Information Notice 1995-28, Emplacement of Support Pads for Spent Fuel Dry Storage Installations at Reactor Sites

Emplacement of Support Pads for Spent Fuel Dry Storage Installations at Reactor Sites

ML031060295
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, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant
Issue date:	06/05/1995
From:	Grimes B K, Travers W D NRC/NMSS/SFPO, Office of Nuclear Reactor Regulation
To:
References
IN-95-028, NUDOCS 9506010112
Download: ML031060295 (12)

June 5, 1995

NRC INFORMATION NOTICE 95-28: EMPLACEMENT OF SUPPORT PADS FOR SPENT FUEL DRYSTORAGE INSTALLATIONS AT REACTOR SITES

Addressees

All holders of operating licenses or construction permits for nuclear powerreactors.Independent spent fuel storage installation designers and fabricators.

Purpose

-The U.S. Nuclear Regulatory Commission (NRC) is issuing this informationnotice to alert addressees to the importance of complying with all conditionsand requirements specified in Section 72.212(b) of Title 10 of the Code ofFederal Regulations (10 CFR 72.212(b)) and other applicable NRC regulationsbefore using certified casks under the provisions of the general license under10 CFR Part 72 for the dry storage of spent fuel. It is expected that therecipients will review this information notice for applicability to theirfacilities and consider actions, as appropriate. However, suggestionscontained in this information notice are not NRC requirements; therefore, nospecific action or written response is required.BackgroundThe NRC reviews and approves cask designs for use in storing spent fuel undera general license as stated in Subpart L of 10 CFR Part 72. Approved caskdesigns are listed in Subpart K of 10 CFR Part 72, (10 CFR 72.214), and acertificate of compliance is issued to the cask designer after the rulemakingapproving the cask design is completed. Once a cask design has been certifiedand casks fabricated, casks may be used to store spent-fuel at nuclear power*reactor sites in accordance with Subpart K of 10 CFR Part 72. Such a licenseis only available to utilities that hold a license to possess or operate apower reactor under 10 CFR Part 50.Before storing spent fuel under the general license, reactor facilitylicensees must meet the requirements stated in 10 CFR 72.212(b). Notably,they must--* Determine and document that storage activities are in accordancewith the provisions and conditions of the certificate of compliancefor the cask.* Ensure that reactor site parameters, including any external hazards,are enveloped by the design-basis values established in the cask9506010112 fDR EVtE Dulcet o0cqc o(S 2OO IN 95-28June 5, 1995 design safety analysis report referenced in the certificate ofcompliance and the related NRC safety evaluation report.* Determine whether cask use will involve a reactor facilityunreviewed safety question or a change to the facility technicalspecifications (10 CFR 50.59).* Review and modify the reactor facility quality assurance program,security program, emergency plan, training program, and radiationcontrol program to include spent fuel storage activities asappropriate.* Develop reactor facility written operating procedures for caskhandling and storage operations.This information notice discusses circumstances regarding the emplacement ofspent fuel dry storage cask pads.Spent fuel storage cask designs are analyzed for normal, off-normal, andaccident conditions, including tip-over and cask drop accidents. In instanceswhere the pad supporting the casks, including the foundation beneath the pad,is not relied upon to perform a safety function, it is not treated as safetyrelated or as important to safety. The cask design safety analysis reportdoes not analyze for the effects of earthquakes, soil stability, or erosion onthe cask pad and foundation.However, 10 CFR 72.212(b)(2) requires that the general licensee ensure that,'cask storage pads and areas have been designed to adequately support thestati(c] load of the stored casks." Section 72.212(b)(3) states that thelicensee shall, determine whether or not the reactor site parameters,including analyses of earthquake intensity and tornado missiles, are envelopedby the cask design bases." The holder of a general license performs theseevaluations to ensure that the design and construction of the cask storage padis adequate to support the static load of the fully loaded storage casks. Inaddition, if potential conditions exist at the reactor site that couldunacceptably diminish cask safety by any credible means, then the licenseemust evaluate the potential conditions to verify that impairment of casksafety is highly unlikely. These evaluations are reviewed during NRCinspections and audits of licensee operations.

