NRC Generic Letter 1996-08

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NRC Generic Letter 1996-008: Interim Guidance on Transportation of Steam Generators
ML031110026
Person / Time
Site: Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Washington Public Power Supply System, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Clinch River  Entergy icon.png
Issue date: 12/15/1996
From: Haughney C J
NRC/NMSS/SFPO
To:
References
GL-96-007, NUDOCS 9611060238
Download: ML031110026 (11)


UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDSWASHINGTON, D.C. 20555December 5, 1996NRC GENERIC LETTER 96-07: INTERIM GUIDANCE ON TRANSPORTATION OFSTEAM GENERATORS

Addressees

All holders of operating licenses and decommissioning facilities with possession-onlylicenses for pressurized-water nuclear power reactors.PurDoseThe U.S. Nuclear Regulatory Commission (NRC) is issuing this letter to notifyaddressees that the U.S. Department of Transportation (DOT) and the NRC haveagreed on how DOT and NRC transportation requirements apply to the shipping ofdiscarded steam generators. The guidance below will he p ensure that methods ofshipping steam generators are both safe and practical. Ii :s expected that recipientswill review the information for applicability to their facilities and consider actions, asappropriate. However, suggestions contained in this generic letter are not NRCrequirements; therefore, no specific action nor written response is required.DescriDtion of CircumstancesDOT and NRC transportation regulations for shipment cf radioactive materials wererecently revised to be compatible with those of International Atomic Energy Agency(IAEA) Safety Series No. 6, 1985 edition. The revisions generally became effectiveApril 1, 1996, and have changed the regulatory framework under which steamgenerators are shipped.Neither the previous nor the revised IAEA, DOT, nor NRC transportation regulationsspecifically address the shipment of large components, including steam generators.Several power reactors, or reactors undergoing decommissioning, plan to shipdiscarded steam generators shortly. The following information provides interimguidance on the shipment of steam generators under the revised regulations. Inaddition to this action, NRC and DOT are jointly studying large componenttransportation issues. The shipment of steam generators and other large componentsmay be specifically addressed in future guidance and revisions of international anddomestic transportation regulations.ihD6~ NDoc.K 0-5o00a0(0 I zos-9611060238broJOToft-5-(;.L .

GL 96-07December 5, 1996 DiscussionDOT and NRC have agreed that steam generators may generally be shipped underDOT procedures and requirements as outlined below:(1) DOT has determined that steam generators are best categorized as surfacecontaminated objects (SCOs). Although the average surface contaminationlevel over the internals of a steam generator may be shown (throughcalculation, reasoned argument, and/or measurement) to meet the limits forinaccessible surfaces in the applicable SCO definition, the requirement is thatthe contamination be averaged over each 300 cm2 (46.5 in2). It is impracticalto measure the contamination level on each 300 cm2 (46.5 in2) of the steamgenerator internals; therefore, reasoned arguments and calculations should beused. At a minimum, the following uncertainties should be accounted for inthe analyses: (a) dose to curie conversions; (b) material differences anduneven crud composition/deposition in the channel head bowl, divider plate,tube sheet, and tubes; and (c) the source term identification (e.g., scalingratios, transuranic contribution to A2 total). If significant uncertainty remainsconcerning the distribution of deposited activity on steam generator surfaces,the licensee should obtain approval from DOT that the steam generator can beproperly classified for shipment as SCO.(2) The maximum radiation level at 3 meters (9.84 feet) from the unshieldedcontents [see 49 CFR 173.427(a)(1) and 10 CFR 71.10(b)(2)] is defined as thelargest measured or calculated dose rate 3 meters (9.84 feet) from any pointon the outside housing of an unshielded steam generator. Materials securelyfastened (e.g., welded) onto the steam generator, to seal penetrations, areconsidered part of the steam generator, for these purposes.(3) DOT has determined that the outside housing of a steam generator isconsidered as part of the "unshielded contents" (i.e., the dose rate is measuredfrom the outside shell). Therefore, the entire steam generator is considered tobe the radioactive material contents, and there is no "package" as defined in49 CFR 173.403. Shippers wishing to ship an unpackaged steam generator asan SCO would, therefore, need to request that DOT grant them relief from theregulatory requirement to package SCO, given the special nature and practicalconsiderations for steam generator shipments. The request should be made inaccordance with 49 CFR Part 107, and should demonstrate that theunpackaged, sealed steam generator provides the safety equivalent to anIndustrial Packaging (IP). If such relief (from the requirement that a steamgenerator be packaged) is not granted, then a steam generator shipped as anSCO must be shipped in an IP or Type A package, pursuant to 49 CFR173.427.(4) If shipped as an SCO, a steam generator is subject to the SCO conveyanceactivity limit of 100 A2given in 49 CFR 173.427, Table 9.

