NG-98-0329, Comments on Pr 10CFR50 Re Engineering Judgment for Activities or Evaluations of Components or Sys.Change to 10CFR50.55a Should Be Defined If NRC Concerned About Specific Application of Using Engineering Judgment

Comments on Pr 10CFR50 Re Engineering Judgment for Activities or Evaluations of Components or Sys.Change to 10CFR50.55a Should Be Defined If NRC Concerned About Specific Application of Using Engineering Judgment

ML20203L920
Person / Time
Site:	Duane Arnold
Issue date:	02/20/1998
From:	Huting M IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:	NRC OFFICE OF THE SECRETARY (SECY)
References
FRN-62FR63892, RULE-PR-50 62FR63892-00011, 62FR63892-11, NG-98-0329, NG-98-329, NUDOCS 9803060304
Download: ML20203L920 (26)

Text

-

Dad'# $' *1.". 3 { !@' e L? P'!Y' h h 3lI? Dall llD1]

c m ia w :s OYY Y Te ephye 319 b517611 161FC r., 3,9 as, ms

% f%R ~0 P2 ;U0 UTILITIES NUCLEAR GENERATION DIVISik NG 98-0329 ADJ '

February 20,1998 DOCKET NUMBER DD Secretary PROPOSED RULE rn 60 US Nuclear Regulatory Commission b'# N 38 N g Washington, D.C. 20555 ATTN. Ruteniaking and Adjudications Staff Project: Duane Arnold Energy Center Docket No.: 50 331 Op. License No.: DPR-40

Subject:

Comments on Proposed Rule "10 CFR 50.55a" Vol. 62, No. 232, dated Wednesday, December 3,1997 File: A-100, A-286a

Dear Sirs:

Attached please find IES Utilities' comments on the subject proposed rule.

Sincerely, Actbk[

ark Huting ['

Program Engineering I

\

MAH/GCP/cfs g

Attachment:

Comments

\'}{}{\\\\\\\f$nNk$.

9803060304 980220 PDR PR 50 62FR63892 PDR 35/o a= <s m,-c, cn,

~

~v w:-r1 i

i

's Attachment to NG-98-0329 Page 1 of 4 COMMENT 1, Paragraph 2.3.1.2.1 Paragraph 50.55a(b)(2)(xi) addresses the need for NRC approval of engineering judgment for activities or evaluations of components or systems within the scope of 50.55a that are not directly addressed by the BPV Code per 10 CFR 50.55a(a)(3).

The foreword to the Code (ASME Section XI) states and recognizes th&t all aspects of operating a nuclear power plant CANNOT be addressed by one book; however, should not be prohibited. The foreword continues to state, The code is not a handbook and cannot replace education, experience, and the use of engineeringjudgment. 'Engineedng Judgment'is then defined or referred to technicalJudgments made i by knowledgeable engineers experienced in the application of the Code. EngineedngJudgments must be consistent with Code philosophy and such judgments must never be used to overrule mandatory requirements.

lWA-1400 specifies owners are responsible for maintenance of flaw evaluations.

Paragraphs lWB 3142.4, IWC 3122.3, and IWF 3122.3 all allow for evaluation of relevant conditions but provide no Code criteria for performing these evaluations.

LWD allows evaluation through reference to IWB. In cases where visual flaws on all classes of piping and any component support flaws are evaluated and accepted, I interpret that since these evaluations are done outside of Ccde approved criteria (they don't exist), they would have to be sent to the NRC for -

pre-approval. This represents most of the evaluations that are done at DAEC and could require significant NRC support on a very expedited basis to avoid plant start up delays. Is this really what was expected?

The NRC should accept the Owner's responsibility of hiring competent engineers. Engineering judgment plays an important role in the development, implementation, and maintenance of an Inservice Inspection Program, if the NRC is concerned about a specific application of using engineering judgment then the change to 10 CFR 50.55a should be better defined.

COMMENT 2, Paragraph 2.3.1.2.3 2._3.1.2.3 Explains the reason for not accepting the Code incorporation of these code cases N-198-1, N 322, and N 324.

Code Case N-198-1 provided exemptions from welds located within containment penetrations made inaccessible by a concent;ic guard pipe.

Code Case N 322 provided alternatives to the examination requirements of item B10.10 in Examination Categor/ B-K-1. This code case does not exempt

Attcchm::nt to NG 98 0329 Page 2 of 4 examinatbn; however, it provides alternatives with some specific requirements to be met.

Code Case N 324 deals with the qualification requirements of Authorized Nuclear Inspector Supervisor (concrete) and Authorized Nuclear Inspector )

(concrete). This should not appear in the rule for Class 1 Piping.  !

IWA 1400(b) requires owners to include allowances for adequate access and clearances for conduct of the examination and tests. However, several plants were constructed or designed prior to ASME Section XI and have areas where access is limited. Code Cases N-198-1 and N 322 provide alternatives to a couple of these areas. I believe the NRC has accepted these cases at different utilities with some additional provisions. If this is the case, then these provisions could be published in 10 CFR 50.55a to allow utilities to use both of these code cases. Reference to Code Case N 324 should be removed from Paragraph 2.3.1.2.3.

COMMENT 3, Paragraph 2.3.1.2.4 2.3.1.2.4 Class 2 Piping provided the justification for using IWC 1220 of the 1989 Addenda through the 1996 addenda. The use of IWC-1220 of the 1989 - 1996 Addenda is acceptable if the licensee defines the Class 2 piping subject to the volumetric and surface examination and submits this information to the NRC for approval pursuant to Paragraph 50.55a(a)(3) being used when proposing alternatives to the Code requiremeds.

IWA-2420(3) specifies that inspection plans are to identify the components subject to examination and test. Therefore, the Code already requires what the NRC is suggesting to be an alternative. Change the requirement to submit under 50.55a(a)(3) pursuant to IWA 2420(3).

COMMENT 4, Paragraph 2.3.1.2.5 2.3.1.2.5 Reconciliation of Quality Requirements provides a limitation on the use of IWA-4222 in the 1995 Addenda through the 1996 Addenda. The 1995 Addenda states that the administrative requirements, those that do not affect the pressure boundary or core support or component support function, need not be reconciled.

However, IWA-4222(b) states that the administrative requirements of either the construction code of the item being replaced or the construction code of the item to be used for replacement shall be met. Therefore, the combination of both paragraphs provides the necessary requirements and addresses the NRC's concerns.

' i Attachment to NG 98-0329 Page 3 of 4 In addition, the definition for " Construction Code" was changed to reflect just the national recognized codes (i.e. ASME, ANSI, etc.).

I suggest specifying the use of the definition of the Construction Code in the 1992 Addendt which includes the Owner's Requirements. With that change I believe this concern would be catisfied.

COMMENT 5, Paragraph 2.3.2.5.1 Proposed 50.55a(b)(3)(ii) would require that Fcensees supplement the stroke time testing requirements of the OM Code with commitments made for GL 89-10 and GL 90 05 motor operated valve testing. This appears to be an unnecessary burden since licensees have already committed to completing certain tasks in their responses to those letters. To require licensees to respond again on the same issues, and to use NRC resources to go over the same issues again is wasteful.

COMMENT 0, Paragraph 2.3.2.5.1 The ability to use variation of stroke time to detect degradation has beer.

supplanted, not supplemented with the programs which verify MOV's ability to meet design bases requirements. The conservatisms built into the thrust requirements for MOVs now may cause degradation during the forced quarterly cycling. Acknowledgment of the increased testing should be reflected in a reduction of older technology te ting, to ensure the reliability and availability of the equipment. Valve cycling frequencies should be reduced, and unnecessary data not be gathered to acknow! edge the gCas made in the GL 89-10 and 96 05 testing and to increase reliability. Therefore, the current design bases testing should be required instead of valve timing to detect degradation, and valve cycling shcJld be reduced to the level which maintains maximum reliability and availability.

COMMENT 7, Paragraph 2.4.1 2.4.1 discusses what the industry has accomplished under the Performance Demonstration ini'iative (PDI) and the basis for the 0-month implementation schedule for Appendix Vill. The PDI Program has been supported by utilities in the industry and has had some success in verifying the qualification of UT examiners; however, there has been no attempt at qualitication on dissimilar metal welds, vessel-to nozzle welds or nozzle inner radius. A 6-month implementation period for these examinations is not appropriate. The rule should clarify this and allow a longer implementation period for the areas which have not yet been developed or for which qualification has not yet occurred.

Attachment to NG-98-0329 Page 4 of 4 COMMEWT 8, Paragraph 2.4.1.1.1 4

The requirement to distribute the 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of annual training over the year makes it very difficult to implement. Certain times of the year are completely consumed by refuel outages, from late August to December, and from early February to June most examiners are on very busy work schedules which would make it difficult to ob;a:n quality training. The best training and practice available are at the EPRI NDE Center with the many PDI specirrens. Distribution of training throughout the year would require several trips to Charlotte or result in lesser quality practice being done with utility / vendor purchased specimens. I feel j that if the training is done at the NDE Center it should be acceptable to have 40 straight hours because this would encourage examiners to use this facility and provide a higher quality training session.

COMMENT 9, Paragraph 2.4.1.1.2 Requiring all flaws to be cracks is both unrealistic and does not ensure a more difficult demonstration. Fine EDM notches properly placed can be just as difficult or more difficult to detect than thermal fatigue cracks. I think it would be acceptable to limit the crack / notch ratio to something like 80/20 but not eliminate it completely.

COMMENT 10, Paragraph 2.5.3.2 The limitation of time frame for Appendix ll is not sensible when considering to which check valves this area applies. NRC has required monitoring check valve performance through various industry requirements for over the past 10 years.

Thus, the operating experience database on check valves did not begin in 1996.

IST Programs contain check valves which may operato in an accident mitigation capacity but see no use during any mode of plant operation. These valves experience no wear pMnomenon.

< s Blind Distribution of NG 98 0329 Lornn ents on Proposed Rule "10 CFR 50.55a" Vol. 62, No. 232, dated Wednesday, December 3,1997 Distribution:

i J. Franz M. McDermott G. Park F.Dohmen K. Peveler C. Rushworth R. Severson AR 972595 DOCU

, , 03 f!92 -

.me-e we+*

Prcpord Rulos

..___,.m

~ s e%~,

Vol (.:. Nn 232 Wedncu1av. (M emter 3.199r TNs section of the F EDEf4At. IdGtST,14 513 which addressas flaws in low and Adwlicatint.s Staff. lland deliver ctamins nouus to the puoac of the proposeo moderate energy Class 3 piping; Code comments to 11545 Rockvdle luo, esiuance of rules and reguiat oas TF9 Case N-523 which addresses the Roci ville. Man land. 20852, betwe+n non op1.c[ce[enin temporary use of mechanical clamps m 7 30 am and 4f15 pm on Federal rue maung prior to tr,e asotmon of the final Class 2 and 3 piping; and Subsection warkogs.

rues IWE and Subsection IWL,1995 Edition You may also provtde cotnments iria

. _ , __ _ _.- with the 1996 Addenda. the NRC's interactivo rulemaking The proposed rule would expedite website thr< ugh the NRC bome page NJCLEAR REGULATORY unplementation of Appendix Vill, (http#www nrc govl This sata provides COMMISSION "Perfortnance Demonstrauon for the asatlability to upload comments as {

j Ultrasonic Examination Systems." ta files tany formatl. If your web browser '

10 CFR Part 60 Section XI, Division 1, with three supports that funcuon. For information fun 3 t 56.,A E26 pNPosed modifications. An expedited about the interact ve websits contact implementauon schedule would also be Ms Carol Gallacher. (301) 415-5905; e-Industry Codes and Standarosi required for a proposed toodification to mail CAGanrc gov.

Arr noed Requirements Secuon XI which addresses volumetnc Single copies of this proposed examinsuon of the Class I high prmsure rulemaking may be obtained by wntten AGENCY: Nuclear HegulatoO safety o,inction (IIPS11 system in request or telelas to 301--415-2200 or Corntmssion. pressunt.ed watr r reactors (PWRs). from Frank C. Cherny, Division of ACTION: Propmed ruie For IST, the proposed amendment Engmeeting Tec hnology, Office of would require licensees to implemamt Nt. clear Rervlatory Resea2ch, U.S.

SUMiaa8tYt 'Ibo Nucicar twgulatory Nuclear Regulatory Commission.

Comnussion (NRCl regulanons require the 1995 Edition with the 1996 Addenda of the ASPE Code for Washington, DC 20555-0001, that nuclear power plant owncts Opereuon and Maham M Naim Telephor e: 301-4154786.or Wallace construt.t Class 1. Class J. anu Class 3 Power Plants (OM Code) for Class 1, E. Norris. Division of Engmeertng com]wnents to actor ance with the Class 2, and Class 3 pumps and valves Technology, U.S. Nuclear Regulatory tu es provided in Section !!!, Divis, ion l' with one limitation and one Commission. Washington, DC 20555-R utrements Ior Lonttrucbon o. 0001. Telechone: 301-415 4 796,

., modification.10 CFR 50.5'ha has been e At era So t i ech clattfied with respect to which pumps Certata docu.nents related to this Fn and valves are to be included in a rulemaklog, locluding comments Ve 1b(e (B V( e fnsp c [ licenseve IST program. Licensees would received, may be exarnined atthe NRC be permitted to implement: Code Case Public Document Room. 2120 L Stmet

1. Class 2. Class J. Class MC imetal i OMN-1 with one modification in lieu t. NW (Lower level), Wa:hington, DC.

containmenti and Class CC (concrete containmenti components in accordance stroke time testing: Appendix II which These same documents suay also be with the rules providtd m Section XI is an alternative to the check valve viewed and downloaded via the

! Divlsion 1 " Requirements for InserEco condiuon monitoring program inte* active rulemakJog website as inspection of Nuclear Power Plant provisions enntained in Suusecuon established by NRC for this rulemakmg.

Components." of.the ASME DPV Code' ISTC of the OM Code) with three FOR FURTNER INFORLIATION CONTACT:

and test Class 1 Clau 2. and Class a PmP 5ed modiacations:imd Subsection Frank C. Cherny Division et pumps and valves in ar. cord nce with iSTD for the IST of snubbers. Finally, Engincenng Technology Office of the rules provided in Section XI, based upon supporting infoimation Nuclear llegulatory Research.,U.S.

Division 1.of the ASME BPV Code. received since the last rulemaking. the Nucicar Regulatory Commission, The NRC proposes to amend to CFR modificauon presendy in 5 50.55a for Washmgton. DC 20555-0001, 50.55a to revise the requirements for containment isoladort valve inservice Telephone: 301-4154786, or Wallare construction. inservice inspection (ISil, testing has been deleted. E Norns. Division of Engineettog and inservice tesung (IST) of nuclear The Statement of Considerations Technology, U.S. Nuclear Regulatory power plant components. For concludes by clarifying the NRC Commission Washington, DC 20555-construcuoto the proposed rule would position regarding ASME Code 000t 'clephone: 301-415 4 796.

permit the use of Section til Dhision 1, Interpretations, and discussmg NRC of the ASME BPV Code.1989 Addenda DirectiJn Setting issue Number 13 (DSI- $7 At. MENT ARY INFORMATION:

through the 1996 Addenda, for Class 1. 13) with regard to NRC endorsement of 1 Bac k stound Class 2, and Class 3 companents with industry codes and standards. 2. Summary of Proposed Revutons to six proposed limitations and a DAftS: Submit comments by March 3, ;3 ,f,5*$ach gg Hemon and inod Ti cation. 1998. Comments received after this date implementation Schedule For W. the propmed amendment wiil be considered if it is practical to do :: Disseussion would require hcensees to implement so, but the Commission tu able to ensure : 3 1:0 Month Update Section XI Daision I. of the ASME consideration only for commems  : 3 i Secnon x1 BPV Code.1495 Edition with the 1996 received on or before this date.  : 311 Clasi 1. L and 3 Compouentt Addenda for Class 1. Class 2. and Class Acontssts: Comments may be sent to ,

'"d "* M" 3 components with f ac proposed

• Secretary, U.S. Nuclear Regulatory i'3 $ $ 3 t n$ "r$ns laden.ent hmitations 1.icensees would be Cort. mission. Washington, DC 20555-permitted to implement: Cooc Case N-  : 312 7 Qvahts Msurance 0001. ATTN: hulemaking and 2.3 : : 3 clan i nping s

\# h

- - . - - _ . - - . - ~ - - - - - - - - -

, iederel Renkter / Vol. 62s No:* 232 / Weduc5dav. Occomber i 1997 / Proposed Rttles 63893 2.3.12.4 Class 2 Peine modificationad3) inspect Class MC t:nplementation sch2dttls would also be 2 312.5 Huononsoon olouatav Imetal containtnenti and Class CC nmuited for a proposed snodificauon tu '

, yQ'[*** (concrete containmenticomponents m accordance with the rules proviited in section XI which addreues.volumetne

, saminauon of the Class 1 high pressure 2 3 21 rian i. 2. arid .i pumpi and val.es 2 3 2 2 tur6cround-mt twie the 1992 Edition with the 1W2 i.afetv mioction (itPSI) system in 2 3 2 3 Clanhranon of sateiv weis e ed valve. Addends of Secuon XI. Division 1. wiin pressunted water reactors (PWRs).

2 3.2 4 1. imitation certain nodificauona. and (4) test C. .s For (ST, the proposed amantiment 2 3 2 41 Quahty Asturante 1. Class 2, and Class 3 pumps and would Nguare licanases to implement 2 3 2 5 Modihcation- valves in accordance with the rules the 1995 Edition with the 1996 2 3 2 5.1 Stn4e tune lettena provided in the 1989 Edition of hection Addenda of the ASMECodefor 2 a ha pedited impiementatiu" XI Divissna 1,of the ASME BPV Code Opersoon and Maintanance of Nuclear p 1 APlencia vill with certain limitations and Power Planta (OM Code) for Claan 1.

rnodaficauons. Every 120 months Class 2, and Class 3 pumps and valves.

