ML20010F605
| ML20010F605 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 08/24/1981 |
| From: | Hess R, Hollenbacher R, Katterhenry A NUS CORP. |
| To: | |
| Shared Package | |
| ML20010F599 | List: |
| References | |
| RTR-NUREG-0612, RTR-NUREG-612 3874, NUDOCS 8109100416 | |
| Download: ML20010F605 (82) | |
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Project No. 5484 NUS Report 3874 THE CONTROL OF HEAVY LOADS AT CRYSTAL RIVER-UNIT NO. 3 NUREG-0612 SIX MONTH 3.T PREPARED FOR FLORIDA POWER CORPORATION
! August 24, 1981 f
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6.14. %y da Prepared B Approved By R. H. Hollenbacher A. Katterhenry Project Engineer Project Manager i
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.j Reviewed By
.. R. W. Hess i
Manager, Plant Engineering O
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TABLE OF CONTENTS f
Section 1 - Introduction i
l Section 2 - Identification of Overhead Handling Systems i
l Section 3 - Justification of Excluded Overhead Handling Systems Section 4 - Evaluation of Load Handling Systems
{ Section 5 - Lif ting Device Compliance with ANSI N14.6-1978 and ANSI B30.9-1971
?
Section 6 - Verification of Testing and Inspection l
Section 7 - Verification of Crane Design 3
Section 8 - Operator Training, Qualification and Conduct i
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LIST OF TABLES 2-1 Crystal River Unit 3 Containment Building Load Handling Systems 1
1 2-2 Crystal River Unit 3 Auxiliary Building Load Handling Systems 2-3 Crystal River U:iit 3 Turbine Building Load Handling Systerr .
2-4 Crystal River Unit 3 Miscellaneous Structures Load Handling Systems l
4-1 RCCR-1/ Polar Crane Loads 4-2 FHCR-7/ Missile Shield Gantry Crane and SFHT-7/ Spent Fuel Pit Gate Hoist Loads 4-3 FHCR-5/ Auxiliary Building Crane Loads h-4 RCCR/2 Reactor Vessel Tool Handling Jib Crane Loads i
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l i LIST OF FIGURES i
i 4-1 Through 4-30 Load Path Diagrams 4
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O Section 1 Introduction To implement the recommendations of NUREG-0612, " Control of Heavy Loads at Nuclear Power Plants," the USNRC sent a letter dated December 22,1930 to all licensees of operating nuclear power plants. This letter requested that the Florida Power Corporation implement certain interim actions as soon as possible and submit a two-part report documenting the results of a review of the Crystal River Unit 3 Nuclear Plant relative to the guidelines of NUREG-0612. This report, the first of two parts, provides the general information requested in Section 2.1 of the Decamber 22, 1980 letter and describes the Florida Power Corporation's ongoing efforts on the control of heavy loads. The second part of this report, providing information requested in Sections 2.2 through 2.4 of the December 22,1980, letter, will be the 9-month submittal.
The subsequent sections of this report are structured to directly respond to the requests for information in Section 2.1 of the December 22, 1980 letter. The paragraphs under the heading " Requested Information" will reiterate NRC questions and the following " Response" will discuss the results of the Florida Power Corporation's review effort.
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1-1
O Section 2 Identification of Overhead Handling Systems REQUESTED INFORMATION:
Report the results of your review of plant arrangements to 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 structural analysis).
RESPONSE
All load handling systems in the Crystal River Unit 3 plant were reviewed to identify the load handling systems in accordance with the December 22, 1980, letter. Tables 2-1 through 2-4 provide a detailed listing of the load handling systems in the containment, auxiliary, turbine and other miscellaneous structures respectively. -
The criteria used to identify the overhead handling systems of concern included:
- 1. The handling system must meet the definition of an Overhead Handling System as defined in NUREG-0612.
2
- 2. The overhead handling system rated lifting capacity is greater than 1000 pounds. This criteria is more conservative than the " heavy load" criteria defined in NUREG-0612, i.e. a spent fuel assembly and its ll handling tool, which is 2750 pounds for Crystal River Unit 3. The l additi2al conservatism was included to take into account the drops of I smaller loads which could potentially havt 8gh impact energies.
[*I
, .1 1 3. The travel path of the overhead handling system can pass over safe shutdown equipment, required for the reactor modes in which the load
.of) handling system can conceivably be operating, over spent fuel or l
l equipment required for safe shutdown or decay heat removal.
2-1 l-l L.
The overhead handling systems identified with this criteria in each area are:
C_cyainment Building Reactor Building Polar Crane RCCR-1 Reactor Vessel Tool Handling Jib Crane RCCR-2 incore Instrument Container Hoist ICHT-3 Reactor Building Mechanized Scaffold Mechanized scaf fold for tendon surveillance Auxiliary Building Auxiliary Building Crane FHCR-5 Spent Fuel Pool Missile Shield Crane FHCR-7 Spent Fuel Pool Gate Chain Holst SFHT-7 Turbine Buildirg None Miscellaneous Structures Intake Gantry Crane CWCR-1 The Reactor Building Polar Crane (RCCR-1), manufactured by the Whiting Corporation, is rated at 180/30 tons for the main and auxiliary hoists, respectively.
The hook travel limits on the crane enable the main hook to be brought to within 9 feet 2 inches of the bridge rail (closest approach) and the auxiliary hook to be brought to within 7 feet 5 inches of the bridge rail (closest approach). The centerline to centerline spacing of the main and auxiliary hooks is 4 feet 4 inches.
i l The reactor vessel tool handling jib crane (RCCR-2) is a Shepard Niles monorali ',hoom)
, l underhung crane supported from a hinged pivot point located 19 feet south and 36 feet
-] east of the containment building center lines. The total length of the monorail is 38
< ! feet with 34 feet available for trolley travel. The electric hoist has a 2-1/2 ton load capacity.
2-2 e
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O The incore instrument container hoist (ICHT-8) is a hand operated,1-ton capacity chain hoist on a push-type trolley suspended from a monorail on the 176 foot elevation over the incore instrument area. The hoist, which is attached to the trolley by a hook, is equipped with a Weston type mechanical load brake. The maximum load lift height is 45 feet.
! The reactor building mechanized scaffold, consisting of a carriage group, platform group and parking brace group, is a Sky Climber, Inc., mechanized scaffolding system which traverses the exterior perimeter of the reactor building. In addition to the work platform, a bridge crane is suspended from the platform trolley. This bridge crane is used to handle a work cage used to raise and lower two workers from ground level to the work platform and to suspend a 5-ton capacity hand geared trolley type electric chain hoist.
The auxiliary building crane (FHCR-5), manufactured by the Whiting Corporation, is a traveling bridge crane rated at 120/15 tons capacity on the main and auxiliary hooks respectively. This crane does not travel over spent fuel pool "A" and is equipped with a system of track limit switches which prevent the movement of the main hoist block over spent fuel pool "B." A 2 ton hoist has been added to the bridge to handle new fuel assemblies. This hoist is only used over the ne,w fuel storage area.
The spent fuel pool missile shield crane (FHCR-7) is a single-leg gantry, deck-leg crane with a 10-ton capacity hoist suspended monorail fas5 on from a single 24-inch bridge girder. The crane travels the legth of spent fuel pool"A."
.1 The spent fuel pool gate hoist is a 2-ton capacity hand operated chain hoist suspended y from a monorail over spent fuel pool "A." The hoist is equipped with a Weston type mechanical load brake and has a maximum load lift height of 36 feet. It is anticipated that this hoist will be replaced with an electric motor operated hoist prior to the third
, l refueling outage.
Il The intake gantry crane is a 50-ton capacity through-leg gantry crane manufactured j by Whiting Corporation. The gantry structure is 52 feet high with an 89-foot span and j' ] a 16-1/2 foot cantilever section. The maximum crane capacity while operating on the i cantilever section is 12 tons. The crane is located at the circulating and service water intake structure.
2-3
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U TABLE 2-1 CRYSTAL RIVER UNIT 3 COIRAINMEtC BUILDING LOIS HANDLING SYSTEMS
' ~
g l l t 1 8
- Description a B 8 l l l or Tag l Function ! Location Exclusion Remarks 8
Number j l l a 8 8 8 ' '
. s s 8 '
I I 1 8' 8 l RCCR-1 l Polar crane ! Elevation 245' ! No ! 180 ton main hoist I l
8 8 l l 30 ton auxiliary hoist !