Description of Circumstances

During its initial siting analysis for dry spent fuel storage at the Palisadesfacility, Consumers Power Company (the licensee) noted that the peak groundacceleration used in the initial analysis for siting the power plant was 0.2g.The design-basis ground motion for the spent fuel dry storage casks is a peakground acceleration of 0.25g. Therefore, the licensee determined that thesafe shutdown ground acceleration of the site was enveloped by the designbasis for the cask. No additional analyses were performed for the sitinganalysis at that tim IN 95-28June 5, 1995 Since the Palisades plant is in close proximity to Lake Michigan, questionswere raised by the NRC staff and interested members of the public regardingthe possible effects of earthquakes on soil liquefaction, wind and waveeffects on ground erosion, and the effects of these phenomena on the casksupport pad and the spent fuel storage casks.As a result of these questions, the licensee performed a detailed analysis ofthe effects of soil erosion, including the effects of high lake waves, wind,and rain on the cask support pad. In addition, the licensee analyzed theeffect of a safe shutdown earthquake (SSE) on soil and foundation stability,based on both existing soil data and new data acquired from additional soilborings taken in response to the questions regarding the stability of the padsite.Other questions addressed by the review included the following:* Whether there had been any changes in the general site conditionssince the submittal of the environmental impact statement forlicensing of the facility (e.g., stability of site topography andwind erosion concerns).* Whether there was sufficient vertical and horizontal separationbetween Lake Michigan and the pad location to provide a conservativemargin against wave-driven erosion.* Whether the cask support pad had been analyzed for the SSE peakground acceleration defined for the Palisades site.* Whether the geologic and seismological analyses had been properlyperformed.The results of the licensee analysis showed that the pad could support thecasks safely. These results are documented in a letter to the NRC dated July27, 1994.NRC independently reviewed the licensee analyses of the soil liquefactioneffects on pad integrity, the pad design and construction, and the stabilityof slopes surrounding the pad to determine both the long-term effects oferosion under normal conditions and the effects of a postulated earthquake.This independent analysis also concluded that the cask pad would adequatelysupport the cask as required by 10 CFR 72.212. The NRC independent assessmentof the licensee analysis is documented in the "Independent NRC Staff FinalSafety Assessment of the Dry Spent Fuel Cask Storage Facility at PalisadesNuclear Power Plant Site," dated September 20, 1994.DiscussionPotential dry cask storage users are required by 10 CFR 72.212 to performwritten evaluations, before use, that establish that the conditions for usingNRC-approved spent fuel storage casks set forth in the certificate ofcompliance have been met. These evaluations include review of the cask design IN 95-28June 5, 1995 safety analysis report and the related NRC safety evaluation report to ensurethat the reactor site parameters are enveloped by the cask design bases. Thelicensee is also required to perform a written evaluation that ensures thatthe cask storage pad and areas are designed to support the static load of thestored cask. The effects of a postulated earthquake based on the earthquakeground motion used for the plant design-basis SSE is valid for the storagecasks without further analysis only if the foundation geology for the cask padis the same as that for the plant. A different soil amplification resultingfrom SSE ground motion at the pad site could result in exceeding the caskdesign basis.This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactone of the technical contacts listed below.rian .Grimes, rector William D. Travers irectorDivision of Project Support Spent Fuel Program OfficeOffice of Nuclear Reactor Office of Nuclear MaterialRegulation Safety and SafeguardsTechnical contacts:F. Sturz, NMSS(301) 415-7278M. Gamberoni, NRR(301) 415-3024

Attachments:

