ML19351G264
| ML19351G264 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 02/17/1981 |
| From: | Hukill H METROPOLITAN EDISON CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| TLL-474, NUDOCS 8102230375 | |
| Download: ML19351G264 (44) | |
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%!tropohtan Edrson Company ii d. &
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J Past Off ce Box 480
%cte*cm. Dennsevania 17057 wr ers 0 -*ct o.at %,- oe.
. Februarj 17. 1951 TLL 47'.
Office of Nuclear Reactor Regulation Attn: D. G. Eisenhut, Director .
Division of Licensing I'. S. Nuclear Regulatorv Cornissica [_.
Washington, D.C. 20555
Dear Sir:
3ree Mile Island Nuclear Station, ' n.t 1 (FI-1)
Operating License No. DPT.-30 Docket No. 50-289 Control oE Feavy Ioads This letter is in response to vour letter of June 26, 1980, concerning the handling and control of heavy loads. We have reviewed our controls for the handlinr. of heavy loads with respect to the interin actions described in Enclosure 2 of your letter. Attached are the responses to the five itens in your Enclosure 2 ard items 2.1.1, 2.1.2, and 2.1.3 of Enclosure 3.
Your letter also requested we submit responses to sections 2.2, 2.3, and 2.'. by December 26, 1980. Because of the delay in submitting this response we are recuestine an extension until Septe=ber 22, 1981 to respond to the remaining items. -
Sincerely, H. D. Huntill Director, M -1 HDH:DG": hah Attachments ,
cc: L. Barrett - w/o Attachments
- 3. J. Snyder - w/o Attachments '
D. Dilanni - w/o Attachments
- 3. H. Grier - w/ Attachments -
/
F. Silver - w/o Attachments 8 R. W. Reid - w/ Attachments
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Attachment TLL '74 ITEM 1: Safe load paths should be defined for the movement of heavy loads to mic*mize the potential for heavy loads, if dropped, to impact irrautated fuel in the reactor vessel and in the spent fuel pool, or to impact safe shutdown equipment. The path should follow, to the extent practical, structural floor members, beams, etc., such that if the load is dropped, the structure is more likely to withstand the impact. These load paths should be defined in procedures, shown on equipment layout drawings, and clearly marked on the floor in the area where the load is to be handled. Deviations from defined load paths should require written alternative procedures approved by the plant safety review committee.
RESPONSE: There are 2 areas of concern in this case: (a) the Reactor Building (with 185 ton polar crane), and (b) the Fuel Handling Suilding (with 110 ton overhead crane). In both buildings lifting operations do conform with the intent of " safe load paths." Certain procedures and equipment layout drawings of the handling areas will be a= ended to include specifically defined safe load paths which fulfill the above stated criteria. (See Attachment (1), Sheets 2-5)
Additionally, we will mark safe load paths in the Reactor Building as indicated on Attachment (1), and amend procedures and drawings to indicate this addition. This is based on a consideration of the following systems and their components, which are reactor safety and/or decay heat removal related:
- 2) Core Cooling
- 3) Decay Heat Renoval
'4) Reactor Vessel Internals, CRDMS
- 5) Building Spray
- 6) Nuclear Instrumentation
- 7) Reactor Protection The cost critical loads to be handled in the Reactor Safety areas are shown on Attachment (3), Survey of Heavy Loads.
As seen in a current Cask Drop Study (Attachment (2) made of the Fuel Handling building area, only the prohibited zone should be indicated both on the floor as required and in the appropriate procedures and layout drawings. An effort is currently underway to re-design the af fected area. This reco==endation is based on consideration of the heaviest load, a 15 ton spent fuel shipping cask.
ITEM 2: Procedures should be developed to cover load handling operations for heavy loads that are or could be handled over or in proximity to irradiated fuel or safe shutdown equipment. At a minimum, procedures should cover handling of those loads listed in Table 3-1 of this report. These procedures should include identification of required equipment; inspections and acceptance criteria required before movement of load; the steps and proper sequence to be followed in handling the load; defining the safe load path; and other special precautions.
s e .
Page 2 TLL 474 RESPONSE: Presently under developcent is a Station Lifting and Handling Control Manual. This manual presents a formal program which outlines methods of fulfilling requirements of various codes, standards and regulations. This manual addresses training, safety, construction, QA, preventative and corrective maintenance and contains copies of the appropriate procedures.
One of tne procedures contained therein is a maintenance procedure still in review, MP 1608, entitled " Lifting and Handling Control Procedure." This procedure specifically states "k'ritten procedures are required in the handling of critical loads." The definition of critical loads will include those that are or could be handled over or in proximity to irradiated fuel or safe shutdown equipment.
In addition, this procedure also requires that " normal periodic inspection shall be supplemented with special visual, NDE and dynamic load tests prior to use on critical loads if required."
Below is a listing of Table 3.1-1 itees and their status with respect to TMI-1.
ITEM STATUS Pb'R-Refueling Building
- 1. Spent Fuel Shipping Cask Procedures to be written prior to 6-30-82
- 2. Pool Divider Gates Procedure to be written prior to 6-30-82
- 4. Irradiated Specimen Precedures to be written Shipping Cask prior to 6-30-82
- 5. Plant Equip =ent (greater Procedures to be written than one (1) ton) prior to 6-30-81
- 6. Spent Resin, filter or Procedures to be written other shipping casks prior to 6-30-81
! 7. New Fuel Shipping Container Procedures implemented t (MP 1505-3)
- 6. Failed Fuel Container Procedures to be written prior to 6-30-82
- 9. Fuel Iransfer Carriage Procedure implemented (MP 1505-3)
Page 3 TLL 474 ITEM STATUS PWR - Containment Building
- 3. In-Service Inspection Tool Not applicable 4 Reactor Coolant Pumps Procedures to be written prior to 6-30-82
- 5. Missile Shields Procedures to be written prior to 6-30-82 lt is felt that procedures shall be developed by the above dates, hence some components / equipment do not currently have procedures for handling.
None of the existing procedures have safe load paths indicated as yet.
When the inf ormation is available from Engineering (per para 1 of the NRC letter) the procedures will be updated.
Crane operator training is already being conducted and a new Maintenance Procedure, MP 1406, will address all operator qualifications.
IT~. 3: Crane operators should be trained, qualified and conduct themselves in accordance with Chapter 2-3 of ANSI B30.2-1976, " Overhead and Gantry Cranes."
