for use. At present, the NRC endorses for Section III, Civision 1, all addenda through the Sumer 1984 Addenda and all editions through the 1983 Edition, and for Section XI, Division 1 all addenda through the Sumer 1983 Addenda and all editions through the 1983 Edition. This amend-ment incorporates by reference all editions through the 1986 Edition and a'il addenda through the Winter 1985 Addenda for both Section III, Division 1, and Section XI, Division 1. This amendment is of particular importance to operating plants because 6 50.55a requires that licensees update their inservice examination and in-service testing programs every ten years to comply with the requirements of the latest edition and addenda of Section XI, Division 1, endorsed by the NRC 12 months prior to the start of the next ten year interval. This amendment is also of importance to plants prchring for their initial inspection interval, for these plants must comply with the latest edition and addenda of Section XI, Division 1, endorsed by the NRC 12 months prior to the date of issuance of the operating license. The ASME Code is developed through the American National Standards Insti.tu'te consensus process. This ensures that the.various technical interests (e.g., utility, manufacturing, insurance, regulatory) are represented on the standards 1 s 4

e development conmittees and their viewpoints are addressed fairly in the stan-dard: writing process.. In general, revisions are made.to improve.the Code by providing nore detailed rules where experience indicates areater guidance is necessary, or relaxing the rules where experience shows equivalent operational safety can.be maintained with a reduced burden on~the. licensees. The consensus process ensures that the. cost. and benefit of revisions to the ASME Code are properly considered from all si. des and are reasonably balanced. Should the NRC staff feel that at any ti.'e in the process safety is being compromised, it can and has taken exception in 5 50.55a to the rules provided in the ASME Code. This does not occur often, but 11 available to the staff d en necessary. This amendment does not conflict with any existing or proposed regulatory action. In particular, the JSME Code rules that address the criteria for allowable cracks in austenitii, stainless steel piping provide the basis for existing and prop *osed generic letters on the inspection of BWR stainless steel piping. It is concluded that this amendment, when implenented, would esult in a -n'et increase in the overall protection of public health and safety, because it will be the improved rules that will be used in new and subsequent inservice inspection programs. Obsolete requirements will not be promulgated from inspection interval to inspection interval. 1. Statement of the Problem The General Design Criteria (Appendix A of 10 CFR Part 50) require th6t structures, systems, and components of light-water-reactors be designed, fabricated, erected, constructed, tested and inspected to quality standards corrensurate with the importance of the safety function performed. Without a set of specific rules to implement these quality standards, it would be ~neces-sary for each erplicant and licensee to develop its own progran for submittal to the fJC. Each program would have to be reviewed by the staff on a case-by-case basis, lhis would increase significantly the licensing review tin'e and would make inspectiuns 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, 5 50.55a mandates use of Section III, Division 1, of the ASME Code for ccrstruction of Class 1, ?, 3 components, and Section XI, Division 1 of the ASME Code for inservice inspection of these corrponents. 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 l ! 50.55a in 1971. The ASME publishes a new edition of the Code every three

years, in the past, new addenda have been published for Section III, Division 1, and for Section XI, Division 1, every six months.

Since 1986., new addenda have been published once a year. It has been a continuing policy of the Connission to update this section of the regulations to keep the references current. In those cases where an item in the ASPE 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 wi.th staff requirements. \\ c

Section 50.55a presently endorses all addenda 'throug'h the Sumer 1984 Addenda, and all editions through the 1983 Edition for Section III, Division 1, and all addenda'through the Summer 1983 Addenda, and all editions through the 1983. Edition'.for Section.XI, - Division 1. The purpos'e of this amendment is to incorporate by reference into the regulations all addenda-th, rough. the. Winter 1985 Addenda and all editions through the 1986 Edition for both Section III, . Division 1 and Section XI,. Division 1. The ASME Code.is developed through the consensus process, which ensures that the various technical interests (e.g., utility, manufacturers, insurance, regu-latory) are represented on the standards development 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 industry consideration in their development. IftheNRCdidnottakeactiontoendorsetheASMECode,theNRCpositioiibn-methods for construction and inservice inspection would have to be establishied 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 impler..ented. 2. Objectives This final rule amends % 50.55a to: o Incorporate by reference into 10 CFR 6 50.55a, the Winter 1984 Ad-denda, Summer 1985 Addenda, Winter 1985 Addenda, and 1986 Edition for Section III, Division 1, and the Winter 1983 Addenda, Sumer 1984 Addenda, Winter 1984 Addenda, Sumer 1985 Addenda, Winter 1985 /ddenda, and 1986 Edition for Section XI, Division 1, of the ASME Code. o Require that when using paragraph IWB-3640 of Section XI, Division 1, for submerged arc welds and shielded metal arc welds the Winter 1985 Addenda be used in place of the rules contained in the Vint,er 1983 Addenda and Winter 1984 Addenda, o Revise footnote 6 to incorporate a reference to Regulatory Guide 1.147, "Inservice Inspection Code Case Acceptability --- ASME Sec-tion XI Division 1," and to correct the referenced titles for Regulatory Guides 1.84 and 1.85. use of mod fication specified in paragraph (b)(2)(iv)(A) for o Limit i Class 2 piping i tpections for residual heat removal systems, emergency core cooling systems, and containment heat removal systems, to ASME i Code editions and addenda up to the 1983 Edition with addenda up through the Summer 1983 addenda. 3. Alternatives-One alternative to incorporating by reference into NRC's regulations the up-dated requirements of Section III, Division 1, and Se-tion XI, Division 1 3 i 4

notincj the need to use the improved IWB-3640. rules contained in the Winter 1985 ~ Addenda, limiting the use of the existing modification for Class 2 piping inspec-tion rules, and making the editorial revision to Footnote 6 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 en a case-by-case basis, the improvement rules for inspection of Class 2 would not be implemented and there 'could be some question as to the applicability of Regulatory Guide 1.147. ~ 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 rtgulations. Be-cause of the volume of these sections, this approach is not practicable. 4. Consequences, ~' a. Costs and Benefits "~ Incorporating by reference the latest edition and recent ad ada of the ASME Code will establish the NRC staff position on 'these Code rules on a generic basis for applicants and 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 manrer in which these revisions are achieved through the American National Standards Institute ( ANSI) consensus process. The ANSI consensus process ensures that participa-tion in ASME Code development is open.to all persons and orcanizations that night reasonably be expected to be directly and materially affected by the activity, and ensures that such persons and organizations shall have the op-portunity for fair and equitable participation without dominance by any single interest. Consensu:, is established when sul,s tantial agreement has been achieved by the interests involved. Consensus requires that c11 views and ob-jections be considered and that a concerted effort be made toward resolution. ASME Code proposed revisions are published for public coment in the ASME Pechanical Engineering and ANSI Reporter publications prior to beirig submitted for final ASkE and ANSI approval. Adverse public comments are referred to th'e appropricte technical comittee for resolution. The consensus process ensures a proper balance between utility, manufacturing, reEulatory and other interests concerned with revisions to the ASME Code, and ensures that the cost of implementing any Code revision is consistent with its

benefit, b.

Impacts on Other Requirements (1) Effect of Amendment on Existing NRC Requirements Section III and Section XI have been revised, in the past, twice a year. These revisions have been published in two addenda each year (i.e., Sumer Addenda and Winter Addenda). Starting in 1986, there is er.ly one addenda fo each of these sections and it will be called the 19XX Addenda (e.g., 19>6 Addenda). The revisior.s are the i!sult of consensus participants a i 4

meeting 4 ' S times a year for the purpose of improving the. existing ~ rules. The; revisions take.into ' account the many -lessons learned in a specific area since the development of a' particular, Code rule. The revisions. generally fall iinto three categories; a.)' technical revisions that incorporate new rules in technical' areas not previously. addressed by - the Code; b) technical revisions to ' existing ' rules; and c) editorial revisions.. When a ' technical revision is made, it' may make the existing set of rules more or less restrictive, or may simply clarify the existing rule without changing its intent.. There are numerous revisions in each addenda. Appendix-A provides a sunnary of those revisions considered to be significant that are included in the addenda and edition affected by the proposed amendment. In general, technical revi.sions are made to improve.the ASME Code by providing more detailed fules where experience indicates greater guidance.is necess_ary,, or relaxing the rules where experience shows equivalent operational safety c,an-be maintained with a reduced burden on the licensee. Relative to implementation of Section Ill, Division 1, 5 50.55a specifies that the ASME Code edition and. Addenda to be applied to reactor coolant pres-sure boundary (i.e., Class 1), and Quality Group B (i.e., Class 2) and Quality Group C (i.e., Class 3) components must he determined by the provisions of ~ paragraph NCA-1140 of Subsection NCA of Section III, Division 1, of the ASME Code, but the applicable edition and addenda must be those which are in-corporated by reference in 6 50.55a. 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 ccnstruction permit is docketed. NCA-1140 further states that later ASME Ccde editions and addendc may be used by mutual consent of the Owner (or his designee) and Certificate Holder. Plants may implement the improved rules on a voluntary basis as they are incorporated by reference into 9 50.55a, but unless they make that choice, there is no additional burden associated with incorporating the proposed Section III edition and addenda. Relative to irplementation of Secticn XI, Division 1, 6 50.55a specifies that: (a) Inservice examinations of components, inservice tests of purrps and valves, and system pressure tests conducted durin0 the initial 120-month inspection interval shall comply with the requirements in the latest edition and addenda of the ASME Code incorporated by reference on the date 12 months prior to the date of issuance of the operating license, subject to any limitations noted ($ 50.55a(4)(1)). (b) Similar to (a), above, for successive 120-month inspection interval it is necessary to comply with the requirements of the latest edition and addenda of the ASME Code incorporated by reference 12 months prior to the start of the 120-month inspection interval, subject.to any limitations nuted ($ 50.55a(4)(ii)). 5 i