GL 96-07December 5, 1996 (5) If the necessary DOT approvals are obtained, and if the requirements of 10CFR 71.10 are otherwise met, no exemptions from NRC requirements areneeded for the provisions of 10 CFR 71.10 to take effect.NRC licensee shipments of steam generators are subject to NRC inspection forcompliance with the DOT regulations, pursuant to 10 CFR 71.5. It is particularlyimportant that each licensee maintain complete documentation of any tests orevaluations required by DOT, for complying with the conditions specified in item (3),above, for shipping steam generators as unpackaged SCO. These may includeengineering evaluations of the unpackaged steam generator's ability to meet the IP orType A package design standards and criteria, if required by DOT as a compensatorymeasure for permitting the unpackaged shipment. The requirements for documentingthe design of IP and Type A packaging are given in 49 CFR 173.411 (c) and 49 CFR173.415, respectively.This generic letter requires no specific action nor written response. If you havequestions about this matter, please contact one of the technical contacts listed belowor the appropriate Office of Nuclear Reactor Regulation project manager.Charles J. Hau ey, ActinJirecJSpent Fuel Project Offic -Office of Nuclear Material Safetyand SafeguardsTechnical contacts: Richard Boyle, DOT(202) 366-4545E-mail: rick.boyle@rspa.dot.govEarl P. Easton, NMSS(301) 415-8520E-mail: exe@nrc.govAttachment: List of Recently Issued NRC Generic LettersF~~/4 /

AttachmentGL 96-07December 5, 1996 LIST OF RECENTLY ISSUED GENERIC LETTERSGenericI attmrDate oflcctinnnra lcceiri TnA, .hkt-t96-0696-0596-04ASSURANCE OF EQUIPMENTOPERABILITY AND CONTAIN-MENT INTEGRITY DURINGDESIGN-BASIS ACCIDENTCONDITIONSPERIODIC VERIFICATION OFDESIGN-BASIS CAPABILITYOF SAFETY-RELATED MOTOR-OPERATED VALVESBORAFLEX DEGRADATION INSPENT FUEL POOL STORAGERACKS11/13/96 ALL HOLDERS OF OLsFOR NPRs, EXCEPT FORTHOSE LICENSES THATHAVE BEEN AMENDED TOPOSSESSION-ONLY STATUS09/18/96 ALL HOLDERS OF OLs(EXCEPT THOSE LICENSESTHAT HAVE BEEN AMENDEDTO POSSESSION-ONLYSTATUS) OR CPs FOR NPRs06/26/96ALL HOLDERS OF OLsFOR NPRs95-09,SUPP. 1MONITORING AND TRAININGSHIPPERS AND CARRIERS OFRADIOACTIVE MATERIALSOF 04/05/96ALL U.S. NUCLEARREGULATORY COMMISSIONLICENSEES96-0396-02RELOCATION OF THE PRES-SURE TEMPERATURE LIMITCURVES AND LOW TEMPERA-TURE OVERPRESSURE PRO-TECTION SYSTEM LIMITSRECONSIDERATION OFNUCLEAR POWER PLANTSECURITY REQUIREMENTSASSOCIATED WITH AN INTERNALTHREAT01/31/96 ALL HOLDERS OF OLsOR CPs FOR NPRs01/31/96 ALL HOLDERS OF OLsOR CPs FOR NPRsOL =CP =NPR =OPERATING LICENSECONSTRUCTION PERMITNUCLEAR POWER REACTORS