RESPONSE: The records of personnel assigned to operate cranes have been reviewed to determine their qualifications to operate overhead and gantry cranes.
A formal training program in " Overhead and Gantry Cranes" is being developed. All persons not already qualified will receive training prior to 6-1-81.
Page 4 TLL 474 1 TEM 4: The crane should be inspected, tested, and maintained in accordance with Chapter 2-2 of ANSI B30.2-1976, " Overhead and Cantry Cranes."
With the exception that tests and inspections should be performed prior to use where it is not practical to meet the frequencies of ANSI B30.2 for periodic inspection and test, or where frequency of crane use is less than the specified inspection and test frequency (e.g., the polar crane inside a PWR containment may only be used every 12 to 18 months during refueling operations, and is generally not accessible during power operation. ANSI B30.2, however, calls for certain inspections to be performed daily or monthly. For such cranes having limited usage, the inspections, tests, and maintenance should be performed prior to their use).
RESPONSE: The cranes at TMI-l are inspected at the frequency shown on Attachment (9) to meet chapter 2-2 of ANSI B30.2-1976 requirements with some frequency exceptions. The inspections are performed in accordance with preventive maintenance procedure E-14 ITEM 3: In addition to th.. above, special attention should be given to procedures, equipment, and personnel for the handling of heavy loads over the core, such as vessel internals or vessel inspection tools. This special review should include the following for these loads:
- a. Review of procedures for installation of rigging or lifting devices and movement of the load to assure that sufficient detail is provided and that instructions ara clear and concise.
- b. Visual inspections of load bearing components of cranes, slings, and special lifting devices to identify flaws or deficiencies that could lead to failure of the component.
- c. Appropriate repair and replacement of defective components.
- d. Verify that the crane operators have been properly trained and are familiar with specific procedures used in handling these loads, e.g., hand signals, conduct of operators, and content of procedures.
RESPONSE: The review of procedures to ensure there is sufficient detail is discussed in the response to item 2. Inspections of load bearing compenents and repairs to defective components are covered in the response to item 2.1.3. Crane operator training is discussed' in the response to item 3.
I SECTION 2.1 NUREG 0612, Section 5.1.1, identifies several general guidelines related to the design and operation of overhead load-handling systems in the areas where spent fuel is stored, in the vicinity of the reactor core, and in other areas of the plant where a load drop could result in damage to equipment required for safe shutdown or i
decay heat removal. Information provided in response to this i
. . . _ ~ _ _ _ . _ - - - _ . __ _ _ _ . _ - . .
o e * .
Page 5 TLL 474 i
section should identify the extent of potentially hazardous load-handling operations at a site, the extent of conformance to appropriate load-handling guidance, and the changes required in order to conform to the guidance.
ITEM 2.1.1: Report the results of your review of plant arrangements to l identify all overhead handling systems from which a load drop may result in damage to any system required for plant shutdown or decay heat removal (taking no credit for any interlocks, technical specifications, operating procedures, or detailed i structural analysis).
ITD1 2.1.2: Justify the exclusion of any overhead handling system from the above category by verifying that there is sufficient physical !
separation from any load-impact point and any safety-related component to permit a determination by inspection that no heavy load drop can result in damage to any system or component required for plant shutdown or core decay heat removal.
RESPONSE All systems and components mentioned in the recommendations section TO ITEMS of item 1 above, were considered. In addition, the worst case 2.1.1 5 15 ton cask drop was reviewed as the limiting factor in the Fuel 2.1.2: Handling Building.
Utilizing the " heavy load" (1 ton) criterion as= defined in your letter and listed in' Attachment (3), there are no heavy i loads which, if dropped may damage a system required for safe-
, shutdown or decay heat removal. .The logic to support'this state-
! ment is as follows:
i
! a. The safe shutdown related equipment whien could possibly be damaged in the Fuel Handling Building-will be protected by interim measures now being undertaken such as painting of the prohibited zone, I adherence to height-weight limitation tables, and procedural / administrative' changes which should be completed prior to 6-1-81.
i
- b. There are no safe shutdown'related' equipment.or. components l in the-Reactor' Building which could be damaged by heavy l
. loads lifted overhead during reactor operation because all such; equipment and components which could be' effected are in an area which is inaccessible during reactor operations, i.e.,=inside the shielded area (see: Attachment-(1).
I Access-to these loads can only be gained after reactor -
l shutdown and cooldown below 2000F*.~ The Decay Heat Removal
! components (pumps and coolers) are in the Auxiliary Building at a level of 263'7" - 275'at a location which presents no l
L access from either the Reactor Building or the Fuel Handling l overhead cranes (see Attachment (4).
L'
- and depressurized_to below-300 psig.
l l- . . . . - , . . . . .. ,.-_ . . --.;___.-,, , .._.- - ,- ... . _ .,, , _,_, _ . .- .. , ,
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Page 6 TLL 474 ITEM With respect to the design and operation of heavy-load-handling 2.1.3: syste=s in the containment and the spent-fuel-pool area and
! those load-handling systems identified in 2.1-1, above, provide
- your evaluation concerning compliance with the guidelines of NUREG 0612, Section 5.1.1. The following specific information should be included in your reply
- a. Drawings or sketches sufficient to clearly identify the location of safe load paths, spent fuel, and safety-related equipment.
)
i
! b. A discussion of measures taken to ensure that load-handling operations remain within safe load paths, including procedures, if any, for deviation from these paths.
- c. A tabulation of heavy loads to be handled by each crane which includes the load identification, load I weight, its designated lifting device, and verification that the handling of such load is governed by a written procedure containing, as a minimum, the information identified in NUREG 0612, Section 5.1.1(2).
- d. Verification that lifting devices identified in 2.1.
3-c, above, comply with the requirements of ANSI. 14.6-1978, or ANSI B30.9-1971 as appropriate. For lifting devices where these standards, as. supplemented.by NUREG 0612, Section 5.1.1(4) or 5.1.1(5) , are not met , describe any proposed alternatives and demonstrate their equivalency.in terms j of load-handling reliability.