(c) If a licensee determines that conformance with certain Code require-ments is impractical for.his facility, the. licensee shall notify.the Comission and submit. information' to support.his determination ($ 50.55a(g)(5)(iii)). 'The Comission will ' evaluate licensee deter-minations that Code requirements 1. are impractical 'and may grant requirements givin due such relief and may impose ' alternative (5 50.55a(g)(6)g(1)). consideration to the burden on the. licensee The existing requirements in 5 50.55a-specified in Items (a) and (b), above, ensure that all plants perform inservice inspection and inservice test pro-grams in conformance with updated versions of Section XI of the ASME Code. The proposed amendment would update the editions and addenda that are endorsed by the NRC staff, and would thereby cause the'se later editions and addenda to be licensees consistent with the time constraints identified in implemented by(b),, above. Items (a) and The recuirement in Item (c), above, provides for the submittal of relf'e~f' requests by licensees. It ensures that in those cases where the generic requirements of Section XI are impractical, or are overly burdensome for a specific facility, that facility may obtain some relief from the particular requirement, provided the licensee demonstrates to the Comission that omission of the Section XI requirement believed to be impractical will not have an adverse affect on prblic health and safety. As noted in Appendix A, there are numerous changes in the addenda being incor-porated by reference into ! 50.55a. Some of the changes reduce the burden of the licensee in implementing the Code, while others increase the burden. In any event, all the revisions were developed as part of the consensus process and, therefore, have been thoroughly reviewed by all elements of the nuclear industry, as well as the NRC staff. It is fair to say that the consensus pro-cess ensures that the value of any revision to the ASME Code is balanced by its burden on th industry. The revisions generally improve plant safety by incorporating new rules to cover areas not previously addressed, or by revising the rules consistent with experience to reduce the number of areas where the Code has been found to,be impractical, inadequate, or insufficiently clear. As noted above, b SC.55a presently requires that licensees update their in-service inspection programs every 10 years to the Section XI rules that were endorsed by the NPC 12 months prior to the start of the next 120-month in-spection interval. There will be a substantial increase in sefety through the endorsement of the later addenda and edition, because it will be these addenda and edition that will be used in subsequent inservice inspection programs. Obsolete requirements will not be promulgated from inspection interval to inspection interval. (2) Effect of Amendment on NRC Regulatory Actions That Address the Inspection of BWR Stainless Steel Piping This amendment addresses one area where an NRC regulatory action exists and where a proposed action is pending. The actions are associated with the } 6

inspection of austenitic stainless steel piping. Cracks in austenitic stain-less steel piping have been a ' concern since.1973 when -intergranular stress corrosion cracking (IGSCC) was first 'noted in some BWR feedwater lines. ~ Since the Winter 1975 Addenda, Section.XI, Division 1, has -provided criteria in paragraph IWB-3514.3 ~for allowable indications ^in :austenitic piping. Because IGSCC of ten exceeded these criteria, the ASME Code developed supple- ~ mental rules that permitted evaluation and possible, acceptance :of these cracks for limited operating periods. These supplemental rules were incorporated into paragraph IWB-3640 in the Winter 1983 Addenda of Section XI, Division 1, to provide procedures and acceptance criteria for determining the acceptability for continued services of austenitic stainicss steel piping with flaws in excess of the allowable indications specified in IWB-3514.3. Generic Letter.84-11, "Inspections of BWR Stainless Steel Piping," was issued to provide licens'ees with a sumary of actions that the staff considered an ac-ceptable response to IGSCC concerns at the time. This generic letter prov'idhd - licensees with the bases for a reinspection program for piping susceptible'to IGSCC. Among other things, the generic letter provides. crack evaluation and repair criteria. These criteria are based, in part, upon' rules provided in the Winter 1983 Addenda of Section XI, Division 1. Because of uncertainties associated with crack sizing, the staff has adopted a criteria in Generic Letter 84-11 that permits operation with cracked welds for the time period that the cracks are evaluated to not exceed 2/3 of the limits for depth and length provided in paragraph IWB-3640 of the Winter 1983 Addenda of Section XI, Division 1. An additional concern expressed by the NRC staff and others was that IWB-3640, as contained in the Winter 1983 Addenda, did not provide an acceptable _ margin against failure for low toughness materials. The ASME established a special task group to address this concern. The result was a revision to IWB-3640 that appeared in the Winter 1985 Addenda. In the opinion of the NRC staff, this revision adequately addresses the concerns associated with the use of IWB-3640 for low toughness materials. The intent of the limitation in the proposed amendment is to prevent the use of IWB-3640 rules in the Winter 1983 Addenda and Winter 1984 Addenda for low toughness materials, and to require instead.the use of the improved rules as they are provided in the Winter 1985 Addenda. NUREG-0313, Revision 2, "Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping," among other things, pro-vides updated guidelines for evaluating IGSCC cracks for limited further opera-tion. This report, which incorporates public coments and is now in the NRC review and. approval process, states that the problem of low toughness material i has been addressed by the Code, and that the Winter 1985 Addenda provides appropriate criteria for all types of welds. NUREG-0313, Revision 2, also addresses the original uncertainties associated j with the ability to adequately size cracks for evaluation by IWB-3640. The-NUREG points out-that this issue has been addressed by the industry, with.sup-port from NRC. Recognizing that much of the uncertainty was associated with examinations being perfonned by examiners with limited knowledge and expertence in sizing IGSCC, the industry established a training and qualification program at the EPRI NDE Center in Charlotte, North Carolin.. 7 i rs

The staff now believes that flaw sizes can' be adequately determined when both examiners and procedures are qualified by tests provided at the EPRI NDE Center. A Generic Letter to implement the criteria in the technical. basis document. NUREG-0313, Revision 2, has been prepared and is in the review and approval process along with the subject HUREG. IUB-3640 as presented in the Winter 1983 Addenda provides the basis for the crack acceptance criteria specified in Generic letter 84-11. The improvements to IWB-3640 for low toughness materials that are contained in the Winter 1985 Addenda provide the basis for the proposed generic letter that would implement the staff technical findings that are provided in NUREG-0313, Revision 2. NRR is presently using the criteria specified in the Winter 1985 Addenda on a case-by-case basis.. Since the 1986 Edition of Section XI, Division 1, is a compos-ite of the 1983* Edition and all subsequent addenda through the Winter.19B5 Addenda, the 1985 Edition contains the acceptable rules for base materials'ahd: low toughness materials. (3) Application of Backfit Rule (650.109) It is the opinion of the Office of the General Counse, that this amendment should not be subjected to the backfit provisions in 10 CFR 550.109. The rationale is that, (1) the Section I!!, Division 1, update applies only to new construction (i.e., the edition and addenda to be used in the construction of a plant are selected based upon the date of the construction pennit and are not changed thereafter, except voluntarily by the licensee, (2) licensees are fully aware that 6 50.55a requires that they update their inservice inspection program every 10 years to the latest edition and addenda of Section XI that were incor-porated by reference in s 50.55a 12 months before the start of the r. ext inspec-tion interval, and (3) endorsino and updating references to the ASFE Code, a national consensus standard developed by participants (including the NRC) with broad and variet interests, is consistent with both the intent ard spirit of the backfit rule (i.e., NRC provides for the protection of the public health and safety, and dots not unilaterally impose an undue burden on applicants or licensees). ( (4) Impact on Requirements of Other Government Agencies Implementation of the new ASME Code rules requires certain additional informa-tic >n collection requirements. The Supporting Statement for Information Collec-tion Requirements in 10 CFR s 50.55a is provided in Appendix B. This amendment to 5 59.556 affects only the lictnsing and operating 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 Flexi-bility Act in the Small Business Administration at 13 CFR Part 121. Since these companies are dominant in their service areas, this amendment does not fell in the province of this Act. This final rule will have no significant ef-feet on a substantial number of small companies. 1 8 L e

~ '(5)' Decision Ratidnale From the above analysis it is_ concluded that this amendment ~ t'o 10 CFR $ -50.555 ~ l - to update the reference.'to incorporate the late'st edition and recent adderda of'. the 'ASME Code. would. result in a net increase' in the overall protection of pub 1ic health and -safety, because the. improved rules would be used in new and ~ subsequent ' inservice ~ inspection.. programs, and wouldf save; applicants and~ 1icensees, and.the NRC. staff both time and effort by providing unifonn detailed criteria against which the staff could review any single submis~sion. No significant additional cost to applicants and lic'ensees 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 implementation is already estabfished in both the industry and the NRC. e et G 9 9 L -~.- CN

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+ e Appendix B Supporting' Statement for Infonnation Collection Requirements in 10 CFR 6 50.55a Justification a. Need for the Information Collection NRC Re,sulations in 10 CFR 6 50.55a incorporate by.refere.nce Division 1 rules of Section III, "Rules for Construction of Nuclear Power. Plant Components," and Division 1 rules of Section XI, "Rules fo'r '" -. Inservice Inspection of Nuclear Power Plant Corrponents," of the - ' American Society' of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code). These' sections of the ASME Code set forth the reouirements to which nuclear power plant components are designed, constructed, tested and inspected. Inherent in these requirements are certain recordkeeping functions. Incorporation of the Winter 1984 Addenda, Sumer 1985 Addenda, Winter 1985 Addenda, and 1986 Edition for Section III, Division 1, of the ASME Code adds the following recordkeeping requirements. Section III o Winter 1984 Addenda NCA-8213(c); Attachment of Nameplates - Nameplates attached with pressure sensitive acrylic adhesive system must meet requirements of mandatory Appendix XXI, "Adhesive Attachment of Nameplates," which stated that Certificate Hoiders OA manuals ~ contain written procedures for the application of nameplates 7 NB/NC/ND-7141; Installation of Pressure Relief Devices - Technical justification for the adequacy of the installation of such devices must be provided in the Over-pressure Protection Report. o Sumer 1985 Addenda NB-4622.11; Temaer Bead Weld Repair to Dissimilar Metal Welds or Buttering - Requires preparation of welding procedure specification, o Vinter 1985 Addenda NCA-8440; Data Reports, Component Sup orts - New provisions t require the use of NF-1 and N-5 Da a Teport Forms. A-1