  • GL 96-07December 5, 1996 (5) If the necessary DOT approvals are obtained, and if the requirements of 10CFR 71.10 are otherwise met, no exemptions from NRC requirements areneeded for the provisions of 10 CFR 71.10 to take effect.NRC licensee shipments of steam generators are subject to NRC inspection forcompliance with the DOT regulations, pursuant to 10 CFR 71.5. It is particularlyimportant that each licensee maintain complete documentation of any tests orevaluations required by DOT, for complying with the conditions specified in item (3),above, for shipping steam generators as unpackaged SCO. These may includeengineering evaluations of the unpackaged steam generator's ability to meet the IP orType A package design standards and criteria, if required by DOT as a compensatorymeasure for permitting the unpackaged shipment. The requirements for documentingthe design of IP and Type A packaging are given in 49 CFR 173.411 (c) and 49 CFR173.41 5, respectively.This generic letter requires no specific action nor written response. If you havequestions about this matter, please contact one of the technical contacts listed belowor the appropriate Office of Nuclear Reactor Regulation project manager.Original 1sf byCharles J. Haughney, Acting DirectorSpent Fuel Project Office.Office of Nuclear Material Safetyand SafeguardsTechnical contacts:Richard Boyle, DOT(202) 366-4545E-mail: rick.boyle(rspa.dot.govEarl P. Easton, NMSS(301) 415-8520E-mail: exe@nrc.govList of Recently Issued NRC Generic Letters*See Previous Concurrence.Attachment:96-07.GLOFC SFPO* [ E SFPO* I C SFPO* C NRR/DRPM* lC OGC* C TEDITOR I NNAME RLewis:LMG EEaston SShankman TMartin ENJenson EKraus *DATE 10/9/96 10/10/96 10/10/96 10/18/96 10/22/96 10/22/96OF DWM* l IMOB lSFPO*l_IMJ :iizIE _NAME RJohnson KRamsey
  • CJHaughneyl DAT E 10/24/96 10/24/96 11/15/96 .. I' , NVC = COVERE = COVER & ENULOUbUKN = Nu COPtY

GL 96-07November 13, 1996 (5) If the necessary DOT approvals are obtained, and if the require ents of 10 CFR71.10 are otherwise met, no exemptions from NRC requiremen are needed for theprovisions of 10 CFR 71.10 to take effect.NRC licensee shipments of steam generators are subject to NRC in pection for compliancewith the DOT regulations, pursuant to 10 CFR 71.5. It is particulaly important that eachlicensee maintain complete documentation of any tests or evalua ions required by DOT, forcomplying with the conditions specified in item (3), above, for s ipping steam generatorsas unpackaged SCO. These may include engineering evaluatio s of the unpackaged steamgenerator's ability to meet the IP or Type A package design st ndards and criteria, ifrequired by DOT as a compensatory measure for permitting the unpackaged shipment. Therequirements for documenting the design of IP and Type A p ckaging are given in49 CFR 173.411 (c) and 49 CFR 173.415, respectively.This generic letter requires no specific action nor written esponse. If you have questionsabout this matter, please contact one of the technical c tacts listed below or theappropriate Office of Nuclear Reactor Regulation projec manager.Charles J. aughney, Acting DirectorSpent Fue Project OfficeOffice of uclear Material Safetyand Sa eguardsTechnical contacts: Richard Boyle, DOT(202) 366-4545E-mail: rick.boyle~rspa. ot.govEarl P. Easton, NMSS(301) 415-8520E-mail: exe@nrc.goEnclosure: List of Recently Issued NR Generic LettersS:IPROJIRXL\SGGENLTR.JRC

  • See Previous Concurrence.OFC SFPO* I E SFPO* I C S/PO* I C NRR/DRPM* I Cl C TEDITOR I NNAME RLewis:LMG EEaston Shank an TMartin ENJenson EKraus *DATE 10/9/96 110/10/96 /10/96 10/18/96 10/22/96 10/22/96OFC 1DWM* IMOB l- S IiiiiP IlINAME RJohnson KRamsey CJ g y lDATE 10/24/96 I AD 96 / 6 1 1 16E .C r v = V Idos L- II., ne1 soC = COVERE = IUUVLK GE CMULU:OUMmu = Rev %0urF