4 1 Ap n i Ill l'r rsonnel Quah6 canon hcensons are inqutrod to update their ISI .0 CFR 50.55a has been clartiled with 2 4 t L2 Appennis vfit sea en s t Crar 6s and IST prospams to meet the s cruon of respect to which pumps and valves are 2 4113 Appenois \ tit smi.nen het Secuonillacorporated by reference 10 be nucluded in a licensee's IST Marustructure into g 50.55a and in eflect 12 months program. A proposed limitation is 2 4 2 Genene tsuer on Appendin vrtl pnot to the start of a new 1;'0 month mcluded which addresses,tbe issue of 2 4 3 Liais Pipiris vo6uinctric t.sarninanon tnterval. . quahty assurance (QAb A proposed 2 6 voluniarv iruplementauon The NRC proposes to arnend to CFR modi 6 cation to the implementation of 2 $ 1 2 comn W 50 $$a to revise the requirements for ihe GM Code is included which construction.151. and IST of nut. lear addresses stroke time testing. Ucensens 25 t I?n r ne lodrement p wer plant components. F or would be permitted to irnplement Code 2 s u 2 snonn ul Maienu, 2 S 113 Mid try U.mensmn. construcuon, the propon.ed rule wnund Case OMi6t with one roodification in 2 s u 4 seamic D,-unn permit the use of Secunn 111. Dmsion 1 heu of stroke time testing. In addition.

2 s u s Quano Auuren e of the ASME IIPV Code.19n9 Addenda a ppendix 11 to the OM Code is an 2 511 h Indepeni ne 9 e of Inspes imn through the 1996 Addenda tilm 1 alternative to the check valve condition 2 512 Modshtaimn Class 2, and Class 3 comt ...nts. Sin morutonng program provistrus 2 $ 121 Appbe stdc Lode \,runn for t"* proposed limitations to the (nntained in Subsection ISW. of the OM C""* " h" " implementation of Secuan lit au Code Three proposedinodifications to te on:wt a n i s.a.m imn nyt. included which address the usues of the implementauon of Appendix 11 are 5 1 engineering judgement, Secuan !!! included which supplement the L5 2 2 ) laws m Lins 4 heing. Met haniul Clan. pine Deu,,. matanals, weld leg dimensions. senmic appendix check valve condition 2 $ 3 OM Cud, design, quality assurance, and motutoring program. Uconsees would .

2 S.3.1 Gode Law mimi independence of inspecuon. A be permitted to une Subsection IS'm for 2 S 3 2 Appendts It modification has been included the IST of snubbessJinally,baner upun 2.5.3 3 butmacuan ISTU addreasing the applicable Code veruon supporting information received since 2.5.3 4 Gnnienment isolahnn Val "i for new construction. the last ruleman ing. the m'Millication

- ' 2.6 AhWhide interpretanons For 151, the proposed amendment presently in $ 50.55a foecnoiminment 2.7 DSI 13 would require licensees to impicment isolation valve inservios testing has n Secuon XI Division 1 of the ASME baen deleted.

2;s p s sam jnne, n hunt t.nurenmental

• BPV Code,1995 Edition with the 19% The mechanism for endorsement of Addenda, for Class 1. Class 2, and Class the ASME standarda,which has been 4 repeIors steduction At t staiement 5, Regulaiory Anaivus 3. Five proposed limitauons to the used since the first endorsement in 6 Regulcorv Heutnhn Ceru6rannn implementation of Section XI are 1971, has been to'tacorporate by

7. ttadht /.naivus included which address the issues of reference the ASME BPV Coda rules engmeenog judgement, qualitv into ir 50.55a. nie regulation identifies

1. Background which editions and addenda of the DPV assurance. Class 1 pipmg. Class 2 The NRC is propount in amend 10 piping, and reconctliation of Code have been approved for use by the CFR 50 55a. which defines the replacement items. Ucensees wnuld be NRC. lin August 6,1992 (57 FR 34666),

mquirements for applyine . -tustry permitted to implement Code Case N- the NEC published a final rule in the codes and standards to nuclear power $13 which addresses flaws in low and Federal Registee to amend to CFR part plants. Section 50 55a presentiv requires mnderste energy Class J piping, and 50. " Domestic Ucensing of Production that nuclear power plant owners Iil Code Case N-523 which addresses the and Utilitation Facilities." ThLa final construct Class 1. Class 2. and Class J temporary use of mechanical clamps in rule amended 6 50.55a to incorporate by components in arrordance with the Class 2 and 3 piping Ucensees would reference the 1986 Addenda,1987 rules provided in the 19H9 bdition of also be permitted to implement Addenda.1988 Addenda,and 1989 Secuon 111. Dmston 1. "Hequirements Subsecuon IWE and Subsecuon IW1.. Edition of Section !!!, Division 1, and for Construc.uon of Nurlear Power Plant 1995 Edition with the 1996 Addenda the 1986 Addenda,1987 Addenda,1984 Components" of the Amentan Socidy The proposed rule would ewedde Addenda, and 1989 Edition of Section nf Met hann al 1:nzinects l ASMEl Hoder implementauon of Appendis Vill. XI. Diviuon 1. of the DPV Code, with and 1%ssure vessei Code IHpv Codel. " Performance Demonstratmn for specified modificauons. The (21insprit Class 1.Clm 2. ano Clm i tiltrasonic Examination SystemC bi amendment imposed an augmented components in at curuant c with the Section X]. Divaton 1. Three propowd esamintuon of reactor vessel shell rules pnmded in the 14"4 Edition of modifications to the implementauma o welds The amendment also separated sertitin XI. Dmuon 1- Requirement s Appendix VIT1 are int.iuded in addrev the requirements for IST of pumps and for Insers n e inspet tion of Nur iear the issues of personr.el cualificanon, unes from thosi for 151 of other power Plant Components " of the AsMt specimen set cracks. and sperimen wt i omponents by placing the OpV Code witb certain hmitauons and microstructure. An espedited requirements for inservice testing in a

. 63894 Fed:rel Redst:r / Vol/ S2; N

? / Wednesday. December 3,1997 / Proposed.Rul2s 6:p:r:te peregraph. For IST of pumps se Canficam w Ufvty.Relsted Valves address an NRC posiuot* with rtgard to and valves, the regulation, through itsv. Limitation o intorporauonby reference of the 1989 a . - Quality Assurance the Foreword in the i A Addenda Editle i of Section XI, endorsed Part 1.~ Modification through the 1996 Addenda of the BPV "Requtrements for Inservice , s Code. That Foreword addresses the use Stroke Time Testtng of" engineering judgement" for LSI Performence Testing of Nuclear Power < . Expv<hted implementauon (after 6 Plant Pressure Relief Device *," Part 6,. acuviues not specadcally considered by emonths from the date of the final the Code. Proposed paragraph "Inservire T6, ting of Pumps in Light. - rule-Beckfit) 50.55a(b)(2)(xi) would require that when Water Reactor Power Plants." and Part*# Section XI - a licensee tellas on engineertng -

10. "Inservire Testing of Valves in """1 Appendia VUI(including three judgement for activittee ocevaluauons Light. Water Reactor Power Plantst' of r -. modifications) of components orsystems within the ASME/ANSIOMa-tc88 OM-1987, to ASME/ANST Personnel Quali6 cation scope of $ 50.55a that arvnot directly fe- Spectmen Set Cracks addressed by the BPV Code, the licensee On August 8,1996 (61 FR 41303), the- Spect' men Set Micmstructure NRC published a final rule in the - must receive NRC approval for those Glass 1 Piping Volumetric Examinadon activities or evaluations pursuant to 10 Federal Regteter to amend 10 CFR '

Voluntary implementation {may be CFR 50.55a(s)(3).. ir 50.55a to incorporate by teforence for used when final rule publishedi the first Ume ASME Section XI. Division Section IU (Not A Backfit) 2.3.1.2.2 QuaWy Ammance 1, Subsection IWE," Requirements for m. Case 1. 2, and 3 Components The second prop"o' sed limitation to the Class MC and Metallic liners of Clase Ilmitations implementation of Section XI pertains CC Components of Light. Water Cooled ' Fngineering judgement to the use of NQA-1 with Section XL Power Plants " and Subsection !WL, Section III Materials Secuan XI references the use oleither "Requeements for Class CC Concrete Wold tes-Dimensions NQA-1 or the Owner's Appendix D Components of Light. Water Cooled s Seismic Design Quilty Anurance Program (to CFR Part Pn ce Plants." Subsection IWE pmvides Quality Assurance 50 Appendix D " Quality Annurance cnteria for vnualinspecuon of the Independence of inspection Critens for N daar Power Plants and i surlare of toetal containments, the steela Mor;if1 cation Fuel Processing Plants") as part of its liners of roncrete containrr.~its, Applicable Code Version for New individual requirements for a QA pressure retaming bolts, and seals and Construction program. At present, $ 50.55a endorses gaskets. Subsecuan IWL provides Section XI(Not A Dackfitj the 1989 Edition of the ASME Code enteria for visual inspection of concrete Subsections IWE and IWL,1995 Edition which references NQA-1-1979 for pressurt* retaining shells and shell with the 1996 Addenda Section XL Ths 1396 Addenda of the camponents and for the examination of Flaws in Cass 3 Piping Mechanical ASME Code refemaces NQA-1-1992 for unbonded post. tensioning rystems. , Qa ing ces n XI Segc R

2. Summary of Proposed Revisions to -

i 50.55a OM Code (Not A Dackfiti requirements of NQAm1.1986 Addenda

• "' Code Case OMN-1 through the 1992 Addenda, that are part

• The revisions to 5 50.55a which Limitation on Length of Test interval Ithe incupomuon by reimace d would result from adoptlun of the 1989 Appendlx II(including three Section XI, and has determined that by Addenda Wrough the 1996 Addenda - itself, NQA-1 would not adequately modifications) have been divided into three groups . Valve Opening and Closing Functions describe how to satisfy the requirements bued on the proposed implementauon Limitation of14ngth ofInitial Test o O CR P ppandix B. ity schedule ti e.,120-month update, Interval .

g ru ,

eapedited, and voluntary). For each nf..' Condition Monitoring Program Plants and Fuel Reprocessing Plants,,,

these groups, it is indicated in Subsection IS"ID since the am various d parentheses whether or not particula' r ~ Containment Isolation Valves " ' "

j, P QA an items are considered a backfit under to -

u g hlch are not CFP 50.109 as discussed in Section 8. u Discussia addressed by NQA-1.

Hacklit Analy sis. This section provides 2.3 120. Month Ug .te CFR (b)(6)(ti) ires (l' a list of each revision and its ,*The info uon on the trols to be

" 2.3.1 Section XI ssed for a nuclear power lant or a fuel cu ion o t e o vi o 1 Case and 3 Components, " 8 P ant 1i da 2.1 List of rach Revision and bsplementation Schedule . Mon 50.55a(bX2) togethu with require rants of Appen B will be S 50.55atgX4)of the proposed rule satisfied." This information is required 120 Month Update (in accordance with 5 50 55af g)(4)(l) and would require thd. licensees implement to be submitted tc,the NRC as part of the Final Safety Analysis Report (FSARI.

$ 50 55alf)(4)(ill the 1995 Edition with the 1996 Standard Revie . Plan (SRP) 17.2, Addenda of Section X1, Division 1. for Cl s 1 d3 mpo ts, including Clau 1.Cass 2,and Cass 3 components " Quality Opersuons Assi Phue." . ace states thatDuring "The QA the 3 "5 and their supports. Five proposed program desenption presented in the Limitat ns limitauons would be included to FSAR must discuss how each criterion Engincenng Judgement address NRC positions on the use r f Quality Assurance Section XL of Appendix B will be met." Further.

Class 1 Pipint the SRP states "The acceptance enteria 2.3.1.2 1. imitations include a commitment to comply with Class 2 Pipmg 2.3.1.2.1 Engineering judgement the regulatory positions presented in the Reconcibation of Quality Requirements OM Code (Not A Backfid appropnate issue of the Regulatory The ftrst proposed limitauon to the Guides including the requirements of Class 1,2.and 3 Pumps and Valves implementauon of Section XI would ANSI Standard N45.2.12 and the Branch

l'cderal Reedst:r / Vol..L2. No. 232 / Wednesdav, Decembe. 3.1997 / Proposed. Rules . 03895 Techntral Postuon listzd in subsection <t ) provisions of Code Case N-198-1 wcre approval pnor to implementatwn.

V of SRP Section 17.1. Thus, the+tw deiermined by the NRC to be Approval was required to ensure that t ommitment tonatitutes an integral part unacceptable because industry safety significant components tn the of the QA prorrum desenpuon and empenence has shown that welds m Residt.al llest Herm, val. Emercency Cote r*qmtements/' The NRC has service seraitne BWR stamlen steel Cooling, and Cor.tainment lleat i sermined that the provisions of NQA- pip..ia mariv of w hich are located in Removal syntett a are not enempted fro *n 1,1986 Addenda thmugh the 1992 Coatamment penetrabons, are sutnected copropnate examtsvhon requirements.

Addenda. would not tausly the cnjena to an arressive environment (BWR Thus. the requirements contatned in spectlied in SRP 17.2 for desenbing how water at reactor operaune iemperaturest IWC-1220. DVC-1221. and IWre122L the requtremients of Appendix B will be and will expencree intem ular htns 1989 Addenda through the 1996 satahed for operettor.al acuviues.There Corrosion Crackmg. La* ptma these Addenda, for deternuning the are numemus areas where Americati welds from exammau .4 could result in components sutiect to exammation and National Standards lastitute ( ANSI) condiuons which reduce the required establishing examinauon requucinents standards or NRC regulatory positions. maryms to failure to unacceptable for Class 2 p6plag may be used if the wlach have been long-standing levels. The provisions of Code Cases N- licensco defines the Class 2 pipmg iornerstones of an Owner's QA 322 and N-324 were determmed to be subtect to volumetne and surfact Program, are either nonmandatory or unacceptable because some important examinauon, and submits this missing altogether from the NQA-1 piptne was exempted from arapection.

provtuons. llowever, the Owner's information to the NRC for approval Access difficulues was the basis in the pursuant to $ 50.55ata)(3).

Section XI QA Pmaram, which has t=en Code cases for exempung these arean approved by the NRC. is adequate. from examination, but the NRC 2.3.1.2.5 Reconcillation of Quality -

T hus. the Commission has detertnined developed the break esclusion zone " " " "

• that the requirements of NQA-1,1986 design and cuammation criteria utilized The fifth proposed limitation to the Addenda through the 1992 Addenda. for most containment penetration pipmg implementation of Secuan XI addresses are at ceptable for use ifa the context of especting not only that Section XI reconciliation of replacement items l

Sectmn XI, as permitted by ..VA-1400. inspecuans would be performed but lb 50 55a(bl(2)(xxl( All and the definiuon pmvided the licensee uulizes its 10 CFR that augmented inspections would be of Construtuon Code Part 50. Appendix B.QA program in performed. These design and ($ 50.55a(b)(2)(an)(B)l. Changes to nVA-( oriunction with Section XI. Changes to esammauon critena att contained in 4222. " Reconciliation of Ownr. s a ht.ei.sce s QA program shall be made Branch Technical Posiuon MED 3-1. n Requirements,"in the 1995 A Jdenda in accordance with to CF1t 50.54(a). attachment of NRC Stanuard Revmw would permit a replacement item Further, where NQA-1 and Secuon XI - Plan J 6 2." Determination of Ruptug produced at a facility not having a 10 do not address the commitmenta 1.ocauons and Dynamic Effects CFR Part 50. Appendix B qualified conta.ned in the licensee's Appendix in Associated with'the Postulated .tuotur, progratn to be used in safety related QA trograin desenption, such of Pipmg." Thus, proposed applicauonc. With re6ard to the commitments shall be applied to $ 50.55alb)(2)(xiii) would require definition of Construction Code, a new Sect on XI activities. Proposed licen*ees to use the rules for nVB-1220 definition of Construction Code

~ l'0 55alb)(2)(mil) contains the that are contatued in the 1989 Edition appeared in nVA-9000 "Clopary," In requirement addressmg licensee's in lieu of the rules in the 1989 Addenda the 1993 Addenda. Due to the changes commitments related to Section XL through the 1996 Addenda. made in IWA-4200 in the 1995 2.3.1.2.3 Class 1 Piplag .

2.3.1.2.4 Claan 2 Piping Addamda, the change in definition could result in standards being utillted which

, The third proposed limitation to the The fourth proposed limitation to the do not cuntain any QA requirements, or implementauon of Section XI would implementauon of Section XI contained contain QA requirements that do not require licensees to use the rules for in $ 50.55a(b)(2)(xiv), would confine fully comply with Appendix B. Thus, Secuun XI DVB-1220 "Componenta- implementauon of Section XI nVC- when implementing the 1995 Addenda Exempt from Examination." that are 1220. " Components Exempt from through the 1996 Addenda, contained in the 1989 Edition in lieu of Exammauon." nVC-1221,"Componer's $ 50.55a(b)(2)(xx)(A) would require the rules in the 1989 Addenda through Within RilR (Residual liest Removall, reconcillation of replacement items to the 1996 Addenda. These later Code ECC (Emergency Cool CoclinFL and the onginal QA requirements. Section addenda contain provisions of Code CllR (Containment llent Removal)

• 50.55a(b)(2)(xxl(B) would require a Cases N-198-1." Exemption from Systerns or t'ortions of Systerns," and - liceruee to reconcile replacement items Exammauon for ASME Class 1 and IWCr-1222," Components Within Class 2 Piping located at Containment to the Constructten L' ode and to the QA Systems or Portions of Systems Other requirements u o . scribed in the Pent trations," N-322. "Examication Than RHR. ECC, and CliR SystemsJ Owner's QA program.

Requirements for latogrally Welded or 1989 Addenda through the 1996 Section XI Article fWA-4000 provides Forged Attachtramts to Class 1 Piping at - Addenda. The provisions of Code Case rules and requirerents for the repair Containment Penetrations;" and N-324 N-408-3. "Alternauve Rules for and replacement u . vssure retaimag "Exammauon Requirements for Examination of Class 2 Piping." were components and their supports.