1 ' NC-3812/NC-3912; Design Rep' ort - Certificate Holder must pro-vide Design Report as part of his responsibility for achieving structural integrity of atmospheric storage tanks (NC-3812) and 0 - 15 psi storage' tanks (NC-3912). o Winter 1984 A'ddenda No additional recordkdeping. NC/ND-7750; Capacity Certification of Vacuum Relief Valves - Requirement that drawings and test results are to be sub-mitted to the ASME designee for review and acceptance. I o 1986 Edition The Sumer 1983 Addenda, Winter 1983 Addenda, Sumer 198.4 Addenda, and 1983 Edition have been incorporated by reTer-ence into 10 CFR $ 50.55a by a previous amendment. I nfo'r-mation collection requirements for the Winter 1984 Addenda, Sumer 1985 Addenda, and Winter 1985 Addenda are discussed above. Incorporation of the Winter 1983 Addenda, Sumer 1984 Addenda, Winter 198i Addenda, Sumer 1985 Addenda, Winter )985 Addenda, and 1986 Edition for Section XI, Division 1, of the ASPE Code adds the following recordkeeping requirements. Section XI o Winter 1983 Addenda IWA-2420; Inspection Plans and Schedules - Requires pre-paration of preservice and inservice inspection plans and schedules. IWA-4210; Storage and Handling of Welding Material - Requires written procedure for storage, handling, and control of welding material. IWA-6210(a)/(c); Owner's Responsibility - Requires Prepara-tion of preservice inspection plans and schedules, records, and sumary report for Class 1 and 2 pressure retaining components and their supports. IWA-6340(b)/(c); Inservice Inspection Records arm Reports - Reqires maintainance of preservice inspection plans, schedules, and reports. Appendix VI (Mandatory); Ultrasonic Examination of Bolts and Studs - Requires records of the personnel performance IThe 1986 Edition of Section III, Division 1, is equivalent to the 1983 Edition, as modified by the Sum.:r 1983 Addenda, Winter 1983 Addenda, Sumer 1984 Addenda, Winter 1984 Addenda, Sumer 1985 Addenda, and the Winter 1985 Addenda. A-2 i __._Q __,__

..e ':, 1 - T > gl + . ~ ,',n_ ?^ ~ i qu'alification tests, written procedures for. ultrasonic- ^ examination, documentation'of the procedure. qualification, calibration records, and examination records, i o Sumer 1984-Addenda . c. No additional recordkeeping.- o Sumer 1985 Addenda No additional recordkeeping. o Winter 1935 Addenda IWA-2232(f); Ultrasonic Examination - Indications that can be identified as originating from surface configuratioDs-or. variations in metallurgical structure of materials may by classified:as geometric indications. The maximum amplitude, location, and extent of a geometric indication ~shall be-

recorded, 2

o 1986 Edition The Sumer 1983 Addenda and 1983 Editinn have been incor-porated by reference into 10 CFR 6 50.55a by a previous amendment.. Information collection requirements for the~ Winter 1983 Addenda, Sumer 1984 Addenda, Winter 1984 Addenda.Sumer 1985 Addenda, and Winter 1985 Addenda are discussed above. b. Practical Utility of the Information Collection These records are used by the licensees, National Board inspec-tors, insurance companies, and the NRC in the review of a vari-ety of activities, many of which affect safety. The records are generally historical in nature and provide data on which futu,re activities can be based. NRC Inspection and Enforcement persoh-rei 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 Information ASME requirements are incorporated to avoid the need for writing equivalent NRC requirements. This amendment will not duplicate the infurmation collection requirements contained in any other aeneric regulatory requirement. ? I The 1986 Edition of Section XI, Division 1, is equivalent to the -1983 Edition, as modified by the Sumer 1983 Addenda, Winter 1983 Addenda, Sumer 1984 Addenda, W nter 1984 Addenda, Sumer 1985 Addenda, and the Wintor 1985 Addenda. A-3 i .,_..,,_,.--...,_C)._,..

d.- Consultations Outside the NRC No consultations. e. .0ther Supportin'g Information ~ NRC applicants and licensees have been complying withethe 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 py 9 50.55a through endorsement of the ASME Code apply to the' t. owners of the 27 nuclear power plants under construction and To the owners of the 100 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 depen-dent 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 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 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 fiPC inspection or cudit. c. Method of Collecting the Information . b See item 2(b). d. Adecuacy of the Description of the Inforn.ation 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 and paragraph IWA-6300 A-4 l.

e of the ASME Code. The record' retention' periods for-information specified in Item 1.a above are: Information Retention Period -0verpressure protection report. ' 3 yrs afjer superseded Procedure for. attachment; of nameplates.. Lifetime Welding procedur'e specification. Lifetime' NF-1/N-5 Data Report Forms'. Lifetime Design Report for storage tanks. Li fetime Test results for vacuum relief valves Lifetime Proced. for-control of welding material. 3 yrs after superseded Preservice Inspection Plan. Lifetime Ultrasonic examination records. Lifetime Lifetime retention of the above records is necessary to ensure .atequate his.torical information on'the design and examinat. ion.of . components and systems to provide a basis for evaluating delrb ' dation of these components and systems at any time during their service lifetime. 3. Estimate of Burden a. Estimated Hours The information collection requirements inherent in incorpor-atino by reference the latest edition and addenda of Sec-tion 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 design, and Section XI requirements that address ultrasonic examinations and preservice inspection programs. The additional Section III requirements incur a one-time burden on plants under construction. 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 provisio'r.s of paragraph NCA-1140 of Subsection NCA of Section III of the ASME Code. NCA-1140 specifies that the owner (or his designee) shell 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 Specifica-tions be earlier than three years prior to the date that the nuclear pc'er plant construction permit is docketed. NCA-1140 further states that later ASME Code editions and addenda may be used by mutual consent of the Dwner (ar his designee) and Certi-ficate Holder. The earliest Section III addenda being addressed in the proposed rule is the Winter 1984 Addenda. Since the last -plant docketed in October 1974 (Palo Verde Units 1, 2, 3), there is no plant under construction for which implementation of th,e Section III edition and addenda specified in the proposed r.ule 3Service lifetime of the component or system. A-E i

is a requirement. Plants may implement'these.impr'oved 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. The additional Section XI requirements incur' an information col-lection burden associated with the documentation of procedures for the storage, handling, and control'of welding material; the documentetion'of preservice inspection plans and schedules; and the implementation of the ultrasonic examination of bolts and studs. 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 incor, porated by reference into 6 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..0n this basis, r:any 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 cumber of plants that may ultimately be required to implement the specified edition and addenda is 127 (i.e., 100 cperating plants and 27 plants under construction). Paragraph IWA-2420 was revised in the Winter 1983 Addenda to require the preparation of preservice and inservice inspection plans, to specify the content of those plans, and to require an implementLtion schedule for the performance of examination and tests. Inservice inspection plans and schedules, including. - those for preservice inspection are rcutinely submitted to the NRC as part of the regulatory process. The types of items specified for inclusion in the plan (e.g., applicable Code editiun ar.d addenda, identifict. tion of components subject to examination and test, and Code requirements for each specified component) are typically included in the plans submitted to the NRC. Therefore, there is no additional recordkeeping burden associated with the revision of IWA-2420. Paragraph IPA-4210 was added in the Winter 1983 Addenda to require a written procedure for the storage, handling, and control of welding material. In general, this procedure would become part of the Owner's Quality Assurance Manual. The pro,- cedure would be prepared once per plant and would, like other. procedures, be maintained annually thereafter. It is estimated i that the time recaired to prepare the original procedure would j be 100 hours, and the time required to maintain the proct. dure l l A-6 l \\

would be 2 hours / year / plant. Assuming that'all. plants' presently ope 4 ting and under constructiori would.at some time implement thW requirement, the. total annual. burden for all 127 plants, averaged /over a. ten-year inspection interval, would. be 1524 hours / year fur all plants (i.e., ~((100 hours / plant)/10-year. interval) + 2 nours/ year / plant) x 127 plants = 1524 hours / year total for all plants). Paragraph's IWA-6210.(a) and (c), and IWA-6340 were revised in the Winter 1983 Addenda to clarify that "inservice inspection" included preservice, as well as inservice programs, and that' Owners were responsible for preparing and maintaining presery-ice inspection plans and schedules. Preservice inspections have been a requirement of Section XI, Division 1 since its inception. Preservice inspection plans and schedules are rou- 'ttnely submitted to the NRC as part of the approval process..for the inservice inspection program. Therefore, there is no addf- - tional recordkeepino burden associated with the revision of ' IWA-6210(a)and(c),andIWA-6340. Appendix VI, "Ultrasonic Examination Of Bolts and Studs" was added to Section XI, Division 1,'as a mandatory appendix in the Winter 1983 Addenda. Appendix VI provides procedures for the ultrasonic examination of Class 1 and Class 2 bolts and studs. The recordkeeping requiretrents of this appendix can be divided into those associated with documenting the examination proce-dures (i.e., initial examination development and updates) and those associated with personnel qualification records (i.e., test administration, taking tests and updating records). It is estimated that initial development of the exanination procedures would require a one tire effort for each plant of approximately 400 hours of e level III Ereminer's titre. Assuming ? updatec of these procedures during each 10-year inspection interval, it is estimated that an additional 96 hours would be expended during each interval by Level III cxamination personnel for updating. The burden associated with docurenting the examination proce-k dures per plant per 10-year inspection interval would then be 406 hours. Assuming the need for three qualifice ultrasonic bolting examiners per plant, and four bolting configurations for each test, it is estimated that for eacn inspection inter-val, the burden associated with personnel qualification records would be a total of 304 hours for each inspection interval for each plant (i.e., 48 hours of test administration,160 hours of updating personnel records, and 96 hours of actual testing of Level I and II technicians). The burden associated with admin-istering personnel qualification records per plant per 10-year inspection interval would then be 304 hours. Conservatively assuming that all plants presently operating and under construc- -tion would at sorre time implement Appendix VI, the total annual burden of the associated recordkeeping is estimated to be 10,,160 hcurs per year for all plants (i.e., (304 + 496 hours / plant.)/- (10-year interval) x 127 plants). A-7 i A