1. List of Recently2. List of RecentlyIssued NMSS Information NoticesIssued NRR Information Notices Attachment IIN 95-28June 5, 1995Page I of ILIST OF RECENTLY ISSUEDNMSS INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to95-2594-64,Supp. 195-0795-01Valve Failure duringPatient Treatment withGamma StereotacticRadiosurgery UnitReactivity Insertion Trans-ient and Accident Limitsfor High Burnup FuelRadiopharmaceutical VialBreakage during PreparationDOT Safety Advisory:High Pressure AluminumSeamless and AluminumComposite Hoop-WrappedCylindersEquipment Failures atIrradiator FacilitiesUnauthorized Transfer ofOwnership or Control ofLicensed ActivitiesAccuracy of Bioassayand EnvironmentalSampling ResultsReporting Fuel Cycleand Materials Events tothe NRC Operations Center05/11/9504/06/9501/27/9501/04/9512/28/9412/07/9411/25/9410/20/94All U.S. Nuclear RegulatoryCommission MedicalLicensees.All holders of OLs or CPsfor Nuclear Power Reactorsand all fuel fabricationlicensees.All U.S. Nuclear RegulatoryCommission medical licenseesauthorized to use byproductmaterial for diagnosticprocedures.All U.S. Nuclear RegulatoryCommission licensees.All U.S. Nuclear RegulatoryCommission irradiatorlicensees.All fuel cycle and materiallicensees.All U.S. Nuclear RegulatoryCommission licensees.All 10 CFR Part 70fuel cycle licensees.94-8989-25,Rev. 194-8193-60,Supp. 1 Attachment 2IN 95-28June 5, 1995 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to95-2795-2694-61,Supp. 195-2595-2495-2395-22NRC Review of NuclearEnergy Institute,"Thermo-Lag 330-1Combustibility EvaluationMethodology Plant ScreeningGuide'Defect in Safety-Related Pump Parts dueto Inadequate HeatTreatmentCorrosion of WilliamPower Gate Valve DiscHoldersValve Failure duringPatient Treatment withGamma StereotacticRadiosurgery UnitSummary of LicensedOperator RequalificationInspection ProgramFindingsControl Room StaffingBelow Minimum RegulatoryRequirementsHardened or ContaminatedLubricants Cause MetalClad Circuit BreakerFailures05/31/9505/31/9505/25/9505/11/9504/25/9504/24/9504/21/95All holders of OLs or CPsfor nuclear power plants.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All U.S. Nuclear RegulatoryCommission MedicalLicensees.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactorsand all licensed operatorsand senior operators atthose reactors.All holders of OLs or CPsfor nuclear power reactors.95-21Unexpected Degradationof Lead Storage Batteries04/20/95All holders of OLs or CPsfor nuclear power reactors.OL = Operating LicenseCP = Construction Permit IN 95-28June 5, 1995 safety analysis report and the related NRC safety evaluation report to ensurethat the reactor site parameters are enveloped by the cask design bases. Thelicensee is also required to perform a written evaluation that ensures thatthe cask storage pad and areas are designed to support the static load of thestored cask. The effects of a postulated earthquake based on the earthquakeground motion used for the plant design-basis SSE is valid for the storagecasks without further analysis only if the foundation geology for the cask padis the same as that for the plant. A different soil amplification resultingfrom SSE ground motion at the pad site could result in exceeding the caskdesign basis.This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactone of the technical contacts listed below.orig /s/'d by EKGrimesBrian K. Grimes, DirectorDivision of ProJect SupportOffice of Nuclear ReactorRegulationorig /s/'d by WDTraversWilliam D. Travers, DirectorSpent Fuel Program OfficeOffice of Nuclear MaterialSafety and SafeguardsTechnical contacts:F. Sturz, NMSS(301) 415-7278M. Gamberoni, NRR(301) 415-3024

Attachments:

1. List of Recently2. List of RecentlyIssued NMSS Information NoticesIssued NRR Information NoticesDOCUMENT NAME: 95-28.IN*See previous concurrence-.-al * ---_ -n h n* .--- ..' *I .Znny with attachmentlenclosure 'N'

• No copyTr celve a copy ei uus mocurnem. mnuacue ^ie o:- uuw umngu wz~. -lW--IOFFICE OECB/DOPS l ADM:PUB I i i C:ECGB/DE I E PD3-III INAME SSKoenick* Tech Ed* GBagchi* GHMarcus*FATC r./12 /or, n;/2s/9Q 05/24/95 05/25/95N921"Ur% L_ I) W/ Hz' -o Iw S__ _ , -- ., 1~ , , .OFFICE SC:OECB/DOPS I OECB/DOPS I D S I LNAME EFGoodwin* RJKiessel* WTravers AEChaffee*DATE 05/25/95 05/2595 05/31/95 2595UttILIAL KtLUKU LuFT

