ML20054M461
| ML20054M461 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 07/07/1982 |
| From: | Musolf D NORTHERN STATES POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-36, REF-GTECI-SF, TASK-A-36, TASK-OR GL-81-07, GL-81-7, NUDOCS 8207130264 | |
| Download: ML20054M461 (54) | |
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Northern States Power Company 414 Nicollet Mall Minneapohs, Minnesota 55401 Telephone (612) 330 5500 July 7, 1982 Director Office of Nuclear Reactor Regulation U S Nuclear Regulatory Commission Washington, DC 20555 MONTICELLO NUCLEAR GENERATING PLA?Tr Docket No. 50-263 License No. DPR-22 Control of IIcavy Loads (Revised Six Month Submittal)
Following discussions with the NRC staff the six month submittal dated September 30, 1981 has been revised and is attached. The September 30, 1981 letter was submitted in response to Mr Eisenhut's letter dated December 22, 1980, titled Control of Heavy Loads (Generic Letter 81-07).
The attached revised report replaces the September 30, 1981 (six month report) letter in its entirety and incorporates the item pertaining to the six month report included in the March 12, 1982 submittal concerning code comparisons.
The analysis of the special lif ting devices (part of 2.1.3d) is not com-plete. In order to do these analyses information must be received from their manufacturer. Following the receipt of this information a detailed analysis must be completed. The target date for completion of this analysis is October 1,1982.
This revision of the six month report necessitates the revision of the nine month report. The target date for the completion of this is also October 1, 1982.
l M wa David Musolf Acting Head-Nuclear Support Services DMM/TMP/bd cc: Regional Administrator-III 0
NRR Project Manager, NRC l' NRC Resident Inspector G Charnoff Attachment I
8207130264 820707 PDR ADOCK 05C00263 P PDR 1
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NRC GENERIC LETTER 81-07 i
j REVISED SIX MONTH REPORT i
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!- MONTICELLO NUCLEAR GENERATING PLANT I
! JULY 7, 1982 4
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Table of Ccntents Page I. REPORT Respmse to Questicn 2.1.1 1 Respon s to Question 2.1.2 2 Respcnse to Questicn 2.1.3 3 Respcnm to Questian 2.1.3a 3 Bespcnm to Questicn 2.1.3b 3 Respcnm to Question 2.1.3c 4 Respcnm to Questicn 2.1.3d 5 Respmm to Questicn 2.1.3e 6 Response to Questicn 2.1.3f 6 Respons to Questicn 2.1.3g 7 II. ATDCIEEITIS Attachmnt I - Ibactor Building and Tarbine Building Crane '
Crane Design Review Table I - List of Overhead Load Handling Devices Ibt Cmsidered Becaum of Physical Separaticn at Capacity Table II -
Heavy Ioads llandled bf the Overhead load IIandling Devices Idmtified in Secticn 2.1.1 Plant Iayout Drawings l
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, 't RESPOfEE 'IO REQUEST EUR ItFORMATION IN SBCTION 2.1 G1ERIC IETTER 81-07 Item 1 (NIC Questim 2.1.1)
-Report the results of your review of plant arrangements to identify all over-head handling systcm frca which a Imd drop may result in damap to any systm required for plant shutzlown or decay heat removal (taking no credit for any interlocks, technical specificaticns, operating procedures, or detailed structural analysis) .
Response
A survey of the Etnticello Plant was perforred to identify the overhead handling systems that fall in the category referred to in Questicn 2.1.1. Them handling systems are listed belcw:
Incaticn Handling Systen Main / Auxiliary -ID No.*
'Iurbine Building Turbine Building Crane 125/5 1 Reactor Building Reactor Building Crane 85/5 2 Drywell SRV Drywell Mcnorail 5 ' 14 Torus Torus Mcnorail 5 15 Reactor Building 'Ibrus Access Hatch 2 28 Hoist & Lifting Ing Intake Structure Chlorine Ccntainer 2 31 tknorail & Cylinder Grab Reactor Building Radwaste & Fuel Pool 5 36 Shield Blocks Manorails Reactor Building Reactor Building Floor / 4 45 Equipnent Drain Tank Hatch Iifting Device Reactor Building ICIC Punp RocIn Access 4 53 Hatch Lifting Device Reactor Building Drott Mobile Crane 3.5 62
- Identificaticn number (ID tb) ustd to identify overhead handling systems in attached tables and figures.
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t t Item 2 (NEC Questicn 2.1.2)
Justify the exclusicn of any overhead handling system fran the above category by verifying that tMre is sufficient physical separatial fran any load-inpact point and any safety-related conpanent to permit a determinatial by inspecticn that no heavy load drop can result in damage to any system ar carpment required for plant shutdown or decay heat removal.