I e. Verification that ANSI B30.2-1976, Chapter 2-2, has been invoked with respect to crane inspection, testing, and maintenance. Where any exception is taken to this standard, L sufficient information should be provided to demonstrate l the equivalency of proposed alternatives.
l l f. Verification that crane design complies with the guidelines of CMAA Specification 70 and Chapter 2-1 of ANSI B30.2-1976, including the demonstration of equivalency of actual design requirements'for instances where specific compliance with these standards is not provided.
l l g. Exceptions, if any, taken to ANS1 B30.2-1976 with respect l to' operator training, qualification, and conduct.
RESPONSE: a. This information has been included in Attachment (1),
Attachment (2), and' Attachment (4). Attachments (5) l and (6) provide elevational views of the Reactor and
! Fuel Handling Buildings, for reference.
l
'b. . Current measures include:
I 1) Existing administrative prohibition'of Reactor' Building polar crane use with the reactor operating. (See Attachment
- 1, page.5) mm m j
9 l
p3, TLL 4/4
- 2) Crane Intericcks in Fuel Handling Building with a 15 ton load. (See Attachment (7).
- 3) Before any heavy overhead load handling job (greater than one ton)can occur in the Reactor Building or Fuel Handling Building,which may adversely affect the ability to maintain the reactor in a cold shutdown condition or which could be handled over or in close proximity to fuel; an RWP, and ALARA and QA review are required. In addition, for any heavy overhead load handling jobs which may adversely affect the ability to maintain the reactor in a cold shutdown condition or which could be handled over or in close proximity to fuel,an approved maintenance procedure will be used.
- c. See Attachment (3) Survey of Heavy Loads
- d. Strict compliance to required standards exists when lifting any load which contains radiological material or is around, over or in any way in the vicinity which may adversely affect the ability to maintain the reactor in a cold shutdown condition or which could be handled over or in close proximity to fuel.
- e. This standard has been invoked and reviewed - currently in the process of implementation in all areas , with estimated completion prior to Reactor Operation.
- f. This area currently under review by Met-Ed. In checking with Crant "snufacturer (Whiting) representative ascertained that crane met requirements of EOCI #61 which at the time of crane design (1968) was current equivalent of CMAA Spec. 70.
- g. In the process of ensuring exact compliancewith this standard programs at TMI-l have currently been initiated which include the following:
i
- 1) Physicals for crane operator personnel to ensure compliance with ANSI B30.2-1976, l
f 2) Establishing both classroom phase and practical j factors training program to initially qualify a number
' of crane operators. This should establish a self perpetuating standardized training program.
! 3) The creation of a training record on each crane operator
! for easy reference and updating.
I l
Page 8 TLL 474 The Fuel Handling Bridges (Main (primarily for CRDM's) and Auxiliary Handling Bridges in the Reactor Building and Fuel Handling / Storage Bridge in the Fuel Handling Building are used during refueling and covecent of fuel. They are operated strictly for the above purposes per approved procedures.
Handling bridges are interlocked with the fuel transfer system to prevent certain inadvertent operations which would damage the fuel control rods or orifice plug assemblies during the transfer operations.
Override and override indicating lights are provided. (See Attachment (8) for additional details.)
Safety factors of at least 5 based on the ultimate strength of the material used was required on all parts including the hoist cable.
The testing operation and maintenance of these bridges in accordance with EOCI :i61 and ANSI 30.2 has been verified. These bridges have mono rail hoists which are rated for 5 tons (North bea=) and 3 tons (South beam).
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- 15 *c:s er between 3000 its. anc'.15 tens er cc:sist cf irradiated P _
Seecificatic_
Spent P..el ele =ents having less than 120 days fuel fer decay transfer of their cash 3.n.1 irradiated fuel shs.11 =ct be lee.ded inte a spent 1: the shipping cash area. .
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vhenever 1cais in excess cf 15 Ocss are te be lifted and ransported
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s'=" be 3.n.3 The icvest surface of e.'.1 1cais in excessene of 15 fcc: tenscr less abcVe the ad=inistratively dted to an elevatic: -
ec rete su-face at the sc d-e 3LS f -0'~ in. elevatics in the fuel
=
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Tc11cving =cdificatic s cr ispr. irs to any of the ice.1 bearing =e=bers ,-
3115 the ers=e shan be subjected Oc a tes* lift of 125 peree:q cf its
! rated 1 cad.
F.xcept as specified in 3.n.2 and 3. n .3 abcve, 1cais in excess of 3.n.6 3000 lbs. shall be ad=1:istratively c :trelled se that they are handled at the icvest practicable elevatics and se that the center of
= ass of the lead is: (1) :sintained the telev edge elevatics of a fuel3h6 stcrage ft-0 in.pec1 cr (2) =sintained conte.ining at suchfuel i--adiated distance that should frc: the icad be released and tip over (such that the ic s di ensien of the lead vcs sub:tantially hori:catal) in any directica, the center of = ass.a. of the s . a.lead
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3.11.8 Specifics:ica 3.11,6 is waived for ::ansfer of :he gste be:veen the spen: fuci pocis frc:: its functional icestien to 1:s s:crage Ices:1ca
! ,] prior :c the Cycic 5 refuel 1=g cu:sge provided:
D? D *D C'
- c w Amendment No. 48 3-55
F 1
~
Mcichmwf0;
- a. There are ne irradiated fuel asse=blies with less than 180 .3dfI days cccling ::=e in :he spen: fuel pools.
v
,4 b. There are no =cre than a c:a1 M 15e irradia:ed fuel asse=clies in the spen: fuel pools.
< c. The lifting devices that are a:: ached be:veen the 1 cad block J
and the ga:c are redundant, and each device is capable of supporting three ti=es the sta:ic plu: dyn==ic 1 cad of the gate. Where the balance of :he icad pa:: is me redundan:,
it shall be capable of supper:ing greater than six ti=es the 4
static plus dynamic lead of the gate.
- Bases .
This specifice. tics vi -d* activit/ relen..?s to un estricted areas resulting frc=
da= age to spent fael s: -ad '- *
- pent fuel s:crase pecls in the pcstulated event of the drepping of a heavy lead *--h e fuel handling building crane. *' n e: a leaded spent fue' *-- sfer cask is =cved cut of the de :::s=inatics pit area and alens the centerline of the spent fael poc1's vest vall to the recei'. ng/ shipping area (Figu e
- iel d c cf h3 fee: which is 13 feet greater than its 9-18, designSectie basis 9), it has drop. a pote b va:s p;erfc:-:ed assu=ing that the cash and its entire An analysis ec tests of te fuel asse-blies are sufficiently is= aged as a resul cf d cyping the cask, to allev ,he escape of all noble gases and iciise in the gap. "his release was tssu=ed to be directly ,o the a =esphere and : cecar instanta ecusly. The site boundary deses resulting frc= this accident are 5.25 a whole body and 1.02 a to tirfreid, and are with1: the li=its specified in 10 Cyn 100.