GL 96-07November 13, 1996 (5) If the necessary DOT approvals are obtained, and if the requirements of 10 CFR71.10 are otherwise met, no exemptions from NRC requirements are needed for theprovisions of 10 CFR 71.10 to take effect.NRC licensee shipments of steam generators are subject to NRC inspection for compliancewith the DOT regulations, pursuant to 10 CFR 71.5. It is articularly important that eachlicensee maintain complete documentation of any tests o evaluations required by DOT, forcomplying with the conditions specified in item (3), abo e, for shipping steam generatorsas unpackaged SCO. These may include engineering aluations of the unpackaged steamgenerator's ability to meet the IP or Type A package esign standards and criteria, ifrequired by DOT as a compensatory measure for pe itting the unpackaged shipment.The requirements for documenting the design of I and Type A packaging are given in49 CFR 173.411 (c) and 49 CFR 173.415, respe ively.This generic letter requires no specific action r written response. If you have questionsabout this matter, please contact one of the chnical contacts listed below or theappropriate Office of Nuclear Reactor Regul ion project manager.harles J. Haughney, Acting Directorpent Fuel Project OfficeOffice of Nuclear Material Safetyand SafeguardsTechnical contacts: Richard Boyle, D T(202) 366-454E-mail: rick.bo le@rspa.dot.govEarl P. Easto , NMSS(301) 415-8 20E-mail: exe nrc.govAttachment: List of Recently I ued NRC Generic LettersS:IPROJIRXLISGGENLTR.JRC *See Previous Concurrence.OFC SFPO E SFPO iSFPO* I C ; DRPM OGC* I C TEDITOR I NNAME RLewis:LMG EEaston/ SShankman TMartin ENJenson EKrausDATE 1 10/9196 1 0/1019h L1/10/96 10/18/96 10/22/96 10/22/96OFC DWM *OB SFPlXlNAME RJohnson KRams y CJ KeDATE toA9o P96 IC) 0.96 _~9._ _

  • _ RII -Kin = Un tC =COVERt: = %;Uvcn OL tNUL.oUNC1I = Rev% %#ur I

GL 96-##October ##, 1996 specified in item (3), above, for shipping steam generators as unpackaged SCO.These may include engineering evaluations of the unpackaged steam generator'sability to meet the IP or Type A package design standards and criteria, ifrequired by DOT as a compensatory measure for permitting the unpackagedshipment. The requirements for documenting the design of IP and Type Apackaging are given in 49 CFR 173.411(c) and 49 CFR 173.415, respectively.This generic letter requires no specific action nor written response. If youhave questions about this matter, please contact one of the technical contactslisted below or the appropriate Office of Nuclear Reactor Regulation projectmanager.William D. Travers, DirectorSpent Fuel Project OfficeOffice of Nuclear Material Safetyand SafeguardsTechnical contacts:e-mail:Richard Boyle, DOT(202) 366-4545rick.boyle@rspa.dot.govEarl P. Easton,(301) 415-8520exe@nrc.govNRC/NMSSAttachment:List of Recently IssuedNRC Generic LettersS:\PROJRXLXSGGENLTR.JRC*See Previous Concurrence.OC SFPO* LE SFPO* I C SFPO* l- C NRR/DRPM- C OGC* I C TEDITORlNAME RLewis:LMG EEaston SShankman TMartin ENJenson EKraus*DATE 10/9/96 10/10/96 10/10/96 10/18/96 10/22/96 10/22/96 =OFC DWM IMOB SFPO SFPNAME RJohnson KRarnser1 CJHhQti4 WD1Welrs /DATE 1/0 &96 l __ _j_ 96/ 6 1__ __ _96= .U ~ I A c e E n L L e ~ U h AE uI _ -5 a n .e f IC = COVERb = t;UVt~h 6L tLM-LVOUMmV = slwV %wr I