ParagraphIWA-2232(f)wasaddedintheWinter1985 Addenda.to provide the conditions by which ultrasonic indications can be classified as geometric indications. The revision specifies that the maximum amplitude, location, and extent of a geometric indication shall be: recorded. Since.such indications are nor-mally recorded in this nenner, there is no additional paperwork burden associated with this requirement. b. Estimated Cost Required to Respond to the Collection - Based upen the hours specified in Item 3.a. it is estimated that the cost of responding to the information collection required by the Sec-tion III, Division 1, and Section XI, Division 1, edition and addenda specified in the proposed amendment to 5 50.55a is a total of $701,040/ year ((10,100.+ 1524) hours. x $60/ hour) for 127 plants, or $5500/ year for eath plant.- , ~

s..

c. Source of Burden Data and Method for Estimating Burden Estimates of the paperwork burden associated with implementing the identified ASME Code revisions were obtained from utility staff inservice inspection specialists, an inservice inspection censultant to utilities, and national lab personnel 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 Cest to the Federal Government NRC inspection personnel who audit plant quality assurance records would include in their audit verification that the above records are being properly prepared and maintained. The time associated with NRC inspectors verifying these reccrds would be extremely small when.the activity is performed as part of a normal quality assurance audit.b G A-8 't o

./ o. -i.. Public Coments Comentor Appendix Dr. W. F. Anderson A Mr. M. fl. Bressler B Nr. M. I. Lewis C m 1 I t i g I n

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helpful. I consider it.most,important that th Therefor'e, f i ssued df f ective.01 th' the.mi nimum possi b1_e del ay.. hopr?' that.none. of' these 3r';;r;;esti.onn woul d ' bs considdr ed' i.o' si gni f icant,that, they would contribule: to. sign li f.icant delay... Thc-NRC: prec tice of sep' erat 3 ng' si mpl e.updati ng of dthe - ef f ec ti+e (c 5 c. d a t e s i such co .r ' t '. e mb.act p-oposed.de -idm.:nt, 'f rom me' e m u n d c. c n '_3 :T .e ege. .cn -to t-crr entfeJ. R :-

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~ . f gn. 3: tnt me.Y v:h i ci.1Sc.l udes g p l i.:c.t i on o f Cub mc *,i on' I WE. cr-i nspecti on.of..M,kel'. Yontalnment buiIdihgs woul'd. be b; (sl ua!.:) e, addi ti on' 6s would be' the~ inc'l'usi on 6f "Subsecti on '.IWL on i rtspecti on of conc' rete containments. i The present lack of new construction in the nuclear industry diminishes the importance of code improvements for' construction, 6$: 1e the incr mr.c in op?r at i ng p-otal eme, wi th more operati ng plant emphasi::es the neea f or increased attention to utta1:atir. 8 code improvements in ??ction XI. I.encourago the NRC-to .g 0e::0mi ne the organi:44 tion of 10CFRSO.55a wrth._mpect to the ~ requirements f or operating plants and to consi der reorgoni:1ng 10CFR50 to provide more suitable capacity for,a clear set of The expanded requirements shorld consider c::panded requirements. incorporation by reference of code rEIul'rements on repairs, clear replacements, and modifications. The e::p ent-i on should allow for later provisions for evaluation of r_omponen ts si ter of f-normd situations, such as seismic events, to aspure capability for . continued service.and.for..inelusion of prbvi sicris f or 1ife e::tdinsi on and the rale of proper maintenahce as a basi.s for'1iie 3 extension. l ^, I t hant; you or the oppor tuni ty to co nment on the proputed .v. J.nc.. t . e _: F 2p.c U..- me c u,11 ti-s or tome hr'.p. ':. i s. >, /

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,a. inc.lud.e.the provision that ~nd, reqGest to NRCgf ore use of spec,ifit.: Code Cases i s' rc:quir, ed _.f..or.Jttiose l i.st6d. I r.i..R. G.'s ; 1. B4, - 1. 85i.an.d. l'.147. I t should alsr mate i t cicar. that < the ' NRC-must be. I nfor med 'pr'i"or; t6 t'h$. use _ of a' t. ode. tasu: b y includt'ng.a -s,tatemsnt -. i n. the '.sub'mi t.fta.l', to th..e.NRCl whi ch. addr e.sses '.th. e. use of.th. e 1. .s r& G%d. code. u [Co'mmen't).' hi.1dh'u Suphl emerYtark. Ir) Wor'mi{ti on 'rsikes,i t Y1Mr) 'o W thdt ~ no 'requesti. f W Us6 of; the.:-1Tsted. cases'"is tequi'r'ed,, - 9 M problems have arisen in st.tuat.t'ons(whe-e. i.he NRC has not' bee;C. adeqQately nctifei of'.the intended.use.of -speci f ic. co'de.cesen. l ~ , and 'ther'u;was n:; t. 'avai l ible to'the>NRC dr.thir$ pttr.ty-," t i 6 inspectors.a complete doctimented bcsis. f or, ingpection.. j ~' p ari.s of ~ p'ar egr-aph g'. ... 6 whe.e' Footnote ..i's referenced: .b.' Thosd. r 2.c.G d b e a: ut. i ' u. c '.. i ry c.d ucc o. .b at o ruv e. fr/ i.c cw should c. c. 9 \\.s : L '. w ;..v w n, b& Foot. acte.A cr 5. (g-(4) 1 apps:sr s. ., pot a rpfr une.e to .s. Footinote 6.-would b.e. appropriate where use of Gec. tion XI is - 1 ' M*.cifidd( A126, :..tho .ror t's ' " dne.o. p.t 1 :n. al C adc. C.c.ces"1.,ho.ul d..b e =. l ' r" th i s r, e,"cr u.n N., c.includhd'to provtue the,b Mis o

2. The proposed adci n t o:.a.. sentence lei ( '.: : (Ti(i) p p e ? r ;. M conflict with the sentence of the original test preceeding it regarding applicability to code addenda subsequent to the Summer 1978 Addenda.

Clarification of the scope of that preceeding c t'i t (2) (i ), (i ii ), and (iv), would g; 'i: v.r . v..- a be hulpful. A l t er r n.. i v.; 1 y, subhuding., in (L) i ' 2 ) or additica ef 3.,oi.h er - ne',;- - ct; : -7 h 'n f 0.r. t h e 1 t mi' ations rel ated to IWB4 t. J640 may wcc; y .n .nt re.ved ed c 1 er i f ic2 t t vr.. 3. The proposal '.o accept the 1586 Edition of Section XI without enception i s a oe:essary improvement in clarifing use of"the code, especially an its provision for inspection of Code Class 2 p.pir g. In L w ; r>t .% r e he s bun confusion abeut a seetni ng contradicticn wtth '. e 1tmltation in ( b ) t ) ( 1 v ) (I.4 ) for plants whose application for a. construction. permit wasI ocketed prior d to . July 11, 1970, b e. l c..t ; ec. ito the.l.ist, c.on. tence. of (b) (2) (1) in;the ex1 sting ten.t. In, t' t s 'we 1 ter<a mind-the Summer 1978, Addhnda , and that sentence. handled the matter adequate 1.y but, as mentioned in 2 above, -thih co. Id be conf used further by the proposed eddi ti on to'ttiot pa-egr oph. The Winter 19G3 Addendo to Secticri XI t ac..ni. d s i g:. i f ex. .'.a ....m. t.. U b '- e I E O* /. '. which na c r e ' ' Tf,

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ii. : (. -. a r,-

., u. n. .h - . i t.. e -,e ud. e 1983 and the 1986 Editio1 for tnspecttor, of Code C1 ass 2 p1p1ng. e . -,., ~.

G *h h ;;G N h 7f 'j&_l.fh;0;. *: U' ,8 ' $. h ..Y. 2 .hE. h.h[fh.' )' [ hb Proposed Rules.@d.f:; AN6 l g,.,,.,. 24016 i - *:.: Federel' Register / V:1. 52..NF123 / Frtiay 'Itin'e 28.'1987. / 4.M '-@.%.. v.. - a S i, resp *eitlvely(%is proposed ame'adm5ni.. " NucNar Regulatory'Rese$rch. O.S. - 6/ Sect 6oa7ud throush'at02 also hsud. [ N '3 6.... revises Footnote 6 to incorporate a ' ?. ' Nuclear Regulatory Commission.',, 'Y. - ltmder sec. las, es Stat; ess (42 UAC 223el. r Q ; 9 * , ' reference to Regulatory Guide 1.147. "tri Washington. DC 20555, Telephorte'(301), For the purposes of ecc.223.es Stal 958.es ;n-Q '.,

• '. ; service Inspection Code Case./

443 7713. - amended (42 U.S.C 2273), il 60.to(al. (bl. -.-, e.1, 2... and (c). so.44; 5aea. 6ata. 5054. and so40(a),..;, - Aceptability-ASME Section XI ". Paperwork !teduction Act Statement, , are lasued under.sec.1elb 68 Stat. 948. as. .G . ' -.1 Division 1." which identifies the Code - %Is proposed rule would' amend.... ? amended (42 US.C 2201( s Cases acceptable to the NRC staff for.