- 1 1 1 I I e i t i 1 8 l 4 I e 8 '
s I I I 8 I
- RCCR-2 j Reactor vessel Pivot is 19' South No l 2-1/2 ton capacity hoist l l l l : tool handling i and 36' East of I i 8 l l jib crane l building center l l !
- e i lines 8 8- 8 3 1 1 1 I I I
.I I 3 I '
. e i i I w a I ' '
s , a i 1 8
- i FHCR-1 i Main fuel handl- : Elevation - 160' I Yes 1 l
, j l ing bridge l l l Not an overhead handling system a g i 1 1 8 8 e i I 8 8 l
l 1 i i i I l
FHCR.-2 l Aux fuel handling l Elevation - 160' l Yes ! Not an overhead handling !
g a bridge 1 l system l .
l l e 8 3 8
. . e t I 3 i i e i i I i I I I '
FHCR-4A : Interconnecting i Elevation - 125' 7" I Yes 8 Not an overhead handling l l l fuel transfer l l i
- system I l l system j l l
- l. I I 8 8 e a j 1 8 i : 1 I 8 l l 1 1 I I'
- DRCR-1 CRDM Jib Crane Elevation - 238' I Yes i 1 ton capacity hoist /does l
l l l l ! not pass over safe shutdown i 8
l l l l equipment !
i I 8 8
- 1. I i I I i
.a.....
O -
O TABLE 2-1 (Cont'd) 4 CRYSTAL RIVER UNIT 3 CONTAINMEtTI BUILDING IDAD RA! CLING SYSTEMS 1 I I I I I Description i I I i 1 l or Tag l Function ! Locatioa. ! Exclusion l Remarks B l Number l l l 8 l 8 1 1 I ! !
FHX-SA Handling and N/A Yes Not an overhead handling j and 5B l transfer sling l l l system l ,
e i i I I I i s i I I I I ,
e i s u -
- e i i e i I j ICHT-8 I Incore instrument j Elevation - 160' 8 No 1 1 ton chain hoist with l l container removal l I i trolley for monorail I a
j j l lI service l 8 a l '
I I I I I I
! l l 1 i l
{ l NICR-1 8 Incore instrument l
Elevation - 177' l Yes j 1/2 ton capacity system l i jib crane i l I i I I I , 1 I I I I I I I I 4 I I I I I I i
- ; ; ; e - 1 I
I I I I I I i i i 1 1 1 I l Mechanized l Reactor building l Reactor building l No l Mechanism is capable of l 8 scaffold I tendon surveil- I roof edge i I traversing entire circum- 1 l l lance ! ! I ference of the reactor ! ,
l building 8
j j l l s I I I I I I I I I I I I I I I i l i I i i l I I I I I I I i i I i 1 I I I I I I I I I I I I I I I i 1 1 I I I I I I I i 1 1 I I I I I 1 8 8 8 I I I I I I I
, I 1 I I I I j i i 1 1 I I I I I I I I I i l i i i 1 1 1 4 1 1
~.J TABLE 2-2 f CRYSTAL RIVER UNIT 3 AUXILIARY BUILDING LOAD HANDLING SYSTEMS 1 I 8 8 8 1 Description I i I 8 8 l or Tag l Function l Location l Exclusion ! Remarks !
l Number j l l l l 3 e I i I 8 g g g a 6 i
- 1 I I I I 3 8 i I 8 8 1 FHCR-3 : Fuel storage i Elevation 162' I Yes a Not an overhead handling I l l handling bridge l l l system !
1 I I i 8 8 1 1 '
I e a 8 I i j FHCR-4B Interconnecting Elevation - 125' 7" Yes Not an overhead handling l l l l !
a fuel transfer I e i system 8 l l system l ! ! O I I e 1 8 I 8 1 ' !
1 , . .
1 I I I I 8 y l FHCR-5 l Refueling crane l Elevation 193' 7" l No l 120 ton main hoist !
- I i a 1 a 15 ton auxiliary hoist l
l l ! ! ! 2 ton auxiliary hoist i 1 1 : I 8 8
. . I ; : ' ' '
1 1 1 I I I 3 l FHCR-6 l Newfuelelevatorl Elevation - 162' l Yes ! Not an overhead handling !
I I assembly 8 l l system !
I i 1 8 8 '
I g 3 i i I e . i : - 8 I g 3 3 1 8 I I 8 8 8 l FHCR-7 l Spent fuel pool l l 1 8
l Hissile shield 8 Elevation 143 l No j 10 ton 1 a crane I 8 8 e i I 1 I I I l I g
I 8 8
! ! l
! i i i 8 8 e i I 8 8 SFHT-7 Spent fuel pool l l
8 l Elevation - 160' l No l 2 ton chain hoist with 1 1 : gate 1 I trolley for monorail
? l l l l l l service I
_ n --... -. - . . .
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J TABLE 2-2 (Cont'd)
CRYSTAL RIVER UNIT 3 AUXILIAM In" .311. _ TDAD li.U.:2LIEG SYS18..3 8 I I I I I I Description i I I I I l or Tag l Function l Location ! Exclusion l Remarks 1 I
Number l l l l l 3 I I I I I i i i i i i 8
SFHT-17 and l Spent fuel pool l Elevation - 158' l Yes l 1/2 ton capacity system l l
SFHT-18 l filter cartridges j j l l 8 1 1 I I I l l l i I I
- ! ! n a , , _ i ..
3 I I I I i
! l 8 8 8 8 1 l WDCR-1 l Waste drumming l Elevation - 134' l Yes l Sufficient physical !
l 1 area crane l
8 l separation exists l
' I I I I I I
! ! ! l l ;
, i I i i i i l a l 1 1 I i
Y
" ! WDCR-2 l Waste drumming l Elevation - 134' I Yes ! 3 ton capacity hoist with I l l area monorail l l l t.rolley; sufficient l t I hoist i I I physical separation exists I e i I I I I I 1 1 I I I
! ! ! ! l 1 I I I I
i I
i I
l WDHT-15 l Evaporator con- l Elevation - 119' l Yes l 1/2 ton capacity system !
j j densate deminer- l 1
l l 8 3 alizer filter i i e i
- l j cartridge l l l l l l 1 1 1 I l l 1 1 I I I I i i I l l 8 T~~ s I i i l I I I
, I I I I I I l MAC1-1 i Hot machine shop I Elevation - 124' I Yes I Sufficient physical 3
- l. l crane l. (hot side) l. l separation exists 8
. e e i i a 1 i I
, 1 I I I I I i 1 1 I I I I l
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TABLE 2-2 (Con 'd)
CRYSTAL RIVER UNIT 3 AUXILI A eY B'Jil.JIt.~ 1. dan it/ LOT.ItJG SYSTt:G l I I I I I i Description I I I I I l or Qg ! Function l Location ! Exclusion ! Remarks !
l Number j l l l l l e i e i I
. i . t i ;
I I I I I I l MACR-2 l Clean machine i Elevation - 124' ! Yes ! Sufficient physical !
I l shop crane l (clean side) l l separation exists !
I i i 1 8 I I I I I I I l i i , , ---- ;
I $ 1 8 I I
, j MUHT-ll I Make-up and puri-l Elevation - 130' l Yes l Suf ficient phy::ical l I I fication prefilter i i I separation exists I i 1 l 1 I I
! ! ! ! ! l i i i i i I
, l MJHT-14 l Make-up and puri- ! Elevation - 129' l Yes l 1/2 ton capacity system !
P
- l and 15 l fication filter 8 l l l 1 e cartridges a .
I I I I e i I I I I I I I
.I I. a 3 i e i i i e 1 8
, ! Monorail ! Equipment hatch ! Elevation - 105' ! Yes ! 12 ton capacity monorail; !
I l H1 l l l sufficient phy'.ical !
l i j i j j separation exf.ts l I l 8 I I i
! ! ! ! ! l
' t i I I I - I s Monorail i Equipment hatch i Elevation - 105' I Yes i 12 ton carp;1 y monorail; I l l H2 l l l suffici nt physical !
l 1
l l l separation er.ists 8 1 1 1 8 1 I e a I [ t I I I I I 3 3 1 1 I I I I Monorail l Equipment hatch 8 Elevation - 138' 9" I Yes I 10 ton capacity monorail; I l l H3 l l ! sufficient physical !
l 8 I l l separation exists l 1 1 I I I I I I I I I I
.. . m .. ~ a .
V v TABLE 2-2 (Cont'd)
CRYSTAL RIVER UNIT 3 AUXILIt.L Y isali..;II. I.07,1) Im:.DLIt!G SYSTr G i e I i I I i Description i i e i I 4 l or Tag l Function l Location ! Exclusion ! Remarks !
l Number 8 l l l l 8 I I I ! !