-Specificatics 3.11.1 requires that spent fuel, having less than 120 days decay post-
.rradistics, ::: be leaded i= a spent fuel tra sfer cask in order to ensure that the deses resulting fr== a highly i= probable spen
- fuil transfer cask drop venli be withi:
these calculated above. -
Specifica 1c 3.11.2 requires the key cperated intericek syste=, which aute=aticany i id-*:s the travel area of the fuel handling crane (refer to Figure 9-1SA, Sectic: 9) while it is lifting and transperting the spent Pael shipping cash, to be imposed whenever
- 1cais in excess of 15 tens are to be lifted asi transpersed while there is a=y spent fuel in stcrage in *he spe rael storage peels in Unit 1. This aute=aticany ensures the.t these heavy leads travel is areas where, in the unlikely event of a lead drop accident, j there vould be =c possibility cf this eve:t resulting in any da= age to the spent fuel stored in the pools er doing any unacceptable s : ::=al A=--ge to *he spent fuel pool struct= e. As described in Sectic: 9 7.1.1, the shipping cask area is designed to vith-ste=d the drcp cf the spent fuel shipping cask fre= an elevatics of 3h9 ft without u acceptable da= age ,o the spent fuel poc1 stru *=e.
Specificatic: 3.11.3 ensees that the icves* s= face of any heavy lead =ever gets higher than cue feet above the cencrete surface of the 3h8 ft-0 in. elevatic in the fuel ha dling building (cc=inal elevatien 3k9 ft-0 in.) thereby keeping any i=pnet feree frc= an " M y lead drop accident vithin accepte.ble li=its.
Specificatien 3.11.h ensures that the preper capacity crase heck is used for lifting and trass;cr-ing leads thus reducing the probability of a lead drep accident.
Fencving =cdificaric cr repairs, specificatics 3. n.5 confir=s the lead rating of the - ane. .
s .
9
[' (1) FSAR, Supple =ent 2, Part VII - -
Amendment No. 48 3-56
@D 0 t (1 AS/7c) 66- dab I M
~_ _ . . - - - _ . _ _ . _ . . _ _ _ _ _ _ . _ . _ . _ _ __.--_,__ _ _ _ _ _ . _ _
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Specificati:n 3.11.0. i..peses at:inistrat:ve li its en handling leads veighing in excess of 3000 lbs. : prevent desage . i- aciated .^ael.
- der.dling loads of less than 3000 lbs. vith:ut these restri::icns is a::eptable because the consequences =f dr:pping loads in this veign: range a e :enna. able to these produced by the fuel her.dling accident censidered in the F,A? and fcuni acceptable.
Spseificacien 3.11.7 prehitite the presence of a spent fuel cask in the Unit i Fuel Ean .'..s~ =.- - -'...,. ..'..'ac ........-.'..v *e . .='.~.^. v - .%.*. ls'.. -* a. c. c ~~r. ' e~ e ' .- . .,
reviev-of spent fuel cac:: handling Operations at CC-1 and concluded the.: such operatiens --- be perf :ned safely.
Specifica:1:n 3,11.3 perni:s :he ::ansfer of the sa:e between :he spen: fuel pools frc= 1:s fune:icasi 1::a:1:n :o 1:s s:: rage loca:1cn prier to :he refueling outage for Cycle 5. ~'ha irradiated fuel inven: ry/ccolde n re uirenents are :o preven:
exceeding 10 CTE 00 and 10 CFR 100 d:se li=i:s should :he ga:e be d: ppad, causing fission produe: releases frc: the irradiated fuel assenblies in either fuel pool.
The lif:ing devices recuirenen: assures : hat either a single failure vill not rasul: in a d:=p fer :he case of redundant lif:ing devices er suffi:1en: =argin, exists suca that a failure vill no: occur for :he case of a single lif:ing device.
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,r hy}yh3 7' C -l REV!SION NO. j TECHN+C AL CATA O.EOCR' #CJEC' Nd '"" dAGE I C: 12 PROJECT; , DEPAR'M ENT / SEC TIC N Entineerine E *)a c i e- __ !
Three Mile Island Uni: .
(-MI-1) a. r e r~.e r
. C.*.o* C */;/"
- - R T_ ..V ' e,1 ^s .- .". ^"'.:_ 5'13'30 i
DOOUMENT TITLE ' Cask Drop Anal;s:.s fer !
- ne Fuel Handlin:; Ecildine l i,
- j. ORIGINATOR SIGNATURE DATE h APPROVAL (S) SIGETUR E r DATE l I T. H. Chan % ~' & b ~
- db!!frI A. ?. Rochtno O{A~]"7 l El']!EC I
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! i bA?PROVALFOREXTER'4ALDISTRIEUT!c5lDATE I
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l* DISTRIBUTION {l ggg7pgg7; 1 d
J. J. Barton ij a. Brief Statement of Problem T. H. Chang !!
J. J. Colit: l The letter from NRC dated May 17, 1979 te M2:-Ed D. K. Croneberger (See Appendix 1) states in paragraph 5, "In ao much as !
J. C. DeVine you have defined a special area (north and east of the *
- 3. D. Elam tracks) where' loads or load heights must be li=ited to J. F. Frit::en preclude violation of safety criteria, we believe that L. Garibian p!
! such limits should be succorted bv analysis and should R. Harding jl be clearlv defined in the facili:V technical specifi-R. W. Heward d cation."