• information collection requirements thaf. (cl and50.54 are fesued under sec.tell, se V

_. implementation in the, inservice ; stat; e49, as amended (42 us.C 2201(t)): and - finsp.ection (ISI) program of light-water-? l are subject to the Paperwork Reduction il soss(e). mS9(bl. 50.7a 60J1<30.72. 50.73

c. 4 3 cooled nuclear power plan'.s. At present. - Act of 1980 (44 U.S.C.,3501 et seq.). Thisi and soJs are tuued'under sec tato, es stat..

the implementation section of. proposed rule has been submitt6d to the ' la enm, ended (42US.C 2201(o)). ' ~ '.'y. Regulatory Guide 1.147 specifies thdl. - Office of Management and Budget for -

12. For#l 50.553.'paragiaph (b)'(1).'the

. apphcants should make 4 specific. . reviewand approval of the paperwork ~. introductory text of paragraph ib)(2)i tequest to the NRC to use Code Cas% requirements. paragraph (b)(2)(i). and Footnote 6 are endorsed in the regulatory suide. The

next revision of Regulatory Caide 1.147

. Regulatory Flexibility Certincation revised to read as follows; ~ (Le Revision 6) will reflect the proposed change in Footnote 6 of the . As required by the Regulatory; . I 50.ssa Codes and stamsards. regulation. It will permit the use of Code Flexibility Act of 1980. 5 U.S.C. 605(b). - a the Cnmm sion hereby certifies that l (b) * * *.. t Cases endorsed in the regulatory guide wahout a specific request to the NRC for.Jthis rule.if promulgated, will not have a . (1) As used in this section. referen'ces , approvat in the interim.it }s the intent significant economic impact on a ~ .! to Section 111 of th'e ASME Boiler artd '. of the NRC that Code Caseslistedin - substantial number of small entitles. ' S Pressure Vessel Code refer to Settlers' '%is proposed rule affeca only the i Division 1. atid include) editions , Regulatory Guide 1.147 may be used .without specific application to the NRC. Licensing and operation of nuclear ronh tG'I986 Editionand/Adden'da Subsection IWE. Requuements for power planta.The companies that own ' ugh the Winter 1985 Addenda 4.( , lass MC Components of Light. Water-these plants do not fall within the scope ' (2) As used in this section, referenced. of the definition of"small entities" set ' to Section XI of the AS TE Boiler and . f rth in the Regulator Flexibility A-t or. Pressure Vessel Code ?i ter to Section , e ion XI v o 1.1 in er 1981 Addenda. However.10 CFR 50.55a the Small Business Siie Standards set XI. Division 1, and includ e tions i i out in regulations issued by the Small - @To~uTgJ.e 198eIditi ddendaa Business Administration at 13 CFR Part' throughlhe WJiliTB55Tddendk.. or ions o e on t t address the 121. subject to the following limitations and A ISI requirements for Class 1. 2. and 3 components and their supports. The IJet of Subjects in 10 CFR Part 50

• {iI regulation does not co rently address rr it ons on sEecific editions and the 151 of.containmera. Since this Antitrust. Clas sified information. Tire. addenda. When applying the 1974.

p'otection. Incorporation b) reference. Edition, etly the addeoda through the propose'd amendment is only intended to r update current regulatury requirementss intergovernmental relations. Nuclea r Summer 1975 Addende may be,used. to include the latest ASME Code edition. power plants and reactors. Penalty. When applying the 1977 Edition, all of , he adderda 2hroTagh the Summer 1978 ar.d addenda, the requirements of Radiation protection. R.eactor siting t Subsection IWE would not be imposed criteria. Reporting and recordkeeping . Addenda must also be used. Addenda upon Commission licensees by this requirements. and editions subsequent to the Surnme: amendment. The applicability of Parsunt to Atomic Energy Act of 1978 Addenda, that are incorporated by Subsection IWE is being considered 1354. as amended, the Energy reference in paragraph (b)(2) of this separa tely. Reorganization Act of1974. as amended, section are not affected by these ErnironrnentalImpact Categorical and 5 U.S C. 553. the NRC proposes to limititions. When applylog the Winter Exclusion adopt the following amendments to 10 1983 Addenda and Winter 1984 CFR Part 50. Addenda, the rules of paragraph IWD-The NRC has determined that this 3640 may be used for a!! applications proposed rule is the type of action PART 50-DOMESTIC LICENSING OF permitted in that paragraph. except' described in catesoncal exclusion 10 PRODUCTION AND UTILIZATION those associated with submerged arc CFR 51.22(c)(3). Therefore, neither an FACILITIES welds (SAW) or shielded metal arc environmentalimpact statement nor an welds (ShiAW). For SAW or SMAW. environmental assessment has been 1.The authority citation for Part 50 use paragraph IWB-3660, as modified by prepared for this proposed rule. continues to read as follows: the Winter 1985 Addenda. Au r h Secs.t a n tet.ta2. m a ss. Regulato'I Analysis 109. 68 St at 936. 937. 946. 953. 954. 955,956. a s

• ASME Code cases that are authorized for The Commission has prepared a

, amended, sec. 234. 83 Stat.12+4. a s amended use by the Commission staff are heted in regulatory analysis for this proposed (42 U S C. 2133. 2134. 22ot. 2232. 2213. 2236. NRC Regulatory Culde 164.* Code Ca se amendment to the regulations.The 2239, 22821; s ecs. 201, 2o2. 206. 88 St a t.1242. Acceptabihty-ASME Section !!! Design and

enalysis examines the costs and 1244.1246, as a mended (42 U3 C. 5641. 5842.

Febncaten." NRC Regulatory Culde 1.85. benefits of the alternatives conside' red 38441. unless otherwiee noted. '

• Code Ca se Acceptabihty-ASME Section !!!

by the Comrnission. Interested persons Section M7 also issued under Pub. L 95 Matenals." and NRC Regulatory Guida %.147 may examine a copy of the regulatory ect. secao. 92 Sta t. 2951 (42 US C. sasi). Inservice Inspection Code Case Sections so 58,50 91 and 50 92 also issued ACC'Ptability-ASME Section X.I Division 1." ana ysis at the NRC Public D,ocument under Pub. L 97-415. 96 Stat. 2073 (42 US C. The use of other Code casee may be Room 1717 H Street NW. Washington. 22391. Secuon are also issued under sec. authertred by the Director of the office of DC. Single copies f e anal sie may be 122. sa Siet. 939 (42 U S C 21521. Sections ' Nuclear Reactor Regulation upon requett obtained fro. r. G.C. Mi man. So ao through scA ateo issued under sec.184. pursuant to i so.55stan(3). ---. D91sion of Enginee os Stat.954. ee amended (42 US C 22341 h [- Received from Mr. M. N. Bressler without transmittal letter. i =

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~ ~., s,. n l Coa.r e tt./ S e c r e t.a r p tj -, s, r P.l ea se l'a cc' epi. t hec..o. as spy..'coope6ts. on Federa l ' Rec i s ter Notice Mo lver,0. 'y2 3.mteber J T:'2,. d a t c d. 'Qne 26. J.9S"',.. Pe c pc. s c d RnI 6 o n.Ce de's ' ,1 . Nno St andards. for.'Nui. lear Pctuer Plants, - 10CFR P' r t 50. ' a , Manv. inter.astnd. parties.i.nlthe general. public-have ' ctated the. 'l v 2 qm '.t h a t ]the a,c t i'cyns.o.V,r eppl a t cr y.. bc4i es ms Qe '. thc[rij appea rl.;t oi.be.' ' V [handaia fdens. 'to ;.th,b-irdds,try.wh i ch : t.heySarp suppos'od > tb.. r.egd.l a t e.. c 7,4~. This proposed rule shows.that.the.NRC.is not a re'gulator ,'but'a' 4 hhndmaiden.. [hc/nu lear.In'a era ubereig tsany*. unexpected'.and unhappy surpr.ises.5ffect. ~ t c, ir dus tev. f ro tr riajor, acc ident to ur.enpec t ede cor ros :( n'. 1 / t hh flPC..st,i l l ul i tJa. ! J.'sec eo t t.sth.e ur.'i t,i no s. of the : nucl eai ; ,q-c ' i hdub t fy. as ~ Gospe i ' tru t h'.?.The 11essd/d o f. iMI "Snd' Chei nclby'l ; havd ', .p dsed'the Nc:C bv eithout e f'f ec t. Th'e pierent 411'tninM no

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it.e.r. E cpcz o,%...: ;.c : c.) ; t t r. r. p. 4 1grie. t. l a.n t.a, F o ),; t u i..t h. u dl l. t hl. nh i da. '. no r .t he i o c en t.c6c cce s o'n ' o f < s t a i n l e s si s t ed l. .. m d +; u c ri A c i org t c a." : r; f r- <.r e: ) J c.' h n t c.. $c c r ;- (.1 pq thc 2NFC Cc dc '.s h d u c, t.ha t ' t,he' NRC.. h as l i t t l.e regard of 1 th oun 'Lic'ctnset. dventi. Pcoort: svaten. The real solutio'n to Coces and St.andards shoulc Le t o predtice ~ the regulatory agencies own standards based on the agency's own experience and analysis. Usino the industry's logic will lead to the same mistake as evidenced in the TMI accident wherein the ntaff con:urrcd with thc. utility to allou non-safety c r a d e POY.' a r.d c h c. c k valso suf'1 ace on the reactor pressu.e boundary 2n

ont 0.itttion to the G

n:ral Dcsion C r i t m i :.. Thia iolation'of r t j 6-n :Ys e di.cct c e r t : : t u t r.. r t e.

the 1rt) rccid<= w. i c i t e. : r nt!! it..;- t.M tt e Pi .2 .t : si!.+ !. % c. 4a for 6SME or Jr.ductly ceveloped codes and standards in the rules { and reqUlations, sud the NRC shall dcwlop their own codes and standards from NRC enperience and data. R e s p.:d-t f. e l J,- b[t c-d. r f Ot,. > Ma.rvir. 1. m s- ~ 7801 :REcdevel t D10d'.'N6h Phila.. PA.19152 (215)624 1574 8-R4-1987. i 4 .\\ \\- prwidedged trf C8Td.m _. _er-em""" N

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• V.W, A 8':18 ?

i .v, ..[. ..?,..- ^ v. 4 .......yr.. s. . u GD..<..d - y 7 'U.Sc. Nuclear $ Regulatory [ Commissions " ' MJ 7 '. ~ Washington}.D.'C. gC555 ~ ' l" m Attn: Docketiing fand Se'evice'.'.Br.nnch li. CFRdO.' 55 0. da t'ed June 16,'.1907 Suo.iect:.Propocod Amendmenti to Dear Sirs; ~ . ~. lEriciosed, are> commen' tsi on the'.sub.iect proposed -aineedincintawhich :.. sorrie areas where' cl ari f ication of' the: amendment "would..b4 '. ~ 6 suggest helpf ul. ',I. consider: it most important that' tpis amendment' be ,7 issued offective with the. minimum possible delay... Theref or'e, I' hope that none'of'these suggestionc would bc considc' rad't,o. ~ significant that they;would contribute to signific'an.t d e l'a y. ~ The'-NRC prN tice 'c'f.se;sarati ng NimN e. updating of. the,cf'f ective'

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u. d r e n '. 2 :. ' .e "ecv rt:cn com i tal o't of the sq.b4cci. ;roposed :--r.co d:r.cr.t, the tir-fr.:" addi-tional significant' amendment would be.et hand. T.te cdditich . a.x en @:v.L @ ' includes hpplr.4 tion'of Cub'cqc t'i on ' IWE An irispects on of steel can'tdi,nment but luingt; would,be.a. :il v.b t i e additior, as would be' the inclusion of Subsection IWL ca inspect.on of concrete. containments. The p~esent lack of new construction in the nuclear industry diminishes the importance of code improvements for construction, @: le the inc&ane in oper.hting p-oblerm with more operating plant emphas t ::es the neea for increased attention to utt,4: cit m o' code i mpr ovcment s i n Ee-tion XI. I encoursgo the NRC to .g m: amine the organi:stion of 10CFR50.55a.with r ':,pect to the requirementu tar operating plants and to consider reorg ani: i n g a clear set of 10CFR50 to provide more suitable capacity f or The expanded requirements should consider c::panded requirements. incorporation by reference of code r Ruirements on repairs, clear replacements, and modi f i cati ons. The e::p any-i on should allow for 1ater provtsions i or evaluatton of components ofter c f f riormal situations, such as seismic events, to assure capability for i nel usio.n. p f prhyi'sions f or,1ife coriti,nued ser vice.and ior i e.: tension and the role of proper.r6aintenahce as a bas.t s' f or - 1 t ie I extension. l t, .s I thant you' cc the oppor tuni ty to comment on the proputed h.w u.... ..- a u -r w w e hr:p.