I i i i i i l Monorail l Prefilters 1
l 8
Elevation - 138' 3" !
I Yes ! Associated with MUHT-ll I I I I i 1 1 I I I I I i i s s e i i 8 l l l 1 0 I I I i 1 8 1
- Monorail i Resin trap and 1 Elevation - 136' I Yes 8 Associated with MUHT-14 and 8 l l purification ! ! ! MUHT-15; 1/2 ton capacity !
l 1
l filters I
l i
l 1
l system 8
l 8
4 I I I I 8 l l l l B 3 e i Monorail i Spent fuel I Elevation - 158' 10" I Yes i Associated with SFHT-17 and 8 l l coolant filters !
! ! 18; 1/2 ton capacity system !
I e i e i I i- 1 I I 1 1 1 <
i i i I 8 j i i i i i !
1 l 1 1 1 I 8 l
Mmorail l Waste drumming 8 Elevations - 234' 8 Yes l Associated with WDCR-2; 3 l l
a area e and 136' 6" e i ton capacity system; suf- 8 l l l l l ficient physical separation !
l 8 exists l
! l l 8 9 1 1 I I i e a I I I i l 8 1. I 1 e i l I I i
! Monorail l Turbine and motor ! Elevation - 108' ! Yes ! Associated vith EFHT-3 and 4; !
8 l driven emergency l l l sufficientphysicalseparationl e i feed pumps 8 : I exists assuming hoist is used 8 l l l l l only when its EFP is out !
8 l l l l of commission (00C) l 8 I e 8 8 4
l l l 8 1 1 1 1 1 8 8 8 i
s l C Q )\
TABLE 2-2 (Cont'd)
CRYSTAL RIVER UNIT 3 AUXIll? i . I; )l' r otn s.I: al.fNG SY ' '
I I I I i 1 1 reescription I i 1 1 1 l or Tag l Punction l Location ! Exclusion ! Remarks l l "u=ber l l l l l t 1 1 1 1 8 i i i i i i I I 1 1 I I 1 1 I I I I l EFiiT-3 l Motor driven l Elevation - 95' l Yes -l 3 ton capacity chainhoist l 1 emergency feed I 8 with trolley for manual j l l i i pump 1 1 I service; sufficient 1 l l l l l physical separation exists l 8 1 i i I I i i 1 1 1 8 8
8 l
}___ -
. j i I ,
I I I I I I i 1 1 Y I EFHT-4 i Turbine driven i Elevation - 95' I Yes i 2 ton capacity chainhoist I o l l emergency feed l l l with trolley for monorail !
l l pump l
- l 8 servicel sufficient l 1 1 1 1 1 physical separation exists 1 I i 1 1 1 1 1 1 1 1 1 8 1 1 1 1 1 1
- : ; & : I 1 1 1 1 1 8 1 1 I I I I l Chainhoistsl Decay heat equip- l Elevations - 95' and l Yes l 10 ton capacity chainhoist l 8 1 ment removal 1 119' i 1 with trolley for monorail 1 l l l l l servicel sufficient !
l l l l l ' physical separation exists l 8 1 1 1 1 1 4 8 i i 1 1 I i l I i 1 1 1 I I I :
I I i 1 1 1 1 I I I i 1 I i 1 1 1 1 1 I i 1 8 8 1 1 I I I I I I i 1 1 1 8 1 1 1 1 1 1 1 1 I I i 1 1 1 1 1 I I I i 1 I I i 1 1 1 I i 1 8 1 1 1 1
(~)
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TABLE 2-3 CRYSTAL RIVER UNIT 3 TURBINE BUILD"IG LOAD IIANDLING SYSTEMS e e i 8 8 i Description I l l l l or Tag l Function l Location i Exclusion : Rer. arks l Number j l l ! !
- : e i ! !
l TBCR-1 l Turbine building l Elevation - 145' l Yes i 160 ton main hoist i j crane 8 l l 30 ton auxiliary hoist l e a i See Section 3 8 g i e I i I e a 8 e
- i e -]I ' __-_
l s TBHT-9 i Turbine room vent i Elevation - 119' Yes 8 1 ton cleinhoist with l l l fans ! ! I trolley for mono' rail a 8
j 8 l : service; sufficient !
i 8 physical separation exists j l l- ._
8 l
l i TBHT-10 Turbine room vent i Elevation - 119' l Yes l 1 ton capacity with trolley l Y l l fans ! I i for monorail service; suf- 8 U j l l l ! ficient physical separation !
- exists l l l l l
, , , g--- ,
j Monorail Water box removal l Elevation - 116' 7" l. Yes l Total of six monorails; !
l i a t 8 sufficient physical l l l l ! I separation G iats 1
l
? ! ! ! . i Monorail l Feedwater booster Elevation - 95' ! Yes ! Total of two monorails; I pumps sufficient physical l l l l :
j j j separation exists l
l l l i l - --
j Monorail i Main feedwater 11evation 166' 10" l Yes j 6 ton capacity hoist; suf- !
l I pumps a e 8 ficient physical separation l l l l l exists s
- ; * ' -__ l l Jib crane l General purpose l I
Elevation - 145' l Yes ! 2 ton capacity hoist; suf-8 lifting l ficient physical separation i l l i e i i exists 1 i e i I '
O) u hi v
TABLE 2-4 CRYSTAL RIVER UNIT 3 MISCELLANEOUS STRUCTURES LOAD HANDLING SYSTEMS
- Description i 8 l or Tag l Function l Location Exclusion Resarks s
"""b
- l. l. l l l l
- ; i Monorail Control complex Control complex Yes Associated with ICHT-2;
,8 ,
l l servicing l 304-G; elevation - i e sufficient physical 8 l
8 183' 10" l separation exists l
I I I
' l ~~ ~
e l: l l ! i l
Monorail Penthouse roof a Control complex; I Yes 8 Not an overhead handling l
l l slab 1
l 8
elevation - 195' !
I l system l Y l
, y1 Trolley l Penetration area l Intermediate build- Yes i Total of four 2 ton capa- I Rails 1 ing 308.H and 309-F; I l city rails; sufficient l l elevations - 128' 4" a j physical separation exists l l l l and 129' l l e i i I l
' ' i l l , s- ! ---
j i I 8 8 I j
I j Chainhoistsl Penetration area l Intermediate build- l Yes l Total of four 2 ton capa- g
- i e ing 308-H and 309-K; e 8 city chainhcists; suf-j 8 l l elevation 119' l ficient physical separation
! i 1 e a exists l e i i 1 8 i i i 1 8 e
. 1 I g r =
,i l 1 I I a EGHT-5 and li Emergency dit . 'l I Emergency diesel Yes 8 2 ton capacity chainhoist l !
l EGHT-6 l generator service ! generator building i i with trolley for monorail 1
300-P; elevation - l l l l l service; sufficient i e i i 119' i 8 physical separation exists l l l l ! e assuming diesel OOC when j j j i
- I l l hoist used j 1 I 8 8 I i 8 I I i 4
O O TABLE 2-4 (Cont'd)
, CRYSTAL RIVER UNIT 3 MISCELLANEOUS STRUCTURES LOAD HANDLING SYSTEMS
! I I I I I I I Description i I ' 8 '
' l or Tag l Function l Iocation l 5 clusion 1 Remarks 8 l Number j l l l l I i i I ! !
1 I 6 6 I 1 l ICHT-2 l Control complex l Control complex l Yes ! 4 ton capacity chainhoist !
l l service l 304-G; elevation -
l l with trolley for monorail l 8 8 8 164' 1 I service; sufficient I l l l l 1 physic.nl separation exists !
I I I I I '
8 I I I I I l I i i i i l
Monorail l Emergency diesel l Emergency diesel l Yes l Associated with EGHT-5 and l 8 1 generator service I generator building i I 6 sufficient physical l
! se;paration exists assuming 1
$l w l 1
I l
1 I
I l
l I
i 300-P; elevation -
141' I
l 1
l I
1 the diesel generator is OOC when the hoist is used I
l 1
I I I I I I 1 l ! '
L i I I I I I I I I CWCR-1 l Intake gantry i Intake structure ! No i 50 ton capacity system !
l l crane l l l l 8 8 I I a l l I I i 1 I
! I I I i i I i
i i l 1 I 8 I I I I I I I I I I I I I I i 1 8 8 1 1 I I I I I I i 1 1 I I I I I I I I I I i l 8 I I i 1 8 I I I I I i 8 i l i i i i I I I I I I I a i i l I e i I I I I I I I I 1 8 I I I I I I I I I I I I I I 8 1 1 I I i 1 1 I I I I I i 1 I
a b
V section 3 Justification of Excluded Overhead Handling Systems REQUESTED INFORMATION:
Justif y 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
The cranes excluded from the list in Section 2 have all been excluded from consideration because they did not meet the criteria listed in Section 2. Therefore, the reasons for justification of excluding these cranes are simply stated as follows:
- 1. Does not meet the NUREG-0612 definition of an overhead handling system.