R. R. Lefin ]
G. P. Miller ll Also, in our technical specification, 3.11.6 states as i' D. Mitchell follows: " Loads in excess of 3,000 lbs. (3,000 -
W. E. Potts yl 30,000 lbs.) shall be administratively controlled so that A. P. Rochino ! they are handled at the lowest practicable elevation and D. G. Slear so that the center of mass of the load is: (1) maintained I C. W. S=yth {j! below elevation 348 ft.-0 in. or (2) maintained at such R. F. Wilson distance from the edge of a fuel storage pool containing j? irradiated fuel that should the load be released and tip
! over in any direction, the center of mass of the load would be at least six feet from the edge of any 1 con-I taining irradiated fuel."
i Henceforth, this analysis was undertakan to investigate (1) should load-height limiation in the area of north !
and east of the tracks (See Appendix 2) be required? If so, what is the limitation in order to ensure no unaccept- ,
. [ able damage to the safe:y relative cable tray bencath the slab? (2) will 1: be a ha::ard when.a postulated 15 ton
~
j !
object drops frc= El. 34S'-0" into the pool?
- b. Summarv of Kev Results i
! Floor has been analyzed based on a'.~2 cts of local penetra-l l tion and structural collapse. Our analysis revealed that i l
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_ . a::p Analys;5 00:
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PAGE - O~ -
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4 :
1 2.5V
SUMMARY
OF CHANGE APPROVAL i OtTE j v
~.- ,
i Revise c. Cenclusiens and d. Rece=enda:1:ns f A. N@,,,,,e 5'/.D ', #
f Abstra:: in c: der to agree with Se::icn 5.0 and i i
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Se::icn 6.0. 3.,< crenece:;,e: ,
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Page la do:inan =ede of failure is structural ecliapse, which yields the fellcuing limitations of lif:ing heigh:s.
a
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.. s :.
,_.a. a.s... n.: re. .
. .r .e , . . ..... . ..,.3e.24. .. .. .s, ,
Ob4e : Uti:n: Maxi u- Liftine Heich: l 1,000 lbs. 32. . ft. j 10,000 lbs. 0.31 f:. l 20,000 lbs. 0.051 ft.
30,000 lbs. 0.036 f:.
(2) Railrcad track area at El. 301'-7": (See Aret EFCD, Figure 1, Appendix 2)
Cbiet: Weich: .u.aximur Liftine Heich:
1,000 lbs. 95.'6 ft.
. , w.,
n .,.
a ..>. :
.c...
..,a.c .:s. ... . :.:.
30,000 lbs. 3.2S f:.
For 15 ten d:cpped fres its cer.:ar of = ass at II. 348'-0" inte the spen: fuel peci, neither structural failure. nor i==ediate wa:er leakage will result.
(For more de:sil see Sect. 4.0)
- c. Cenclusiens (1) ?ue :: the insufficient reinforcement fer the slab at El. 305'-0", (only f6 a 12" top and be :c=), (See Reference 1), the slab at the east and ner:h of :he ::ack area is unable to sustain any object of 15 tens and less dropped frc: El. 34S'-0". The f ailure of the slab along with the f alling object !
8 could des:rcy the en;ineered safeguard circuits located right beneath the slab. !,
t (2) The 5 foo: thick cencrete slab at the be::cm cf the spent fuel peel will ;
have about 6 inches of solid, uncracked concrete remainin;. This 6 inches i of solid cenerete shall prevent the peci frem immediate water leakage. ;
4
- d. Reecmnende:icns The recc= endations ara as fellcws:
(1) A wei;h:-height limitatioc based en this analysis at the north and east of~
the track area shall be administratively restricted. The change of the technical specification has to be done accordingly. McVever, the impact of d
thic li=itation to TMI-2 recovery operation should be investi;c:cd.
(2) The possibili:y of re=cvin; -he red cable tray con:aining ES/R 757, ES/R 577 -
and ES/R 167 a: El. 293'-0" ce the sou:h wall area so Sa: any object droppeu would not cause :he ruin of both colors at the same time shall be inves:igated.
(3) Another possibility of ins:alling energy abscrbing =a:erial such as =etal honeyecebed panel en top of the floor also shall be investigated. The energy abscrbing =aterial could relax the limitation of lif ting height to sc=e degree.
- eV.
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.c. c:. m entents i
Abstract *itle ? ate Mc.
2 2
- a. 3rief Statement of Proble
- 1
- b. Su
- sary or Key Results 1
- c. Conclusiens la
- d. Recc=menda:icn la See:1en 1.0 Purpose and Su==ary 2 2.0 Methods 2 3.0 Ivaluation 6 4.0 Results 6 5.0 Cenclusiens 7 6.0 Recc=mendatien S 7.0 References 9 j- 8.0 Appendix (1): The let:er frc U.S. NRC to Me:-Ed Co=pany en May 17, 1979 10 Appendix (2): Fi;;ure 1 - Plan f or Fuel.
F.andling Building '12 i
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.I The purpescs of this analysis are :c dete nine whether or no: the height lini:::ien for objects weighing 15 tons and less is necessary in the east and north ::ack area, and also to investi a:e if :he spen: fuel pool slab
+
can sustain a 15 :en object d: pped inte :ne pool frc i:s center of mass a: El. 31.5'-0".
This analysis includes pene: ration prediction, simplified-linear one degree
. of freeden system, slab resistance, and energy balance between the inpac:
l and strain energy. Tables are presented te show the results.
2.0 ME--!CDS The slab may be des:rcyed by excessively local penetration or (and) structural cellapse due to a missile fc ce.
2.1 Pene:ra:icn Predic:icn:
- Two metheds have been e= ployed for investiga
- ing the penetration depth so that ne scabbing shall occur at the ho::cm of the slab. They are:
2.1.1 Modified Petry formula (See Reference 3).
[ a
, X = Kp nW log,0 1- V- (Eq. 2a) 215000 I
I- where: K = .0022 (ft. 3/lb.)
P W = weight of missile (pounds).
I l . ,
l A = centact area (ft.~)
l V = missile velocity (ft./sec.)
X = penetration depth (ft-). .
i t
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+e-r--- * * 'h 'e - +- *v-- -,--+v-<we-e-e-~-we-+-ewt e-*--vw .%ww v v-w---e- e- -r-- +vem- -r'--'--+r--+ v w +-+-'e1 e " r-' ' '" "7 *
['f 7G(C d ref &f f (ej TDR 142 Pa;e 3 2.1.2 Modified 30RC (National Lefense Research Ccamittee) formula (See Reference 3):
for X/d < 2.0
- -b V
, 1 *O y, - 4 gng (Eq. 2b)
(1000d f or X/d > 2.0 1.8 V +d (Eq. 2b)
X = K'~4 1000 /
where: X = penetration depth (in.)
d = missile diameter (in.)
k=180/yf'c f'c = concrete compressive strength (psi)
N = missile shape facter, taken 0.84 for blunt-nosed missiles.