Respcnse Table I lists the overhead handling systems which have been excitded fran further ccnsideraticn becaum of capacity or physical separaticn fran any system ar carpatent required for plant shutdwn or decay Mat removal. In additicn the follwing handling systems have beel eliminatal fran cassideraticn for the fol-lwing reascns:
- 1. Reactor Recirc Punps Mmorail Motor lloist (Capacity 32,000 lbs) ID m. 6 The functicn of this 1 cal handling device is to assist in tM assembly and disassembly of the Beactor Recirculaticn Punps druing plant shutdwn. 'Ihis device is located in the drywell. 'IM items handlal by this handling device would typically cmsist of the Rx Recirc Punp Drive Motor and the individual parts of the Itc Pecirc Punp as it is disassembled. 'IM potential inpact item of cmcern is the applicable loop of the Rx lbcirc System. It is pos-sible, but highly unlikely, that dropping tM Rx Recirc drive motor could rupture the recirc system piping of the loop being repaired. Whm this device is uscd to disassemble a Ibc Recirc Punp tM applicable punp will be isolated. It is physicall; impossible to drop this heavy load and dis-able both Rx Becirc loops. 'Iberefore this load handling device is eliminated becaum of system redundancy and sole purpose use.
- 2. IIICI 'lurbine Mcnorail (Capacity 8,000 lbs) ID 2. 17
'Ihe functial of this load Mndling device is to assist in the assembly and disassembly of the IIICI turbine. This device would cnly be uscd whm the HICI system is not required to be operable per plant tech 1ical specifica-tims. Any load handlal by this load handling device could not inpact cn tM redundant sfstem to tM IIECI system. 'IM ICIC system would be available -
to makeup water to the Rx. Therefore this load handling device has becn eliminated because of system redundancy and sole purpose use.
- 3. "A" '1brbine Floor Portable A-Frame & Monorail (Cap.10,000 lbs) ID No. 44
'Ihe functicn of this load handling device is to assist in the assembly and disassembly of tM turbine generator. This device is nornnlly uscd to assemble and disassemble the turbine governor, bypass valves and the stop and ccntrol valves. This 1 cal handling device will cnly be used far this purpose when tM plant is shutdmn.
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- 4. "A" RHR Punp Room Access Hatch Lifting Ings(4) (Cap. 7,500 lbs ea) ID tb. 54
'Ihem lifting lugs were installed during cmstructicn of the plant. '1 hey were used for various purpoms during the cmstructim phase. '1 hey have not bem used for renoval of the associated shield blodcs cr for RHR or Core Spray System equipent maintenance since the plant became operaticnal.
Them lifting lugs are being removed.
- 5. "B" RHR Punp Rocm Access Hatch Lifting Ings(4) (Cap. 7500 lbs ea) ID tb. 55 Them lifting lugs were installed during ccnstructicn of the plant. '1 hey were used for various purposes during this ccnstructicn phase. '1 hey have not been used for removal of the associated shield blocks or for RHR or Core Spray System equip,ent raintenance since the plant became operatimal.
Them lifting lugs are being renoved.
- 6. "B" Turbine Building Portable A-Frame & Mcnorail (Cap.10,000 lbs) ID tb.61 The functicn of this load handling devim is to assist in tin assembly and disassembly of the turbine generator. '1his device is normally used to as-semble and disassemble tin turbine governor, bypass valves and the stcp and ccntrol valves. 'Ihis load handling device will cnly be used for this purpose whcn the plant is shutdcwn.
Item 3 (NRC Questicn 2.1.3)
With respect to the design and cperaticn of heavy load handling systens in the reactor building and thom load handling systems identified in tin respcnse to Questicn 1 above, provide your evaluaticn ecncerning ccmpliance with the guide-
-lines of ? UREX 3 0612, Secticn 5.1.1. The follcwing specific infomaticn should be included in the reply:
Sub Questicn 2.1.3a Drawings or dcetches sufficient to clearly identify the locaticns of safe load paths, spent fuel ard safe shutdown equipmnt.
Respcnse Drawings are attached that show the locaticn of the reactor core, the spent fuel pool, safe shutdown equipent, and safe load paths.
Sub Questicn 2.1.3b A dimussicn of neasures taken to msure tint load handling cperaticns remain within safe load paths, including prccedures, if any, for deviaticns frcm these load paths.
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. t Respcnse Procedures are used to ccntrol the handling of loads by the Peactor Building Crane and the Turbine Building Crane. Them procedures define the path of movement that is to be follmed for each load handled by these cranes. As a part of the interin work for the ccntrol of heavy loads, (enclosure 2 of Ibclear Regulatory Ccmaissicn letter dated 22 December 1980), these procedures were reviewed and revised, as necessary, to msure that tin load paths defined in the procedure were safe load paths. 'Ihese procedures require prior approval bf the Operaticns Comtittee of any deviations fran the designated load path.