- 2. The rated capacity is less than or equal to 1000 pounds.
- 3. The handling system path of travel does not pass over or near safe shutdown or decay heat removal equipment or spent fuel.
The justification for the exclusion of most handling systems is succinctly described in the remarks column of Tables 2-1 through 2-4. Additional explanations, however, are necessary for the main fuel handling bridge, the auxiliary fuel handling bridge and the turbine building crane. Both the main and auxiliary fuel handling bridges handle no loads greater than the weight of a spent fuel assembly and its associated handling tool. Since these load drops have already been addressed in the Crystal River FSAR, they need not be reconsidered under NUREG-0612.
O b
3-1 l.
t
. . _ _ _ - _ . . _ - _ _ ~ _ - . _ . _ . . . ._ _ . . _ - . . - - _ _ . = . _ _ -
l l
i i
I i '
O The turbine building crane was excluded from the list because it does not travel f over safe shutdown or decay heat removal equipment. It is noted that the bus bar
{ from the startup transformer to the 4160 KV essential switchgear located in the
- control building passes through the turbine building near the main equipment
, hatchway. While this is the preferred power source for safe shutdown equipment, j
j the transformer, and the bus bar are not classified as safety-related. Alternate sources of power exist through separate circuits from Unit I and 2 and the j emergency diesel generators. There is also a suction line running from the main
- condenser hotwell to the auxiliary feed pumps. However, the condensate storage tank is the primary source of water for the auxiliary feed system and the condenser i hotwell is not considered safety-related.
1 l
} As part of the Florida Power Corporation's comprehensive program designed to implement the interim actions addressed in Enclosure I to the December 22,1980, letter, testing, maintenance and operating procedures and an operator training J program have been developed for the turbine building crane. While not defining any safe load paths, the operating instructions for the turbine building crane da j designate exclusion areas (see Figure 4-8) where load handling operations should be l kept to a minimum and where additional precautions should be taken.
.I
)
s I
i
~
l l
- O 3-2
h O
d b Section 4 Evaluation of Load Handling Systems REQUESTED INFORMATION:
With respect to the design and operation of heavy-load-handling systems in the containment and the spent-fuel-pool area and those load-handling systems identi-fled 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:
i a. Drawings or sketches sufficient to clearly identify the location of safe load paths, spent fuel, and safety-related equipment.
- 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 weight, its designated lif ting 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.l(2).
RESPONSE
To implement the interim actions descrked in Enclosure 2 to the December 22, 1980 "Eisenhut" letter, Florida Power Corporation has developed a comprehensive load handling program for Crystal River Unit 3. To rpecifically address the issue of controlling heavy loads, the program has consisted of three distinct phases:
- 1. Identifying heavy ioads which could be handled over spent fuel or equipment required for safe shutdown or decay heat removal (Tables 4.1 through 4.4).
I O
u 4-1 1
O 2- oeti"i"8 ie d 9 t" ' < these ie d 8 "dit"8 aer tie" te veio er ->"i-ize the time of load travel over spent fuel or equipment required for sale shutdown or decay heat removal. (Figures 4-1 through 4-30).
- 3. Developing crane operating procedures and an extensive operator training program to ensure that load handling operations follow the defined load paths.
It is planned that this program will be fully implemented prior to the third refueling outage. Information obtained from the analyses made in conjunction with the 9-month report as well as operations and maintenance comments are intended to be factored into the operating procedures and training program as they become available.
The following paragraphs discuss the loads, load paths and load handling procedures for the cranes of concern identificd in Section 2.
REACTOR BUILDING POLAR CRANE The defined heavy loads for the polar crane are listed in Table 4-1. Each of these loads is controlled administratively by applicable refueling or maintenance procedures and by the polar crane operating procedure, " Operation of the Reactor Building Polar Crane", which identifies the load paths for each load. It is noted that due to the concern for load handling operations around the reactor vessel, the heavy load definition used in Table 4-1 was expanded to include loads whose cumulative weight when added to the weight of 800 pound crane auxiliary hook and
, bottom block assembly equaled approximately 1000 pounds. The following para-graphs discuss the information provided in Table 4-1 and the polar crane load path figures.
Three, 26 ton missile shields are normally placed over the reactor vessel and supported from the D ring walls at elevation 180 feet. In maving these missile i
shields to their laydown area along the west wall of containment, care is taken to keep the edge of the missile shield over the D ring wall so that any load drop would be onto the wall rather than the reactor vessel or refueling canal. As the missile
/*3 shields leave the D ring wall heading west they are lowered to the 160 foot l
Q 4-2 l
4 .
elevation floor. A 10 inch decay heat return line and the 14 inch core flood line are located at elevation 112 feet directly west of the D ring wall. Figures 4-9, 4-15 and 4-16 show this load path.
The seven pressurizer missi!e shields, maximum weight of 15 tons, are supported by the D ring wall at the ISO foot elevation above the pressurizer. These shields are moved off the D ring wall, lowered to the 160 foot elevation floor and then moved to lay down area along the west containment wall. Care is taken to avoid the possibility of allowing the pressurizer missie shields to rotate and fall on the pressurizer and reactor coolant system piping. Leaving the D ring, one of the two pressurizer missile shield load paths passes over core flood piping and the 12 inch decay heat return line at elevation 112. Figures 4-9, 4-15 and 4-16 show the pressurizer load paths.
Handling of the stud tensioners, stud handling tools, studs, alignment studs, stud support spacers, stud hole seal plugs, control rod drive cooling water header spool pieces and the triangular service structure piatforms a!! takes place while the head is on the reactor vessel. Aside from passing over the reactor vessel, these loads are carried above the 160 foot elevation floor and all pass over the decay heat return line located west of the D ring walls, at elevation 112 feet. Figures 4-10, 4-11,4-16,4-19,4-20 and 4-21 show these load paths.
The refueling cavity seal plate can be installed when the head is either on or off the reactor vessel although it is normally installed with the head on the reacto.-
vessel. Because the seal plate can not impact spent fuel, the only drop targets are the reactor vessel primary coolant piping and the decay heat return line west of the D ring walls at elevation 112. Figure 4-20 shows the load path.
The fuel transfer tube covers are unbolted from the transfer tube flanges at the east end of the refueling canal and moved to storage. The flanges can pass over a 10 inch core flood line located under the refueling canal. The load path is shown on Figures 4-11 and 4-19.
O 4-3
q U The head lif ting pendants are normally pinned to the reactor vessel head and internals lif:ing device for transport fram the laydown area to the reactor vessel head but can l>e hanoted separately and first pinned to the head. The reactor vessel head and internals handling fixture is pinned to the main crar.e hook and lif ted over the auxiliary fuel handling bridge to the reactor vessel where it is pinned to the head lif ting pendants. Possible load drop targets e,re the 10 inch decay heat return lines and core flood I;nes located west of the D ring wall at elevation 112 foot, the reactor vessel, and primary coolant piping located under the refueling canal.
Figures 4-11 and 4-23 show the load path.
The reactor vessel head and lifting rig weighs approximately 160 tons. It is lif ted off the reactor vessel flange to an elevution high enough to clear the guide studs.
Then it is moved west and raised to approximately the 172 foot elevation to clear the auxiliary fuel handling bridge before being lowered to the 160 foot elevation floor and placed on the head stand. The reactor vessel, primary coolant piping under the refueling canal and the 10 inch decay heat return and core flood lines are all possible targets. Figures 4-11 and 4-17 show the load path.
The internals handling fixture is pinned to the reactor head and internals lif ting fixture (tripod sectios.: and moved as a unit from the internals handling fixture laydown area to the reactor vessel to remove the plenum. Possible load drop targets include the 10 inch deuy heat return line, primary coolant piping located under the refueling canal and the reactor vessel. Figures 4-10 and 4-23 show the load paths.
The indexing fixture and associated equipment is pinned to the reactor vessel head and internals lifting device and moved from its laydown area to the reactor vessel flange (plenum removed). The combined assembly weighs approximately 12 tons.