Integrally Welded or Forged incorporated into Subsection nVC in the Versions of nVA-4000 previous to the ~

Attachments to Class 2 Piping at 1989 Addenda. These provisions 1995 Addenda permitted a licensee to Contamment Penetrauons:" which were contam rules for determining which purchase a replacement item to the found to be unacceptaMe Becauw 'ie Class 2 components are subiect to standari's of the ongmal Construcuon NRC had previously determined the vohametnc and surface rum nauon Code or a later version, provided that Code cases to be unacceptable. thev The NRC had prevmusly determined were not endorsed in any revision of the techmcal requir*ments of an item that the prouuons of the Code Cee such as design and fabncahon.as well Regulatorv Guide 1.147. " Inservice - were acceptable it the hcensee defined .ns the nontechmcal requirements inspecuan Code Cr.se Acceptability- the Class 2 pipme subject to volumetne bdent fled as admimstrettve ASME Sechon XI. Division 1." The and surface esaminauon and recened requirements in (W A-42221 such as Q A

, 6389fl Fed:rd Regist:r / Vol.:62. No. 232 / Wednesday, December 3,1997 / Proposed Rules and Authonaed laspection of thslat:r c rept:ced or the administrative versmn were reconciled with those of. OM Cods thzt have been in:.orporated requirements of the Construction Code the ongmal Construction Code and by reference into 4 50 55a. Paragraph of the item being used for replacement. 50.55a[b)(3) together with $ $0.55a10(4)

Owner's Requirements. Reconciliation flowever, the definition of ensures that the replacement itom meets "Construcuan Code" was changed in of the proposed rule would require that t ertain standards of quality so that it is licensees implement the 1995 Ediuon the 1993 Addenda. In versions of sausiactory for the spoofied design and Secuon X1 previous to the 1993 with the 1996 Addenda of the OM Code.

operstmq condauons. La the 1995 Existing 5 50 f.5al0(1) has bsen modified Addenda Cortstruction Code was Addenda, the provisions of Code Case ,, defined in IWA-9000. " Glossary," as to clartly which pumps and vahes toe N-554,"Alternauve Reqmrements for "the body of technical reqturements that to be included in the IST program. One Recentilladon of Replacement items," governed the construcuon of the item." proposed limitation to implementauon were incorporated into an extensive included in the body of technu.nl of the OM Code addressing QA, and one rewnte of IWA-4200. As a result of requirements that governed the proposed modi!!cauon of the OM Code these cbinges to nVA.-1200, specifically construcuon of the item was a addressing stroke time tesung hav e tweu IWA-4222f a){2), the nontechnical included

• requirement to reconcile the Owner's requirements for Class 1,2, and 3 aalety. specificadon requirements, which relatec' replacement items would no 2.3.2.2 Hackground4)M Code included NRC regulatory requirements, longer need to be reconciled which rsey and appliceble Owner design and Until 1990, the ASME Code result in noncompliance with to CFR procuremeta specificauons that invoke Part 50. As pendia B. NRC regulations requirements addressmg IST of pumps technical and nontechnical ana valves were contained in .*

• tion XI l

require that any item which performs a requirements le g., to CFR Part 50, safety.related function must meet Subsections DVP (pumpsl an AV i Appendix B). In the 1993 Addenda, the (valves). Tbv provisions of D 'and Appendix 11. Appendix il (nvokes, among other things, controls on definiuon became nauonally recognized nVV were last incorporated by reference j

Codes such as ASME, Specifications into $ 50.55a in a f(nal rulemaking supphers of safety related requmng reconcittation of the items. By not such as the American Society of Testmg published on August 6.1r92157 FR admitmtrative requirements, the and Matenals ( ASTMl, and designated 3466e). In 1990, the ASME published provisions in i VA-4222(a)(2)of the Code Cases. Either definition of the initial edition of the OM Code 1995 Addenda through the 1996 Construction Code would include the original Construction Codes for the which provides rules for IST of pumps Addenda, would allow vendora having desigt, and construction of piping, such and valves. The requirements contained a QA prograrn which does not meet in the 1990 Edition are identical to the as B31.1," Power Piping," and B31.7*

Appendix D to be utillud,and may " Nuclear Piping," and those for the requirements containec. in the 1939 result in noncompliance with Appendix design and construction of storage Edidon of Section XI Subsections nVP B. These deficienctes could be resolved tanks, such as the American Petroleum (pumps)and nVV (valves).The ASME if the Code rovided for commercial Insutute (API) 620. " Design and Board on Nuclear Codes and Standards grade item edication in accordance Construction of Large, Welded, low. hu trusfed responsibility for rules l

with to CFR Part 21 " Reporting of Pressure Storage Tanks," and API 650. on IST from Secuon XI to the OM Defects and Noncompliance."llowever, " Welded Steel Tanks for Oil Storage. Committee. As such, the Section XI IWA4222 does not addreas commercial llowever, many of these standards rules for inservice testing of pumps and grude dedicauon. In addition,it should utilized for construction do not contain valves that are presently incorporated be pointed out that a separate Code Case any QA requirements, or they contain by reference into NRC regulations are no which provides an alternative for a specific provision in IWA-4200 Code QA require +nents that da not fully longer being updated by Section XI.

comply with Appendix B. Therefore,in Case N-567," Alternative Requirements order to satisfy Appenuix B,QA The ASME 1990 Ediuon of the OM for Class 1,2, and 3 Replacement Code con sists of one section (Section requirements similar to or meeting Components," was modified to require Appendix B were invoked in the IST) entitled " Rules for Insemce the reconciliation of nontechnical Testing of Light. Water Reactor Power Owner's original procuremect requirernents before the Code Case was Plants," This section is divided into documents. Thus, when implementin8 four subsections, ISTA, " General approved. Therefore, an inconsistency nvA-4200 (including subparagraphs costs between the Code and a Code P VA-4 221, fWA-4222, IW A-4 223' Requirements," ISTB, " Inservice Testtng Case. Thus, when implementing the BVA-4224, and nVA-5224), of Pumps in Light. Water Reactor Power 1995 Addenda through the 1996 Plants;" ISTC, "insemce Testing of Addenda,5 b0.55a(b)(2)(u)( A) would $ 50.55a(b)(U(ul(B) would require a licensee to reconcile replacement items Valves in Light. Water Reactor Power require reconcillation of replacement Plants ** and ISM ** Exam.nadon and items to the onginal QA requirements. to the Construcuan C:de and to the QA requirements as described in the Performance Testing of Nuclear Power The provisions of the Code in DVA- Owner s QA program. Plant Dynamic Restraints (Snubbersl."

4222(a)(2) discussed above address 2.3.2 The IST of snubbers is govern'ed by newly manufactured replacement parts. OM Code (120. Month tJpdate) plant technical specifications and, thus, nVA-4200 in the 1995 Addenda gj A further hmitauon on the use of Article 2 3 2.1 Class 1* **. and 3 Pumps and has never been included in $ 50.55a.

Therefore, this proposed rule de through the 1996 Addenda is contained .

The proposed amendment to requires imp lementauon of Subsections in % 50 55alb)(2)(n)(B). IWA-42221b) S 50.55alf)(4) would require that IST of l dIST ST^$5 addresses the use of items from a facility pumps and valves be performed in 5O v ou d er P t licensees which was shutdown or for which accordance with tbn ASME " Code for to implement Stibsect on ISTD of the construcuon was hahed. lWA-42221b) Operation and Maintenance of Nuclear 1996 Addenda by making a change to permits the use of either the _

administrative requirements of the Power Plants"(OM Code). A proposed their technical specificat ons in new sect on, b 50.55alb)(3), would accordance with apphcable NRC Construcuon Code of the item being specify the editions and addenda of the requirements.

, ^

Fed:tti Rt cister i Vol. t>2. No. 232 / Wednesday. December 3.1997 / Proposed Rules 63897 2.3.2.1 Clar ficatim cf Safety Retzted CFR 50 54. Further, where NQA-1 and Valves 5 years that mcludes approximately 150 the OM Code do not address the MOVs with participatmg liceraces each The existing 5 50.55af f)(1) has teen ' mmuments contained in the testing a few MOVs three times over this interpreted by sorne liceraces to rnean in nsee s Appendts Il QA prorrum intervah and (3) based ou the insults of that all safety-related pumps and salm av tiptwn. such cornmitments shall bn the dynamic testing program. LOG wtll regardless of ASME Code Class lur apphed to OM Codo activities. Proposed estabhsh a long term penodic test equ6 valent' were to be included in the *. 50 55albH 3)til addressos liceraec a program. Proposed 4 50.55a(b)(3)(ill IST program. The NRC proposes to ' ommitments related to the OM Code. would require that hcensees modify this paragraph to :lanfy that th"  :.3.2.5 Modification supplement the stroke time testing pmvisions of ( So $$alfl[1] apply oniv to '"quirements of the OM Code with these pumps and valves in steam, wster. air. 21211 Stroke Time Testing cc.mmittnents, and liquid radioactive waste systems proposed 6 50 $$a(b)(3)(ll) would that perfonn a function to shut down reqt.are that the stroke time testing 2.4 Expedited Ireplementation the reactor, maintain the reactor in a raquirement of Subsection IS*lt of the 2.4.1 Appendia \,Ill safe shutdown condillon. rnitigate Ihe UM Code applicable for motor operated The proposed rule would require that (onsequences of an acudent, or provide s ah es IMOVs) be supplemented with

• hcensees expedite implementation of overpressure prutection for sut.h systems. programs that licensees have preymusly mandatory Appendix VID.

i emmitted to prionn. pnor to tuuance " performance Demonstration for 2.3.2.4 Liarutation of this amendment to $ 50.35a for Ultrasonic Examinauon Systems " to 2.3.2.4.1 Quality Anaurante demonstratmg the design basis Secuon XI,1995 Editjon with the 1996 rapabdity of MOVs. Stroke time testing Addenda. Three proposed modifications The hmitation to the implementatmn of MOVs has been specified in ASME i

of the OM Code pertama to the use of would be mcluded to address NRC wtmn XI and is currently requtred by posiuons on the use of Appendix Vltl.

NQ A-1," Quality Assurant e Hequirements for Nuclear Faubt cs t 50 55a10 This same tesung is required Licensees would be requtred to l M the UM Code. This tesung to a useful implement Appendts Vih. including the with the OM Coda. The OM Code toon and complements other tests used modiGcanons. for all examinations of referetxes the use of either NQ A -) or w sentv MOV funcuon. Vansuon in the Owners Appendix 11 Quahtv the pressure vessel, piping. nonles, and measun d stroke times can ludicate bolts and stuis which occur after ti Assurano Pmgratn as pan of as 6 alse degradttwn. AdditionaFy, individual requirements for & UA months from the date ni the final rule.

i criodic stroking provides valve The proposed rule would not requtre program. At presa.it,5 50 55a enoorm men iso and some measure of on- any thange to a licensee's 151 schedule NQA-t-1979 for the OM Code The demand rettat61 sty. However, as for exam: nation at thase components, 1996 Addenda also endorses NQA i ihscussed in NRC Generne Letter (CL) but would requirt that the provision:.of 1979. Thus, the 1990 GM Code ha n .i mio " Safety Related Motor Operated Appendix VIII be used for all endorsed a latar version of NQA-1 Vahe Testing and Survedlance" dated ilecause this rulemaking would examinauons after that date rather than lune 28.1989,it is now recognized that the ultrasonic tesung (UT) pmcedures l Incorporate the OM Code by refereno the stro - re testing alone is not n

toto $ 50 55a for the first time, a and personnel requtrements presently .

s ulficier.. ovide assurance of MOV being uulized by licensees.

limitatior is included to address the < apability us.uer design. basis Appendts Vlt! pmvndes the l same issues discuaaed prevmusly in the i ono suons.

requirements for performance Secuan XI anction on Q A. Subsequent to licensees implementing demonstrauon for ultrasonic testing The NRC has determined that the programs pursuant to CL 89-10, the provisions of NQA-1,1979 Addenda, (tTT) pmcedures, equipment, and NRt. issued Generte Letter 96-05. parsonnel used to detect Daws and site would not adequately descnbe how in "penodic Venfication of Design llasis satisfy the requtrements of Appendis it flaws. Its requirements are appllcable to Capability of Safety Related Motor- all t.rT perfonned for Class 1. Class 2.

as sausfied by 6 50.34(b)(b)(ii). Further. Operated Valves." on September 18. and Class J items (i e.. reactor vessel, there are vanous aspects of operanonal 1996 This genenc letter requested phase QA and admtmstrouve controis noules, piping. and bolung and studs).

hcensees to establish a program, or to These requtrements are also to be which are not addressed by NQA-1 ensure the effecuveness of their current There are numerous areas where uulized when implemenung the program, to venty on a penodic bans augtnented inservice inspecuon A nencan National Standards Institute ihat safety.related motor operated - pmgram for reactor vessel shell welds

( ANSil standards or NRC regulatory vshes continue to be capable of positions, which are speedied m SRp presently required by 17.2 are either nonmandatory or performmg their safety funcuons within % 50 55alg)(6)till(A). The NRC has the current licensmg bases of the reviewed the 1995 Edition with the missme altogether from the NQA-1 14cthtv Prior to issuance of this rul<

provisions. Ilowever, the Owner s QA 1996 Addenda of Appendix Vill and has hcensees have made licensma determined that the provisions Program, which has been appru ed h

( ommitments pursuant to GL 9fd5 that < ontamed m this appendix should be the NRC. is adequate. Thus, the NRC he hase been reviewed by the NRC stall. used wth three modifications determined that the requirements of Most hcensees ' eve committed to NQA-1-1979 that are pan of the (addressed below) This mandatory partit ipate in the loint Own"rs C.roup appendis would nortnally be adopted as mcorporation by reference of the UM IKX;) rrogram on MOV periodic Ca. is acceptabic for use m the part of the rouane 120-month update Venhcauon The KX; program mcludes spe< ified in % 50 55atg)l4L but because sIST ontest A 14ofprovided the OM the Code, o penmtted htensee unhm h three phases til bcensees will estat>hsh ol the importante of the Appendix Vlil an mterim static diagnostic testinc procram, the NRC has deterrr med that its to(TR Part 50. Appendis 11 U A proctam des cloped by LOG w Oh a lesi program m t_oniunctmn w oh the t M its requirements should be implemented _

ircquent v bared on martm and salets aber ti months from the date of the final Code ".hanges to bcensee s QA program wruhcance, t:) JOG will coordinate a rule. The performance demonstration shall be maae in m< cordatue woh tu dsnamic testmg program over the nest requiremeats in Apnendix VIII would ic .-

e 03890' _Itd:ral Register / Vol. 02. No. 732 / We'dnesday. Decembeir.3.1997 / Proposed Rulco

~

sutatznuallyimprove'ths abilltv of an ~

within approximat:lv 0 tnonths if skillsi frorn those used for single-sided' *b, examiner to detcet and charactente are not maintained.Thus?lo hours of t examinauon. ~'

flawr in exarnined romponents. UT annual training is not sufficient practice . Appendia Vill was originally .

procedures and personnel requirements to maintain skills. The NRC t+liever developed using UT lessons scarned are presenuy contatned in Section XI that a minimum of 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of annual from two-sided examinatforts of welds.

but. as detailed in the documented training, not 10 hourt. is rvquired to This UT expenence provided theinput evaluation required by 6 50.109(a)(4L maintain an examiner's abillues in this for designmg specimens and selecting.

persortnel qualified to Appendix Vm are highly specialized skill arm The NRC locating, and characterizing Dawa. ..

sigtuficantly better at detecting Daws. expects that licaisees would distribute Studies have stown that defect The industry's Perforteance the traininr, over the cource of the year charactensuca such as shape, size -

Demor:stration Inittauve (PDI) to ensure that interpretauon skills do depth, till angle, slew angle. toughness, established a process in accordance not diminish. and c. rack up alfoct the probability of with Appent'ix YQ ler reactor vessel.

noule. ptping. and bolting 2 4'1'1*2 68'g8 APP'"dit VIII S P'C '"*" Set dems a parucular Daw. For exam #,

it was demonstrated in one particular esammauons. PDI has received ~

study (Reference 22 in the documented considerabis 6upport from the industry, The second propobd modiflcauon of evaluauon) that c. parucular flaw wes and every licensee has contnbuted Appendix Vllt would require that all over three times mwe reflecuve in one financially. The majority of the cost of flaws in the specimen sets used for . . direcuon. thus emier to detect, than in PDI was in setting up the samples, Perfortnance demonstration for piping, the opposite direction. Specimens which has be.en completed. Propowd vessels, and nonles be cracks. For designed for two sided examinauon

% 50 55alg)(6)(il)(C)(!) would require PtPinE. Appendix Vmsequires that all may not have defects which are licent.ees to uullem the impmved of the Dawn in a specimen set be cracks. appropnate for single-sided requirements in Appendix Vill for all llowever I r vessels and noules, performance demonstrauon: 1.e.. the esaminauons of reactor vessels M endix P Vm would allow as many as specimens may not adequately test an k i the flaws to be notches. For the examiners proficiency in detecting (6ncluding performed aftet noules), piping,and 6 months from the date bolting ,up<rpose of demonstrating flaws. Therefore. in order to proceed l

' of the final rule. To date, the PDI nondestructive examinadon (NDE) with the effort of qualifying UT systems program has qualified over 300 08Pabilities, notches are not realistic (equipment, procedures, and perso'inell individuals for piping and five teams for representations of service induced for single-sided examinations, proposed

• essel examinauons. Thus, the NRC cracks. An inspector cannot properly $ 50.55a[b)(2)(xx) would require the does not believe that a 4 month interpret service induced cracks by industry to develop sets of specimens implementation pened would result in 9ualit> lnR with specimens containing that contain inicrostruc'ures similar to hardshtp. ya % tm sA.- notches. Notches are easier to detect , the types found in the components to be than finws because astches have a inspected and flaws with non. optimum 2.4.1.1 Modihcaucus higher acinlitude and simpler signal characteristics, such as skew, tilt, and 2.4.1.1.1. Appendia Vill Personnel charactenstics. Notches are easier to roughnals, consistent with field Qualificauon interpret and, in fact, the probability of experience that provide realistic detectinh nutches can be much higher challenges for single sided perfonnance The first propmxi modificadon of than the probability of detecting cracks demonstration. '

Appendix Vill relates to its requirement under similar condluons. In addition, that ultrasome examination personnel Appendix Vm provides a screening test 2.4.2 Generic Letter on Appendix V ll meet the requirements of Appendia Vtl. that uses a relauvely small sample size A draft generic letter was published in

'Quahficauon of Nondestructive contair ing faw flaws. If some of the Examinauon Personnel for Ultrasonic the Federal Resister (61 FR 69120) for flaws are replaced by notches that are public comment on December 31.1996, Examination " to Section XL Appendix unrealisuc. the scree .ing inst becomes to alert the industry to the importance Vil first appeared in Section XI in the ineffective. Brceuse of these of using equipment, procedures, and 1968 Addenda and was incorporated by considerations, the flaws in the examiners capable of reliably detecting reference into $ 50.55a in a final rule a s irpedirisiiser:Tiillized for piping by and siting Daws in the performance of publishs 1 on August 6,1992 (a7 FR comprehensive examinations of reactor ITRI(6f iliiPD1 are all cracts. The 34666) The NRC believes that the regulatoryliRIysh for this iulemaking vessels and piping. The generic letter requirement in Appendix Vll-4240 for contains a detailed r'iscussion of the stated that even though the need for personnel to receive a minimum of 10 importance of using cracks in the improvement clearly existed, the staff hours of training on an annual basis is specimens. Thus, proposed had reached the conclusion that inadequate. Proposed 5 50.55alb)(2)(xill) would require that all immediate backfitting of Appendix Vm 5 50 55a(bM2)(xvtil would require that flaws in the specimen sets used for in advance of this proposed rulemaking all personnel qualified for perferming performance desmonstradon be cracks. was not warranted. This conclusio s was ultrasonic examinations in accordance based on consideration of defense in.

with Appendix Vm receive 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of 2.4.1.1.3 Appendix VIII Specimen Sei Wcrostmeture depth measures. Code margins in annual traming which includes component design, leakage monitoring lateratory wnp and examination of The third proposed modification of systems, and also that Appendix Vm flaw ed spegmen,s. Signsis can be ~ Appendix Vlt! would require that all difhcult to interpret, and as detailed in was already being applied to selected specimens for single-side tests contain piping subiect to intergranular stress

• the nyulatory analysis for this microstructures like the components to corrosion cracking. The NRC received rulertating. expenence and studies be inspected and flaws with non- to comment letters on the generic letter, indicate that the examiner must practice optimum charactenstics consistent with The comments generally were very on a frequent basis to mamtain the field expenence that provide realistic similar and can be surnmanred in the capatality for proper .nterpretation. In challences to the UT techniqun. following five items:(1)It is addiuon, these studies have shown that Appendix Vm does not disunguish inappropriate to request licensees to this capability begins to diminish specimens for two sided examinations voluntanly corimit to a program tn a b .; [-  %

n. .