Designated safe load paths have not becn nurked cn the floor for the reactor and turbine building cranes for tin follming reascns:
- 1. As part of the AIARA program at Mcnticello the reactor building floor at elevaticn 1027' is covered with a protective covering to minimize the spread of ccntaminaticn and to speed up the deccntaminaticn process. Successive layers of protective covering are addal as necessary during reactor mainte-nance activities. This covering would obscure marked load paths.
- 2. The dimensicns of most heavy loads handled in tin reactor building are such that they span or nearly span the distance between the reactor building floor beams.
- 3. All or a major portion of tin load paths for the reactor vessel lead and tle reactor vessel internals are through the equipnent storage pool where tin load path is physically restricted by the dimensicns of the (quipment storage pool.
- 4. The physical dimensicns and tle space available for laydmn of major heavy loads cn the 1027' elevaticn of tin reactor building does not alls major deviaticns fran load paths identified in the procedures for handling heavy loads in tin reactor building.
- 5. In the turbine building, safe load paths have not been identified in proce-dures or marked cn tle floor for the follming reascns:
- a. There are many combinaticns of circumstances that make it inpossible to idmtify specific laydown areas and load paths for each heavy load.
- b. -In lieu of safe load paths, two areas Inve been established which ocntrol tin movement of heavy loads. In tle exclusicn area, as identified in the procedure for handling heavy loads in the turbine building and as identi-fied by painted lines cn the turbine tuilding floor at elevaticn 951',
certain specifically idmtified loads are excluded. All other idmtified leavy loads may be transportal via any load path provided they are trans-parted as specified by procedure. In all areas not identified as an exclusicn area there are no restricticns cn the movement of any loads.
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- c. 'Ibe basis for not identifying safe load paths and specific laydcwn areas is a review performed of heavy loads transported cn the turbine floor and an analysis performed of the ccmsequmce of dropping any of these identi-fled loads. This analysis revealed that with tle excepticn of the gene-tar field and the high and Icw pressure turbine spindles, them loads can be safely transported over any area of the turbine floor if tie maximum distance betwem the load and the floor is limited to 6 inches.
This analysis revealed that if a load that is permittal bfprocedure .
is transported by procedure over the exc'usicn area and is dropped, tie load will not penetrate the floor and no spalling of the underside of the floor will occur.
- 6. With the excepticn of the turbine and reactor building cranes, all other lifting devices identified in this report have a fixed load path as deter-mined by the length of the associated mmorail or tiny have no load path because they have a fixal lifting point.
- 7. Q11y trained, permanent Northern States Power (NSP) Ccrapany ernployecs are pernitted to operate tin turbine and reactor building cranes.
Sub Questicn 2.1.3c A tabulatim of heavy loads to be handled by each crane which includes tha load identificaticn, Ical weight, its designatal lifting device, and verificaticn that the handling of such loads are governed by a written procedure ccntaining, as a minimum, tie infornaticn idstified in IURDG 0612, Section 5.1.1(2).
Respcnse See Table II.
Procedures were prepared and/or revised to meet the requirements of NUREG 0612 Section 5.1.1(2) as part of the interim actims for the ccntrol of heavy loads, (Nuclear Regulatory Comissicn letter dated 22 Decmkr 1980) .
Sub Questicm 2.1.3d Verificaticn that the lifting devices identified in the respcnse to Questicn 2.1.3c comply with the requirenents of AIBI N14.6-1978 or AIEI B30.9-1971 as appropriate. For lifting devices where these standard, as supplemented bf IUREG 0612, Secticn 5.1.1(4) or 5.1.1(5) are not net, describe any proposed alternatives and dencnstrate tinir equivalency in terms of load handling reliability.
Respcnse
- 1. Slings A?BI B30.9-1971 The slings used for handling leavy loads by lifting devices identified in this report ccraply with the design and inspecticn requirements of AtEI B30.9-1971. 'Ibe slings have a minimum factor of safety of five (5) and the 5
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- .s rated capacity of the slings used for handling leavy loads shall be taken as those listed in tables 3 through 14 of AtEI B30.9.c 7te Wire Ibpe Tech-nical Board was ccntactal regarding the basis for tinisafety factor, of five (5) in tln design and manufacture of nylcn and wire rope slings.- 7he Wire ' s Rape Tectnical Board is made up of design engineer representatives from, cling ,
manufacturers. 7tn Wire Rope Teclnical Board is the major source of teclnical informatiot used to establish the AtEI B30.9 code by the APEI B30.9 Code Connittee. Informaticn received from this source revealed ..that~ the basis for a safety factor in the design and manufacture of slings is lio account 'for 2 service factors incitxling deterioraticn of slings frcm use and dynamic 1oads, 4 N associatal with transporting any load. Since dynamic load is accounted fcrl - (N in tin sling rating, no additicnal derating is believed necessary. ( %
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,-5' Only trained, permanent tbrthern States Pcwer (IEP) Canpany erplcyees are \ - $
permittal to operate the turbine reactor and building cranes. Additional 1' -
1, assurance is thus provided that sling ratings will not .be exceeded. - #
- 2. Special Lifting Devices AtBI U1E6-1978 /s X',. \j (3 }' .
y e Retrieval of informaticn regarding tae design sv1 r$nufacture of,special '5 lifting devices supplied to,the Manticello thclear Gas erating Plant is in N m I 4, progress. When this i ticn is received a deterinisaticn will be rinde r N as to their ccuplian AICI B14.6-1978. ~^ .