Since Eq. 2b, one of the recommended empirical formulas by ACI 349 committee, yields a better solution according to Sandia's test report, the modified NDRC equation-is adopted for this analysis.
2.2 Structural Collapse:
A check to see the possible excessive displacement in the slab is of great .
interest before analycing non-linear structural response at this time. Hence, a linear-simplified single degree of freedom system is modeled for the slab and utilizing a conservative-rectangular forcing function of which time duration equals to one hundredth of a second (See Reference 4).
2.2.1 The moment vs. curvature diagram of the slab is obtained by. assuming a straight line strain deformation at all stages of rotation (See Reference 8). The evaluation is based on 5000 psi of ultimate concrete strength and grade 40 for -
the reinforcing steel. The dynamic increase factor recommended by ACI 349 due
, to sudden load effect is brought into consideration (See Reference 6).
k
, , , * , g* ,4 g,.w. he'. w e
- 9.'." W.,,**[jf-' , p ep=_ g
'P 4 ' g ,* _
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ll~/fc<chmu t(2) '
TDR 142 Page 4 i
2.2.0 An approximate bi-lir. ear load vs. displacement diagram can : hen be easily obtained by integrating the >bmen:-Curva:ure area times the moment arm, i.e.:
1 B
l jg =
fXdx (Eq. 2c) (See Reference 5) is A
i 2.2.3 Utilice the idea of kinetic energy balancing the poten:ial energy, i.e. :
hMV = R ll -bd 81 (Eq. 2d) (See Reference 4)
/
where: M = mass of the missile V = s:riking velocity of the missile i
R = ultima:e load resis:ance of the structure h
el = displacement at steel yield b ,= maximum displacement Note: all units are in_ pound, foot and second. ,
J I The only unknown, [L m, from the above equation can be determined. Then the ductility ratio will be found by:
i A.
m (Eq. 2c)
I
".d el 2.2.4 In order :o ensure no structural failure, one has'to limit the due:ility-ra:io to an allowable upperbound value. The result based on ACI 349, Appendix C by allowing.," = 10 yields the most conserva:1ve solution and.
is presented in a weight vs. height table.
l l
hf4(b/NC6sf(b)
TDR 142 Page 5 2.2.3 A similar proccaure, then, is performed to ge: .the weight vs. height result for the railroad track slab and aise is tabulated.
2.3 Object Dropped into the Pool:
For the 15 ton object dropped into the spent fuel pool, buoyant as well cs drag forces resisted by water are considered. The striking velocity at the botton of the spent fuel pool is determined by: (See Reference 7)
L-V= ",. (H) and (2q. 2f) 2at Z,' (H) - V2 + e-2aH $gao[e (1-2ati-S-Vo2 + c fe 2at / -1)S 2
. 2a" 9 a ( -= /
(Eq. 2g)
V g j yW where: 2 , = terminal velocity = , (1-j (Eq. 2h) a =[AoC./2W
. )'m!
H = water depth b =[g/w g = gravitational acceleration L = length of object (assumed 17 feet here)
Ao = hori ental c css-sectional area of object (assumed 6' diameter here)
Vo =. initial velocity of object
) = weigh: density of water
)'m = weight density of object C, = dra; coefficient NOTE: all units are in foot, pound, and second. .
Q C h !>ft1 T $
TDR 142 Page 6 Tne missils residual velocity after perforating the 3/16 inch s: eel liner can be determined by - (See Reference 7)
~
y ,. . .2 -
1.12 x 106 (dt)1'5 !'
lh (Eq.'2k) a .
where: Vr = residual velocity (ft./sec.)
t= thickness of steel liner (inch)
If the residual velocity is greater than zero the steel liner vill be perforated.
Af ter knowing the missile weight and its striking velocity, one can determine the penetration depth, check :he strue: ural response and eb:ain the depth of the crack.
3.0 EVALUATION Two approaches named impulse momentum and energy balance methods are co=monly utilized for s:ructural response analysis. However, by using impulse mementum method, the difficulty one vill face is to determine the forcing function for
, the missile and structure in:eraction. The assuming values may be very f ar away from the true ones which in fact needed a test result. Therefore, the ener:y balance method is emploved for this analvsis.
The main reinforcement running from support to support for the long and narrow j slab makes this structure a one way slab. With both ends assumed to be fixed, the collapse mechanism, therefore, will be plastic hinces at both ends and at middle span where the missile hit.
The allowable due:111:y ratio is the key value for the energy balance methods.
It is variable from one criteria to the other. Among them, the ASCE manual allows the highes value of 30 while ACI 349 conservatively specifies an upper limit of 10 for 2 structural section having equal amounts of tension and compression reinforcements. A highcr value can be used if suf ficient justi-fication can be provided. L'e feel that since this analysis deals wi:h an extensively important safeguard circuit, a ductility ratio of 10 seems to be a proper and safe assumption.
4.0 RESULTS Our analysis shows that the structural collapse rather than the local penetra-tion is critical for both of the slabs at El. 305'-0" and railroad : rack area.
. The results based on ACI 349 f or the slab at El. 305'-0" are tabulated as the following: (See P. 37, Reference 9) e 6 gp wy
- n + -&--*-(q -w+ - ' , - N-w u- --em -
M e t'
W b Nfl&1 b
$ TDR 142 Page 7 4
Naich: Hei:ht Limitations "'eich: Hei:ht Limitations i 500 lbs. - 129.76 ft. 10.000 lbs. - 0.32 f t.
750 lbs. - 5'/ . 6 7 f:. 11,000 lbs . - 0. 27 f t .
1,000 lbs. - 32.44 f:. . 12,000 lbs. - 0.23 ft.
1,500 lbs. - 14.42 ft. le,000 lbs. - 0.17 f:.
2,000 lbs. - 8.11 f : . - 16,000 lb s. - 0.13 f t.
3,000 lbs. - 3.60 ft. 1S,000 lbs. - 0.10 ft.
4,000 lbs. - 2.03 f:. . 20,000 lbs. - 0.081 ft.
5,000 lbs. - 1. 30 f t ." 22,000 lbs. - 0.067 ft.
6,000 lbs. - 0.90 ft. ~ 24,000 lbs. - 0.056 ft.