" '~ IN 95-28June 2, 1995Page 4 ofthat the reactor site parameters are enveloped by the cask desi bases. Thelicensee is also required to perform a written evaluation that nsures thatthe cask storage pad and areas are designed to support the st ic load of thestored cask. The effects of a postulated earthquake based the earthquakeground motion used for the plant design-basis SSE is valid or the storagecasks without further analysis only if the foundation geo ogy for the cask padis the same as that for the plant. A different soil am ification resultingfrom SSE ground motion at the pad site could result in xceeding the caskdesign basis.This information notice requires no specific actio or written response. Ifyou have any questions about the information in t is notice, please contactone of the technical contacts listed below.orig /s/'d by BKGrimes orig /s/'d by WDTraversBrian K. Grimes, Director 1liam D. Travers, DirectorDivision of Project Support Spent Fuel Program OfficeOffice of Nuclear Reactor Office of Nuclear MaterialRegulation Safety and SafeguardsTechnical contacts: F. Sturz, NMSS(301) 415-7278M. Gamberoni NRR(301) 415-3 24

Attachments:

1. List of Recently Issued N S Information Notices2. List of Recently Issued R Information NoticesT NAME: 95-28.INevious concurrenceDOCUMEN*See orn-A -_- ad Kol -...L I:.Afl hL. *h. h- IC' -rny without atachmentenclosure El -Copy with suachmentienlosure IN

• No copyIOFFICE OECB/DOPS I I ADM:PUB l -C:ECGB/DE E PD3-INAME ISSKoenick* ITech Ed* 1GBagchi* l nrcus*__ -._u_ okinr n,__2 L91nfATno /77 iO^I nr' iq-051Z4195lU31101vafN,UrIL J/ I '. I v<{ I _t _ .__ , _ _ _ _ _ _OFFICE SC:OECB/DOPS I OECB/DOPS I D:SFPC:OECB/DOPS I PNAME EFGoodwin* RJKiessel* WTravers*AEChaffee* mgDATE 105/25/95 05/25/95 05/31/95 6/ 195 5____ /_9UOFILIAL Kt.UKU buPT IN 95-xxMay xx, 1995 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactone of the technical contacts listed below.Brian K. Grimes, DirectorDivision of Project SupportOffice of Nuclear ReactorRegulationWilliam D. Travers, DirectorSpent Fuel Program OfficeOffice of Nuclear MaterialSafety and SafeguardsTechnical contacts:urz, NMSS(301) 415-7278M. Gamberoni, NRR(301) 415-3024

Attachments:

1. List of Recently2. List of RecentlyIssued NMSS Information NoticesIssued NRR Information NoticesDOCUMENT NAME:G:\SSK2\ISFSIPAD.IN*See previous concurrence--- --*-- En ----.l .L... .1. t I- e, with t tt-nhmentenclosure BE" = Copy with attachment/enclosure "N"