Al

(

Fcd:ral Rtgister / \ 01. 62. No. 232 / Wednescav. Dectmber 3,1997 / Proposed Rules 63(190 pnmtlettIrst2)1he urtency for licensee's to voluntanly comtrat so tubhcation of a fisatrule would obviate L5 Voluntary linpletnentation the need for the genenc leuer.

implemenung Appendix Vl!!is 2.5.1 sertion lit incons, stent with the staternent in the 2 41 Clm 1 Piping Volurnetnc genene letter thtt a safety (cts (N mies f.saminauon The NRC 1.as reviewed the 1989 Addemia.1990 Addenda,1991 ut entst that would warrant u tracunate A proposed snodifitstron of Sec' ion \ddenda.1992 Editjon,1992 Addenda at irtingin advance of the rulemaking;(3) the performance bued XI woald requtre hcensees of 1993 Addenda,1994 Addenda.1995 pressunred wster reactor piarrts t I ditmn, and 1996 Addenda of Secuon qualification program of Appen tra V111 should be opptcsed art alte*natise to the supplement the surface emammauon of Ul thvision 1, for Claas 1' Class 2. and Llus 1 thth P."asure Safety truecuan #' '"" "'

a mplemer t d b i ! to d ie recognized as an acceptable alternetisc un ory -l i e ' E d for Appendia Vl!!.(4)the NRC should gwig.2500-1 for nominal pipe stren '

' d INPS) between 4 finches) and 1 +

provide guidance on inc orporatm8 [et[e 50 55a a A ppenota Vill and/or 101 into plant (inc hesl. with a volumetne (ultrasonic I O specific let programs; and 15) the cuaminauon. This requirement is The senion of Secuon ill uullred by htensees a chosen pnot to propoud because (1)inside diameter fiten auPdt car T I d US R 8 5 (onstrucutsu.Secuon 50.55a permits augmet.ted inspection commitments to a stre range has been prevtousiv hansnt to use We original Code ediuon not yet referented in the discovered (as detailed in NRC Cenene i onstrucuen tode dunng the 1.etter 85-20. "High Pressure iniection/ operauonal phase or voluntartly update i er rd to the first comment, the

• Up e recurig in Habc or i to a later ursion which has been NRC disagrees that it is inappropnate to and W,ilcos ilaats. and in NRC endorsed by $ 50 55a. Accordingly, the request licoruces trholuntanly e ommit Inf nusuu Noun ptopused hmitsuons to Secuon Ill n( solable het ome effect ve only when a licenset to a pmgrarn in a generic letter ibis is sun Innuon soluntanly updates to a later version.

one mechanism available to the NitC for l'rpine. ,1 (2) failure of this line tould alerting hrenscen. for einmple.10 n suit in a smau bmak lou ed cmiant The modific auon would only apply to a degraried conditions w hir h may acudent while directly affecting th appbr ant for a new construction permit.

unacceptably affect the funcuon of system designed to mitigate such an 2.5 1 1 1.1 nitations safety.related components T he set ond event, and (3) volumetne esaminations comtnent takes the generic letter are already required by the Code for 2.5 L1.1 1.ngineering judgement I

statement out of content What the Cass 2 pomona of this system (Table Tb first proposed limitauon to the genenc leuer t.ctually stated was that a IWC-2500-1 F.xamination Category C- implett+ntauon of Secuon 111 would safaty concern did not exist to wanant F-11 within the same NPS range, Thus, estabbsh an NRC restrtction with regard irnmediata backfitting in advance of the not uly are die requimments betwnn to th Foreword in the 1992 Addenda I rulemaking because of defense-in depth Class 1 and Claae 2 inconststent (with through the 1996 Addenda of the BPV measures, Code snargins in design, and the Claas 1 portions being subiect ta less Code. That Foreword addroues the use that Appendia VlD was already being sinntent tesung mouinments as og ,?cngmeertog judgement" for .

applied to selected piping subiect to compared with Class 2 portions of the construction 4cuvities notspecifically intergranular stress corrosion crackmg rame type nf piping), but operaung considered by the Code. Proposed The NRC strongly dingrees that etPenence haasbown that these reactor paragraph 50.55alb)(1)(1) would require Appendia VI!! and Appendin Vllt a, e clant presenre boundary (RCPD) pape that when a licensee tellas on .

implemented b" PDI should be examinations need to be tuore engtfacenng judgement for activities o; alternauves to the present Code rules, enmprehenswe. Proposed onenta or systems t

As detailed in the documented $ p50 55a(b)(21(av) would require evaluauons within the scopeof of comp $ 50.55a that are not evaluation for backfitting Appendis licensees to supplament the Secuon XI directly addressed by the BPV Code, the VFL lt.has been demonstrated that n, quired surface examination for the licensee must receive NRC approval fe' examiners previously considered Clac.s 1 portion of the f(PSI system with those acuvities or evuluations pursuant qualified under Secuon XI generails volumetnc etaininetton in order to to 6 50.55ala)(3).

have margtaal UT skJlls. This was ' ensure the integnty of the reactor 2.5.1.1.2 Section III Materials evident from the discouragingly low coolant pressure boundary as required percentage of examiners iniually by General Design Critena (GDC) 14,10 The second proposed liraltation to the satisfying the acreening enteria for CFR Part 50, Appendis A,or similar implementation of Section ill pertams to detecting flawn unc'er the PDi program provisions in the licensing basis for a reference to Section II,"Matenals,"

Comment iow regardmg guidance on these facihtles, and Cnteria !! and XVI Part D, "Properues." Section !!, Part D.

incorporating Aopendit Villinto of to CFR Part 50. Appendin B. contained many pnotbg enors in the present 151 programs, and cornment in e 1.icensees would be required to perionn 1992 Edition. These errors were regarding Code edition ar. corrected in the 1992 Addenda.

the volumetnc examinauon dunng anY automatically resolved m a rulemalmg ISI program mspecuan of the f(PSI Proposed $ 50 55a(b)(1)(ii) would format require that Secuon II,1992 Addenda.

system performed after ti months from At the time the generic letter w as be apphed when using the 1592 Ediuon issued. tha proposed rulemakinc w as the date of the Gnal rule. Uuhaauon of hcensee s catsung 151 schedules w di of Section ill The hmitauon is still under development The purpose at result in the wlumetric esaminahons nec essary to ensure that users of the the genetic letter was to alert the being implemented in a reasonatde Code use the design stresses intended mdustri to the 111 generany poor by the ASME Code.

penod of time w hde not impattmc peri irmame in detet tane thsw s and W icnsths of outares or requmng fauuts 2.5.1.1.3 Weld tw Dimensions the Commisuon s mient to endorse shuidown solely for perturmance of Appendts VI!! via ru!= making The llurd proposed linutation to the these examinauons. implementauon of Secuon !!! would

l 63t100_ . Federal Rogister / Vol. t,3, No~ 233 / yednesday, Decemtier 3.1997 / Proposed Rules concet a con 01ct in the'denten and . - NQA61 as pari ofits individual

• w no are rtmponsible for performing the const ucuen tuquircrcents in Subsectinn toquirements for a QA program by work being inspected." Subpararreph NU (Class 1 omponentsl, Subsection integrating portions of NOA-1 into the M, states "Each t erson who venfies NC (Class 21, and Subsection ND (Class QA program denned in NCA--6000 (or.formante of work acuvities for j 31 of Section ill.1989 Addenda through " Quality Assurance." At present, ourposes of acceptance shall be .

the 1996 Addenda of the i PV Code. $ 50.55a endorses the 1989 Edluon of qualified to perform the assigned task "

Two equations in ND-36n3.4fe)(1), the ASME Codewhich references hQA- Hy exemptant Supplement 10S-1 Footnote 11 to Figure NG-3673.2(blil, 1-1986 for Section III. The 1996 paragraph 2 from the requirements of and Firure NTb3673 2(b)-1 were Addenda of the ASME Code references NCA--1134.10. Secuan IU could promote modihed in the 1989 Addenda and ete NOA-t-1992 for Secuen !!!. noncompliance with 13 CFR 50, no lonrer in agreernent with Figures The NRC has reviewed the Appendix 11, *Quahty Assurance Nil-4427-1. NG-4427-1, and ND-4427- requirementa of NQA-1 1986 Adrienda Crttene for Nuclear Power Plants and

1. This change results in a different through the 1991 Addenna, that are part fuel Reprocessmg Plants," Critenon 1.

weld leg dimension depending on of thelacorporation by reference of "Organiution."' Itis enterion requires whether the dimension is denved from Section III, and has determined that the that persons performing QA funcuons the text or calculated from the figures, provisions of NQA-1 are acceptable for report to a management level such that Thus, to ent ure consistency, proposed use in the context of Secuon !!! authonty and organlutional freedom.

5 50.55albl(1)(iii) would requue that activiues. Portions of NQA-1 are including sufficient independence from licensees use the 1989 Edition for the integrated lato Section IU above referent ed paragraphs and figuras administrative, quality, and technical cost and schedule when opposed to safety considerations, are provided.

In lieu of the 1989 Addenda through the provisions which provide a cornplete Thus,in proposed $ 50.55alb)(1)(vil.

1996 Addenda. QA program for design and licensees would be pernutted to use the 2.5.1.1.4 Seisma. Design construction. NQA-1 by itsell would provisions contained in NCA-not adequately destnbe huw to satisfy 4134.10(a),in the 1989 Addenda The fourth proposed limitation to the the requirements of 10 CFR Part 50.

through 0 e 1994 Addenda, but would implementation of Sntion ill ertams to Appendix II. Quality Assurance new mquirements for piping esign be pmhibited from using these Critena for Nuclear Power Plants and provistoris in the 1995 Edluon through evaluation t ontamed in the 1994 Fuel Repmcassing Plants." The Addenda throusth the 1996 Addenda of the 1996 Addenda' additional cntarta contained in Section ,

the til'V Code. The NRC has determined !!!, such as nucles' accroditation, audits, 2.5.1.2 Modification that changes to subartales ND-3200, and third party inspecuun, establishes a Design by Analysis." Nil-3600, 2.5.1.2.1 Applicable Code Version for complete pmgram and satisfies the

" Piping Design." NC-3600," Piping New Construction requirementa of Appsudix D (! e., the Design," and ND-3600. " Piping prmisions of Sectico U1 integrated with The proposed modificauon of Secuen Design," of Secuon Ill for Class 1,2, and NQA-1l. Decause licenstes ma y IU addresses a possibleconflict between 3 piping design evaluation for reversit.g voluntarily choose to apply later NCA-1140 and 6 50.55s for new dynamic loads le g., earthquake and provialons of Section IU, proposed construction. NCA-1140 of Section III other similar type dynaulc loads which $ 50.55a(b)(1)(v) contains a lituitauon requires that the length of time between cycle 8, bout a mean value) are whichvould require that tha edition the date of the edition and addenda unacceptable. The new requirer.ents are and addenda of NQA-1 spectfled by used (Or new construction and the based on the premise that loads such as - NCA-4000 of Section 10 be used in docLat date of the nuclear power plant earthquake loads are not capable of g conjunction with the administrative. te no greater than three years. Paragraph pmducing collepse or gross distortion of quality, and technical provisions . 50.55a[b)(1) requires that the edition a component. The requirements,in part, contained in the edition of Secuon IU and addenda utiltred be incorporated by are based on General Electnc- being utilized. . .

reference into the regulations. T'ue evaluations on the test data performed poasibility exists that the edition and under sponsorship of the Electric Power 2.5.1.1.8 -Independence ofInspection addenda required by the ASME Code to Reseach Insutute (EPRll and the NRC. The sixth proposed linutation to the be used for new con truction wou;d not flowever, NRC evaluauons of the data implementation of Section !!! would be incorporated by reference into do not support the changes and indicate Prohibit licensees in.m using $ 50.55a. In cHer to resolve this lower rnargms than those estm ted in subparagraph NCA-4134.10(a), possible discrepancy, the NRC proposes earlier evaluations The ASME has " Inspection " in the 1995 Edition to modify'existlng $$$ 50.55a(c)(3)(1),

established a special working group to through the 1996 Addenda. Prior to this 50.55a(d)(2)(1), and 50.55 ate 1(2)(1), to reevaluate the bases for the seismic edit!cn and addenda NCA-4134.10(a) permit an epplicant for a construction required that the provisions of NQA-1, permit to use the latest ediuon and design for pip (ing. Thus,in proposed

$ 50.55a(b)(1) iv) licensees would be " Quality Assurance Program addenda which has been incorporated permitted to use articles ND-3200, NB- Requirements for Nuclear facilitiet by reference into 4 50.55s(b)(1)if the 3600. NC-3600, and ND-3600,in the Basic Requirement 10," Inspection " requirements of the ASME Code and the 1989 Addenda through the 1993 and Supplement 10S-1, mguladons cannot simultaneously bu Addenda, but would be prohibited from " Supplementary Requirements for satisfied.

nsing these requirements in the 1994 Inspection," be utilized witLout Addenda through the 1996 Addenda. excepuon. In the 1995 Edluon, NCA- 2.5.2 Section XI (Voluntan 4134.10;a) was rnodified so that imp lementation) 2.5.1.1.5 Quality Aasurance paragraph 2 ef Supplement *05-1 and 1.icensees would be permitted to The fifth proposed limitation to the the requirements for independence of update from the 1992 Edition with the implementauon of Section ill pertams to inspection were no longer naquired 1992 Addenda of Subsection (WE and the use of NO A-1. " Quality Assurance Supplement 10S-1,2.1, states that Subsection IWL to the 1995 Edition Requirements for Nuclear facilities." " Inspection Personnel shall not report wnh the 1996 Addenda in addition.

with Secuon 111. Section !!! references directly to the immediate superworn licensees cou'd implement Code Ca.e

)

federal Kettster d Vol. 62. No. 222 / Wednesday. December 3.1997 / Proposed Rules 63901 N-513. ' 1 $ aluauon Gnteria for * ) ears. Lach plant had a pre-esistinc lbl tennoning ss stems..The current Temporary Ac ceptance of Flawa in program to address Class 1. Class J. and wordmg ot 4 50 55alg)(b)(li) lull 2)

Class .I hpine. ' at d Code Omse N-523- Class J components f be rule ich it to requit mg licensees to implement "the

1. "Mnharutat Clamping Devns for the lac casee a distretion w hether to inservice exammahons which

(.lau 4 and 3 piptog ' have two separata 151 programs. er i onespond to the number of years of tuerte the cuotamment 151 procri.ru with operauon w hath are specified in 2511 Subset tion IWI..and the pre esnung program. Subsection IWL" has c.reated confusion l Suben bon lWL lt has been oser a year since the fmal regarding whether th3 first esammation j Many of the provisions an Section X1 rule was usued. and some licenscen of concrete is requtted to rneet the Subsn twn IWL. "Hequirements Jur hate begun the development 01 a etaminauon schedule in Section XI. l Class CC Concreto Components of 1.ight- 4 ontainment 151 prograrn to comp t) Sub6ei. tion nVL. !WL-2410. w hich n Water Cooled Powet 'lanta." portatning with the required 5 year based on the date of the Structural to the inspection of the tendons of implementauon period. This :teenty Test ISIT). or muy be t oncrete cotitainments wcre based on t ontainment IS! program will be based periormed at any time between guiJarne tontained in Regulatory Guide on the 1992 Edition with the 1992 September 9.1996 and Septamber 9.