Sub Questicn 2.1.3e $' \
Verificaticn that AtEI B30.2-1976, Chapter 2-2 has been invcked with respect to crane inspectim, testing and maintenance. Where any excepticn is taken to this standard, sufficient informaticn should be provided to demonstrate the ,cquivalency of proposed alternatives. ; . _
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Procedures for inspecticn,$ sting and riaintenance of the cranes wer'e-reviewed and N '
revised us appropriate as part. of" theynterim Actions- for Ccntrolgf Ileavy Ioads, ~
enclosure 2 of tuclear Regulatory letter" dated 22 December 1980,1to conply with the standard of AtEI B30.2-1976, Chapter 2-2. tb excepticn to#the,q:andards is taken. ] q
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Verificaticn tint crane design ccqalies witbthe guidelines c'( 09A Specificaticn:
70 and Clupter 2-1 of AtEI B30.2-1976,' includincJ the demonstraticn of equival ncy '
of actual design requirenents, for instances shere specific' :c7pliances '
with ;)these standards is not provided. t s f\ N,
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Respcnse ', .
These guidelines apply to overinad and gantry type, top running, ru1tiple girder,' ", a electric, traveling cranes. The reactor building and turbine luilding cranes ,
were both r:nnufactured prior to tin issuance of these guidelines.:. The reactor building crane ins ban modifial to provide redundant lifting features for -
Mmticello based cn Regulatory Guide 1.13. The miification takes into cmsid- ,
eraticn the A!EI B30.2, CMAA Specification 70 requiremern; and Regulatory Guide :'
1.104 (subsequcntly withirac.) . The modificaticns made were found acceptable ,
with provisicns by the tR: as describri in the lac lettter oE Mr.y*19,1977. -
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A ccmpariscn between the design of the Reactor and Turbine Building Cranes and g the CMAA-70 and AtEI B30.2-1976 codes 'is shown in attachmmt 1. 7tum ccxles are not applicable to the other lifting devices listed in 2.1.1 of this reNet. ,, .
Sub Cuesticn 2.1.3q ,
Excepticns, if any, taken to AtEI B30.2-1976 with respect to operator training, qualificaticn, and ccmduct.
Restm se_ ,
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operator training, qualificaticn and cmduct was reviewed as apart of tin interim acticns for the ccntrol of heavy loads, enclosure 2 of thclear Regulatory letter datal 22 December 1980. Ib excepticn is taken to AtEI B30.2-197G,in this respect.
Enclosures:
Attactrunt 1 d
Table I-Table II l
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Table I List of Overh3ad Ioad Handling Devices Not Ca1sideral f
" Because of Physical Separatim or Capacity e
Locatim Handling Devicne Capacity
- ID tb.
RX Building Pufueling Faci ities'ChEinel 50 lbs 3 H,tndling J1b Bocn Rx Building Refuel ~ing Facilities retor 1500 lbs 4 Diive.Jil Crane A Rx Building Refueling Facilities tbtor 1500 lbs 5 Drive Jib Crane B Rx Building Channel Handling 50 lbs 7 Overlmad Rigging
^
R.U._ Building Radwaste Calveyor 12000 lbs 8 Ioad-Out Matorail R.W. Building Radwaste Centrifuge 4000 lbs 9 Hoist A
/
R. W. Building Radwaste Caltrifuge 4000 lbs 10 t
\ \ Hoist B
' s t
K.M Puiiding Radwaste Building 6000 lbs 11
<. ftnorail:
d 0.d.' Stack Off Gas Stack 6000 lbs 12 ttxiorail R.W. Building Padwaste Building 6000 lbs 13 Sunp iknor.til Turbine Building C 'Ibrbine Building Portable 1500 lbs 16 A Fram3 lirlorail C Drywell MSIV Area Lifting Ing 1000 lbs 18
- A Heavy Iorl has been defined (per IUREG 0612) as, any load carried in a a givcn area after a plant becomes cperatialal, that weighs more than the combinal weight of a single spent fuel assembly and its associated handling tool for the specific plant in questial. At ttnticello FMclear Plant this weight has bem colservatively calculated to be 1500 lbs.
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Table I (Ccnt'd)
Incatim llandling Device Capacity I .D. Ib.