Along the load path, possible load drop targets include the decay heat return line, the primary coolant piping under the refueling canal and the reactor vessel and core. Figures 4-10 and 4-23 show the load path. .
The plenum is lif ted from the reactor vessel and moved to the internals storage stand at the west end of the refueling canal. Possible load drop targets are the reactor vessel, spent fuel, and primary coolant and core flood (decay heat removal) system piping located under the refueling canal. Figures 4-11 and 4-17 show the load path.
4-4
O The internals stand is moved the length of the refueling canal passing over the reactor vessel with the head on. Possible load drop targets are primary coolant piping and the core flood (decay heat) piping located under the refueling canal and the reactor vessel. Figures 4-11 and 4-24 show the lead path.
The plenum and core barrel can only be moved when the core is unloaded, Figure 4-
- 17. Therefore, no possible load drop targets exist.
The specimen container is moved from the specimen storage stand located near the reactor vessel head storage area to the refueling canal near the reactor vessel flange. Possible load drop targets include the decay heat return line and primary coolant piping located under the refueling cavity. Figures 4-11 and 4-17 show the load path.
The 50 ton reactor coolant oump motors can be removed for maintenance while the core remains in the vessel. The motors must be lif ted from elevation 140 feet over the top of the D ring wall at elevation ISO and then lowered tc' the 160 foot elevation floor and moved to the maintenance area. Possible loaJ drop targets include the reactor coolant pumps, reactor coolant piping and, in the case of pump B1, the single,12 inch decay heat suction line. The load paths are shown on Figures 4-10 and 4-18. The reactor coolant pumps are removed along the same load paths as the reactor coolant pump motors and pass over the same load drop targets.
The control rod drive modules and components can be removed from the reactor vessel head while the head is either on the vessel or at the head storage area. Load drop targets include the reactor vessel primary coolant piping under_ the refueling canal and decay heat piping west of the D ring wall at elevation 112 feet. Figures 4-11,4-16 and 4-22 show the load paths.
Miscellaneous parts and/or components of the refueling machines and fuel transfer carriage and upender can be moved by the polar crane. A possible load drop target is the decay heat return and core flood lines at the 112 foot elevation. Figures 4-10 and 4-24 show the load paths.
O 4-5
O Floor hatch covers are stored adjacent to the hatch and are not moved over safety related equipment.
The ISI tool, ARIES, is moved into the containment in crates and assembled. It if used for periodic inspections of the reactor vessel and, while it is mainly used when the core is removed, it can be used to inspect the upper reactor vessel nozzles with fuel in the core. The ISI tool is moved from the asserr bly area to the reactor vessel flange. Possible load drop targets include the decy heat return line at elevation 112 feet, primary coolant piping under the refueling canal the reactor vessel and spent fuel. Figures 4-10,4-22 and 4-24 show the load path.
The east ladder cage must be removed from the east and of the refueling canal to permit storage of the plenum and core barrel. A possible load target is the decay heat removal / core flood piping located under the cavity. Figures 4-11 and 4-19 show the load path.
The crane main hook and bottom block assembly and auxiliary hook and bottom block assembly are both considered as heavy loads. With a hook centerline to hook centerline distance of 4 feet 4 inches, both hooks can be over the reactor vessel at one time. All safety equipment in containment required during crane operation and spent fuel can be considered as a load drop target.
Although not a routine practice, it is possible that the polar crane can require a load test. The safe load test area designated for this test is shown on Figure 4-14.
REACTOR VESSEL TOOL HANDLING JIB HOIST The defined heavy loads for the reactor vessel tool handling jib hoist are listed on Table 4-4. Handling of all these loads is governed by the applicable refueling procedures and the hoist operating procedure, " Operation of Miscellaneous Cranes and Hoists". The loads listed in Table 4-4 are all moved to and from the top head panel storage area to the reactor vessel. These loads are considered significant because they can be dcopped on spent fuel and, as the jib hoist beam is swung inside the D ring wall, a load drop can impact or. the 12 inch decay heat suction line and reactor coolant piping. Figure 4-25 shows the load path and Figure 4-1 shows the hoist safe load test area.
4-6
_ _ _ _ _ , , . _ . - ~_ . - , _ , _ _ _ _ _ ~ , - . _ _ __. .. _ . _ _ _ . . - . - - . _ _ _ .
INCORE INSTRUMENT CONTAINER HOIST The incore instrument container hoist moves incore instrument containers from the refueling canal to the instrument pit. Handling of these loads is governed by the hoist operating procedure, " Operation of Miscellaneous Cranes and Hoists". The listed loads can only be moved along the stationary hoist traA travel path shown in Figure 4-25. A possible load drop target is spent fuel stored in failed fuel containers in the refueling canal.
REACTOR BUILDING MECHANIZED SCAFFOLD The reactor building mechanized scaffold is used during reactor modes 5 and 6 to retension the reactor containment tendons. For this operation the heaviest tool used is a 5 ton hydraulic jack. If this jack is dropped from the scaffold while over the Auxiliary Building, the jack would drop through the roof and could hit the spent fuel pool. To prevent this, load handling operations using the scaffold over the auxiliary building are limited to times when the missile shields are inplace over the spent fuel pool. Other areas which could be impacted by a load drcp include electrical penetration rooms, the intermediate building, etc. Operation of this scaffold is governed by the procedure, " Operation of Miscellaneous Cranes and Hoists". The mechanized scaffold test area is shown on Figure 6-4.
AUXILIARY BUILDING CRANE The heavy loads defined for the Auxiliary Building Crane are shown on Table 4-3.
Each of these loads is controlled administratively by applicable refueling or maintenance procedures and by the crane operating procedure, " Operation of the Auxiliary Building Crane", which identifies the load paths for each load.
The loading bay hatch covers are removed from the hatch aid stored in the missile shield storage area when the hatchway is in use. The load path for the hatch covers does not come in proximity to spent fuel or equipraent required for safe shutdown or decay heat removal. Figures 4-12 and 4-26 show the load path.
l Spent fuel casks are not presently handled at Crystal River Unit 3. The safe i
(] handling of spent fuel casks will be arMressed in detail as a separate issue apart from NUREG 0612. However, load pths are shown on Figures 4-12, 4-26 and 4-29.
l l 4-7
The new fuel shipping cask is moved from the hatchway to and from the spent fuel pool missile shield laydown area. It does not cross over spent fuel or equipment required for safe shutdown or decay heat removal. Figures 4-12 and 4-27 show the load path.
The 1532 pound new fuel asse:nblics are removed fra.n the new fuel shipping cask and moved to either the decontamination pit for inspection and then to the new fuel storage pit or directly to the new fuel pit for storage. From the new fuel storage pit, the new fuel assemblies are moved to the new fuel elevator located in spent fuel pool "B". Possible load drop targets are essential motor control cerners and cable trays located on the 143 foot elevation and spent fuel. Figures ',-12 ud 4-30 show the load paths.
The missile shield handling fixture is a lif ting beam used to move the new fuel pit missile shields and the spent fuel pool missile shields. The new fuel pit missile shields are only lif ted high enough to be stacked on their adjacent misslie shield thereby allowing access to one half of the new fuel storage pit. There are no potential load drop targets for this lif t. The spent fuel missile shields are moved from the spent fuel pool to and from the missile shield laydown area. Since the spent f' uel pool missile shields float (FSAR Section 9.6.1.5), spent fuel is not considered as a possible load drop target. Possible load drop targets are considered to be the makeup tank, the boric acid storage tank and essentian notor control centers and cable trays located on the 143 foot elevation. Figures 4-12, 4-23 and 4-29 show the load paths.
New control components and their containers are lif ted up through the crane hatchway and moved to the missile shield laydown area. There the control components are removed and moved to the decontamination pit for inspection and then to the new fuel pit for storage. From the new fuel storage pit, control components are moved to the new fuel elevator. Fossible targets for load drops include spent fuel and essential motor control centers and cable trays located on the 143 foot elevation. Load paths are shown in Figures 4-13 and 4-30. ,
The spent fuel cask loading pit gate is lif ted from the gate slots in the pit opening and stored in spent fuel pool "B" north of the cask loading pit opening. A load drop of the spent fuel cask loading pit gate could damage the spent fue! pool liner or spent fuel if it is stored nearby. Figures 4-12 and 4-29 show the load path.