135. ' intervice inspecuon of Ungrouted Addenda as required by the fmal rule 2001 Accordtog to s endons m Prestressed Concrete flowever, other hiensees have mdicated $ 50 55alg)(6)(ii)(B)(2) of the final Contamments? A final rule put hsbed that they will request NRC appros al rulemaking, the first exammauon of on August n. 1996 (61 FR 41303) pursuant to 6 50 55alall3) to use later concrete may be performed at any ume incorporated by reference the 1992 ediuons and addenda of Subsection lWE between September 9,1990, and Edition with the 1992 Addenda of and Subsectmn DVL before this September 9,2001. The date of the first Submtun IWE. " Requirements for propo<ed rule becomes 6nal Thus, to esamination of concrete is not Class MC and Metallic laners of Class provie fleaitnhty % 50 55alb)(2)Ivil has c onditional upon comphance with

, t.C Components of LightTVater Cooled t.cen nodshed. Licensees would be Subsection IWI,-2410 or the SIT. The l

Power Plants? and Subsecunn !WL At permitted to implement either the purpose of the itahared words is to that time, there were sescral key presen'h tvquired 1992 Edition w ith maintain the present 5 year schedule for positions in the regulatory guide the 1992 Addenda of the latest esamination of the post tensmning addressing the trendmg of prestress containtnent etanunauon pros nions. sysicm as operaung plaats transiuon to losses. unanucipated tendon clonrabun i c.1995 Edition with the 199h Subsection nVL. For operattog recctors.

grease leakage. and excessne water in Addenda there n no need to repeat the 1. 3. 56 ear the sampled sheathing fdler grease not t or those liternees implementine the implementation cycle.

addtcued in Subset tion IWL because 1992 Edition with the 1992 Addend.i. Section 50 55a(g)(b)(li)(B)(2) also the ASME Code committees had not )ct all of the modincations c.ontamed in stated that the first examinauon i ompleted consideration of these paragraphs 50,55alb)(2)(isll A) through performed shall serve the same purpose posmons Due to the importanui of 50 55alb)(2)(in)(D)(3) must be apphed as for operaung plants as the preservice these positiona, the final rula addressed presently required by b 50.55a. exammahon specafied for plants not yet them m paragraphs 50.55a(b)(2)(ixil A) Licensecs wishtng to implement the it, opereuon. The effected plants are through 50 55alb)(2)(in)(D)(3). In 1995 Edition with the 1996 Addenda presently operaung, but they will be addauon the final nale contained would be required to apply paragrn hs pedorming the examination of concrete 6 50 55alb)(2)(in1(E) w hich addressed 50.55alb)(2)(Lx)( A). under Subsection nVL for the first time.

the occurrence of degradauon m 50.55 afb)(2)(La)(D)(3), and  !!ecause the plants are operating, a f inaccessible areas of contamments. 50 55 afb)(2)(lu)(E) paragraph Section XI preservice examinauon Since publicauon of the 1992 5 50 55alb)(2)(is) would thus be cannot be performed. Therefore, the first Addenda, the ASME Code committees modified. According to concrete exan..nauc.n is to be an have completed thett considerauon of 5 50.55a(g)(6)(li)lD)(1), the contamment msemce crammauon which will sen e those regulatory guide postuons.Most exammations pedormed during the 5, as the baseline (the same purpose for have been incorporated into subsequent year implementauon penod are those opemung plants as the presemce ediuon and addenda, and the 1995 esammauons which are required by esammaunn speciGed for plants not )et Editmn with the 1996 Addenda Subsecuan IWE durmg the first penod in operauon) With completion of this addresses all of the modifications hsted of what will be the first containment first exammauon of concrete, the second atme escept grease leakage anu inspecuan interval. (Since Subsecuan five-year Subsecuan (WL 151 penod degradation in inaccessible areas. Thus. (WL n based on a 5 year schedule. would begm. Likewise, enammauons of licensees would be required to utthre standard Sect:an XI penods do not the post.tensmning system at the nth the mod.fications presently in v 50.55a apply for the examinauon of concrete year (e g..the 15th year post tensionmg addressing grease leakage e nd contamments and their post tensioning system esammauon),if pedormed to the degradatmn in 6naccessible areas The systems). With completion of the nrst requirements of T.ubsection IWL.are to NRC has determmed that the pmvumns penod examinahons, the second penod be pedormeu e 151 ttquirements, r ontamed in Subsecuan nVE and of the first containment 151 interval not the preserm requirements.

Subsection (WL.1995 Edition with the would begir The end of the thttd The NRC has also been requested to 1996 Addenda Code. in contunct on penod completes the first containmert (lattfy the schedule for future weh the modificauons, would be 151 mten al. a contamment 151120 esamtnauons of concrete ar.d their post-au eptable month update has been completed. and tensioning systems at both operating The final nde pubhshed on August H the snond contamment IS) inten al and new pl.nts There a no requirement 1996 (61 FR 41303) incorporated would begin. in Subsection IWL to pedorm the Subsntwn IWE and Subsection IWl. As hcensees have begun descicain ' esammation of the concrete and the c.to % 50 55a for the first time The f mal 'neir (ontainment 151 proctams the esamination of the post. tensioning rule (ontamed a requirement for NRC has rxened requests to clatih the ustem at tne same time. The litensees to develop and implement a impirmentation schedule for ISI of esarnmauon of the concrete under

< ontainment ISI program within fue roncrete t antamments and their post Subse(tion IWL and the en.ammation of

• 03002 l'ederal Rtrister / Vol 62. No. 232 / Wednesday. December 3.19d / Propossd Rules the liner platea of t;oncrete " pumps, valves, expansion toints. and NRC has det:rmtasd that for motor-tontainment' under 6ubsection IWE haat exchangers: (2) the discovery and operated salves. Code Case OMN-1 is may be perf snned at any time during- t rpair of flaws or deficiencies rernaining acceptable in lieu of Subsection ISTC.

the Sqeat enpedited implementation. frur's r ngir i l constraction: (3) leakage except for leakage rate testing (ISTC 4.11 This examination of the concrete and through a flange gasket:(4) threaded w hich must continue to be performed.

liner plate provides the baseline for* connections employing nonstructura As indicated in Attachment 1 to GL 96-t cropanson with future containn2ent seal welds for leakage prevention 05, the Code case meets the intent of the 1st Coordinaucra of these sche lules in (through seal weld leakage is not a genene letter, but with certain future exam. nations is 1+ft to each " structaral flaw, thread 1,tegrity must be limitations which were discussed in the licensee New plants would be required maintainedl; and (5) degraded socket genenc letter. The NRC supports the to follow all of the provisions contained welds. A pror ned limitation would be OMN-1 maximum motor operated valve in Subsecuan fWL. i e.. sothly die added in 6 50 55 afb)(2)(rvi)(B) which test interval of to years based on current {

preservice examinttion requireraents would preclude the use of Code Case N- howledge and experience, but believe and adopt (l's 1. 3. 5 year examu.ation $13 for these applications, it prudent to require that licensees schedule ISI schedule. The first paracaph of Secuan 4.0 of evahtate the infonnation obtained for 2.5.2.2 f laws inriana 3 Piping Code Case N-513 contains the flaw each motor operated valve during the acceptance crtteria. The enterta provide first five years of use of the Code cue.

Proposed 6 50 55a[b)(2)(xvil would a safey margin baad o s service joading or three refueling outages (whle.bever is permit licensees to use Co to Case N- ' condluons. The second paragraph of longer) to validate assumptions made in 513. " Evaluation Criteria for Temporary Section 4.0 however, would permit a jusufying a longer test interval. These l Acceptance of Flaws in Class 3 Piping." reduction of the safety factors based on limitations on the use of OMN-1 would ,

anu Code Case N-523-1." Mechanical a detailed engineenng evaluation. No be add 6d to the rule as a modification i l Clamping Devices for Class 2 and 3 enteria or guidance is givcn for in $ 50.55e(b)(3)(lii)(A). Thus. Code Case Piping?Section XI centains repair justifying a redu; tion, or limiting the OMN-1 is acceptable in lieu of i methods for pipes nth a flaw exceeding amount of redur Jon. Tbs acceptance Subsection ISTC other than leakage rate l acceptable limits. These repairs restore entena of the first paragraph are based testing requbements, with the l the internty of the fitwed piping. There on sound pnnciples. The second modification that five years or three am e ertain cases, however, where a paregraph would allow ever finer refueling outages (whichever is longer)

Section XI Code repair rusy be calculation until the availabla margins from initialimplementation of Code impractical for a flew detected dunng became miacceptably low. A limitation Case OMN-1, the adequacy of the test plant operation 16 e., a plant shutdos n would be aoded in proposed interval for each motor operated valve would be required to effect the Code 6 50.55 afb)(2)txvi)( Al requiring that must be evaluated and adjusted as repairl For many safety relate'l piping wben implementing Code case N-%13 necessary, systems. immediate repair is required thw spectfic safety factors in the 1 u It addltion, as noted in CL 96-05, regardless of plant status. Ilowever. it paragraph of S,ction 4.0 be seusfled, licensees are cautioned when

' has been determined that undir certain . The use of Code Case N-513. with the implementing Code Case GMN-1 that conditions, temporary acceptance of . limitations, and Code Case N-523 1 the benefits of performing a particular

, flaws, including through-wall leaking. would obviate the need for licensees to test should be balanced against the of low and moderste energy Class 3 request approval for defemog repairs. poter.lal adverse effects placed on the piping is acceptable provided tho' the thus saving NRC and licensee resources, valves or systems caused by this testing.

condiuons 4 e met; ano the repair is. Code Case OMN-1 specifies that an IST eficcted dur og the next outate. At 2.5.3 OM Code (Voluntary program should consist of a rnixture of present, liconsees must request NRC imp lementation) static and dynamic testing. While there staff approval to defer Section XICode Licensees would be permitted to may be benefits to performing dynamic repair for these Class 3 moderate energy implement Code Case OMN-1 in lieu of testing, there are also potential (200 xF. 275 psig) piping systems. The stroke time testing as required in detriments to its use (i.e. valve NRC has reviewed Code Case N-513 Subsection ISTC. Licensees would also damage). Licensees should be cognizant and Code Case N-523-1 and has be permitted to implement Appendix 11 of this for each MOV when selecting the determined that Code Case N-523-1 is as an alternative to the condiuon appropriate method or combination of acceptable. Code Case N-513 is monitoring program provisions methods for the IST program.

arceptabla axcept for the scope and Section 4. . contained in Subsection ISTC. However' . 24 3.2 . Appendix !!

licensees choosing to implement Secuon Lo(e) of the Scope to Code Appendix 11 would be required to apply Paragraph ISTC 4.5.5 of Subsection Case N-513 limits the use of the: the three proposed modificadons to ISTC pennits the Owner to use requirements to Class 3 piping. Appendix 11 to supplement check valve Appendix !!." Check Valve Condition However. Section 1.0(c) would allow Monitonng Program." of the OM Code. '

condition monitonn6. In addluon.

the llaw evaluation cntena to be applied licennees would be permitted to use rz an alternative to the testing or to all sites of ferntic steel and sustenitic ' Subsection ISTD for the IST of snubbers. examination provisions of ISTC 4.5.1 stainless steel pipe and tube. Without through ISTC 4.5.4. If an Owner elects some limitation or + scope of the 2.5.3.1 Code Case OMN-1 to use Appendix !!.the provisions of Code Case the fir J.auan cri wia An alternative to the provisions Appendix 11 becogne mandatory.

could be applica mponents sm.n as contained in 4 50.55alb)(3)(til is Howner, upon reviewing the appendit pumps and valo ,. onginal construction included in proposed 5 50.55alb)(3)(iii) the NRC has determined that the deficiencies. and pressure boundary which would permit licensees to requirements in Appendix !! must be leakace; applic4uons for which the voluntanly implement ASME Code Case supplemented. The first area that the t nteria should not be utilized. Thus, the OMN-1. " Alternative Rules for NRC believes requires supplementation NRC l'as determined that the Code Case Preservice and Inservice Testing of is the demonstration of acceptable vahe shall not be apphed to:(1) components Certain Electric Motor Operated Valve performance. Appendix 11 requires no other than pipe and tube, such as Assemblies in LWR Power Plants." The testing or xamination . of the check N e, _

' G3903 e

Tsd:ral Ruisttr / Vol. fa. No. m / Wednesday December 3.1997 / Proposed Rules required to return to the requirements of acceptance standards and (21 develop a valve obturator movement to both the basts document.that would provide, as open arid closed postuons. Tenur g or IST 4 5.4. !!awever, the NRC beheves the requirements of IST 4 5.1 through a mantmum, a documented basis for not examinauon of the check valve obturator in one direcuon only cannot IST 4 5 4 must be also rnet.14nce,il the includine the regutrements for analysis monitoring procratu a disconunued, of leaLane rates and corrective acuens in l assure tne unarnbguous detecuan of a proposeo 4 50 55alb!!3RahllC) would Part to for those CIVs that do not funcuonally degraded check valve. The require a hcensee to implement the pmvide a reactor coolant system isive obturator must be tested or pressure notauon function. The NRC esamined in teth the openmg and provisions of IST 4 At through IST I

• made a commitment vta the closmg direcuous to assess its condiuon 454 and confirm acceptable performance. Supplementary informauon to l *5'3'3 Subsection ISTD reevaluate the need for the modificauon Proposed 4 50 $$afbH3HivH A) would The IST of dynamic restraints or to Secuon XI. Subsecuon fWV.

require bi. directional testing of checa snubbers is governed by plant technical followtog review of this OM temmutee s alves Length of test inteful is the second specification and, thus. Las never been basis document. This basis documet.t area of Appendia 11 where the NRC mciuded m 5 50 $$a. Ilows,ver, the NRC was transmitted to the NRC in a letter has revnwed Subsecuon ISTD.1995 from Steve Wemman. Secretary.OM beheves the rules must be Ldition with the 1996 Addenda, and has Committee, to Enc S. Beckjord. Director.

supplementad. Appendix It was fint determined that the provatons for IST OfDce of Nuclear Regulatory Research, incorporated lato the OM Code m the 1996 Addenda.Thus,the operstmg al snubbers are an acceptable alternative dated February 16.1994. The NRC has esperience database does not yet exist to to the requirements contained in the dete rmined that the requirements of 10 support long term test intervals for tha plant technic.al specificauons. CFR 50. Appendix 1. ensure adequate condiuon mon.toring concept. Under subsection ISTD 1996 Addenda, idenufication analysn. and correctise the tunent chec.L valve IST program mcludes new provisions for sersice life actions for leatage monitoring of CIVs.

me st v alves are tested quanctly durme monitoring of snubbers. The new ar.d that the esisting modification in plant operation. The interval far certain pronuons requite that the servne h. ves 4 50 55alb)(2)(viil should t e deleted.

et snudbers be predicted and evaluated The regulatory analys s for this s alves has been entended to rc.oehne m ensure that the service hfe will not be proposed rule contains a detaded outates. Under the apper dit, a heensee rueeded before the nest scheduled dacussion of the basa document would be able to extend the, mtervat without limit. A pohcy of prudent and retuchne outap,e. These new provisions findings and the NRC staff evaluauon.

sale mterval extension dictates that ans umply fortnahse preventative maintenance pracuces presently found 2.6 ASME Cade laterpretatious additionalinterval extension must be hmited to one fuel cycle, and this in most plants. Because the IST of 'The ASME issues interpretations to cutension must be based on sufficient snubbers is govemed by plant technical clartty trovisions of the BPV and OM expenence to justify the addibonai time specincauons. Subsection ISTD is not Codes. Requests for Interpretations are Interval changes or extensions must be mciuded m the proposed mandatory submitted by users, and after justified and limited within the ennuna requirements of the rulemabag but *Ppropriate committee deliberations hcensees may shoose to voluntanly and balloting, responses are issued by periormance and expenence database-Condition monitonag and the current implement Subsecuon ISTD.1995 the ASME. Generally.the NRC agrees Edition with the 1996 Addenda, b.j with these interpretations. When the

- expenence data base may quahly some velves for an imtial extension to every processmg a change u their technical NRC incorporates by reference specific other fuel cycle, while trending and specifications. This proposed ediuons and addenda into its evaluauon of the data may dictate that modification is contained in regulations, the NRC has a certain the testma interval for some valves be s 50 55atbl(3)(v). understanding of those editions and reduced. Extensions of IST intervals 2.5 u Containment Laolation \,alv" addenda. Because an Interpretation is must consider plant safety and be The proposed amendment would issued subsequent to issuance of the supported by trendtag an'd esatuaung delete the esisting modification in provnion to which it refers, the both Benene and plant. specific interpretation may affect that performance data to ensure the 5 50 55alb)(21tviil for IST of understanding. While the NRC contamment isolauon valves (CIVs).

component is capable of performine its which was added to the regulauons m acknowledps that the ASME is the intended function os er the enure IST a rulamaking eflective on August 6 officialinterpreter of the Cnde the NRC interval. Proposed 6 50 55a(bl(3lhvHB) 1992 (57 FR 34666). That rulemahng wstl not accept ASME interpreuuons would limit the time between the mittal mcorporatec; by ref erence, amons other that. in NRC's optnion, are contrary to test or enamtnation and second test or thmgs. the 1989 Edition of ASME NRC requirements or t'tay adversely esammatian to two fuel cycles or three impact facthty operauons.

Section XI. Subsect on IWV that years (whichever is longer), with Interpretations have been issued which add;tional entensions limited to one fu, ; endorsed Part 10 of ASME/ ANSI OMa1988 for valve inserv ce tesung A in some cases. connicted with or were cycle. and the total intsn al would be modincation to the tesung requirements inconsatent w ith NRC requirements, hmited te a mtsimum of to gcars An These resulted m enforcement acuons.

estension or reduction in the mten al of Part to related to CIVs was included m the rulemabna indicanna that Gi particular concern are Code be: ween tests or examinations would Interpretauons that may be have to be supported by trending and paracraphs 4 2 L3te) and 4 2 L310 of Part to were to be apphed to ClVs As implemented following imtiation of evaluation of 3erformance data entorcement acuon by the NRC. ASME The final arw m Appendis !! w huh noted in the "Supplementarv informanon

• for the August b.1992 Code Interpretations were discussed in the Communion behes es should be rulemaking, the ASME Operations and Part 9900. TechnftalGuionnce of the supplemented a the requirement NRC inspecoun Manual Part 9900 appbcable to a hcensee w ho Mamtenarne TOM) Committee had mitaated action to t1) pertorm a prondes that htensees should eserci.e -

ducontinues a t ondition moniterms c aution w hen appipng interpretations program. A bcensee who discontmues (cmprehensise review oiOM Part to Civ tesung requirements and as they are not specihtally part of the use of Appenda 11, under IST 4 5 5 a r.

federal Rettier / Vol. 62. No. 232 / Mdn:sd:v. Dec:mber 3.1997 =/ dProposed Ru 63004 standards. As part cf this cvelu tion, tbs * - nuclear power plants. h incorporation by seference into 6 59.S$a-and have not reutved NRC approval. Staff is addressing issues relevant sense, the proposed tcrtheruleaNRC's would have endorsement a o 2'7 D51 13 .

