NRC Generic Letter 1981-07

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NRC Generic Letter 1981-007: Control of Heavy Loads
ML031080524
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, 05000363, 05000355, Zimmer, 05000578, Fort Saint Vrain, Washington Public Power Supply System, Shoreham, Satsop, Trojan, Bailly, Atlantic Nuclear Power Plant, Cherokee, Marble Hill, Hartsville, Phipps Bend, Yellow Creek  Entergy icon.png
Issue date: 02/03/1981
From: Eisenhut D G
Office of Nuclear Reactor Regulation
To:
References
GL-81-007, NUDOCS 8103120014
Download: ML031080524 (11)


.01ES4P/3/ LALL POWER REACTOR LICENSEESDocket No. 50-348Farley Unit 1Docket No. 50-313Arkansas Unit 1Docket No. 50-3Indian Point Unit 1Docket No. 50-247Indian Point Unit 2Docket No. 50-368Arkansas Unit 2Docket No. 50-317Calvert Cliffs Unit 1Docket No. 50-318Calvert Cliffs Unit 2Docket No. 50-293Pilgrim Unit 1Docket No. 50-325Brunswick Unit 1Docket No. 50-324Brunswick Unit 2DocketIndian50-286Point Unit 3Docket No. 50-155Big Rock PointDocket No. 50-255PalisadesDocket No. 50-409LacrosseDocket No. 50-269Oconee Unit 1Docket No. 50-270Oconee Unit 2Docket No. 50-261H. B. Robinson Unit 2Docket No. 50-10Dresden Unit 1Docket No. 50-237Dresden Unit 2Docket No. 50-249Dresden Unit 3Docket No. 50-254Quad-Cities Unit 1Docket No. 50-265Quad-Cities Unit 2Docket No. 50-295Zion Unit 1Docket No. 50-304Zion Unit 2DocketOconeeNo. 50-287Unit 3Docket No. 50-334Beaver Valley Unit 1Docket No. 50-302Crystal River 3Docket No.50-335St. Lucie Unit 1Docket No. 50-250Turkey Point Unit 3Docket No. 50-251Turkey Point Unit 4Docket No. 50-321Edwin I. Hatch Unit 1Docket No. 50-366Edwin I. Hatch Unit 2Docket No. 50-315D. C. Cook Unit 1\QDocket No. 50-213Connecticut Yankee(Haddam Neck)ABElD0-1SloBI200l4

-2 -Docket No. 50-316D. C. Cook Unit 2Docket No. 50-344TrojanDocket No. 50-305KewauneeDocket No. 50-331Duane ArnoldDocket No. 50-333FitzPatrickDocket No. 50-29Yankee-RoweDocket No. 50-219Oyster Creek Unit 1Docket No. 50-267Ft. St. VrainDocket No. 50-339Ndrth Anna 2Docket No. 50-309Maine YankeeDocket No.50-272Salem Unit 1Docket No.50-311Salem 2Docket No. 50-289Three Mile Island Unit 1Docket No. 50-320Three Mile Island Unit 2Docket No. 50-298Cooper StationDocket No. 50-244R. E. Ginna 1Docket No. 50-312Rancho SecoDocket No.50-206San Onofre 1Docket No. 50-220Nine Mile Point Unit 1Docket No. 50-259Browns Ferry Unit 1Docket No. 50-245Millstone Unit 1Docket No. 50-260Browns Ferry Unit 2Docket No. 50-336Millstone Unit 2Docket No. 50-296Browns Ferry Unit 3Docket No. 50-263MonticelloDocket No. 50-346Davis-Besse 1Docket No. 50-282Prairie Island Unit 1Docket No. 50-306Prairie Island Unit 2Docket No. 50-285Ft. CalhounDocket No. 50-271Vermont YankeeDocket No. 50-338North Anna 1Docket No.50-280Surry Unit 1Docket No. 50-133Humboldt BayDocket No.50-281Surry Unit 2Docket No. 50-277Peach Bottom 2Docket No. 50-266Point Beach Unit 1Docket No. 50-278Peach Bottom 3Docket No. 50-301Point Beach Unit 2 FEB z 7 1981PLANTS UNDER.OL REVIEW1.2.3.4.5.6.7.8.9.10.11.12.13.14.15.16.17.18.19.20.21.22.23.24.25.26.27.28.29.Clinton 1/2Byron 1/2Braidwood 1/2LaSalle 1/2Midland 1/2McGuire 2So. Texas 1/2ShorehamWaterfordGrand Gulf 1/2Diablo Canyon 1/2Susquehana 1/2St. Lucie 2Summer 1San Onofre 2/3Bellefonte 1/2Watts Bar 1/2Sequoyah 2Comanche Peak 1/250-46 1/46250-454, 455-50-456/45750-373, 37450-329,33050- -37050-498, 49950-32 250-38250-416/41750-275, 32350-387, 3885-0-38950-39550-361, 36250-438, 43950-390, 39150- 32850-445, 446IWPPSS-2Fermi 2Zimmer 1Perry 1/2Palo VerdeCatawbaMarble HillWolf CreekCallaway50-39750-34150-35850-440,50-528,50-413,50-546,50-4 8250-4 83,441529, 530414547486I 4 REB 2 7 2981OPERATING PLANTS1. Sequoyah 1 50-3272. Salem 2 50-3113. McGuire 1 50-3694. Farley 2 50-364a, FEB 2 7 1981PLANTS UNDER CONSTRUCTION1.2.3.4.5.6.7.8.9.10.11.12.13.14.15.16.17.18.19 .20.Cherokee 1/2/3Beaver Valley 2St. Lucie 2Vogtle 1/2River Bend 1/2Forked RiverNine Mile Point 2Millstone 3.Bailly 2Limerick 1/2Hope Creek 1/2Seabrook 1/250-491,50-41250-389 .50-4 24,50-458,50-36350-41050-42350-36750-352,"50-354,50-443,492, 493425459353355444Hartsville 1/2/3/4Phipps Bend 1/2Yellow Creek 1/2WPPSS 1/3/4/5Harris 1/2/3/4FNP50-518,50-553,50-566,50-460,50-400,50-437519,554567508,401,520, 521513, 509402, 403