10-22-1996 12: 24PM FP-' FETZER-KRAUS. INC. 202 537 r 33FROM NRCzSFPO OZ.61.2980 0. 46GL 96-flOctober tt, 1996 lpments of steam generators Utt'so: are subject to NRC inspectionfor compliance with the DOT regulations, pursuant to 10 CFR Part 71.5. It isparticularly laportant that each licensoe Maintain complete documentation ofany tests or evaluations required by DOT, for complying with the conditionsspecified In item (3), above, for shipping steam generators as unpackaged SCO.These may include engineering evaluations of the unpackaged steam generator'sability to meet the IP or Type A package design standards and criteria, ifrequired by DOT as a compensatory measure for permitting the unpackagedshipment. The requirements for documenting the design of IP and Type Apackaging are given In 49 CFR 173.411(c) and 49 CFR 173,415, respectively.This generic letter requires no specific actlon r written response. If youhave questions about this matter, please contact one of the technical contactslisted below or the appropriate Office of Nuclear Reactor Regulation .fiRt-project manager.William D. Travers, DirectorSpent Fuel Project OfficeOffice of Nuclear Material Safetyand SafeguardsP. 8P. 3Technical contacts:0-mail;Pr 7 r Attachment-)J4u. L st of RecentlyRichard Boyle, DOT(202) 366-4545rick.boylegrspa.dot.govEarl P. Easton, NRC/NMSS(301) 411-85tOexetnre.govIssued NRC Generic LettersSA~PROJUfIXLOGOENLTR4RO*'oo Previous Concurence,OFC E FO C E 11 NRIMA OCTEITNAME R~ewis:LMG EH eston $Shankmnun 1TMerJlDATE 1019198 101IDbI9B 10/10196la J1I/96 ' 10 *A 6 sOFC __ M86F0S1NAME P.Johnson l(Rarnsey V4Houghnev WDT'revera _ _ _ _ __ _ _ _ _DATE I /Be1 16 0 /96loc)

GL 96-##October ##, 1996P ge 3 of 3Shipments of steam generators by NRC licensees are subject'to NRC inspectionfor compliance with the DOT regulations, pursuant to 10/tFR Part 71.5. It isparticularly important that each licensee maintain complete documentation ofany tests or evaluations required by DOT, for complying with the conditionsspecified in item (3), above, for shipping steam generators as unpackaged SCO.These may include engineering evaluations of the 'unpackaged steam generator'sability to meet the IP or Type A package design standards and criteria, ifrequired by DOT as a compensatory measure for permitting the unpackagedshipment. The requirements for documenting the design of IP and Type Apackaging are given in 49 CFR 173.411(c)/and 49 CFR 173.415, respectively.This generic letter requires no specific action or written response. If youhave questions about this matter, please contact one of the technical contactslisted below or the appropriate OfFice of Nuclear Reactor Regulation (NRR)project manager. //William D. Travers, DirectorSpent Fuel Project OfficeOffice of Nuclear Material Safetyand SafeguardsTechnicalRichard Boyle, DOT(202) 366-4545rick.boyle@rspa.dot.govEarl P. Easton, NRC/NMSS(301) 415-8520exe@nrc.govAtt1.Issued NRC Generic LettersQ.%PRn-1%RYXI r1FNLTR-JRCSee Previous Concurrence.SFO ICNRR/DROCGC~ iOFC SFPO* I E SFPO* l FO C NRDRP l DICEG S, TEDITORlNAME RLewis:LMG EEaston SShankman (, ar en EKrausDATE 10/9/96 10/10/96 10/10/96 1s / Ig/96 /1P296 I /96OFC DWM lIMOB l SFPO l _SFPO lNAME RJohnson3,~L KRamsey CJHaughney WDTraversDATE o' /z5 /96 I /96 I /96 I /96 ll _0 V il h LPJi F-UnUI 1EC = COVERL = tCUVt:K & tFULPLU:OUREI'm = Rev1 %0vr I

This generic letter requires no specific action or written re onse. If youhave questions about this matter, please contact one of the echnical contactslisted below or the appropriate Office of Nuclear Reactor egulation (NRR)project manager.am D. Travers, DirectorSpent Fuel Project OfficeOffice of Nuclear Material Safetyand SafeguardsTechnical contacts: Richar Boyle, DOT Earl P. Easton, NRC/NMSS(20 366-4545 (301) 415-8520Attachment:1. List of Recentl Issued NRC Generic LettersS:IPROJXRXLISGGENLTR.JRC *See Previous Concurrence.OFC lSF P9 lE SFOSP R/RMOGC l TEDITORllNAME RLev LNG EEastozpe aSn TMartin ENJenson EKrausDATE 1j/9 /196 (o/to/96 1o/10/96 / /96 / /96 j /96OFC DWM l IMOB I SFPO SFPOllNAME RJohnson KRamsey CJHaughney WDTraversDATE / /96 I /96 I /96 / /96C = COVER E = COVER & ENCLOSURE N = NO COPY3

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