4-8 en, , - - - - g -
- - . -,,-- , . -e e- r - - - - - -
The new fuel elevator may require maintenance. Th!:, would necessitate first decontaminating the elevator in the decontamination pit and then moving it to and lowering it down through the hatchway so that it can be taken to the maintenance shop. Possible load drop targets are the essential motor control centers and cable trays on the 10 foot elevation. Figures '4-12 and 4-29 show the load path.
Miscellaneous load handling operations have been considered for various un-programmed load handling operations involving load storage in the spent fuel pool missile shield storage area and maintenance operations which involve load handling over the "B" spent fuel pool. The various loads moved from the hatchway to the missile shield storage area are not moved over spent fuel or equipment required for safe shutdown or decay heat removal. Fnr the various loads moved from the "A" Spent Fuel Pool area and transferred to the auxiliary building crane and moved over the "B" spent fuel pool, possible load drop targets are spent fuel and essential motor control centers and cable trays on the 143 foot elevation. Figures 4-12, '+-
26,4-27 and 4-28 show the load paths.
The main and auxiliary hoist hook and bottom block assemblies are also considered as heavy loads. Assuming unrestricted travel of the crane, possible loads drop targets include spent fuel, essential motor control centers and cable trays on the 143 foot elevation and the boric acid storage tanks.
In the event that the auxiliary building crane is extensively modified and will require a load test, Figure 4-2 shows the auxiliary building crane load test path that would be used.
SPENT FUEL POOL MISSILE SHIELD GANTRY CRANF AND SPENT FUEL POOL GATE HOIST Table 4-2 lists the heavy loads defined for the spent fuel pool missile shield gantry crane and the spent fuel pool gate hoist. Handling of these loads is governed by applicable surveillance and refueling procedures and by the crane and hoist operating procedure, " Operation of Miscellaneous Cranes and Hoists", which defines load handling paths. For the spent fuel pool missile shield gantry crane, the G
V 4-9
_ _ _ - _. __ , . , _ _ _ - ~ . - - _
1
!O 1
ieads ef ceecere ere verioes meintemence iifts ie 18e spent feei geei A area.
j Because the missile shields float, they are not considered as having a damage
! potential. The potential load drop target is spent fuel. The hoist which handles the spent fuel pool gate is used to raise the gate out of the slotted opening between the "A" 2nd "B" spent fuel pools and place the gau against the cast well of the "A" f spent fuel pool. Possible load drop targets include the spent fuel pool liner and spent fuel. Figure 4-23 shows the load paths.
f A load test path for the spent fuel pool missile shield gantry crane is shown in Figure 4-3.
INTAKE GANTRY CRANE 1
The gantry crane at the intake structure is used primarily for pulling the i circulating water pumps and motors for maintenance and for placing the stop logs
' in the intake structure. The essential equipment at the intake structure consists of the buried conduits which carry water to the nuclear service water (NSSW) pumps and the traveling screens and associated equipment for these conduits. The conduits traverse the crane runways east of the circulating water pumps. The pump maintenance area is west of the circulating water pumps while the stop log l storage area is east of the essential service water conduits. Figures 4-6 and 4-7 1
l show safe load exclusion areas when either of the NSSW conduits is operable.
- Figure 4-5 shows the area to be avoided if a load test is conducted en the gantry i crane.
e o
j 4-10
,v.g.--_---,.-,-.,-r. , , - . e-~,.,r.,-_,en,,,vw,--,.---w,,r-..e-,,e,,,,- .-,n,,-,---tm, ++ we -%r w-,----r n em- e- + - + - -em* - , * + ~ < +"ev -+
TABLE 4-1 RCCR-1/ POLAR CRANE LOADS i i i i 1 l i 8 Mode (s) of I l l l l l Operation !
I Crane s Designated Governing Expected for l
[ l l l Load l Weight Lifting Device i Handling Procedure 8 Load Move I e i I g g l 4 8 e i 1 3 1 ' '
s Reactor vessel i I :
l l missile ! 26 tons a Slings ! FP-409 3-6 I l shields (3) l l l
l l 1
l l l r -! !
, , i i i i a Pressurizer 8 l l l l missile i
- a 15 tons Slings 8 None identified 8 3-6 l shields (7) 8 l
1 l
1 l
I l
I I j'
~
- l l ~~I I
~ g I l Stud I 3
e Ref. FP-409 (8.14) 1 e 4-6 I tensioners (2) 1 ton l Sling l FP-405 (8.6) l l I I I I 8 l l l ! Ref. FP-405 (8.1) ! 5, 6 i I
l l l FP-409 (8.14) l l 3 1 8 8 1 3
, , , , - - - _ _ .- . .. ; a l l 1 8 8 8 Stud handling 170 lb. N/A Ref. FP-405 (9.1) 5, 6 l l l l l l
- tools I e 1 8 I I I I 8 8 l
l l
i
-+-i r
i i
i Studs 915 & 945 a e Stud handling tool 8 Ref. PP-405 (9.8) I 6 l (915 - North) l 640 lb. l ! ! !
l (945 - South) l l l l l g i e i 1 8
- I I u ' 's I e i I I I I Alignment j 400 lb. Stud handling tool Ref. FP-405 (9.9) 6 l l l l l
- studs (2) : I e i I I
! ! l l l
i o
b O 1
TABLE 4-1 (Cont'd) ;
i RCCR-1/ POLAR CRANE IDADS
' l 1 I I i I I I I e i Mode (s) of I l
I Crane
- l I l
Designated l
Governing
! Operation Expected for !
l l l l Load I Weight i Lifeing Device a llandling Procedure I Load Move I
! l = ' ._______l___ l l l IbI tool - ARIES l 17 ton l Sling ! ! 6 I i
j (assembled) l l l None Identified ! !
1 i I e i I I I I I I I I I e I _J._ ___ e e i 1 8 8 _..f I r 1 8 i I I i
! East ladder cage l l l Cage must be removed I !
j (deep end of re- l 150 lb. l Sling l for storage of core l 4-6 l I fueling canal) l I I barrel and rienum I i 4
I i I I I I 8 l l 8 I I I I I I I I g ; ; . _4 ___ _
____.l. n pl 1 I I I
, I I i . I. . i j Gl Crane main hoist l l l l l 8 boton block and I 5 ton i N/A 4 N/A I 3-6 8 I I i I I I I hook i I I I i l i e i I I 4
1 I i 1 1 I l
l l
I l
I I
.fI _ l I
I i 1 1 I I I Crane auxiliary I a l I I l hoist bottom bloclil 800 lb. ! N/A I N/A ! 3-6 !
l and hook l l l l l 1 1 1 1 8 I I I I I I I I i i I I I I I I I I I I I I I I I
, I I I I I I I I I I I I I I I I I I I I I I I I I I I 1 I I l i i I I '
i 1 1 I e i I I I I I I n a J_ _ e I j .
, 0) 4 TABLE 4-1 (Cont'd)
RCCR-1/ POLAR CRANE IDADS g i l I 8 8 i i 8 I i Mode (s) of I l l l l ! Operation !
I Crane 8 l
Designated l Governing Expected for l Load Weight l l I i Lifting Device ! Ilandling Procedure I Load Move 8
' -_---- l --_--- _
_-_...j . _ _ . . . _
8 I I I I I I I CRDM's and compo- I 914 lb j Handling Tool Ref. MP-157; MP-108 3-6 nints l l l
- 8 e i 1 e B i I I g l I I I I 1 - e ----- --I- 1 l l l 1 I I I I I I I I I PIrts and compo- 1 Maintenance or replace-l l l l 3 nents of refueling i 2500 lb i Sling a ment of large or heavy 8 4-6 I l machines l l l components ! e i e i i I I I I I I I I
-i- I a a t
@g g i i i I
,' g i i
- I I I
' wlIFuel transfer j j j Maintenance or replace- l l c:rriage, up- g 150 lb i Sling i ment of large or heavy a 4-6 l l cinder, or parts l l l components l l I frr same I I I SP-601 1 1 1
g l l 1 1 1 3 I I' I I I a e s____ _1 1 i
I e e e I i I I i I I d
l Hztch covers l 10 ton l Sling ! Maintenance Procedure ! 5, 6 1 I 3 i I 8 I I I I I I I I I I I I I
' 3 f a t -1 3 3 I l 1 I l l I I I I '
i i ISI tool - ARIES I I I I 8 l (unassembled in l 16 ton l Sling ! !!cnc Identified I 4-6 1 l crates) l 1
l l l 8 l l 8 I I
- 3 I I I I I I I I
- I I I l l 1 I I I l l l 1 1 I e a
_J_ I I
fm (~
O
, TABLE 4-1 (Cont'd)
RCCR-l/ POLAR CRANE IDADS
! ! I Mode (s) of j l l l l Operation I i Crane j i Designated j Governing Expected for l l
l Load ,a Weight i Lifting Device 1 IIandling Procedure I Load Move 1
-_____L_______. __. ...l I g l t 1 1 I Plenum I 58.5 ton i Internals Handling i Ref. FP-501 (11.5) 6 l l Fixture and Adapter l l' l
g l
(15.5) 1 I l A 4
- ! ____1 I l l 1 1_ _ _ _ _ _ _ I I l Internbli exage l 8,200 lb. ! Sling ! Ref. FP-501 (13.5) ! 5, 6 !