7,000 lbs. - 0.66 ft. ' 26,000 lbs. - 0.048 ft.
8,000 lbs. - 0.51 ft. - 28,000 lbs. - 0.041 ft.
9,000 lbs. - 0.40 ft. 30,000 lbs. - 0.036 ft.
And the weigh:-height limi:ation for the railroad track slab at El. 301'-7" is as follows: (See p. 42 Reference 9)
Wei2h: Heicht Limitations Weicht Hei2ht Limita: ions 1,000 lbs. - 98.46 ft. 12,000 lbs. - 8.21 f t.
2,000 lbs. - 49.22.ft. 14,000 lbs. - 7.03 ft.
3,000 lbs. - 32.81 ft. 16,000 lbs. - 6.16 f t.
4,000 lbs. - 24.61 ft. 18,000 lbs. - 5.47 ft.
5,000 lbs. - 19.69 ft. ~ 20,000 lbs. - 4.92 ft.
6,000 lbs. - 16.41 ft. " 22,000 lbs. - 4.48 ft.
7,000 lbs. - 14.07 ft. 24,000 lbs. - 4.10 ft.
S,000 lbs. - 12.30 ft. 26,000 lbs. - 3.79 ft.
9,000 lbe. - 10.94 ft. 28,000 lbs. - 3.52 ft.
10,000 lbs. - 9.85 ft. ~ 30,000 lbs. - 3.28 ft.
11,000 lbs. - 8.94 f:.
The missile striking veloci5y for the 15 ten object dropped into the pool from El. 348'-0" is 28.68 ft./sec. Further analysis shows the 3/16" steel liner will be perforated and the penetration on the concrete is about 2 inches. No structural failure is detected. The depth of the concrete crack is about 52 inches. (See p'. 43-52, Reference 9) 5.0 cc::CLUSIC! S 5.1 Due to the insufficient reinforce =en: for the slab at El. 305'-0", (only #6 at 12" top and botton),(See , Reference 1), the slab a: the east and north of
! the track area is unable to sustain any object of 15 tons and less dropped from El. 348'-0". The failure of the slab along with the falling object could destroy the engineerec safeguard circui:s located right beneath the slab.
i 5.2 The 5 foot thick concrete slab at the bottom of the spent fuel pool vill have about 6 inches of solid, uncracked concrete re~aining. This 6 inches of solid concrete shall prevent the pool from immediate water leakage, l
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- l. Gilber: Associates, Inc. Drawing No. E4:1-llc.
- 2. Gilber: Associates, Inc. Drawing No. E4:1-1Ca.
- 3. " Full-Scale Tornado-Missile Inpa:: Tests", IFR: NP-640, Projec: 399, by Sandia Labora:ories, Pages 4-1 to 4-5.
- 4. "Strue: ural Dynamics" by Jchn Biggs, Chapters 2 and 5, McGraw Hill Books.
- 5. ",,,,,,.
Class Notes of C.E. 366" by C. P. Siess, University of
.......is, . c. , . .
- 6. "ACI 349-1977, Appendix C".
- 7. " Design of S: uctures for Missile I= pact", 3C-Top-9-A by 3echtel Power Corporation, 197'.
- 8. " Reinforced Concrete Structures" by R. Park and T. Paulay
- 9. Calculation Nu=ber 110lX-322C-OlS for TMI-l Cask Drop Analysis by T. H. Chang.
8.0 APPENDICES
- 1. The ic:ter f ce the U.S. Nuclear Regulatory Commission to Metropolitan Edison Ccmpany en iby 17, 1979.
- 2. Figure 1: Plar - Fuel Handling Building.
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[5, j$e I $ FUEL HANDLING BUILDING CRANE g!h 8 I
i KEY INTERLDCX SYSTEM LIMITS EBi THREE hilLE ISLAND NUCLEAR STATION LNIT.1
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ne:hanism, as veil as the fuel handling techanisms.
Tne . carriage en the main handling bridge vill have an overhung acter centrol center as shown en Sket:h ic. A and a larger censole te acec==cda e the centrels s
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ne heist er heists en the carriages vill overhang the basic stru:ture by apprer.1-
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should not appreciably affect the use of :.he plant walkvay.
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to a peny =ctereducer rat'ed 1/5 E.P. ,1500 Tt?M, L60 Velts, 3 phase, 60 cycle, "TT va '" 30 Min. 55' C. rise, Class H insulatien strip heater and extended shaft
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Eridge and carriage trucks vill be equipped with flat wheels, flame hardened, and guide rollers en (1) briise truck and en (1) carriage truck.
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wheels vill be equipped with roller bearings.
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Pcsitioning of the centrol red handling mechanis: ever either fuel transfer systen vill be by bettering cut the hydraulic sheck abscriers against shinned rail and e ,.4...&2_.. s' .a.p s . ., . s .' '. .' .. . .N. . .e, . ' . *.u... .'u a. .' b.1**...-.C"....*.-..'..'..e7.".=..' S' ..
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cperator is visually Observing the underwater cperatiens at the best vantage peint.
The centrels are interlocked, such as the bridge, carriage or heist /hcists c:.nnet be =cved sinultaneou:ly. Thr. bridge or carriage can be =cved enly when the grapples are in the full up pcsition. Full up indicating li ht,S everride, and ov =. ".* .* ^. c * .~.' .' ~ s'. ' ~.g~ .c...
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inadvertent operatiens Vhich Venid damage the fuel, contrcl reds, er crifice plus a . .n. w ... <.. . .A.,,.4,e.
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are provided.
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er fully cl: sed prier to rai:ing er lowering of the mechanica; everride and over-4 A c .4 . A. 4 ......u , . 4 . e. .4.w.
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cf the grapples is prevente'. When a specified 1 cad is reached. Override and over-4a . , a
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- - :..~...,.; = -. a 3-A lesi m:nitor vill mes:ure and display leads en the grapples. '*he moniter pr:vides .he li .iting circuits for s'2:h cable, evericad, cpening of grapple, a .'. . e s '. c ' ~".' . .* . . .h a. c i.e ," .." *..'e. ".~.
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Manual release of fuel bundle grapple vill be provided. Entire centrcl red e., ..,., . s. 4 . 3 4..s.. e .. _, .cd -- c.