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l,i,, Then prloposed, amend.medtl wouldrprovide;[R.G.(1.147As licipf ull provi'st on. by', t .1isting f i'ncl'uding Tin.- F.ootnoteT6nthe. ef,ecence.to, r

oy 'acceptabl e code, cases.. yThe 1f ollowing ' ci pri f i' cal. ions 7

use of f Dotnote. 6;..w6u.l d be hel ful.also - -/,- a. Ei thers the..b'pd,' E4 f ith'e ' regul ati on.or Footnote _ 6'shoul d. ' include lhe drovisi'on that n'o request' to NBC:for~use of"specific Code _ Casec'.i s~ requi rad f or..those 1 i strid i n R. G. s 11. 84, 1.05, and 1. 1 4 7.. It shoul:E algt : r.al:e i t ci car that the NRC must 50 informed prior; ttr thy uGe of # rode caue br including a u t.st.e m e n t in the submittall.to the NPC which addresses the use of.tne rWluted codo.. s. ' }Comm'entf.Shi1Y the Suppl ementary.,1mlor md.h.t en o,~,,mes, i t. cicar - the: listed cases is requiredi

• 1:;

,,-{ .that.no,' request fy use of c problems have arison in' situations.whe-e the NRC has not been< adequately noti f ei, of :the intended use of' specifit. code, caseu c-n d there was 'not avail.sbl e to the NGC.o-thi t C ;..er ty inspectors a complete documented bc. sis for inspection. b. Those parts c4 biragr'aph g. where Footnote 6 is referenced; . d w; _ o. .F s t . e % v. c. D d.c.G d a o a:: w.; m c. .y .. ce Wooid , ' 2., c d .p ..m. pp e n i. M c r ei v.

n:.e '. o be bactacte 4 cr* 5.

<a s Foo.tn'ote 6.would.be appropr1 ate whrfre use.of'Gection XI is, , a;p.c i_ f i ed. Al a c; ; 'hc ror f t- " cv. e s t i r m e. ' Cr c Cc.ces" c,houl d t e included to provice, the bei a i or :nta r Kr.r.jn.m, 2. The proposou additt c:.i. c er.t. m c c in C.: i -'i t i ) 4ppe ?rb t a conflict with the sentence of the original text preceeding it regarding applicability to code addend.4 subsequent to the Summer 1978 Addenda. Clarification of the s<: ope of that preceeding

• .:. b ' t.m i i

, (iii), 2nd (i v), would . p! *;: .c. .a .2 be helpt'ul. Al t er re *. i v I y, subheedtnya 'n u., ).t ;4 ) or addit:on of .m o'.h er " ; S - v- - ; ; ;+ 'v. fo-the 1 tai *ations related to IWBg. 3640 may ecc; N. .n .h.. n w.Jed c 1 er a fac ita ur.. 3. The proposal ".o accept the 1586 Edition of Section XI without exception i s

6. ne-essary improvement in clarifing use of'the code, especially 4n its provision for inspection of Code Class 2 p. p i t.g. I n t.:' e ; r A * %:. hes b. t. n can'a ion

.ib eu t a t.i e.tii nej contradicticn w 2 '. n r.e l i mt t.at i on in (b)'2)(.v) G) for plants . whose application for a construction permit was docketed prior to .Li).(2)(i) in,the

• July 1, 1970, re111.ve to'the last mentence of

( . existing' te::t. Inl t'i s 'wer ter,s 'mi nd the ' Summer" -1'r78 ; Addenda and that sentenc'e handled the matter adequately but, as men.ti'oned in 2 9bove, Abii. co/1d be conf used f urt her by the proposed oddition t.o't N t pe egroph. Thc-W1 nter 19G3 Addendc to Sect 1on X! l'.c outd u u.14 t ;i. - .m t.. feb: ' l.R. -1,.. w h i s. n.< r e .., i. p, c l o. i4t La via ,ti. v...:.. 'e

ty w_

n. cb. ... ee vt .ie 1983 and the l'06 Edttion for i n spec t i or) of Cout Class 2 piping. i \\ E ~V

l[ry(., l S' h , 1., 7, : ~ l0, ' Me 3_ g gpg ' ' Appendix B1. j .. 3 o. 24018- . Federal' Register / W1. 52. N.123 / Fdda', June.28,1987 / Proposed Rules - 'I y . respectively.%is proposed amendment. Nucleer Regulatory Research. U.S. - Secnons satoo through sato2 also tosued ~ revises Footnote e to incorporate a Nucleer Regulatory Commission, under sec. t ea, es Stat oss (42 U.S C mel. i refe-rence to Regulatory Guide 1.147.*In. Washington, DC 20555. Telephone (301) -. Fee the purpe of sec m, es Stat. osa, u service Inspection Code Case 443 7713. amended (42 USC 22731. Il 50.1o(s). (b). Aceptability-ASME Section Xj and (cl. 50 44. Saes sa48,5034. and 5040(a) Division 1.".which identifies the Code Paperwork Reduction Act Statement are issued under sec.16tb. es Stat on as a mended (42 U.S C 2201[bl). Ii 50.10(bl e nd, . Cases acceptable to 1he NRC staff for. This proposed rule would amend (c) and 50.54 are tesued under sec. sett. ea .iroplementatlo iln the inservice Information collection requirements that Stat. 949. as amended (42 U.S C 2201(i}}: and ' inspection (ISI) program of light water

• are subject to the Panerwork Reduction il 50.55(el. 50.59(bt 50.70,5011. 30.72. 50.73 cooled nudear power plants. At present. Act of 1980 (44 U.S.C. 3501 et seq.). This. r and so.7s are issued under sec. teto, sa Stat.

the Implementatto.. section of proposed rule has been submitted to the 950, se amended (42 UAC 2201(oll Regulatory Guide 1.147 specifies tha'l tj Office of Management and Budget for

2. For I so Ma. paragraph (b)(1) the review and approvalof the paperwork introductory text of paragraph (b)(2).~

req est to lhe RC to use Cc d as requirements, paragraph (b)(2)(i), and Footnote 6 are endorsed in the regulatory guide.Th next revision of Regulatory Guide 1.147 Regulatory flexibility Ce'rtification revised to read as follows: (i e Revision 6) will reflect the As required by the Regulatory I 50.554 Cod +e and standanss, proposed change in Footnote 6 of de Flex b lity Act of 1980. 5 U.S.C. 605(b). regulation. it will permit the use of Code the Commission hereby certifies that (b) * *

• Cases endorsed in the regulatory guide -

this rule.if promulgated. will not have a (1) As used in this section. references without a specific request to the NRC for algnificant economicimpact on a to Sectio 1111 of the ASME Boiler and . approval. in the interim. lt is the intent substantial number of small entities. Pressure Vessel Code refer to Section egu$acry nie pr p sed rule affects only the If Division 1. and include) edition uld 1 eY ed with ut specific apg.4 licensing and operation of nuclear ros:h the Bae Edi:ionan(Adderida ication to the NRC. power plants.The companies that own ugh the Wmter 385 Addendaad these plants do not fall within the scope (2) As used in this section, referenced 'Cl SAC o po en s o u. ater to Section XI of the ASME Doller a of the definition of"small entities" set . Pressure Vessel Code refer to Sect,nd Cooled Power Plants", was added to Section XI. Division 1. in the Winter f rth in the Regulator Flex.ibibty Act or ion the Small Busines: Size Standards set XI. Division 1. and inclad e itions 1981 Addenda. However,10 CFR 50.55a

g i

out in regulations issued by the Small (through the 1986Editi ddendae Business Administration at 13 CFR Part tnrough the WUiTeTM337U3dendgF. r ions of Sec n It t address the 121. subject to the following limitations and A ISI requiremenu for Class 1,2. and 3 components and their supports.ne uit of Subjects in 10 CFR Part 50 regulation dcas not currently address (i)Umitati no n specif.ic editions and the ISI of containments. Since this Antitrust. Cla s sified informa tion. Fire addenda. When applying the 1974 proposed amendment is only intended to protection. Incorporation by reference. Edition, only the addenda through the update current regulatory requirements intergovernmental rela tions. Nuclear Summer 1975 Addenda may be used. to include the latest ASME Code edition. power plants and reactors. Penalty, When applying the 1977 Edition, all of ar.d addenda, the requirements of Radiation protection. Reactor siting The addenda through the Summer 1978 Subsection IWE would not be imposed critena. Reporting and recordkeeping Addenda must also be used. Addenda upon Commission licensees by this req uirer.ent s, and editions subsequent to the Jummer a endment. The applicabihty o[ INrswt to Atomic Energy Act of 19'8 Addenda, that are incorporatcJ by Subsection IWE is being considered 1954, as amended, the Energy reference in paragraph (b)(2) of this separa tely. Reorganization Act of 1974, as amended, section are not affected by these and 5 U.S C. 553, the NRC proposes to limitations. When applylog the Winter Em ironrnental lrepact; Categorical adopt the following amendments to 10 1983 Addenda and Winter 1984 Exclusion CFR Part 50 Addenda, the rules of paragraph IWB-The NRC has determined that this 3640 may be used for all applications proposed rule is the type of acticn PART 50-DOMESTIC LICENSING OF permitted in that paragraph, except' described in categorical e xclusion 10 PRODUCTION AND UTILIZATION those associated with submerged arc CFR 51.22(c)(31. Therefore, neither en FACILITIES welds (SAW) or shielded metal arc environmentalimpact statement not an welds (SMAW). For SAW or SM AW. environmental assessment has been

1. The authority citation for Part 50 use paragraph IWB-3640, as modified by prepared for this proposed rule.

c ntinues to read as follows; the Winter 1985 Addenda. Reg 21atory Analysis Authority Sees 103.104. t e t. t a2.1 a3.168. 16168 Sist. 936. 937. 948. 953. 954. 955. 95& a s e ASMECode ceses that are authonted for The Commission has prepared a , amended. sec. 254. a3 Sist.1244. a s emended use by the Commission staff are listed in regulatory analysis for this proposed (42 U S C 2133. 2134. 2201, m2. 2233,2236. NRC Regulatory Cutde 164.