Since 1992, when the Commissica including periodic updauna, theimpact -of to CFR 50.109 Ithe Ba streamlining the process for NRC review Secuon XI1995 Edibon with the 1996 last revised 4 50.55a to endorso new and endersement of the ASME . <: Code.

c. Addenda. As most of the technical ASME Code Editions and addenda (57 ,i- clanges to this edition / addenda merely FR 346t.6). ceveral developnients have 2.8 Steam Generators occorred which have rotsed some ASME Code requirements forsepair methodoloey. of incorporate improved technology imposition of these fundcmental issues with respect to the . beat exchanger tubes by sleeving were requirements is not expected to either Commissions endorsement of ASME added to Section XIin the 1989 '

Codes. First, on October 21.1993.'

Ent2rgy Operations. lac. submitted a Addenda, Minimum Code requirements ' Mcrease request that would relieve it from so that licensees would not have t0 % i paragr'aphs (WF-2510. Table IWF-250 updating its ISI and IST programs to the develop sleeving regrams and haveTWF-2430, would result la fewer Icst ASMECadaeditionandaddenda them approved b the NRC on a case- supports being examined which would incorporated by reference into 6 50.55a. by cast utils. Th NRC has reviewed - decrease the occupational exposure Th3 unde? lying promise of the request the Coos requirements for sleeving and compared to prer.ent support inspection was that a licensee should not be determined that they are acceptable.- plans. It is esumated that an examiner required to upgrade its ISI and IST flowever. it should be recognized that receives approximately 100 millistms program without considering whether there are other relevant requirements. for every 25 supports examined, ths costs of the upgrude are warranted in light of the increased safety afforded and that a considerable amount of effort Adoption of the new provisions is is presently being expended due to the expected to decrease the total number of by the updated Code ediuon and number of occurrences of degraded -

addenda. Though the request was later supports to be examit.ed by steam generater tubing. For example, approximately 115 per unit per interval.

withdrawn, the underlying premise lirensees are required by either 10 CFR Thus, the reuuction in occupational resulted in NRC reconsideration of the50.55alf) or by the plant technical exposure is estimated to be 4r 0 t 20 month update. Requtrtog Code specifications to perform periodic millitems per unit each inst t: n upd ates every 120 months is still under insery ce inspecuens and to repair (e.g.. interval or 50.14 rems for 10. nits.

acttve consideration. However, the slesvingl or reuove from armice (by. The proposed rule would impose proposed rule has been prepared underinstallinst plugs in the tube endal all Appendix Vill to Section T1.1995 the traditional approach: 1.e.. licensees tubes found to contain flaws exceeding ' Edition with the 1996 *sddenda. DPV

, would be required to updats their ISI the plugging ilmit (i.e. tube repair - Code, for the first time and would end IST programa every 120 months to cntenal. In addition, cutrent technical erpedite its implementauon. Appendix the latest edition and addenda specifications coeuin operational VfD provides rules for the performance incorporated by reference into 6 $0.55a. leakage limits. Licensee s have dernonstration of ultrasome if a decision is reached subsequent to frequendy found it necessary to examination systems, proceduns, and publicauon of the proposed rule tbt is implement measures beyond minimum + personnel. Implementation of this adverse to this approach, this position Code and technical specification ~ appendix should result in a decrease in wul be corrected prior to* pubilcadon of requirements to ensure adeounte tube occupational exposure. Appendix Vf!!

the final rule. integnty when significant degradation qualified procedures and personnel Seconct.the National Technology should reduce repeat ultrasonic testing pmblems are encountered.Thuat Transfer and Advancement Act of 1995, NRC determination that the sleeving the

• (UT). which could reduce occupational PL 104-113, was signed into law on requirem mts are acceptable should - be exposure. In addition, flaws should be March 7.1996. The Act directs federal kept in perspective. '

detected at an earlier stage of growth agencJes to achieve greater reliance on resulting in less extensive repair technical standards developed by 3. Finding of No Significant ~

EnvironmentalImpact operations, which could further reduce voluntary consensus standards occupational exposure.

development organtrations. Finally, the P ced upon an environmental ne proposed rule would incorporate Commission commenced a Strategic assessment, the Commission has ty reference into the regulations the Assessment and Rebaselining Initiative. detsrmined, under the National 1995 Edition with the 1996 Addenda of One of the issues addressed in this effort Environmental Policy Act of 1969 the OM Code, imposition of the OM was Direction Setting issue (OSil 13. amended, and the Commission's Code is r et expected to either increase which raised the question. "In - regulations in Subpart A of to CFR Part or decrease occupational exposure. The performing its regulatory 51, that this rule,if adopted would not types of testing associated with the 1995 responsibilities. what cont'deration have a significant effect on the quality Edition with the 1996 Addenda of the should the NRC give to industry of the human environment and therefore OM Code are essentially the same as the activities " A draft paper addressing an environmental impact statement is DSI-13 was published for public OM standards contained in the 1989 not required. Edition of Section XI .eferenced in a enmment on September 16.1996, after The proposed rule is one part n' a final rule published on August (L 1992 which the Commission held public regulatory framework directed to meetings tri facshtate understanding of ensuring pressure boundary integnty (57 FR 34666).

Actions requeed of applicants ano the issues and receive comments on the and the operational readiness of pamps beensees to implement the proposed f3S1 13 draft paper. Based on the pubhc and valves. The proposed rule rule are of the same nature as those comments. the Commission has directed incorporates provisions rcontained in the applicants and licensees have the NRC Staff to address how industry BPV Code and the OM Code for the perforrning for many years. Therefore, initiatives should be evaluated, and to construuic n. inservice inspectiort, and this acuon should not increase the evaluate several issues related to inservice NRC testing of components used in endorsement of industry codes and

e a Federal Retist:r / Vol. 02, No. 232 / Wednzsday, December 3,1997 / Proposed Rules 63005' pot:nti:1 fora tiegnuv3 environmental A fisirs. NEO!1-10202;13150-00111.

im pact. Wl~ -- Components," of the Amencia Socirty -

Ofute of Monarernent and Budget, ' of Mecharutal Engineers (ASME)Iloller Tbb NRC has sent a copy of the Washmgton DC 20503.,

Environmental Asseument and the and Pressure vessel Code (BPV Code),

proposed rule to every State 1,nanon Corntnents in OMH on the infortnabon 121 inspec t Class 1. Class 2. Class 3 e tillet tmns or on the above issues - Class MC (rnetal contatnment) and Class Offirar and requestod their comments should be submitted by January 2,1998 CC tooncrete containmenti components -

on the Environmental Assessment. T he Comaients received after this date will environmental assessment is avallable in accordance with the rules provided be e onsidered if it is practical to do so, in Scciton XI. Division 1, for inspection at the NRC Pubhc Document Room,21201. Street NW sut usurance of consideratirm cannot " Requirements for Inservice Inspectinn flower 14vell Washington,In Single be given to comments realved after this of Nuclear Power Plant Components," of date

• topies of the environmental assessment the HPV Code. and 131 test Class 1. Class are available from f rank C. Cherny, Public Protecuon Notification 2, and Class 3 pumps and valves in Division of En ieenna Technology, The NRC may not conduct nr sponsor. accordance with1.1.lcensena the rules provided in Office of Nuclear Regulatory Researth, Section X1, Divtsion are -

and a person is not required to respond required to updata every 120 months to U S. Nuclear Regulatory Cornrmssion, to. a collection ofinforer.ation unless it Washington, DC 20555-0001. displays a currently valid OMil control the vemon of Section XI incorporated Telephone: 301-4154786, or Wallac e by reference into 5 50 55a 12 months number E. Norns. Division of Engineenr2R pnot to the start of a new ten year-Technology, U.S. Nuclear Regulatorv , 5. H'Iulato'I Anai *64 I I"'"* l Comrnission, Washington. DC 205%- The propued amendment to $ 50.55a The Commission has prepared a drah 000), Telephone: 301-415 4 790 wuld requue hcensees to update ISIin nyulatory analysis on this pmposed regulation. The analysis exammes the accordance with Section XI of the

4. Paperwork Reduction Act Statement ASME HPV Code and . .lT in accordance

< osts and benefits of the alterneuves with the ASME OM Code. Licensees This proposed rule amends e onsidered by the Commtation. The would be raqmred to implement the mformauna collecuan requirements that draft analysts is sysslable for inspecuon 1995 Edition wth the 1996 Addenda of are subtect to the Paperwork Reductmn in ti,e NRC Public Document Room.

! Act of 1995 (44 U.S.C. 3501 et my 1 (1) Sc"non XI. Dmston 1 for Class 1.

21201. Street NW (tmwer t.evell. Class 2, Class 3. Class MC, and Class CC This rule has bnen submitted to the Washington DC. The Commina.un Office of Managemerit and Hudret 4r components:(2) the " Code for '

requests public cornment on the draft Operstmn and Maintenance of Nuclear rev:ew and approval of the paperwork analysis Single copies of the analysts requirements, Power Plants" lOM Codel for Claan 1, may tie obtained from Frank C. Chemy. Class 2. and Class 3 pumps and valves:

The public reporting burden for this Omston of Engmeertng Technology, informauon collecucn is estimated to and 131 Appendas VIII," performance Office of Nuclear Regulatory Researth. Demoastrauon for Ultmsonic everage 67 person hours per response. U.S. Nuclear Regulatory Commission.

including the time for reviewing Esamination Systems," to Section XI, Washington, DC 20555-000), Divismn 1. As permitted by instructions, searching ettsung data Telephone- 301-415-6785;Wallace E.

sourtes, gathering and mamtamnog the $ 50.55ala)(31, licensees mayvaluntarily

- Norns. Division of Engineering

• update to the 1989 Addenda through the data needed, and compleung and Technclogy, U.S. Nuclear rtegulatorv 1996 Addenda of Section Illo;the BFV reviewmg the cxillecuon of informauon. Comtoission. Washin6 tan!DC 20555- Code, with limitation. In addition, the -

The U.S. Nuclear Regulatory 0001 Telephone: 301-415 4 796.

Commission is seeking public comment modificauon for containment isolation.

on the potuttalimpact of the 6. Regulatory Flexibility Certificauon ** *' '"**'*i IttDE tD*t "EEl i'd t infonnation collections contained m the in accordance with the Regulatory the 1989 Edluon of the BPV Code has proposed rule and on the followmg Flcsibility Act of 1980i5 U.S C. 605(bl. been%deleted.1.lcensees will continue to red to update their 151 and IST issues: .

the Commission certifies that this rule p, *very 120 months to the

1. Is the proposed informauon will not, if promulgated, have a ver m cunn XI and the OM Code collection necessary for the proper signtficant economic impact on a performance of the functions of the incorporated by reference and in effect substantial number of small enuties at least 12 months pnot to the start of NRC, including whether the tnformation This proposed rule affects only the a new 120 month interval, will have prseucal uulity7 bcensmg and operation of nuclear

2. Is the estimate of burden aqcurate r The NRC position on the routine 120, power plants The companies that own month update to 4 50 55a has

3. la there a way to enhance the quality. utility, and clanty of the these plants do not fall within the scope consistently been that 10 CFR 50.109 information to be collected? of the definition of "smah erttitles" set - does not requite a backfit analysis of the

4. Ilow can the burden of th forth n'n the Regulatory Flexibility Act or rouune 120-month update to 6 50.55s.

the small Busmess Sire Standards set The basis for the NRC position is that, informauon collection be mu imtred. out in regulations issued by the Small including the use of automated 111 Secuan 111. Division 1. update c ollection techniques ? Husiness Admitustration at 13 CFR Part applies only to new construction (i.e..

12t Send cornments on any aspect of this the edition and addenda to be used in proposed collection of informatmn L Backfit Analysis the construction of a plant are selected mcluding suggesuons for further based upon the date of the construction The Nuclear Regulatory Comitussmn permit and are not chanced thereafter, reducing the burden. to the informatmn ARC) regulations,10 CFR 50 55a and Records Management Branch IT-+ except voluntanly by the licensee),(2)

F33). U S Nuclear Regulatory requirn that nuclear powet plant beensees understand that $ 50.55a Commission, Washington DC 20%s- owners t ilconstruct Class 1. Class 2. requires that thev update their inservice and Closa ,1 components in accordante inspection proc sm every 10 years to the 0001, or by internet electronic mail at with the rules provided in Sectmn ill.

HIS tuNRC Gov; and to the Desk Of fic cr. thsision 1. " Requirements for latest edition ar.d addend)- f Sect on XI Office of informauon and Regulatory that were mcorporated by reference in Constructmn of Nuclear Power Plant 4 50 55a and in effect 12 months before

e

. 630004 FederaltRwist:r / Vol. 02. No. 232 / W:dnesday, D:cember 3,1997 / P:opossd Rnics . '

th'a start of thxt inspocuon interval, , . r:th:r than the UT procedurer end . . equipment, tools, and stills to attain the .

and13)endorstog and updating , personnel requirements presendy being - required quality and the need for references to the ASME Code, a national utilized by licensees.e .-

venticauon of quality by inspectiun and coraensus standard developed by the The NRC has concluded, on the basis test. Evidente indicates that there are participants (includmg the NRC) with . of the documented evaluauon required shortcomings m the qualificauons of broad and ve..ed interests.is consistent by 6 50.109ta)(4), that imposidou of personnel and procedures in ensuring with both the intentead spirit of the . Appendis Vill, which would gready the reliability of the examinations.s -

bathnt rule ll.e., NRC provides fur the . enhance the overalllevel of assurance of These safety significant revisions tn the -

protectiouf the public bealth and the safety and reliability of ultrasonic Code include specific requirements for safety, and does not unilat. rally impase . examination ter hniques in detecting (TT performance demonstration. with undue burden on applicants or and sizing Daws,is necessary to bring licernees). Finally, to ensure that any staustically based acceptana critena for the facilities deacnbed into compliance blind testing of UT systems (ptocedures, interested member of the public that with GDC 14,10 CTR Part 50, Appendix equipment, and personnel) used to may not have had an opponunity to A, or similar pmviainns in the licensing detect and size Qaws.Gitaris XVI '

participate in the nauonal cotaensus basis for these faca11 ties, and Criterie 11 requdes that measures shall be v ,

standard process is able to communicate and XVI, of to CTR Part 50, Appendix established to assure that conditions with the NRC, proposed rules are D. .- t , 4 :' . . . , ,

published in the Federal Register. adverse to quality, such as failures, a The modificalau to Section X1 to malfunctions, deficiencies, deviations.

The provisions for IST of pumps and require licensees in supplement the valves were originally contained in defecuve material and equipment, and surface examination of the Class 1 Section XI Subsections nVP and DVV. portion (RCPD) of the ID'S! system with gonconformances are prompdy . ~

Sect on XI,1989 Edition was idecutled and corrected. In analyzing k volumetric evamination would ensure incorporated by reference in the August the integrity of the reactor coolant the occurrences of pipe break and 6,1992 rulemaking (57 FR 346661. The system pressure boundary and leakage,it is apparent that the RCPD is 1990 OM Code standards, Parts 1,6, and maintenance of emergency core cooling subject to certain types of degradation.

10 of ASMIVANSI-OM-1987, are system operebility..The operability of Information gathered by the NRC staff ident. cal to Secuor. XI 1989 Edition. this system is necessary to ensure the indicates that many licensees have not This proposed amendment is an protection of the public health and reacted to this serious safety concern by administrative change simply safety, and the NRC has concluded, on performing more comprehensive-refarenctag the 1995 Edition with the the basis of the documented evaluation examinations. The NRC believes that 1996 Addenda of the OM Code. required b $ 50.109(a)(4), that licensees there is a basis for reasonably Therefore, imposition of the 1995 nust su p ement the Section XI concluilag that such degradation could I Edition with the 1996 Addenda of the require surface examination for the occur 6 virtually au PWRs. Nuse of OM Code la not a backfit. Class 1 portion of the HPSI system with the serious degradauon which has Appendix Vlu,"Perfermarwe occurred, and the belief that additional volumetric axamination in order to Demonstrauon for Ultra onic ensure the integritycf the reactor occurrences of noncompliance with Examination. Systems," to Section XI GDC 14, and Criteria U and XVI will be -

coolant pteasuns boundary as required

~ would be used to demonstrate the by GDC 14, to CFRPart 50, Ap endix reported, the NRC has determined that quali!1 cation ci personnel and A, or similar provialans in the censing imposition of Appendix VIH and procedures for performing basis for these deci8tles,and Criteria u volumetric examination of the HPSI -

nondestructive examinauon of welds in and XVI.of to CF; / art 50, Appendix system 6 months after the final rule has components of systems that include the D. Volumetric examination would be 1*en Published under the compliance reactor coolant system and the required during any 151 p.ogram , exception to $ 50.109(a)(4)(1)is emergency core cooling systems in inspection of the f(PSIsystem appropriate, therefore, a hadfit analysis nuclear power facilities. Appendix VIH performed after 6 months from the date is n t required and the cost beneSt would greedy enhance the reliability of of the final rule. t. . .

standards of $ 50.109(a)(3) do not apply, detection and sir.ing of cracks and flaws, CDC 14. " Reactor coolant pressure A complete discussion is contained in and it delineates a method for boundary," (RCPD) or similar provisions the documented evaluation.

qualificauon of the personnel and - in the licensing basis for these facilities, The rationale for application of the procedures. The appendix would specify that the RCPD be designed, , backfit rule and the backfit lustification normally be imposed by the 120 month fabricated, erected, and tasted so as to for the various items contained in this update requirement, but because of its have an extremely low probability of -proposed rule are contained in the importance, implementation of abnormalleakage, or rapidly regulatoryanalysis and documented Appendix VIIIis being expedited by the propagating fauure,and of gross evaluation. The regulatory analysis and rulemaking. Because of the expedited rupture. There has recendy been an' documented evaluation are available for implementauon schedule. the occurrence of gross rupture in the Class inspection at the NRC Public Document imposiuon of Appendix VUIis being 1 po-tion of a HPSI system, and a Room,2120 L Street NW (lower Level),

considered a backfit. Licensees would number of occurrences of abnormal Washington, DC. Single copies of the be required to implement Appendix leakage in the RCPD in other plants, regulatory analysis anc. documented Vill, including the modificauons, for all imposidon of Appendix VIH and the evaluat on are available from Frank C.

examinauons of the pressure vessel. HPSI volumetric examination is also Cherny, Division of Enginciring piping. nor. ries, and bolts and studs necessary to bring the facilities Technology, Office of Nuclear which occur after 6 months from the desenbed into compliance with Criteria Regulatory Research, U.S. Nuclear date of the final rule. The proposed rule !!," Quality Assurance Program." and Regulatory Commission Washington.

would not require any chance to e Criteria XVI," Corrective Actions," of DC 20555-0001, Telephone 301-.415-licensec a 151 schedule for examination Appendix B to it, 4 part 50. Criteria 6786 or Wallace E. Norris. Division of of these components, but would requtre !! requtres, in part, tnat a QA program Engineermg Technology, Office of that the provisions of Appendix Vlu be shall take into account the need for Nuclear Regulatory Research, U.S.