• No copyTro receive copy of this 9ocuFment, M--al m. ..ne ads ---KY ..g..I--OFFICE OECB/DOPS l ADM:PUB 1 1 C:ECGE/DE LNAME SSKoenick* Tech Ed* GBagchi* GHMarcus*U- I-' -I Y 2 ue ln , M enATFnA j9 19/Or.05/26/9I0 U/ Z4+/ SDUU/ rADSF;_ .Un I L I'WJ ~/ -Z __ I __1 __ I --.--t -OFFICE SC:OECB/DOPS OECB/DOPS I D: IF )/NMN5 I C:OECB/DOPS D:DOPS/NRR INAME jEFGoodwin* RJKiessel* WT rs/ AEChaffee* BKGrimesDATE 105/25/95 05/25/95 05/n /9 05/25/95 05/ /95OFFIClA RECORD COPY IN 95-xxMay xx, 1995 This Information Notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactone of the technical contacts listed below.William D. Travers, DirectorSpent Fuel Program OfficeOffice of Nuclear Material Safetyand SafeguardsBrian Grimes, DirectorDivision of Operational ProgramsOffice of Nuclear Reactor RegulationTechnical Contacts:Fritz Sturz, NMSS(301) 415-7278M. Gamberoni, NRR(301) 415-3024Attachm1. Lis2. LisDOCUMENT NAME:To receive a copy ofattachment/enclosureients:t of Recently Issued NMSS Information Noticest of Recently Issued NRR Information NoticesG:\SSK2\ISFSIPAD.INthis document, indicate in the box: "C" = Copy without atte ment/enclosure "E E Copy with."I,, = No copyprI II I II uIr; coDuLnx I Irnn-TTT Z"IInFlTrrInFCril/nOpsI II ELH EUI IL:,; ripD/UrLX I W- I r-U.1- LALNAM S o AU1 l ..-h IHFar -Ar I-NAME ISSKoenick I GH1 1 ar sIIUI .fnI V121IIIx 6I 'MATrnL /9 qAorIn5 I Alu/5/4 9 I1 D02 9/1 V11UtilE UJVQ7/7 W --, I- -- Iff __,,,,,OFFICE SC:OECB/DO D:SFPO/NMSS 1C:OECB/DOPS D:DOPS/NDNAME EFGoodwi nAt J5 l RJKir05 95r05/ /Chaffee BKGrimeslDATE 05/b--505AM950//5 5,~/95 05/ /95 K>IN 95-xxMay xx, 1995 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactone of the technical contacts listed below.Brian K. Grimes, DirectorDivision of Project SupportOffice of Nuclear ReactorRegulationWilliam D. Travers, DirectorSpent Fuel Program OfficeOffice of Nuclear MaterialSafety and SafeguardsTechnical Contacts:Fritz Sturz, NMSS(301) 415-7278M. Gamberoni, NRR(301) 415-3024

Attachments:

1. List of Recently2. List of RecentlyIssued NMSS Information NoticesIssued NRR Information NoticesDOCUMENT NAME: G:\SSK2\ISFSIPAD.INTo receive a copy of this documernt,Indicate in the box:"C' = Copy without attachment/enctosure"E" = Copy withaittaclhmenhJ n9,grLWu*u C --.u .,WYOFFICE OECB/DOPS TECH ED* :EGB/DPD3-IIINAME SSKoenick* _AGBagchi* GHMarcus*11h --- ^r~ i II~n ATrI nri/OKin;/ /Qs05/lIYD)A 1U3/ /VDI1Ulm IL 1V.J/ / .Jv / my I --,OFFICE SC:OECB/DOPS OECB/DOPS D:SFPON v l lC:OECB/DOPS l DDOPS/NINAME EFGoodwin* RJKiessel* WTravM19// / AEChaffee* BKGrimes CKJDATE 05/ /95 05/ /95 05/ /95 1 05/ /95 0 5/ 9* See previous concurrence I , -- 1.I)IN 95-xxMay xx, 1995 This Information Notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactone of the technical contacts listed below.William D. Travers, DirectorSpent Fuel Program OfficeOffice of Nuclear Material Safetyand SafeguardsBrian Grimes, DirectorDivision of Operational ProgramsOffice of Nuclear Reactor RegulationTechnical Contacts:Fritz Sturz, NMSS(301) 415-7278M. Gamberoni, NRR(301) 415-3024

Attachments:

1. List of Recently2. List of RecentlyIssued NMSS Information NoticesIssued NRR Information NoticesDOCUMENT NAME:To receive a copy ofattachment/enclosureG:\SSK2\ISFSIPAD.INthis docunent, indicate in the box: 'IC" = Copy without"U" I No copyattachment/enclosure"E"= Copy withEIIOFFICE OECB/DOPS I _ :TEH ED IG C:ECGB/DE I lPD3-III INAME SSKoenick I J i LGBa chi GHMarcus lC)ATE05/ /95105.A2/9505/ /95105/ /95III -r __, ___ I __I__ ,-, ,-- I_OFFICE SC:OECB/DOP OECB/DOPS D:SFPO/NMSS [C:OECB/DOPS I D:DOPS/N I___________ RR LNAME EFGoodwin jRJKiessel WTravers AEChaffee BKGrimes -DATE 05/ /95 05/ /95 05/ /95 105/ /95 05/ /95