I l Etand 1 l l l
' I I I I g - - - - - ,e l I I 3
, , , , i I j 3 l 1 1 I
- Plenum u.d cor*; I I Internals Handling i 1
Ref. FP-501 (13.21) 8 1 7l b;rrel oc cor4 l 162 ton ! Fixture and Adapter ! (17.20) ! 6 !
! g bstrad alone 1 l ,, l l l i I I I
- j j 8
, __l
, - ___ l l l l I I 8 8 j Specimen storage j 400 lb l
Sling l Ref. FP-501 (19.2.1.3) l 6 l
, container (rack) : I I I i e I I I 8
) i I I I 3 g ; ; __4__._____ ____.____a- _ _ - 1 l l 1 1 I I l t i I I I 1 50.5 ton i Sling Ref. MP-115 l RP motors l l 5, 6 l 3 a i I I I I I 1 8 I I g i e 1 --
I I g i e : 1 - -- a i l l I I I
- RCP, components, e l l I I lI structural or supporting steel l 23 ton l Sling l Ref. MP-ll5 l 4-6 '!
j j j l l l tbove or around : i For removal from reactor i I l RCP's l l l building l l 1 1 I I l l 1 1 I I i i J. I i 1
1 TABLE 4-1 (Cont'd)
RCCR-l/ POLAR CRANE IDADS t
! Mode (s) of I I
l l l ! Operation !
I Crane l
Designated l Governing l Expected for l l
s l Load i Weight i Lifting Device i Handling Procedure I Load Move I
. . i I I i l i 5 '
I Head lifting l l l l l
e pendants (3) 850 lb. I N/A I REF. FP-409 I 6 I i e i I I I e 8 i i I I l ! ! ! I .
i I i I l Headandinternalsl l l Ref. FP-409 (8.25) l !
j handling fixture j 6 ton l N/A l Alternate path l 6 l 8 I I I I I i . . -t .
t i e i 1 1 1 I Reactor vessel I l l l l
ei head with lift i 160 ton i Handling fixture I Ref. FP-409 (8.36) 1 6 I hl rig (tripod) l l l l !
I I I I I I, ; : t. _ __t_ i e i i I i I l Internals hand- l 3400 lb. ! N/A l Ref. FP-501 (8, 8, 9) l 6 !
ling extension j j l l l_ l 4 : I I I I g , , r --t- .
I 4 4 3 I I
' e i i i i I g l i l I Tripod i 6 ton i N/A I Ref. FP-501 (9.2) I 6 I I e e I i I e I I I I I i 1 8 I I I
- , S - ___! i l l 8 3 I I l Index fixtute and l l l Ref. FP-501 (9.5) l !
j associatedadapterq 12,500 lb. I Slings l (11.3) l 6 1 and pendants and i i I (11.4) 1 I l spreader ring l l l ! !
I I I I I I e I i 1 1 I .
I I I I I I e i i i I
O
(
TABLE 4-1 (Cont'd)
RCCR-1/ POLAR CRANE LOADS
]
i t I i i i I I I I e i Mode (s) of I I I I i i I I i l e i Operation 4
. Crane Designated Governing Expected for l l Load l l l l
) I I Wei.ght i Lifting Device i Handling Procedure i Load Move 1 e a a i i I l Stud support l l l l 1
l spacers (in j ao Au. j a risig ,
.~ . ..w, is...,
I 1
crate) i I
I e
I I
I I
e i
1 8 I a .__8 I I I I I I I I I I e I I i Stud hole seal i I I I I l plugs (58) l 200 lb. l Sling l Ref. FP-407, 408 l 5, 6 l
, l (in crate) l l l l l l r!
-1 l
1 l
- l 1
--l I
l i
- l CRDM cooling l l l l
l I water header 1 100 lb. I Sling
- I Ref. FP-409 (8.9) 1 4-6 1 l spool pieces l l l l l l 1 I I I I I ;- ; ; - ; -I I 6 I I I e l ServiceStructurel l l l l l platforlas (tri-l l-1/2 ton l Sling i Ref. FP-409 (8.18) l 4-6 l l angular) i I e a l I i 1 I I e s a a. I.
1 1 I I I 1
! Refueling cavity l ! ! ! !
l seal plate l l-1/2 ton l Sling l t .c rt Identified l 6 l 1 I I I I I 1 ; ; 1 -1 1 I I I I I I l Fuel transfer l l l l l 1
tube covers (2) l 1 ton l
Sling l
Ref. MP-125 I 5, 6 1 4 I I 8 I I I I I I i I i l 1 i 1 1 1 I i l i 1 i l i I i 1 1
' E I i l
TABLE 4-2 FHCR-7/ MISSILE SIIIELD GANTRY CRAtIE AND i SFHT-7/ SPENT FUEL PIT GATE ff0IST LOADS i
I l I I I I I I I I Mode (s) of I l l l l l Operstion !
I Crane Designated Governing Load l l l l Expected for l l I Weight i Lifting Device 1 Handling Proceddre i Load Move i I . e i i a 1 I a 3 8 1 1 1 1 I I I Spent fuel pool l I I Ref. SP-434 (6.1.10) l-6 Sling and spreader beam ! l l l missile shields l 6300 lb. ! (6.1.13) i I ll ASMG thru P with j l l l l 1 8 I I I I I I I I I i '
I.
g I I I i i
_J l 4
' i i I I i I I I I i 1 1 l Various items in l l l ! !
l spent fuel pit "A" l Variable i Slings l Ref. FP-601 (2.7) l l-6 l fI area (i.e., re- Less than i 3 I For maintenance and/or I a G l fueling machine l 1 ton ! -
l testing ! !
I I parts, fueltrans-l l l l l 1 fer carriages and i I I I I l hydraulic units, l l ! ! !
q l etc.) l l
l l l l 1 1 I I I I I I l~ l l
l l
I i l t -- 4 i a i i i l i l i I I Spent fuel pool 8 3900 lb. I Sling i Gate is moved by mono- I l-6 8 l "A-B" gate 8
l l ra11 hoist SFIIT-7 l !
I I I I
I FP-1001 1 I 1 3 1 I I I i I I I 3 I i l 1 I I I l i I I I I i 1 8 8 I I I I I I I
- I I
' I I I I I I I I I 4 1 1 I I I I I I I I I I I I I I I i 1 I I I I e i I I I ,
W TABLE 4-3 FHCR-5/ AUXILIARY BUILDING CRANE LOADS l l l I i i i e e i Mode (s) of I l l l l ! Operation !
Crane Designated Governing Expected for l l l l l l 8 Load Weight : Lifting Device IIandling Procedure i Load Move I
- i. i i e e i 3 i Loading bay
- i Less than i Sling i Ref. FP-301 (5.1) i I l-6 i
3 lI hatch cover l 1 ton l l FP-302 (6.5) l !
I i l FP-1001 (6.8) l l l l 1 8 8 3 l
t l
i l
I
---lI l I
l I
l l 1 1 I I
- Spent fuel cask i To be addressed a Cask yoke i Ref. FP-301 (5.17) i 1-6 I l (loaded) l as a separate l l FP-1001 l l 7l l licensing issue l l (Enc. A,13) l l 5;l3 l l l l l g i Ref. FP-301 (5.E6 e i l
l I
- 1 1 1 l I I I i j , ; -r- --: :
I I I I I I l New fuel shipping l 7300 lb. l Sling l Ref. FP-302 (6.7) l 1-6 l cask (loaded - 2 I I I I I l assemblies) l l ! ! !
3 l I i 1 4 I I I I I
- : -o ? '
i e i 8 i i l New fuel l 1532 lb. l New fuel handling tool l Ref. FP-302 (9.0) l 1-6 !