I Drywell MSIV Area Lifting Ing 1000 lbs 19 Steam Chase MSIV Area Mmorail 6000 lbs 20 Steam Chase MSIV Area Mcnorail 6000 lbs 21 1
D. G. Building Diesel Generator A 470 lbs 22 '
Mcnorail, A & B Lifting Ings l D. G. Building Diesel Generatar B 470 lbs 23 Mcnorail, A & B Lifting Ings
'Iurbine Building Electric Breakers Bridge 1000 lbs 24 Hoist Pocn A Turbine Building Electric Breakers Bridge 1000 lbs 25 Iloist Roon B R.W. Building Radwasta Storage 20000 lbs 26 Bridge Crane llot techine Shop Ilot Machine Shop 4000 lbs 27 Mcnorail II Storage Building CO &H Mm rail 4000 lbs 29 2 2 2 Intake Structure Screen IIouse 10000 lbs 30 Bridge Crane Intake Structure Trash Basket 4000 lbs 32 Jib Crane Turbine Building Cmdenser Tube Pulling Pit 2000 lbs 33 Mcnorail & Lifting Ing R.W. Building Radwaste Capping 1000 lbs 34 Staticn Mcnorail Rx Building MCU Pilter Shield 10000 lbs 35 Block thorail f Turbine Building Cmdmsate Domin Holding 6400 lbs 37 I Punp A Hatch tinorail l
Turbine Building Cmdensate Denin Holding 6400 lbs 38 Punp B Hatch Mmorail 2
Table I (Cmt'd)
Incaticn Handling Devi Capacity I.D. No.
'nirbine Building .Cmdensate Demin Holding 6400 lbs 39 Punp C Hatch Manorail
'nirbine Building Cmdensate Denin Holding 6400 lbs 40 I
Punp D Hatch Manorail
'nirbine Building Cmdensate Demin Holding 6400 lbs 41 Pttp E Hatch Mmorail R.W. Storage New Shipping Building 20000 lbs 42 l
Building Crane Rx Building Rx Pefueling Platfom 1000 lbs 43 l Handling Device Rx Building Reactor Vessel Service 1500 lbs 46 Platform R.W. Building Radwaste Devices 2000 lbs 47 Entrance Mmorail R.U. Building Hot Machine Shop Jib 2000 lbs 48 Crane and Lifting Ing O.G. Storage Off Gas Storage 15000 lbs 49 Building Building Jib Crane O. G. Storage Off Gas Storage 1000 lbs 50 l Building Building Mcnorails Rx Building CRD Rebuild Area 1000 lbs 51 Mcmorail Rx Building Drywell Equipnent Hatch 3000 lbs 52 Manorail & Lifting Device Rx Building Iow Ievel Ccntaminaticn 1000 lbs 56 Work Area Mmorail-Rx Building Rx Building Closed Cooling 6000 lbs 57 Water Heat Exchanger Lifting Ings Turbine Building Rx Feedwater Punp A Immorail 2000 lbs 58 Turbine Building Rx Feedwater Punp B Monorail 2000 lbs 59
'nirbine Building Miscellaneous Lifting Ings 6000 lbs 60 3
Table II Ileavy Ioads Irandled ly the Overhead Ioad IIandling Device Idmtified in Secticn 2.1.1 Crane Ioad Weight Lifting Device Procedure ID #1 'Ibrbine H.P. Ibad 108,420 lbs Slings Yes
'Ibrbine L.P. Ilood A 60,515 lbs Slings Yes
'Ibrbine L.P. Ibod B 60,515 lbs Slings Yes L.P. Inner Casing A 103,280 lbs Slings Yes L.P. Inner Casing B 103,280 lbs Slings Yes L.P. Fotor A & B 226,000 lbs Strongback & Yes Slings II.P. Rotor 82,583 Strcngback & Yes Slings L.P. 'Ibrbine Diaphragms 9000-12000 lbs Slings Yes L.P. 'Ibrbine Diaphragms 12000-18000 lbs Slings Yes Bypass Valves Shield Block 2,700 lbs Slings Yes Generator Rotor 281,832 lbs Slings Yes Generator Endbells 12,000 lbs Slings Yes Exciter flood 22,000 lbs Slings Yes Exciter Rotor 35,000 lbs Slings Yes R.F.P. Motor 35,000 lbs Slings Yes Condensate Punp Shield Block 10,800 lbs Slings Yes Ccndensate Punp 18,600 lbs Slings Yes Ccndensate Ptmp Motor 12,900 lbs Slings Yes IIIP IIcaters 45,100 lbs Slings Yes IIP Ileaters 46,900 lbs Slings Yes
'Ibrbine Gen Bearing Diaphragms 5,580 lbs Slings Yes Pallets & Miscellaneous Material 2,000 lbs Pallet Lifting Yes Device
'Ibrbine Rotor Stands 22,400 lbs Slings Yes ID #2 Vessel Service Platform 6,000 lbs Slings Yes Stud Detenticner Carousel 20,000 lbs RPV Ibad Yes Strcngback Fuel Pool Shield Blocks (3) 10,000 lbs Slings Yes RPV ilead 90,000 lbs RPV Ilead Yes Strcngback Drywell Ibad 80,000 lbs IU Ibad Yes Strcngback 1 Fuel Pool Skinmer Tank 6,000 lbs Slings Ib Shield Blocks (3) 1
Table II (Ccnt'd)
Crane Steam Separator 66,000 lbs Dryer Separator Yes Strcngback & Slings ;