  • os -~ UNITED STATES( NUCLEAR REGULATORY COMMISSION, i t -WASHINGTON. 0. C. 20555February 3, 1981TO ALL LICENSEES OF OPERATING PLANTS AND APPLICANTS FOR OPERATING LICENSESAND HOLDERS OF CONSTRUCTION PERMITS*

SUBJECT: CONTROL OF HEAVY LOADS (Generic Letter 81-07)Gentlemen:By our letter dated December 22, 1980, you were requested to review yourcontrols of the handling of heavy loads to determfine the extent to whichthe guidelines of NUREG-0612 are presently satisfied at your facility andto identify the changes and modifications that would be required in orderto fully satisfy these guidelines.To expedite your review, three enclosures were included with the letter.One of the enclosures was Request for Additional Information on Controlof Heavy Loads (Enclosure 3). We have found that five oages fromEnclosure 3 were missing due to a reproduction error. The missing pagesare enclosed with this letter. In addition the December 22, 1980, letteron Page 2 in Item 1 required that information identified in Section 2.1through 2.4 of Enclosure 3 be included in a report documenting theresults.of your review. This requirement should be modified to read:"Sections 2.1 through 2.4 for PWR Dlants and Sections 2.1 through 2.3for BWP. plants."Because of these errors we are extending the Enclosure 2 90-day implementationrequirement to May 15, 1981.

Sincerely,\M %orecoa Ei enDivision o Licensing

Enclosure:

'Enclosure 3" missingDages*With the exception of licensees for Indian Point 2 and 3, Zion 1 and 2and Three Mile Island 1 Attachment (4)ANALYI1S OF PLANT STRUCTURESnhe following information should be provided for analyses conducted to demon-strate compliance with Criteria III and IV of IZLVEG 0612, Section 5.1.1. INITIAL CONlDITIONS/ASSL~r2'TIONSDiscuss the assumptions used in the analysis, including:a. Weight of heavy loadb. Impact area of loadc. Drop heightd. Drop locatione. Assumptions regarding credit taken in the analysis forthe action of impact limitersf. Thickness of walls or floor slabs impactedg. Assumptions regarding drag forces caused by th-:environmenth. Load combinations consideredi. Material properties of steel and concrete2. ;;.0DOF Aor A LLYSIS.Provide the method of analysis used to demonstrate that sufficient load-carrying capability exists within the wall(s) or floor slab(s). Identifyany computer codes employed, and provide a description of their capabilities.If test data was e=ployed, provide it and describe its applicability.3. CONCLUSIONProvide an evaluation comparing the results of this analysis vith CriteriaIII and IV of NJREG 0612, Section 5.1. Wnere safe-shutdown equipment hasa ceiling or wall separating it fronan overhead handling system, providean evaluation to demonstrate that postulated load drops do not penetratethe ceiling or cause secondary missiles that could prevent a safe-shutdowns~ste- fro= performing its safety functio (3) A description of any Engineered SafetyFeature filter system which includes infor-mation sufficient to demonstrate compliancewith the guidelines of USNRC RegulatoryGuide 1.52, "Design, Testing, and MaintenanceCriteria for Engineered Safety Feature Atmos-phere Cleanup System Air Filtration andAbsorption Units of Light-Water-CooledNuclear Power Plants."(4) A discussion of any initial conditions(e.g., manual valves locked shut, containmentairlocks or equipment hatches shut) necessaryto ensure that releases will be terminated ormitigated upon Engineered Safety Featureactuation and the measures employed (i.e., Tech-nical Specification and administrative controls)to ensure that these initial conditions aresatisfied and that Engineered Safety Featuresystems are operable prior to the load lift.2. )ETHOD OF ANALYSISDiscuss the method of analysis used to demonstrate that post-accident dosewill be well within lOCFRlOO limits. In presenting methodology used indetermining the radiological consequences, the following information shouldbe provided.a. A description of the mathematical or physical modelemployed.b. An identification and summary of any computer programused in this analysis.c. The consideration of uncertainties in calculationalmethods, equipment performance, instrunentationresponse characteristics, or other indeterminateeffects taken into account in the evaluation of theresults.3. CONCLUSIONProvide an evaluation comparing the results of the analysis to Criterion Iof NUPREG 0612, Section 5.1. If the postulated heavy-load-drop accidentanalyzed bounds other postulated heavy-load drops, a list of these boundedheavy loads should be provided.A-2i bounds other postulated heavy-load drops, a list of these bounded heavyloads should be provided.3-2 hiztacnment to)3 of 6SHIELDED SHIPPING. CASIS CERTIFICATEDFOR NUCLEAR POWER PLANTSI -WasteCROSS LOT INL2ES. (APPRO.)PRIYD:AP LICERSEESECOM'MAy ICESreEPoly TigerNhuclear Engineering Co.35,000APL, SEC, O'C, DLP,XCO N?;, Ss', VUD6771SN-1Nuclear Engineering Co.60,000APL, QPC,amU, VEPDLU, EPP,J-10028,0O0DLC9079M!;-100 Ser. 2Eitt;zat lvclear andDevelopment Corp.98, 0ODAPL,DL?,17xCEC, CI-E,JCP, MA,PLC90soE;-600Bittr;an Nuclear andDevelopmen: Cop.p42,0ooeBGE,U ='_,cr" ,XprtdEC,3cP,FzC,s!1%lA,YACC':':;-I10 Ser. 1Eitt=an Nuclear andDevelopment Corp.46,OD0APL,N?,r.V:VC3NGE.JC°,=-_,Y.A,PCr,DL? ImcE,RGE9C-SC90929093E;-l00SEX-300EN-400Eittman Nuclear andDevelopnent Corp-Eittmzn huclear andDevelopment Corp.ittman Nuclear atdDevelopment Corp.36,500BEG, CAM-, CEC, Z1 ,JCP, MA, IPmp ?EC43,00043,000XSYA90949096CSS I-21-095-C!S 1-21-30DCher.-Nuclear Systems,Inc.Chem-1;uclear Systems,Inc .56,500APC.CIVE.,) Cs,,JCP,1PGC,VEPAPL,CYA,FPL,0??,APL,F?L,XLC,PEC,dEC,iarc,crc,PC,PEG,C?L,sPC,CPL,CPC,hN.%E,?EC,TVA,GPC,h';EI57,450IDPC,3 C?,*So *tgtbbc':. 21 o 5 .o~f atsbrovis'-ID.t-.

Attachment (5)S of 6SHIELDED SHIPPING CASKS CERTIFICATEDFOR NUCLEAR POWER PLAINTSIII -ByproductsGROSS LOT IX'LES. (APPROX.)PRIVY LICENSEESECOMARY LICENSEE*597159806275G-E-=GE-40D10, 00018,50030. DOD .a6.000Cht-Nucl^er Systm.s,Inc.Ch=-Nucle.&r Systems.Inc.PECME, NSP ,APC, CPL, MFC, rL,FPC, Np?, VD?APC, ZGE, CPL. DPC,TPL, FPC, GPC. Nsp,TVA, VEPCIS-: 600Set attached li stof abbT evitat sns .

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