3 used for all examinations ehcr that date special controls, processes, test Nuclear Regulatory Comminston.

' * - .Federd RegistIr / Vol. 02. No.-232 QVednesday. Decembei 3.1997 / Proposed Rulesr 03907

. .Waaldi; ton,DC20555-0001. 1 of paract:ph tfN4):p:rarraphs k)(1). (v) QuahtY assurance /WhIn Op" plying Telephone: 301-415 4 790. (g)('s)(1), the introductory text of editions and addec la later than the' a 1989 Edition of Secuon IU, the-List of Subjects in 10 CFR Part 50 fg)rstra (Gilli)( ph (g)(4 A)(!), ), paragraphs (g)(6)(ill( A!!."), and requirements of NQA-1.** Quality Antitrust. Classified infonnauon. Fire Foottwtes 5 and 7 to read as follow Anurance Requittments for Nuclear prevention,incorporat on by teference.

intergoeernmeetal relations. N uclear @&sa Cees ans standarca. facilities." 1980 Edition through the power plants and reactors. Pe salties, * *' ' ' ' ' 1992 Acidenda are acceptable for'use providad that both NQA-1 and the '

Radiation protecnon. Reactor siting (b) The ASME Boller and Preuur' I criteria. Reportmg and recordkeepins; \,essei Codecand the ASME Code icr quality assurance provisions spectfied requirements. Operation and, Maintenance of Nuclear in NCA4000 are used la cxanjunction l For the reuons set out in the Power Planta, which are referemed to with the admtnistrauve, quality, and preamble and under the authonty of the the following parogrupbs, were edp lou mhd in b Atomic fnergy Act of 1954, as amended, approved forincxirporation by reference cdtuon and addenda cf Section EU being the Energy Reoryanization Act of 1974. uu;tred.

by the Director of the Federal Register. .

as amended, and 5 U.S C 553. the NRC A nouce of any changes made to the (vil Independence of inspection.

la propostng to adopt the followmg metenallocorporated by reference will Licensees shall not apply NCAd amend nents to 10 CFR Part 50. be publ!-hed in the Federal Register. 4134.10(a) of Section 10.1995 Edition Copier of the ASME Boiler and Pressure with the 1990 Addenda, and shall use PART 50-DOMESTIC UCENSINO OF Vessel Code and the ASME Code for NCA4114.10(a),1994 Addenda.

PRODUCTION AND UTluZAT10N Operation and Maintenance of Nuclear FACluTIES Power Plants inay be purchased from (2) As used in this section, references to Secuon XI of tM ASME Bouer and

1. The authonty utatmn 1o. Part 50 gfne rs Un ed Engi nng nter. Pressure Vessel Code refer to Secuon XI, continues to read u fallowr 343 g,,. 47th Street. New York NY Divisi n 1, and include editions through Aethenty: s=s 102.103.t04.105, tat. 10017. They are also available for the 1995 Edition and addenda 2hrough 1a2, in3. Ins 1e9. e,n stac 9 u. 917. 93n. inspection at the NRC Ubrary. Two the 1996 Addenda, subject to the 94a. 953. 954. 955. 9ss, as amended, se' White FlintNorth 11545 Rockville j

f H wing irnstauons and modifications:

234,83 Stat 1444,as amended 142 U S C * *

• 2132.2133,2134.2135,2201,2232,2233. Pike. Rockville, Maryland 208%2-2730 *

• 2236. 2239. 22s21. sets. 201, as amended. As used in this section, references tiv) Pressure retaining wel'ds in AS)' '.

202,206. es Stat.12 42. u amended.12 44. t Secuan IU of the ASME Doder and

,1246 (42 U.S C 5641,5842. 56461 Pressure. 'essel Code refer to Secton IU, Code Class 2 piping (opplies to Tables IWC-2520 or IWG2520-3, Category C,.

Sect on 50 7 also usued undet Pub L 95- FI-t ot ser. t0.92 Stat. 2951(42 U S C 5asti the 1995 Edition and addenda through the 1996 Addenda, sub}ect to the (A) APProPnate Code Claan 2 pipe 6$ ta 955 e n (42$s following limitations and modifications: welds in Residual Heat Ramoval 2131. 2235), ser. t02. Pub. L 91-190. e3 Stat. (1) FnEnneering judgement. When a Systems, Emergency Care Canling

-y 653 (42 USC 43321. Secuans 5013. . licensee rolles on engmeeting judgment Systems, and Containm=ntilaat so.setddl. and 50 t03 also usued under sec. for activities ar evaluations of Removal Systmns, taunt be eramined, tos.6a stat. 939 as amended (42 U.S C components nr. systems within the scope when applytag editions andaddenda 2tas). Secuans to n. 50.n. 50 55 and 50 Se of to CFR 50.SSa that are not directly up to the 1983 Edition through the also tasued under sec. t as. 6a Stat 955 (42 addressed by the ASME Boiler and Summer 1983 Addenda of Section XI t,I UAC 22351. Secuans so.33a. 50.55a and the ASMF Code, the extent of -

Pressure Veass.1 Coda. the NRC must 9 . ail 42 U 43 2 8PProve the activitiea nt evaluations eaamination for these systema must be Secuans 50.34 and 5o.54 also tasued under pursuant to 10 CFR 50.55ala)(3) determined by the requireroents of sec 204,64 Stat.1245 (42 U.S C 5844) (ll) Section IU Matenals. When paragraph (WG1220. Table DVG2520 Sedions so.38. 50 91, and 50 92 also issued applying the 1992 Edition of Section 10. Category C-F and C-C. and paragraph under Pub. L 97-415. 96 Stat. 2073 (4 2 licenstes shallapply the 1992 Edibon IWC-2411 in the 1974 Edluon and U,5 C 12391. Sectmn 50 78 also usued under with the 1992 Addenda of Secuon U of Addenda through the Summer 1975 sec.121,68 Stat 939 (42 U S C 2152). the ASME Boiler and Pressure Veasel Addenda.

Secuens 50.80-50 e1 alas issued under sec. Code' 1e4,6a Stat 9! s amended (42 U.S C. (iii) Weld leg dimensions. When (B) For a nuclear power plant whose 2134). Appana.: .Ialso Lasued under sac.

applying the 1989 Addendte through the applicati n i r aconstruction peruut 187.68 Stat. 955 (42 U.S.C 22371 was docketed pnor to luly 1.1978, 1996 Addenda of Sect on Hl. Licensees

2. Section 50 55a is amended by w ap shall not apply paragraph NB- uP removing and reserving paragraphs 3683.4(c)(1) Footncste 11 to Figure NC- Ed t S (b)(2)(vill and (g)(4)(iv) adding 3673.2(b)-1, and Figure ND-3673.2tb}- 1983 Addenda of Section XI of the paragraphs (b)(2)(xi) through (b)(2)(u l. 1. and shall continue to use the ASME Code. the extent of examination (b)(3), (g)(6)(ii)( A)(6), and (g)(6)(ii)(C). requirements in the 1989 Edition for f r Code Class 2 pipe welds may tw and revising the introductory text of this paragraph and figures. determmed by the requirements of paragraph (b) paragraph (b)(1). the (iv) Seismic design. Licensees may paragraph IWC-1220. Table DVC-2520 introductory text of paragraph (b)(2), use Articles NB-3200. NB-3600. NC- Category C-F and C-C and paragraph paragraphs (b)(2)(iv). (b)(2)(vil. 3600. and ND-3600 0.rouch the 1993 IWC-2411 in the 1974 Edition and (b)(2)(viii), the introductory text of Addenda. subject to the limitat on Addenda through the Summer 1975 paracraph (b)(21 tis). paragraphs Ic)(3), specified in ib)(1)(iii) of this sectmn - Addenda of Secuon XI of the ASME (d)(2),(e)U), the introductory text of Ucensees shall not use the provisions in C de or other nquirements the paragraph (O. paragraphs (0(1). l0(2), the 1994 Addenda throuch the 1996 Commission may adopt.

(0(3)(sii). (0(3)(iv). the introductory test Addenda for these Articles * * * *

• s1

, , G3006 Federci Register./ Vol. 02..No.,232 / Wsdnesday, Decemi.er 3.1997 /Tropos:d Rults (vi) Effectiva sdiuon end addenda of XI.1989 Addands through the 1990 used for perl tmenca d monstradon for Subsecuan nVE end Subsection IWI . Addenda, and shall apply iWD-1220. piping, vessels,and nozzles shall be Secuon XI. Ucsosees shall use either

• 1989 Edition.- tratLs. ' ' ' '

• the 1992 Edluon with the 1992 . (xiv) Class 2 pi, sing. Prior to applying (six) Appendiz VIIrspecimen set .

Addeuda or the 1995 Edition with the the provisions of nVG-1220. imcrostructure. All specimens for 1996 Addenda of Subsection DVE and "Cornponents Exempt imm single-side tests shall contain .

Subsection IW1. as modified and Examinsuon:" nVC-1221, "Com ponents microstructures of the type found in supplemented by the requireme!!ts in Within EllR, ECX , and OIR Systems or components *o be inspected.~a nd flaws

$ 50 $$alb)(2)(ix) and $ 50.55a(b)(2)(x)." Portions of Systams," and nYC-1222 with non.opamum rhamrnristics (vil)(Reserved) " Components Within Systems or (viill Secuon XI References to OM -

Portions of Systems Other Than Rll! . consistent with field exponence that provide realistic challenges to the LTT Part 4, OM Part 6 and OH Part 10 (Table ECC.and OIRSystems,"1989 Addenda techniques. -

IWA-1600-1). When using Table IWA- through the 1996 Addanda, licensees 1600-1," Referenced Standards and (xxl Reconcilia' tion of Qulity shall define the Cass 2 piping subject Requiremants. The following limitat2ons Specificauons"in the Secuon XI, .

to volumetric and surface examinauon, Division 1,1987 Addenda,14$8 apply when implementing Section XI.

and submit this infonnation for IWA-4200,1995. Addenda through the Addenda, or 19't9 Edition, the specified approval by the NRC staff punuant to 1996 Addenda: . , ,1

• • Revision Date or Indicator" for ASME/ $ 50.55a(s)(3) prior to troplementation.

ANSI OM Part 4. ASMluANSI Part 6 ,(xv) Cass 1 pioing volumetnc ( A) Ucenseca sh' a ll not apply DVA-4200,of Section XI 1995 Addenda and ASMF/ ANSI Part 10 shall be the . examinadon. When performing weld through the 1996 Addenda, fora OMa-1988 Addenda to the OM-1987 e==miristions oilligh Pressure Safety Edluon. These requirements have been Inlection Systems, as required by Table reconcillation of the ariminiatmuve incorporated into the 1990 Edluon of . requirements for replacement items, and IWB-2500-1.Examinadon Category B- shall reconcile the administrative the GM Code which is incorporated by J. Item Numbers D9.20. D9.21, and reference in paragraph (b)(3) of this D9.22.alllicensees of prvssunaed water requiremenis with the original section. reactor facilities shall perfonn Construcuon Code and the Owner's (ix) Examinadon of concrete requiremenp required by the 1995 volumetric extminadon of the Class 1 Edition, containments. Licensees applying portion of the system after (insert 6 Subsection fWL,1992 Edition with the - months from the date of the tinal rulel. (B) Utensees shall not apply the 1992 Addenda,shallapply allof the (xvil Flows in Cass 3 piping moderate definiuon of Construction Code in modificadons in this paragraph. energy (200 aF. 275 psig) piping. IWA-9000,"Clossary,"1993 Addenda l icensees choosing to apply the 1995 Ucenwes may use the provisions of through the 1996 Addenda, and shall apply the definiuon of Construction Edidon with the 1996 Addenda shall Code Case N-513i" Evaluation Criteria Code in IWA-9000,1992 Edition.

a pply paragra phs (b)(2)(ix)( A), (D)(3), for Temporary Acceptance of Flaws in and (E) of this section. , Casa 3 Piping." Fev 0, and Code Case (3) As used in this section. seferences

. . . . . N-623-1. "Mda nical Camping to the OM Code refer to the ASME Code Devices for Class 2 and 3 Piping." for Operation and Maintenance of (xi) Engineering judgment, When a Nuclear Power Plants,and include y~ licensee relies on engineering judgment; Ucensees choosing to apply Code Case addenda through the.1996 Addenda and for activides or evaluations of N-523a1 shall apply all of its components or systems within the scope pmvisions, Ucensees choosing to apply editions through the 1995 Edition sub}ect to the following limitations and of to CFR 50.55a that are not directly e Code Case N-513 shall appl aU of its moitfkations:

addrened by the ASME Doller and.. Provisions subject to the foi owing:

.e Pressure Vessel Code, the NRC must (A) When implementing Code Case (1) Quabty Assurance. When applying N-513, be specmc safe 4 facton in editions and addenda of the OM Code, approve the activities or evaluations .'

pursuant to 10 CFR 50.55alal(3).. 1990 and later, the requirements of (xil) Quality Aasurance. When E'[ tied to, .

$ 3Ya I be NQA4,"Quahn Assurance Requirements for Nuclear Facilities,"

applying Section XI editions and addenda later than the 1989 Edition, the aTI) Components otner than pipe and 1979 Addenda, are acceptable as tube, such as pumps, valves, expansion pennitted by ISTA 1.4 of the OM Code, requirements of NQA-1," Quality 8oints, and heat exchangers: Provided the licensee utilizes its to CFR Assurance Requirements for Nuclear Facilities," 1979 Addenda through the (2)Tha discovery and repair of Daws Part 50, Appmdix B, quality assurance 1989 Edluon are acceptable as permitted or deficiencies remaining from original program,in conjuncun wnh the OM construction: Code requirements Changes to by IWA-1400 of Section XI, provided the licensee uultzes itr to CFR Pasi 50, (3) Leakage through a flange gasket: licensee's quality assurance pmgram (4) Threaded connections employing shall be made in accordance with to Appendix in conjunction with Section XI B, quality assurance program, nonstructural seal welds for leakage CFR 50.54(a), in addition, where NQ A-requirements. Changes to licensee's prevendon (through seal weld leakage is 1 and the OM Code do not address the quality assurance program shall be not a structural Daw, thread lategnty commitments contained in the must be ma!atained); and licensee's Appendix B quality assurance made in accordance with to CFR (5) Degraded socket welds, program description, such commitments 50.54(al. in addition, where NQA-1 and (xvii) Appendix VIII personnel shall be applied to OM Code activitics.

Section XI do not address the qual 10 cation. All personnel qualified for (ii) Stroke time testing. Licensees commitments contained in the performing ultrasonic examinations in shall comply with the provisions on licensee's Appendix B quality usurance accordance with Appendix VIII shall stroke time tesung in OM Code ISTC ptogram desenption, such commitments receive 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of annual training that 12,1995 Edidon with the 1996 shall be applied to Section XI activities. includes laboratory work and Addenda, and the programs developed (sin) Class n piping. Licensees shall examination of Dawed specimens. under their licensmg commitments for not apply (WB-1220. " Components (xvill) Appendix Vlll specimen set Fxempt from Examinauon." of Section demonstrating design basis repability of cracks. All faaws in the specimen sets motor-operated valves.

' ' A federal Rettster- / Vol. (22. Nov 232 / Wednesday, December 3,1997 /'Propos:d. Rules G3009 (dil Code Can OMN-1, As r.n ' . 5,, by reference in parserspb (b)(1) of this a constructionTerm'i was issued prior to alternauve to 4 60 S$alb)(3)lli),licensims secuan shall be applied. -

January 1;.1971, pumps and. valves must may use Code Case OMN-1, (til The ASME Code provisions tueet the test inquirements nf pare graphs

' Atternative Hules for i rnservice and apphed to the prmsure vessel may be (0(4) and (f)(t) of this taction to the inservit e Testtug of Cenam t.loctric dated no eather than the suminer 1972 Operated Valve Assembhen m bWR extent practical. Pumps and valves Addenda of the 1971 edition, which are part of the reactorcoolant -

power plants." Rev. O,199$ f.dition -- bill The ASME Code pmvisiorts pressure boundarymust meet the . -

with the 1996 Addenda,in r.ontuncuon applied to piptog, pumps, and valves with ISTC 4.3,199h Edition with the - ratutrementa appikable to components may be dated no cariter than the Winter which are clakstfied as ASME Code :

1996 Addenda Licensees choostng to 1972 Addenda of the 1971 ediuon, and Class 1 Other purnps and valves in app;y the Code cme shall apply all of its . . . . e steam.weter,att,and liquid radioacuve.