Steam Dryer 44,000 lbs Dryer Separatar Yes Strcngback & Slings Ibc Head Insulaticn 9,000 lbs Slings Yes Pefueling Canal Shield 30,000 lbs Slings Yeq Spmt Fuel Shipping Ca* 49,464 lbs Special Device !b y Ibw Fuel Storage Shield Block (3) 6,000 lbs Slings !b G Model 1600 Cadc 25,950 lbs Special Device Yes Equip Storage Pool Shield 87,000 lbs Slings Yes Block (3)
Ibc Cavity Shield Block (6) 100,000 lbs Slings Yes Fuel Pool Shield Blocks 10,000 lbs Slings Yes itw Fuel Shipping Ccntainer 2,000 lbs Slings Yes RW Head Piping 2,000 lbs Slings Yes Fuel Preparaticn Machine 10,000 lbs Slings Yeg RW Invessel Work Platform 100,000 los Slings Ib ID #14 tiiscellaneous Ioads 10,000 lbs Slings Ib ID #15 Miscellaneous Ioads 10,000 lbs Slings Ib ID #28 Miscellaneous Ioads 4,000 lbs Slings Ib ID #31 Chlorine Ccntainer 3,580 lbs Strcngback Ib ID #36 Radwaste & Fuel Pool Filter 7,600 lbs Slings !b Denin Shield Blocks (5)
ID #45 Miscellaneous Icads 8,000 lbs Slings tb i ID #53 ICIC Punp Room Shield Block 8,000 lbs Slings tb l ED #62 Miscellaneous Ioads 7,000 lbs Slings Ib l
- 1. Procedures will be writtcn prior to the handling of them heavy loads.
- 2. Procedures have been prepared for each use of the RW invessel work platform.
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Attachnent 1 REACTOR BUIIDItG AfD TURBI?E BUIIDIIU CRA!E DESIGN REVIEW CMAA Specificatioi 70 and ASNI B30.2-1976 apply to the Pnactor Building and Ibrbine Building Cranes.
The Reactor Building and Turbine Building Cranes were designed to catply with EOCI Specificaticn 61, which was superceded by otAA Specification 70. 7tu difference betweat them two specificaticns which inpact the evaluaticn of the safe handling of heavy loads are addressed belcw with resprct to the Beactcr Building and Tu :bine Building Cranes: The evaluatim will take into ccnsidera-tim the requirements of CMAA specification 70, AtEI B30.2-1976 and tle guidance of Regulatory Guide 1.13.
It is to be noted that the Franklin Research Cmter, a divisicn of the Franklin Institute, ccnductal a ccrpariscn of the recatraendations of OiAA-70 with tluse ccntained in ECCI-61. Generally, the requirements of OiAA-70 represent the codificaticn of gocxl mgineering practice which should have been incorporated in cranes built to EOCI-61 specificaticn although specific requirements were not ccntained in EOCI-61. The Franklin Posearch Center study is addressal in "Teclnical Evaluaticn Poport", IEC Docket No. 50-334, dated September 24, 1981 performed under tEC Contract Ib. IEC-03-79-18.
The follcwing generally tracks those points of cmcern addressed in the ref-crenced Franklin Institute conparism for the lac.
Holst Rope Safety Factor CMAA-70 requires the hoist rope safety factor be calculated cn the canbined weight of the botton block assembly and the ratal load. This requirement is met bf the Reactor Building and Turbine Building Cranes.
Structural Steel CMAA-70 requires AS7M A36 structural steel. The ocdinary structural steel for Reactor Building and Turbine Building cranes ccnforms with AS3M A36 and 1cw alloy sttwtural steel ccnforms to ASit! A 242.
Stress Requirenents_
Although the specificaticn requirenents differ, the stress requirements of CMAA-70 for bridge girders, end trucks and trolley francs are met by tin Reactor Building and Turbine Building Cranes.
Crane Hook Intches A!EI B30.2-1976 adds the alditicnal requirements, applicable to safe heavy load handling, that crane hocks have latclus, if practical, in that applicaticn.
This requirenunt is met by the Peactor Building and Turbine Building Cranes.
Page 1 of 5
Attactment 1 (Ccnt'd)
Irpact Allcwance CMAA-70, Article 3.3.2.1.1.3 requires that crane design calculaticns incitxle an inpact allcuance of 0.5% of the lmd per foot per minute of hoisting speed but not less than 15%. E0CI-61 specifies cnly a maximum allowance of 15%.