• Code Case amendment to the regulations. The 1230. 2282). uca. 201. 2o2. 206. 88 St at.1242.

Acceptabihty-ASME Section !!! Design and analysis examines the costs and 1244.1246. a e amended (42 U.S C 5841. 5842. Febncat,on." NRC Regulatory Guide 1.45. benefits of the alternatives considered 6461. unine othemn noted. Code Can Acceptabihty-ASME Section !!! by the Commission. Interested persons Secuon 50 7 also losued under Pub. L 95 Metenals." and NRC Regulatory Guide t.147 may examine a c fih* I !I ect. sec.10. 92 Stat. 293t (42 U.S C 5&51). In"rwe Inspection Code Can Sections So 58. So 91 and 50 92 also issuad Accepi.bility-ASME Section XI Division 1." anaiysis at ihe NRC Public Document under Pub. L ??-415. 96 Stat. 2fyr3 (42 U.S C The tu of other Code cases may be Room.1717 H Street NW Washington-2239). Section 50 ta also issued under sec. authonted by the Director of the Omco of DC. SinMe copiee of anag may be 122. as Stat. a3e (42 U.S C 21521 Sections Nucleer Reactor Regulation upon request obtained fro.. t. C.C. Mi man. 50 ao through 50 at also innd under ecc. is4. pursuant to l 50.55ala)(31 D91sion of Enginee es Stat. 954, as amended (42 U.S C 2234). [ch Received from Mr. M. N. BreSSler without transmittal letter, s 1

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20355' lF u:O. Dear 10. Secreta <pt. Ple'a s6 acc.ep t theto as my conpents on Federal Register No 't i c e '.'o l u rm 52, ?!urebe r 1&2 datad. June 56.1987, Proposed. Rule on Cedes .cno Standards for Nuclear Pouer Plants,- 10CFR Part 50. ,.Manv interested pai-ties in the general public have'steted the

• v.2 c u. t h e t,the ections.of,reculatory bc. dies;meLe t h e :r., a pp o a r. 5 0 - b e.

.he.ndmaidens to thd[tr(dustrf which. they aria supposed to regulate. .,, g :

• Tnis p'roposed rule shous that the NRC is not'a regulator i but'a f

handtna i d e n. In a era,wherein rnany unexpected and unhappy surprises affect the r.uc her.3edue*ry~feof. c.3 j o r accidert to ur;engected corcosIcn. the NRC still b l i the-1 e 'sccs.o t s the or i t inos of the. nuel esi-1 r.diin t r y as Gospe l truth. The Itssons vf Till a'E.d Chernobyl have patted the NRC b. uithout affect. The peozent will thinnins F. e 1 c. 1.32 g ce ; cef -: 2 3:

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The real colut200 to Coces and S*.andards shoulc: t. s3 t.o p r o diac e the regulatory agencies own standards based on the agency's own experience and analysis. Using the industry's logic will lead to the saine mistake as evidenced in the TMI accident wherein t hre ntaff con:urrcd vith t h c-u t i 1 1 t. y t c. al1ou r.:.n-nafet,. ccede PCRY ard chuch val.e sifface on the reactor p.cusure boundary in r o a t. p.i l c t i c n to the G:ncral Ocsson Critoria. Th: I.tolattoo .f c ; e l s. s ;en a direct cert : ut e

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i Osocc r ni! 1 a.;';.- t..;. t it.- F ...t. . :.: i i l '..M. c.. ? 4. for #4SME or 3r.ductiy developed codes and standards an the rules and re gu l a t i oris. and the T!PC shall dc. Plop t hia i r own codes and standar ds f rom NRC e :perience ord data. L{ef i't c d, Rosp s tf. ell.- r ks% - 1 < Marvie. 1;. e L.n s ~ 7801 Roo f eve l t. D'I vd. tt 62 Phila.. PA 19152 (?l5)624 1574 ~ S-A4-1907. e g -. + g pow)qQtdDyC8fd.m.e#" 4W i

AW DOCKET NUMBER PROPOSED RUI.E $ ) o C5,z ne Mow ~ J PM ~ 7* William F Anderson cv 13042 Feach Blossom Dr. Sun City West, AZ 85375 87 SEP 1 A8:18 August 19, :as7 .sa DCL-i U.S. Nuclear Regulatory Commission M- Washington, D.C. 20555 Attn: Docketing and Service Branch

Subject:

Proposed Amendment to 10CFR50.55a dated June 26, 1987 Dear Sirs; Enclosed a-e comments on the subject proposed amendment which suggest some areas where clarification of the amendment would be helpful. I consider it most important that this amendment be issued effective with the minimum possible delay. Therefore, I hope that nor.e of these suggestions would bc considcr2d so significant that they would contribute to significant delay. l The NRC practice of separating simple upda' ting of the offective l ccds dates, such es in the sub,ect croposed emendmant, from mere I nebstsntial antndctnts of the -cgul? tion is to be comnended. With completion of the subject prcposed amendment, he time for ar additional significant amendment would be at hand. The additicn f cn amendmc.it which includes applicction of Eubcoction IWE en inspection of steel containment build.ngs would be a saleable addition as would be the inclusion of Subsection IWL on inspection of concrete containments. ,, a p y.m.ye,w:9. - n,%,,.,,,,.;,, y %,,,, ~r The present lack of new construction in the nuclear industry diminishes the importance of code improvements for construction, while the incree,se in operating problems with more operating plant emphasi:es the need for increased attention to utilization of code improvements in Section XI. I encourege the NRC to examine the organi:ation of 10CFR50.05a with respect to the requirements for operating plants and to consider reorgani:ing 10CFR50 to provide more suitable capacity for a clear set of expanded requirements. The expanded equirements should consider clear incorporation by ref erence of code require'ments on repairs, replacements, and modifications. The e:-:pansion should allow for later provisions for evaluation of components after off-normal situations, such as seismic events, to ayure capability for continued service end for inclusion of prbvisions for lifs maintenahce as a basis f or 11fe entension and the role of proper i entension. I ( m I thank you for the opportunity to comment on the proposed eme t M ,t anJ h:p2 the' - '.w me"t 3 si.ll b-> of 23me hcip. 's " l ' n. e r *

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COMMENTS ON PROPOSED AMENDMENT TO 10CFR50.53a of June 26, 1907 4 from W. F. Anderson

1. The proposed amundment would provide a helpful provision by including in Footnote 6 the reference to R.G.

1.147 as a listing of acceptable code cases. The f ollowing clarti;;ations of tne use of footnote 6 would be helpful also: Either,the body of the regulation or Footnete 6 should a. include the provision that no request to NRC for see of specific Code Cases is required for those listed in R.G.s 1.84, 1.85, and 1.147. It should also make it clear that the NRC must be informea prior to the use of e ccdc case by incl =.:ing a statement in the submittal to the NRC which addresses the ase of the .ulated ccdc. Comment: While the Supplementary Inicrmati:- nahes it cics* that no request for use of the listed casestis required, problems have arisen in situations where the bRC has not been adequately notifed of the intended use of specific code cases and there was not av1113ble to the NRC or thir; party inspectors a complete documented basis for ins:ecti;n. where Footnote 6 is referenced b. Those parts of paragraph g.

h;uld ce onaminc.: for clarl'.y er.d use o' that rs'2 unce. Ir (g ) (11, (2i, and (5) it oppcor c ths.t the p oper et Jerence should be Footnote 4 or 5. In (g) (4) i n appeer i that e - ef er ence to Footnote 6 would be appropriate where use of Sec*.*cn XI is sp.cified. Also, the words "snd optional Code Cerns" chould be includeo to pr ovide the basis f or this r ef er ence.

2. The proposed additional suntunce in (b) (2) (i).ppetru to conflict with the sentence of the original text preceeding it regarding applicability to code addenda subsequent to the Summer 1978 Addenda.

Clarification of the scope of that preceeding sentancu :.s appliceble only'to (b) (2) (ii), (iii). and (iv), would be helpful. Alternettvely, subheedings in (b) U :1 ) or addition of 2nother subparagsrph (v) for the limitations -elated to IWB-U640 may accomplish the needed clarification.

3. The proposal to accept the 1986 Edition of Section XI without exception is a necessary improvement in clarifing use of the code, especially in its provision for inspection of Code Class 2 piping. In the past ~ther e has been con f usion abcut a seeming contradiction with the limitation in (b) (2) (t v) '?)

fer plants whose application for a construction permit was cocketed prior to July 1, 1978, relative to the l ast centence of (t ) (2) (i ) in the existing text. In this writerb mind the Summer 1576 Addenda and that sentence handled the matter adequately :ut, as mentioned in 2 above, this could be confused further-by the proposed eddition to that paregraph. The Winter 1903 Adda-da to Section /! Includ d c.: gr.i i a c an t - c - 1 a c', t n 'ab ? o I WC 2O. - .. h i c h.ere ... ; p '. '. _ tu.W n.' '. f v aas c r n m t +.. - %c cl ar i f ication onvul d elimine e eny quest: an M.m .le ue of ue 1983 and the 1986 Edition for inspection of Coce Cl ass 2 p t ping.