I Al The a dequacy of the test interval id) * *

• provtsions' wast Asystems.that perform a function to (2) The Cde Edition Addenda, and shut down the reactor or maintain the for eat.h volve shall be evaluated and reactor in a safe shutdown condition, adiusted as ruessary but not later than optional Code Casests to be applied to the systems and coin onents identified iniugate the consequences of an hve years or thtt e refuehng outares (whabever is lonp.ori from initial in paiagraph (d)(1)o this anction must accident, or provide overpressure irnplementation of ASME Code Case te detenntned by the rules of paragraph protection forsuch systems (in meeting N4 NCA-1143, Subsection NCA of Secuon the rtw;ntrements of the 1986 Edition, or lu of the ASME Boiler Vouel and later, of the Boiler and Pressure Veuel (H)(Reserved) Pressure Code, but: or OM Code), must rneet the test livi Appendia it The fullowing modificalmus apply when (i) The edition and addenda must be requirements applicable to components im lement ng appendia 11, ..Ched those which are incorporated by which are clustiled as ASME Code '

relcrente in parecraph (b)(1) of this Class 2 or Class 3. '

It de, 9 5id wt a wtion. and. !n cue of conflict between (2) For a boiling or pressurir.ed weten 1996 Addenda paracroph (b)(1) of thJs sectwn and cooled nuclear power facility whose

( Al Valve opening and closing paragoph NCA-1140, the latest ediuon construction permit was issued on or functions must be demonstrated wben and addenda incorporated by referente after lanuary 1,1974, pumps and valves flow tesung or emarmnauon methods in paragraph (b)(1) of this section shall which are classified as ASME Code (nonmtrusive, or disassemtily and apphed. Class 1 and Class 2 must be designed inspecuan) are used, (illThe ASMECode provisions and be provided with scress to enable (Ill The truttal interval for tests and applied t the spiems and components the perfonnance of inservice tes's for amiciated exatmnauons shall not "iey be dated no eather than the 1980 operatic sai rwdiness set forth in esteed two fuel cycles or 3 years, Edition, and editions of Secumi XIof the ASME whidiever is longer; any eatension of flill The ASME Code Casesti must Boller and P. essure Vessel Code and this interval shall not exceed one fuel have been determined suitable for use Addeoda6 in effect 6 taonths prior to cycle per estension with the maximum by the NRC. the date of issuance of the construction interval not to exceed to years; trendtng (e)' ' ' permit. The pumps and valvainay and evaluauon of erisung data r. hall be (2) The Code Edition, Addenda, and, meet the requirements set forth in used to reduce or calend ume the CPtional Code Caese to he applied to subsequent editions of this mde and laterval between tests. the systems and compon uta identified addenda which are incorporated by (C)If the Appendix Ilcondition in Paragraph (e)(1) of thi: section must referenes in paragraph (b) of this momtonng program ts disconunued, be detennmed by the rules of paragraph section, subject to limitations and then the rnquirements of ISTC 4.5.1 NCA-1140. Subsection NCA of Secuon modifict.tions listed therein.

through 4.5.4 shall be implemented. 111of the ASME Boiler and Pressure g3y . . .

(v) Subsecuon ISTTL Licensees may Vessel Code, but:

use Subsection ISTD, OM Code,1995 (i)The edition and addenda must be (iii)(A) Pumps and valves,in facilities Edition with the 1996 Addenda, by those which are incorporated by whose construcuon permit was issued muung a change to their technical reference in parayaph (b)(1) of this before linsert effecuve date of the unal spectfications to accordance with section, and,in case of confilct between rulel, which are clustfled as ASME applicable NRC requirements.1.~ensees paragraph (b)(1) of this section and C de Class 1 must be designed and be choosmg to apply the subsection shall paragraph NCA-1140, the latest edp.iu provided with access to enable the and addenda incorporated by reference performance ofinservice testing of the aTcl * * *ly all of its provisions. m paragraph (b)(1) of this section shall pumps and valves for assessing (3) The Code Edition. Addeoda, and be apphed, operational readiness met forth in optional Code Cases to be apphed tu (ii) The ASME Code provisions Section M of rditions of the ASME components of the ructor coolant applied to the systems and components Boiler and Pressure Vessel Code and pressure boundary must be determmed may be dated no earlier than the 1980 Addenda 6 applied to the construction of by the provisions of paragraph NCA- Edition, and the particular pump or valve or the 1140. Subsection NLA of See tion in of (iii) The ASME Code Cases must have Summer 1973 Addenda, whichever is the ASME Boiler and Pressure Vessel been determmed suitable for use by the 'ater.

Code. but: NRC. (B) Pumps and valves, in facilities (i) The edition and addenda apphed (f)Inserv ce testmg requirements w hose construcuon permit is issued on to a component must be those w hat.h are Requirements for inservne mspection of or after Itnsert effective date of the final incorporated by referente in parac.rept- Class 1. Class 2, Clas! J. Class MC. and r lel, w bich are classtfied as ASME lbll1) of this section and in (me of Class CC tomponents hntluding their Code Class 1 must be designed and be i onfhtt trtween parastoph ibit11 of this supporto are located in % 50 55alel provided with access to enable the sertmn and paracraph NCA-1140. the iti for a toihng or pressurized water. performance of inservice testing of the latest edition and addenda incorporated i ooled nuclear power facihty w hose pumps and valses for auessing

03910 Fed:rd Rer,ister-/ NoL G2, No. 232 / Wednesday. Docember 3.1997./. Proposed Rules

.-~

opmtional readiness set forthin.a... .. weste systems tLat provide pressure . . ..t)(1) All. prev 40usly grantsd reliefs edit'ons end eddinds of tha ASME D'Ai . bounduy integnty for systemsthat. m under $ 50.ssa to licensees for the :

Code referenced inparagraph (b)(3) of m perform a function to sbut down the .. ' extent of volumetriceamination of > .

this section et the time the construction, ruactor or maittain the reactor in er safer reactor _ vessel shall welds specified in .

perm 2t i lasued. *,.a3 r hutdown conditioa, or mitigate the.. Item BL10 of Examination Category 11-(iv)( Al Pumps and valves, in faciliues consequences of an accident.mustmeet A " Pressure Retaining Walds in Reactor g who.e con.truction permit was issued , the requirem9nts applicable to. hsel,".inTable 3VB-25&1 of M before (insert eflective date of rulelo . - components wiuch azo classifiedas u . SubenctionJWB in applicable edition whica are classified u ASME Code .. ASME Code Cass 2 or Class 3.. .

and add-nda of Sectinn XI. Division 1, Cass 2 and Cass 3 nust be designed u .- .. . . *<

of the ASME Boiler and Pressure b'*sel and be myided with arrman in enable <

tee p ormance ofinsarvice tacting c6 (3) . . . < Codeeduring the inservice inspection (1) Components (including supports) latervalin eHect on Septenber e, IM2 the pumps and valves for ====aning are hereby avvoked, subject to the -

cperational readiness set forth in - - which udass&d u ASME Code .

Eection XI of editions of the ASME :. Qa.ss i must be desi f uod and be ~ en sW&moMcadot in Provided with ar is to enablathe~ H $ sa.55algX6WXAXMv) for ucensees -

t!oller and Pressure Venaal Code and -

that defer the augmented examination ir.

Addenda 6 applied to the construction of the particular pump or valve or the

" [,,

g , ** '[ , $ secord== with $ 50.t5alg)(6Xil)' AX,3).

I Summer 1973 Addenda,whicheveris AU Mcensees she3 a"Ennant the :

hreservice aramination requirements set . reactor vessel naamination by th in Secum XI of ediums M 6e -

I*** > '- imp lementing once, as partof the -

(B) Pumps and s alves,in facilities ASME Boller and Pressum Vessel Code and Addenda 6 e ded to the insenice inspecum interval in eW -

wbose construction permit is issued on S*Ptember 8,1992, the examinatic 1

or after thsen effective date of the fit.al trucdo-af Punculu ,

cc mponent. requirements for reactor vessel al -

rulel, which ars classified ca ASME . welds specifica in item 81.10 of Code Cass 2 and 3 must be designed Framination Category B-A,"Pn -

2 and be provided with access to enahia (4) Throughout the servica life of a Retnining W-Ids in Reactor Vesk -

the perforrrance of laservice testing ot boilt or pressunzed water-cooled Table IWB-250M of Subsection IWU of the pumps and valves for assessing nuclear power faculty, components the 1989 Edition of Secton XI. Division operational readiness set forth in (including supports) which are 1, of the ASU, Coller and Pressure editions t.ad addenda ofJhe ASME OM classified as ASME Code Q. ass 1 Cass Vessel Code, r2bject to the conditions Code reic anced in paragraph (b)(3) of 2 and Qass 3 must meet the specified in ! ' Mafa)(6'(!i)(AXJ) and this section at the time the constru aon requirements, except design arid access (4). The na ted exammation, when permit is issued. '. Provisions and preservice avamination

. . . . . requirements, set forth in SectionXLoi not defenCi t accordance with 6e provisions of i 50.55alg)(6)(llXA)(J),

(4) Throughout the service Efe of a editions of the ASME Doller and ..

shall be performed in accordance with boiling or pressudzed water cooled . Pressure Vessel Code and Addenda 'that the related procedures specified in the nuclear power facility, pumps and. become effective subsequent to editions SectierrXI edition and addenda

~ valves which are classified as ASME . specifled in paragraphs (g)(2) and (g)(3) applicable to the inservice inspection-Code Class 1. Class 2 an i Class 3 must

~

of this section and that are incorporated intervalin effect on September 8,1992 '

rueet the inservice test requirementa.. by reference in paragraph (b) of this and may 1.e used as a substitute fur the except design and ar== provisions, set section, to the extent practical with1" reactor vessel shell weld ====in= Hon forth in the ASME OM Code and ,

the limitadous of design, geometry and - scheduled for implementation during addenda that becoms, efle tiva, materials of construction -! the the ir.aervice ins on intervalin subsequent to editions and addenda cornponents. Cotnponents which are effect on Septem r 8,1992. For the specified in paragraphs (f)(2) and (fh3) classified as Cass MC pressure retalning potepose of this augmented examination, of this section and that are Inccgorated NnPonents and their integral .. -

" essentially 100%" as used in Table by referencs ic paragraph Wf this attachments, and components which are IWB-2500-1 means more than 90 nacuon, to the extent practi..ai withis classified as Cass CL pressure retain 8 percent of the examination volume of the limitauons of design, geometry and co nponents and their integral . . each weldAra the reduction in matenals oiconstruccon of the attachments must meet the coverage is due to interferes.ce by components. requimments, except design and acces* another cr mponent, or part geometry,

, , , , , pmvisions and preservice examination . ., ,, , , ,

g,,, requirements, set forth in Section XI of (6) Augmented er=minations of (1) For a boiling or pressurized water. the ASME Boiler and Pressure 'It ssel reactor vessel shell welds that are cooled nucient power facility whose Code and Addenda that are performed in accordance with $ En.

construction permit was issued before incorporated by reference in paragraph 55a(g)(6)(ll)(A) alter (insert 6 menths January 1,1971, components (including (b) of this se:: tion, subject to the f.um the date of the final rulel must be supports) must meet the requiremen 2 of limitation listed in paragraph (b)(IXvil performed in accordance with paragraphs (g)(4) and (,,)(5) of this and the modificauons listed paragraph (b)(2XLx) and (b)(2)(x) of Gis section, tr. $ 50.55als)(6)(li)tC).

wetion to the extent practical. , , , , ,

Components which are part of the the egnt pracucal wuhin the drnuation of design, geometry and (C) Application of Appendix VIIIto reactor coolans pressure boundary and ,

Section XI Exammctions.

Weir supports must meet the snatenals of onstrucum of the (2) All reactor vessel (including requtre nants noplical,le to component C " P"" "' nozzles) ultrasonic examinations, all which are classified as A MI. Code pipmg ultrast.nic examinations, and all Clas.s 1. Other pressure vessels, piping, (iv) (Reserved) bo' ting ultrasonic examinadons purnps and valves, and their supports in (6) * *

• p.tec .ned after nt-rt 6 months from steam, water, air, and liquid radioactive- (ii) * *

• tA, site of the firal nile must be

c. o nFetteral: Register / Nol. 62..No. 232 / Wrdnesdavi Dec mber 3..1997 / Proposea RtJes 63011 performed in accordance svitit.fm tm 3 oaTrs:Comm:nts on the proposed ruli Intergov:rnmtat:1 rel:tions Nuclear ?

Appendix VIH of Section XIJDivision 1, must t e recetved on or before January 2, power plants and reactors, Radiation 1995, Edition withthe 199C Addenda of 1998. .

. m . n. . - .c p the ASME Boller and Pressure Veasel protection, Reactor siting cnteria, Code. "C' anontssts: Mail comments to:- - Reporung and recordleeping (2)(Roservedl , n ..u .c %, Secretary, U.S. Nuclear Regulatory requirements.

Commasioni Washington; DC-20555-0001 Attention: Rulemaking and ; '. 10 CFH P,ntt 70

' For ASME Code Editione and A'ddenda AQudicauon Staff. llar.d deliver issued pnor to the Wintar1977. Addenda.the Criminal penalties. Hazardous comments to 11555 Rockville Pike, Code Edition and Addenda 4pphenhl= to th* traterials transportation, Material component is governed by the arder or.' ..V Maryland, between 7:45 am and 4:15 -

control a.nd amountmg, Nuclear pm on Federal workdays. .- .

t t ir uclear nergy a s am.. Copies of any comments rece'ved may materials. Pack agtng ar_d containers.

Radiation protection; Reporting and for the Winter 1977 addenda and subsequent be examined at the NRCPublic ediuona and addenda the method for Dccurnent Room,2120 L Street NW. ncordkeeping requtrements Scientific determming the applicable Code editions and (Lower ievell, Washington,DC - equipment, Secunty measures. Special addauda is cs.tained la Paragraph NCA. For infonnation on submitting nuclear material.

11to of Secuon tu of the ASME Code.+ comments electronically, see the Fo. the reasons set out la the

' discussion under Electmnic Access in Preamble and under tne authority of the

' For purposes of this regulation the' the Supplementary information section.

proposed IEEE-279 twa "in e5ect" on Atcmic Energy Act of 1954, as amended, FOR FURTHER INFORMATION CONTACT:Stan the Energy Reorgsnhation Act of 1974 August so,19sa, er.d the revtied Lasue (EEE-279-1971 tacame "La effect" on june 3,1971. Turel. Office of Nuclear Regulaton', as amended, the National Copies may to obtained from the Institute of Research, U.S. Nuct at Regulatory E'2vironmental Policy Act of 1069, as Electncal and Electronics Engineers United Commission, Washington, DC 20555- amended, and 5 U.S.C. 553, the NRf' '

Engtneenna Center,345 East 47th SL New 0001, telephone (301) 415-6234, e-mail considering adopting the following .

York NY 1001/. Copies am available for s9 M ure-Eav* amendments to 10 CFR Forts 50 and 70.

anspect on at the NRC Library, we White SUPPLEMENTARY INFORMATION: For Filat North.11545, Rockvtus pas. Rockville. additional information see the Direct PART 50-OOMESTIC LICENSING OF Maryland 20a52-273a.

Final Rule published in the rules PRODUCTION AND UTILIZAi ON secuon of this Federal Register. FACILfTIES <

Deted at Rxkvilla. MD this 27th da y of October 1997. Procedural Barkeround t. The authority citation for to CFR For the Nuclear Regulatory Comunassion. Because NRC cot.siders ! bis action Part 50 continues to read as follows:

L heeph Canaa, noncontroversial and routine,-we are Anthorsty: Seca. 102,103,104,105,tal,

• publishing this proposed ru.e . ta2, te3. Isa, ta9,6a Stat. na,937,938.

IFR Doc. 97-315aa Filed 12-2-97: a 45 ami concurantly as a direct final Tule. The 94a,953,954. 955,958, as amen'.ed, sec. 4

• • • ""C***"**" direct final rule will become (ffective ou 234. a3 Stat. 444, as an'iended (42 E (

- February 17,

• 998. However,if the NRC 2132,2133,2134,2135.2201.2232,2233,

, receives significant adverse comments 2238,223". 22a21: seca. 201 as amended, i

1 NUCLEAR REGULATORY on the direct final rule by January 2, 202,206. as Stat.1242, as amended 1244, COMMISSION .. 1998, then the NRC will publish h 124a.142 U.S.C 5841. 5842, steel.

.' ~ documant that withdraws the direct ^ Section 50.7 also issued under Pub. L 95-10 CFR Parts 50 and 70 ' 631, sec. sc. 92 Stat. 29st, as amended by final mle. If the direct final rule is i withdrawn, theNRC willaddresa in a Nb.Lt024 i sec. 2902 toa Stat. 3123..

RIN 3150-AF87.- 42 U.S.C Sa51). Sections 50.10 also tasued

- Final Rule the mmments received in . under secs.101,1as,68 Stat. 936,955, as Criticality Accident Requirements response to the pro osed revisions in a amended (42 U.S.C 2131,22351: sec. t02.

! subsequent final ru a Absent signiScant PuL L 91-190, a3 Stat a53 (42 U.S.C 4?32).

AGEMcv1 Nuclear Regulatory modifications to the p oposed revisiour. Sections 50.13. 50.54tddl. sad 50.103 also Commission' requiring repubhcation, the NRC wilj Luued under pei toa. 6a Stat. 919, as

• ' not initiate a second comment penod annended (42 U.S.C 213al. Sections 50.23.

for this action in the event the direct 50.35. 50.55, and so se also issued under sec SUMuARY1 The Nuclear Reguleory final rule is withdrawn. 185. 6a Stat. 955 (42 U.S.C 2L151. Sections Commission (NRC)is amen kg its 5043a,50.55a ud Appendix Q also issued regulations to provide light. water Electronic Ac eas under sec.102. Pub. L 91-190. a3 Stat. a53 nuclear power reactor licensees with You .nay also provide comments via (42 U.S.C .3321. Sectione 50.34 and 50.54 greater flexibility in meeting Ge the NRC's interactive rulemaking web also issued under sc. 204, as Stat. 2245 (42 U.S.C 5a441. Secuons so.5s. 50.91, and requirement that licensees authont.ed to site (nros.gh the NEC home page (httpd possess more than a small amount of /" " 5 'ov). This site prevides the 50.92 also issued under Pub. L 97-415.96 Stat. 2073142 U.S.C 2239). Section 5478 special nuclear matenal (SNM) mattain availabi...y tr ipland comments a.s files also issued under sec.122, te Stat. 939112 a criticality monitoring system in each (any f rmat). ' your web browser U.S.C 215?l. Secuona 50.a0 50.a1 also area where the material is handled, supports t'ut funcuon. For informauon issued under see ta4. 6a Stat. 954, as used, or stored. This action is taken as about the intenctive rulemaking site. amended (42 U.S C 22341. Appendtx F also a result r i the expenence gamed it. contact Ms. Carol Callagher, (301141s-. ' sound under sec. t 87. 6a Stat. 955 (42 U.S C j processtag and evaluatmg a number of 6215; e. mall CAG4vnrc. gov. 2237) exempuon requests from po--*r reactor List of Subjects licensees and NRC's safety assessments 2. Secuan 50.68 is added under the in response to these rtquests that Io CITI Part 50 center headtng " Issuance. Limitauons, cr *cluded that the likelihood of and Conditions of Licenses and Anutrust, Classified informauon. Construcuan Peruuts" to read as crtucality was negligible.

Crimmal penalties. Fire prevenuon. follows:

l l