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d..' *. ..e- a. .k ar. '. .e.=s vill be indicated by a mechanical drive Vecder Rect type digital readent. Stearns-Reger does not presently have this system in operatien, but feels it will ch:
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have fcund a vertical positioning syste: = cst desirable, and have therefcre, included the abcve as standard equipment.
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steel cable: and stainless steel dru=s. Sheaves vill be 27 4pH stainless steel.
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The 16 inch cuter, rotating, rigid :.act is fabricated frem spu. cast 3Ch ::ainless ma.k *.n.ed ca.. ' . " . . . O.D. T.'... va.i
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The grapple mechanisns are Oc designed se as the whole =cchanis can be re=eved by the staticn Orancs. The mechani ms can be lifted up thrcuch the sheave and reel support t0ver and taken to a remote location for insrecti:n and maintenance.
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- All starter: and. c:ntrols (cxcept Dillen lead cell and resdeut) are standard electrical store items. The design is such that a plant clectrician can trouble shoot and replace inc;crative electrical hardware, shculd the cc acien arise.
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-a-Seventy (70) fee cf air hese and electried cabic vil be provided fer festecning to the pcVer staticn. The electric cable vill also include the neces ary wires to interleck the Handling Bridges tc the Tran:fer Syste=s.
The air cnd electrice.1 connections between the bridge and ce.rriage vill be by festcening the air hose and electrical cables.
Tvc (2) 110 velt cenvenience outlets vill be provided en the cen:cle. A 110 velt circuit vill also be previded fer strip heaters in =c:crs, =ctor centrol center, and censele.
All indicating lights vill be push to test.
i All, equi) :ent will withstand ever a short peried 68 FSIG and te=perature rise to 2 "- ' f'.
The fuel bundle grapple asse=bly will be shewn en Sketches No. D and E. The fuel grapple is sc designe:i that when leaded with the fuel bundle, the fuel grapple cannot be cpened as a result of cperater errer, electrical er air failure. The lifting ff gers vill be fabricate:1 frc= 17-1.7.4 tainle's: teel, heat treated te the H-1100 ccndition. The varying elevatient at the pick up peints vill be ec=pensate:
for by the lifti .g fingers being attached to leveling believ. .
The centrol red an:1 crifice plug grapple vill be as shown en Sketch No. F.
The contrcl rod or crifice plus vill be with:frawn into a bronse machined guide as shewn en Sketch No. F. The guide vill facilitate the incertien of the centrol reci or crifice plus pins into the fuel bundle.
A running test at ficcr level cf the bridges and carriages will be dcne er Je:perary rail: prior to thc attachment of the fuel handling, and where applicable, centrcl red handlinc mechemis=s. Thic test vill pri=arily be for the checkcut of the drive =echani =s.
Folleving the running test, the carriage: vill be ec=pletely asse= bled with the applicable handling =cchanisms an:1 mounted en a ec=cn bridce which will be :ecure:i to an elevated test stand located ever a test pit which is apprcximately 15 x 15 x 15 feet. .
An extensive simulated checkcut vill be =ade en the handling mechanic ==, centrol:,
interlecks, lead sensing vertical positiening, and carriace pcsitioning. A dt=y fuel bundic, du ::y' tcp nc::le a::e=bly, dun.=y centrol red, and crifice plug is to be used for thi: test.
A detailed to:t procedure vill be sub=itted prior to any fabricatien.
"Feundatien and cutlinc
- drawings vill be provided one (1) =cnth after receipt of drawing: giving building :i:cs and elevations for the equip =cn in:tallation.
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% Mwkmed 9 LAST LCCAT*ON FREOUENCY PERFORMED MISA RB Polar Crane At Refueling 02-18-79 MISA Fuel Handling Crane C 02-07-80
- 'ISA . Turbine Bldg. North C 02-25-80 MISA Turbine Bldg. South C 02-25-80 MISA Feedwater pump Crane C 11-12-79 MISA Control Bldg. Vent Equip. Hoist C 05-19-80 MISA Pcwder Vessel Resin Crane C 05-16-80 MISA Machine Shop Crane C 02-11-80
- IS;. Machine Shop Store Recm Crane C 02-01-80 MISA Cire. <ater House Crane C 03-18-80
'MISA Headstand Jib Crane At Refueling 10-12-79
ISA Incore Jib Crane At Refueling 10-12-79 MISA East Removable Jib Crane At Refueling 10-12-79 MISA West Removable Jib Crane At Refueling 10-12-79 MISA Electric Shop Crane C 05-19-80 MISA Electric Shop 2nd Floor Crane C 02-04-80 MISA Reactor Pool Jib Crane At Refueling 10-12-79 MISA-18A- Screen House Trasn Hoist C 07-14-80 MISA-188- Screen House Trash Hoist C 07-14-80 MISA Feed Pump Area Hoist same As MISA-5 Deleted MISA Chemical Addition Room Crane C 12-26-79 C - seci annual AI/SR No. 800253 Response Attachment 1
$AP w %Mw wN~ R LAST LOCATION FREOUENCY PERFORMED MISA RB Polar Crane At Refueling 02-18-79 MISA Fuel Handling Crane C 02-07-80 MISA Turbine Bldg. North C 02-25-80 MISA Turbine Bldg. South C 02-25-80 MISA Feedwater Pump Crane C 11-12-79 MISA Control Bldg. Vent Equip. Hoist C 05-19-80 MISA Powder Vessel Resin Crane C 05-16-80 MISA Machine Shop Crane C 02-11-80 MISA Machine Shop Store Room Crane C 02-01-80 MISA Cire. Water House Crane C 03-18-80 MISA Headstand Jib Crane At Refueling 10-12-79 MISA Incore Jib Crane At Refueling 10-12-79 MISA East Removable Jib Crane At Refueling 10-12-79 MISA West Removable Jib Crane At Refueling 10-12-79 MISA Electric Shop Crane C 05-19-80 MISA Electric Shop 2nd Floor Crane C 02-04-80 MISA Reactor Pool Jib Crane At Refueling 10-12-79 MISA-18A- Screen House Trash Holst C 07-14-80 MISA-18B- Screen House Trash Hoist C 07-14-80 MISA Feed Pump Area Hoist same As MISA-5 Deleted MISA Chemical Addition Room Crane C 12-26-79 C - semi annual AI/SR No. 800253 Response Attachment 1 81022 a o 375 p