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m Y ... n., fia r v i n I. L tr u l s 7801 Ro o s o'. e l t Blvd.#62 87 AUG 31 P12:04 Phi 1e.. PA lo)52 Secretary Uni:cd States t:actate Poculatory C o x.:t. t s t. s o r

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L. C. St.0 $$ 00Cr( ' '.. gp un. Dcar l1. Secretarvt Please accept these as my comnents on Federal Recaster rJotice Volume, 52, Numbcr lh2 datad June 26,1987, Peccestd Rule on Cedes eno Standards for Nuclear Pouer Plants, 10CFR Part 50. Many interested parties in the general public have stated the vapu that the ections of raculatory b; dies mil.e trem appear to be handmascens to tne industry which they are suoposed to regulate. This proposed rule shous that the NRC'in not a regulator , but a hcndmaiden. In a era uherein many unexpected and unhampv surprises affect the e.u c ! s F.- 3rdust-, fro?. esfor accident to uis"cected corrosien. scceots the writinos of the nuclear tho TPC still t l i m- : 2 r. dos t i i a s Gos pe l truth. The lessons of Ti1I ard Chernobyl have passed the NRC bv nithout effect. The present vsli tm2nn:ns acM i =,+ i t.. ; cil s s a stcci c: rrosion c e cou.cu ) ; t t : r-c;u e s t a : r, t e g o t

ngurei. i t e..M r. d e L.

.ne f MC stetf. I I s ti M..'1 CocC 41 6 s col ~.ar e d 3 C 1 (hC pe ocjLheu.* t Ilir l.d PCint f uith uall th a noa ssa nor the recent corrozion of stainless steel e v > d t..c c ci e n I x e :. t c c 1 2.. se sor -) c.'ent-t. Ar.c t'. leg the tFC Codr. shows that the tGC has 12ttle regard of i ts oun 1.1censec e vent Reports syntom. The real solution to Coces and Standards should be to produce thD regulatory agencies own standards based on the agency's own Cxperience and analysis. Using the industry's logic will lead to tha same mistake as evidenced in the TMI accident wherein the stoff concurred with the ut,ility to allou non-safety orade PORY ar.d check valve suffice on the reactor pressure boundary in contiadiction to the G:nceal Dcrian Critoria. This '.iolation of rules was a direct co r.ti 1 cu to r to the Tt11 accidens. I resce.rfully suc7ett that thc NRC ca.mi.atc all allousore for ASME or inductiv developed codes and standards an the rules cnd regulatiores. ,.d the NRC shall develop their oun codes and ctandards from NRC e"perience ard data. Respehtful1y t[ted. e h e M a r v 1. r. I.,

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['t~d b0 A ? M ZMs4 o taon, 24018 Federal Register / Vol. 51 No.123 / Friday, June 20, 1987 / Proposed Rules tespectively.This proposed amendment Nuclear Regulatory Research. U.S. Sections 50.100 through 50.102 also lesued revises Footnote 6 to incorporate a Nuclear Regulatory Commission, under sec. tee. es Stat. ss5 (42 U.S C. 22361 teference to Regulatory Guide 1.147. "In-Wa shington, DC 20555, Telephon > (301) For the purpoon of sec. 223. es Stat. osa, as service Ir spection Code Case 443-7713, amended 142 U.S C 2273), I 50.to(s). Ibl. Aceptability-ASME Section XI and (c). 50 44,50.46. 50.48,50.54. and 50 00(a) Disision 1," which identifies the Code Paperwork Reduction Act Statement are inued under sec.161b. es Stat. 94& a s amended (42 U.S C 22o1(b)h ll 50.to(b) and Cases acceptable to the NRC staff for This proposed rule would amend (c) and 50.54 are isived under sec.16tl. es implementation in the inservice information collection requirements that Stat. 949. as amended (42 U S C 2201(11); and inspection (ISI) program of light. water-are subject to the Paperwork Reduction il 50.55(e). 50 59(bl. 5010. 5011,5012. 5013 cooled nuclear power plants. At present, Act of 1980 (44 U.S.C. 3501 et seg ). This and so.ro are issued under sec. teto, sa Stat. the implementation section of proposed rule has been submitted to the 950.e amended (42 U.S C. 2201(o)). Regulatory Guide 1.147 specifies that Office of Management and Budget for

2. For i 50.55a, paragraph (b)(1), the applicants should make a specific review and approval of the paperwork introductory text of paragraph (b)(2),

request to the NRC to use Code Cas requirements. paragraph (b)(2)(1), and Footnote 6 are endorsed in the regulatory guide. The revised to read as fo11ows: next revision of Regulatory Guide 1.147 Regulatory Mexibility Certification (i.e., Revision 6) will reflect the As required by the Regulatory i 50.55a Codes and standards. proposed change in Footnote 6 of the Flex bility Act of 1980,5 U.S.C. 605(b). regulation. It will permit the use of Code the Commission hereby certifies that (b)**' Cases endorsed in tl.e regulatory guide this rule,if promulgated, will net have a (1) As used in this section, references without a specific request to the NRC for significant economic impact on a to Eection !!! of the ASME Boiler and q approval. In the interim, it is the intent substantial number of small entities. Pressure Vessel Code refer to Sect;on y of the NRC that Code Cases listed in This proposed rule affects only the 11 Division 1, and includeKditions Reguletory Guide 1.147 may be used licensir: and operation of nuclear ou2 Ee 1MIXft.ipnmoWAddenda q without specif;c application to the NRC. power iants. The companies that own ough the Winter 198fAddendaad Subsection IWE, Requirements for these p ants do not fall within the scope (2) As used in this section, referenced Class MC Component,s of Ught.% ater of the definition of"small entities" set to Section XI of the ASME Boiler and Cooled Power Plants, was added to Section XI. Division 1,in the Winter forth in the Regulator Flexibility Act or Pressure Vessel Code rest to Section the Small Business Size Standards set XI. Division 1, and includAtions 1981 Addenda. However.10 CFR 50.55a out in regulations issued by the Small (thMuug. the i966EdMofurs(TAddenda Business Administration at 13 CFR Part Ini5 ugh the baueFins Addend or ion of ec ion It t address the

121, sub)ect to the followinglimitatao, and /\\

151 requirements for Clase 1,2, and 3 com onents and their suppnets.The Ust of Subjects in 10 CFR Part 50 ]i) t lens on specific editions and Antitrust, Cla s sified information, Fire addenda. When applying the 1974 t ISIof con sin ent 51 et proposed amendment is only intended to protection. Incorporation by reference, Edition, only the addenda through the update curren' regulatory requiremente intergovernmental rela tions, Nucle ar Summer 1975 Addenda may be used. to include the latest ASME Code edition Power plants and reactors, Penalty, When applying the 1977 Edition, all of ar.d addenda. the requirements of Radi. tion protection, Reactor siting the addenda through the Suremer 1978 Subsection IWE would not be imposed criteria, Reporting and recordkeepmg Addenda must also be used. Addenda upon Commission licensees by this requirements, and editions subsequent to the Summer amendment.The applicability of Pursuant to Atomic Energy Act of 1978 Addenda, that are incorporated by Subsection IWE is being considered 1954. as amended, the Energy reference in paragraph (b)(2) of this separately, Reorganization Act of1974, as amended, section are not affected by these and 5 U.S.C. 553. the NRC proposes to limitations. When applying the Winter Ens ironmental lropact; Categorical adopt the following amendments to 10 1983 Addenda and Winter 1984 Exclusion CFR Part 50. Addenda, the rules of paragraph IWS The NRC has determined that this 3640 may be used for all applications proposed rule is the type of action PART 50-DOMESTIC UCENSING OF permitted in that paragraph, except described in categorical exclusion 10 PRODUCTION AAD UTIUZATION those associated with submerged arc CFR 51.22(c)(3) Therefore, neither an FACIUTIES welds (SAW) or shielded metal are environmental impact statement nor an welds (SMAW). For SAW or SMAW, environmental assessment has been 1.The authority citation for Part 50 use paragraph IWS3640. as modified by prepared for this proposed rule, continues to read as follows: the Winter 1985 Addenda. Authority: Sees.103.104.161.182.183 168. Regulatory Anal).sie 18168 Sm 9m 937St. On 9R en 9% as

• ASME Code cans that are authonsed for The Commission has prepared a

, amended. see. 234. 63 Stat.1244. se amended use by the Commission steff are hsted in regulator) analysis for this preposed (42 U S C 2133. 2134. 2201,2232. 2233. 2236. NRC Regulatory Culde 164. "Code Case amendment to the regulations. The 2239. 2282) secs. 201. 2c2. 20s. se Stat.1242. Acceptabihty-ASME section m Desten end analysis examines the costs and 1244.1246. as amended (42 U S C 5841. 5642. Fabncation." NRC Resulatory Cuide l as, benefits of the alternatives considered 5646). unless otherwise noted. "Code Cas,,e Acceptability-ASME Section 111 by the Commission. Interested ersons S=ch n 50 7 also issued under Pub L 95 Matenals, and NRC Regulatory Code 1.147 E 801. sec.1o. 92 Stat. 0951142 U.S C. 5851). Inseruce Inspection Code Case may examine a copy of the regulatory Sections so 5a. 50 el and 50 s: stso issued Accept.b Aty-ASME Section XI Dwision t." anal) sis at the NRC Public Document under Pub. L 9'-415. 96 Stat. 2o'3142 U.S C. The use of other Code cases may be Room.1717 H Street NW., Washington. 2:391. Sechen so f s also iss ued under sec. authonned by the Director of the Office of DC. Single copieJs11utenah eis may be 122. os Stat. e3a (42 U S C. 2152) Secnons Nuclear Reactor Regulation upon requot obtained fro.. Mr. C C. Mdlmanl So ao through 50 et also iswed under sec.164. pursuant to l Solsalal(3). DWision of Enginee o os Stat. 954. ee amended (42 U.S C. 2:34). [cr[- Received from Mr. M. N. Bressler without transmittal letter.}}