Ccnsequently, for cranes with hoist speeds in excess of 30 feet per minute, it is possible that the impact allcwance applied under EOCI-61 will be less than tint required by CMAA-7G. 'Itu overhead cranes subject to this review operate at hoist speeds not in excess of 30 fyn.
'Ibrsicnal Forces CMAA-70, Article 3.3.2.1.3 requires that twisting mments due to overhanging loads and lateral forces acting eccentric to the horizcntal neutral axis of a girder be calculated cn the basis of the distance betwem the center of gravity of the load, or force ccnter line, and the girder shear cmter measured normal to the force vector. ECCI-61 states that such nonents are to be calculated with reference to girder center of gravity. For girder secticns synnetrical about each principal central axis, e.g., box secticn or I-beam girders, tre slear center coincides with tle centroiti of the girder section and there is no difference between tin two requirennnts. Box secticn girders are used for the Reactar Building and 'Ibrbine Building Cranes.
Bending Stress CMAA-70, Article 3.3.2.2 requires that bending stress calculaticns include a wind load of 5 pounds per square foot in design stress calculaticns based cn the sum of dead and live loads. E0CI-61 requires tint the design of outdoor cranes include a wind load of 10 pounds per square foot of projected area but is not specific cmcerning tln ccnbinaticn of wind loads with other dead and live loads. Although tin combinaticn of a wind load with other design loading calculations ccnstitutes a codificaticn of the sann goal cngineering practice that would Inve bem used in the cranes built to ECCI-61 specificaticns, the Beactor Building and Turbine Cranes are installed indoors and therefore are not subject to wind loading.
Irngitudinal Stiffeners CMAA-70, Article 3.3.3.1 specifies the nnximum allowable web depth / thickness (h/t) ratio for baK girders using 1cngittriinal stiffeners and requirements ccncerning the locatim and minimum nunent of inertia for such stiffeners.
E0CI-61 allcus the um of Icngitudinal stiffeners but provides no similar guidance. Requirements of CMAA-70 represent a codificaticn of the girder de-sign practice and the design standards employed in the Reactor Building and
'Iurbine Building Cranes built to EOCI-61 specificaticns.
Page 2 of 5 L
Attachnent 1 (Ccnt'd)
Allowable Corpressive Strength CMAA-70, Article 3.3.3.1.3 idmtifies allmable conpressive stresses to be approximately 50% of yield strength of tle reccmnended structural material (A-36) for girders, where the ratio of the distance between web plates to tin thickness of the top cover plate (b/c ratio) is less than or equal to 38.
Allwable capressive stresses decream linearly for b/c ratios in excess of
- 38. ECCI-61 provides a similar methal for calculating allowable capressive stresses except tlut the allmable stress decreases from approximtley 50% of yield cnly after the b/c ratio exceeds 41. Ccnsequently, structural members with b/c ratios in the general range of 38 to 52 designed under EOCI-61 will allm a slightly higlur ccrpressive stress than thom designed under CMAA-70.
This variaticn is not of ccnsequcnce since the b/c ratios of structural nembers for tle Ibactar Building and 7brbine Building Cranes are 13.5 and 17.5, respectively.
Fatique Ccnsideraticns CMAA-70, Article 3.3.3.1.3 provides substantial guidance with respect to fatique failure by indicating allcwable stress ranges far various structural nembers in joints under repeated loads. DOCI-61 does not address fatigue failure. 7tu requirements of CMAA-70 are not of ccnsequence far the Ibactor Building and Turbine Building Cranes since these cranes are not generally subjectal to frequent loads at or near desicp ccmditicns (CMAA-70 provides allmable stress ranges for loading cycles in excess of 20,000) and are not generally subjected to stress reversal (CMAA-70 allowable stress range is reducal to belm the basic allowable stress for cnly a limited number of joint ccnfiguraticns) .
Iloist Rope Requirements CMAA-70, Article 4.2.1 requires that tln capacity load, plus the inttcm block, divided by the number of parts of rope, not exceed 20% of the published rope breaking strength. ECCI-61 requires that the rated capacity load divided by the number of parts of rope, not exceed 20% of the publishal rope breaking strength. The capacity load plus tin bottom block, dividal by the number of parts of rope yields 4.36 tcns and 7.97 tcns for the Ibactar Building and 7brbine Building Cranes, respectively. 7hese values are less than 20 percent of tin published breaking strengths of 39.3 tcns and 44.9 tcns, for 7/8 inch l and cne inch 6 x 37 Improved Plow Steel Fiber Core Wire Rope, for the Peactor l Building and 7brbine Building Cranes, respectively.
Drum Design Crushing and Bending Ioads CMAA-70, Article 4.4.1 requires that the drum be designed to withstand ccxnbined crushing and bending loads. EOCI-61 requires cnly that tiu drun in designed to withstand anximum load bending and crushing loads with no stipulaticn that them loads be combined. This variaticn is not expected to be of ccnsequence Page 3 of 5
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Attachment 1 (Cont'd) since tin requirements of QiAA-70 represent the codificaticn of good cngi-neering practice which has been incorporated in the Reactor Building Crane built to 01AA-70, and nirbine Building Cranes built to EOCI-61 specificaticn, although a specific requirement was not contained in EOCI-61.
Drum Design Groove Depth and, Pitch 1
Q1AA-70, Article 4.4.3 provides reccrrended drun grove depth and pitch. 'Ihe Reactor Building Crane drum groove depth and pitch was designed in accordance with CMAA-70. EOCI-61 provides no similar guidance. 'Ihe recomendati<ns in CMAA-70 ccnstitute a codificaticn of good mgineering practice with regard to reeving stability and reducticn of rope wear and are not expected to differ 4
substantially frcn practices employed in tiu design of the Turbine Building Crane built to EOCI-61 specificaticn.
Gear Design CMAA-70, Article 4.5 requires that gearing horsepcwer rating be based cn cer-tain American Gear Manufacturers Associaticn (A01A) Standards d provides a method for determining allwable horsepcwer. EOCI-61 provides no cie.iMr
, guidance. The recomendaticns in CMAA-70 ccnstitute a codificaticn of good engineering practice for gear design and do not differ substantially from tin practices employed in the design of the Beactor Building and Turbine Building cranes built to EOCI-61 specificaticns.
Bridge Brake Design CMAA-70, Article 4.7.2.2 requires that bridge Irakes, for cranes with cab ccn-trol and the cab-cn-tle-trolley, be rated at least 75% of bridge motor torque.
EOCI-61 requires a brake rating of 50% of Iridge notar torque for similar cm-figuraticns. A cab-cn-trolley ccntrol arrangement is not used for the Reactor Building and Turbine Cranes subject to this review. 'Ihe Reactor Building Crane bridge brakes are rated at 150 percent of the motor full load torque. The tirbine Building Crane bridge and trolley brakes are rated at 100 percent of the motor full load torque. Tin Reactor Building Crane trollef brakes are ratcxl at 125 percent of the motor full load torque.
Hoist Brake Design OiAA-70, Article 4.7.4.2 requires that hoist holding trakes, when used with a l methal of ccntrol breaking other than mechanical, have torque ratings no less than 125% of the hoist notor torque. EOCI-61 requires a hoist holding Irake torque without regard to tin type of ccntrol Irake employed. The Reactor Building crane nnin and auxiliary hoist trakes are rated at 125 percent of the Irist motcr full load torque with electrical ccntrol braking systems. 'Ite tirbine Building nnin and auxiliary hoist brakes are rated at 125 percent of the hoist motor full load torque with electrical ccntrol braking systems.
Page 4 of 5
. _ _ _ . - ~ . _ _ . . _ __ .. _ . _
Attachnent 1 (Ccnt'd)
Bunpers and Stops 04AA-70, Article 4.12 provides substantial guidance for the design and installaticn of bridge and trolley bunpers and stops for crancs which operate near the ends of bridge and trolley travel, tb similcr guidance is provided in EOCI-61. This variaticn is not expected to be significant for the Reactor Building and Turbine Building Cranes since these cranes are not expected to be operated under load at substantial bridge or trolley speed near the end of travel. Further, guidance of 04AA-70 ccnstitutes the codificaticn of good engineering practice and will be expected to be satisfied by equivalent requirements for cranes prcxluced according to E0CI-61.
Static Ccntrol Systens CMAA-70, Article 5.4.6 provides substantial guidance for the use of static ccntrol systems. ECCI-61 provides guidance fcr magnetic ccntrol systems cnly.
This variaticn is not an issue of ccnsequcnce because nagnetic control systems were generally emplcyod in cranes designed when EOCI-61 was in effect and the static ccntrol requirements idmtified in 04AA-70 ccnstitute a codificaticn of the same gcxxl engineering practice tint was used in the design of static ccn-trol systems in the Reactor Building and nirbine Cranes built to ECCI-61 spec-ifications.
Restart Protecticn 04AA-70, Article 5.6.2 rcxguires that cranes not equipped with spring return controllers or mcracntrary-ccntact push buttcns be providcri with a device that will disccnnect all notors upcn power failure and will not permit any rotor to be restarted until tin ccntroller handle is brought to tin off position. tb similar guidance is provided in EOCI-61.
7tn variaticn is not of ccnsequence for tin 31rbine Building Crane since the lever type ccntroller is provided with a spring retum to the "OFF" positicn j and the crane is also provid(xl with a spring return " dead man" switch (to the i "OFF" positicn) that interrupts all pcwer to nove the crane, the trolley or any hoists. The Peactor Building Crane, although not provided with spring return
! ccntrollers, is provided with ntraentary ccntact push buttcms for pmdant ccn-trol and a spring return " dead man" witch (to the "OFF" positicn) that inter-rupts all power to rove the crane, the trolley or any toists.
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