I assemblies (10.0) l l l l l
- e i I (12.0) I i i i l l I I i 1 I i 3 8 l i i ; l l l Missile shield i 500 lb i Sling i FP-302 8 1-6 I l handling fixtures l l. l l l (SFMS) l l l l l l g i i I i 3 1 1 I i l a l 8
! ! l l
4 TABLE 4-3 (Cont'd) 1 FHCR-5/ AUXILIARY BUILDING CRANE LOADS i i i i i i i i 8 I Mode (s) of I I e i i I i I e 8 I Operation 8 Crane I Designated Governing Expected for l l l l l Load Weight s I i Lifting Device : Handling Procedure I Load Move I
! ! e t i
& I I I I a I i l i e 1 l Various loads l l l l l Variable i Slings n e Identified 1-6 I which are hoisted l up to the operat- i Less Than j
j l
l ing deck from the l 2 ton l l l l l loading bay l l l l 8
e i i I i l l l I 1
_.L __.a n -
i i i I i i t I e i i i i fI various loads on i I -
e i I G: missile shields ! Variable l Slings l For removal from build- l 1-6 l l above spent fuel l Less than l , j ing l l 1 pool "B" after i 1000 lb 1 OR 8 l transferral by l l l l l the missile shieldI 1 i l l l e crane from the i e i For maintainence or e I i spent fuel pool l l l storage l l l "A" area l l l l I
e i l I l- e l
1 l
I l
i
-+-e
-+ i 1
I 8 Crane main hoist I i i i l l bottom block and ! 3-1/2 ton l N/A l N/A l l-6 l
! hook j j l l l 1 i e I i I e I I i i 1 e i i i -- r I i l i i I I
- Crane auxiliary l l l l l
- hoistbottomblocksl 700 lb. I N/A i N/A i 1-6 l and hook l l l l l 8 e 1 i i 1 4
' ' I e 8
f' TABLE 4-3 (Cont'd)
FHCR-5/ AUXILIARY BUILDING CRANE IDADS l l ! I Mode (s) of I i l l l l Operation !
! Crane e i Designated l Governing l Expected for l l Load l Weight ! Lifting Device i Handling Procedure i Load Move I
, . e i i I i i I 8 '
I New fuel pit j 7 tons Handling fixture l Ref. FP-302 (12.2) l l-li l l
missile shields 1 1 Missile shields are i I l with SFMS ,
l l l stacked on top of each ! !
l l l l other l l 3 3 I I I I a . I I I I i T ' .
I i 8 8 3
- New control compo Il 1,L J lb Sling Ref. FP-301 (6.2.5) l-6 l l l l fl a!
I nent container !
I 1
(7.2.3) i i
I l
, , e- -
--+ 1
- 1 I . I ~
I I l New control j 132 lb l Sling /Short handling l Ref. FP-303 (9.2.10) l l-6 !
I tool (9.3.12) l component l l l l a I I I g i e 1 I I i l I i I '
s 1 I I I l Spent fuel cask l 2 ton l Sling ! Ref. FP-301 l 1-6 !
l P i t gate j j l l l l l 1 1 I I i , . -e- ---
--* I I I I I I I I I I I I I Spent fuel pool 8900 lb. Sling and spreader Ref. SP-434 l-6 l l l l l l missile shields i i beam a i 3 I a l i I I e i 4 i i I
- : : s__ _ . _ _'
_ 8 l New fuel elevator ! 220 lb ! Sling ! No identified procedure I l-6 l l and associated l l l l !
I equipment I I, j I l
8
p (b
, TABLE 4-4 RCCR-2/ REACTOR VESSEL TOOL IIANDLING JIS CRAt!E IDADS 1 I I i i i i I I I I i Mode (s) of I I I I I I 1 8 I I e i Operation e Crane I Designated Governing Expected for l "
l l l l i Load I Weight i Lifting Device i Handling Procedure I Load Move I
! ' e . i i i
! CRDM cooling water! 100 lb ! Sling ! Ref. FP-409 (8.9) l 5, 6 i i
j header spool pieced j '
l l 1 1 1 8 I I I I I I I I l-1 'I l Incore instrument l 300 lb l N/A l May be moved by RCCR-1 l 4-6 l
I tube plug tool I I i also 1 I i 1 1 I I I 1 I I i 1 I 1 I I i ' !
.-_i j i i i 1 8 4 i Rod assembly 1 150 lb i N/A I Tools used for mainte- 1 4-6 i '
! handling tool, ! and less l l nance and removal of l l
.; leadscrew tool, l l l CRDM's. May be moved
{l
-- I stator / water jacket t I by RCCR-1 also.
l I
l I
I tool, hold down l l l l l l bolt tool l l l l l 1 I i 1 I i l i i :- - - e :
1 I I i 1 8 l Longhandledtooll 40 lb l N/A l This tool is used for j 4-6 l
, I and attachments I I i various manipulations I
! ! l 8
l l around or above the core l l l l l when RV he.' is off. l. l
]
I I I May be moved by RCCR-1 I i
~
! l l l also. ! l I 1 1 I I I I ! ! --4---- 4 --
1 I Source handling ! 30 lb ! N/A l Tool is used when RV l 6 !
l tool l l l head is off. May be l l l l l l moved by RCCR-1 also, I l l 1 8 8 I I I I 1 l i I i i l I i I 8 4 1 1 1 I ;
- n t I g l
REACTOR J \\ / / I
\ -k' -f -[.MUV-36 ~
I,-/
.a J
A / /' % ; c?
O _~ l l Fi i
,o , TW >
BI RCP
/.
D HV- jj '
/
^ ::
- v. 4 -
\ TEST %Q
@?sy @%
m AREA
- =
7,1 4h hh'u c!
n DS ,
..o _t
.i.- -
4-22
FIGURE 4-2 REFUELING CRANE FHCR-5 LOAD TEST PATH O l V ,
iI, I j . .:.. .g. , m
.i . a ;.. O. E.S
- l
,, l. -- ,
i c Aw, vo ws .
1.AY DOW *J rt 'V MCd '
l
>4l l' I. '.
. GE A l
~:7.' '
- 3Ol l
'+ J - .
/ BORIC ACID . > l'
% l B. A. S.T. asic'do/ f'STCRAGE - -
q l mes ! ,,' -TANK ! a
,,{/33 /fFI,*P / - /fk e3A .
.3, l
, ti . s u
- / i a - -
s
.- n- a ~.
/\ '
,a?
N ,
y ,
1 l
l SPENT- FUEL- POOL i y P
l
'**i
, 1 - \ / . , 4 3 MISS LE. SHIEL..O. z ST. ORA,GE -- -..
l N.
s . .
. m.," A
- A. -
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., . ' &, - 4':.t :. l -%%'s ' ' ., W.'s? ::. '.=.* . . -i'.?he.
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' W. 9 ,: - - .. s. - . n.- %. . .s**.,...C.,. .. A
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- er- f-- '*' ' ** ** r " _f.1. . #*
.c s .-
..e .- ' N.h J--
l t+-23
FIGURE 4-3 SPENT FUEL POOL MISSILE SHIELD HANDLING CRANE
[ LOAD TEST PATH E Q u s PM E9T M A T C. N,
, S.W. SYSTEM D.H. SYSTEM [ fl
', , . , . 't/ jl,
. J L, _ .. _ _ _ _
. _ _ ____ S.E , gonL TEST V'UD 3 = "r A / ASSEM BLY
^#CA MAxEUP SYSTEM A GATE x xe yjh POOL !
,- S.E,'A# c \/
3 __ __
VU3- C 3 A __.-
t
.-- .a
.D.C. S Y S T E M S.F. COOLING %; 5 --
l O
I i
l O 4-24 l
l
FIGURE 4-4 O ^
LOAD TEST AREA - MECHANIZED SCAFFOLD 4
INTERMEDIATE --
.s x
/
BUILDING \
ROOF ELEV 18 9 '
ROOF ELEV REACTOR BUILDING 02' 6
TEST \
~
AREA s AUXILIARY BUILDING ROOF ELEV 209' BWST O
4-25
I I FIGURE 4-5 (J
LOAD TEST EXCT.USION AREA - Ch'CR-1
,__ u _, ,, ,
__ .. g . i m xNNNvsNNxxN g ,
i KNNN\\XNN\\\\ .
k: o*= ,: x 9 ,. . N N
,s ,
iL Ji:_j 'h s p
I 3L-xv s
.x a EXCLUSION \' \$
AREA I c.._ .... _ _ A
?x N r d ::a n= 5t =g ,
.sa -e _ , as' c-x y
b'st'%+>
%, s m. -
c:=m c:_::=-,
OE m, ,
C-
,sr - - - .3 y em
^ xN, l
t- '8% -
r-
'3 *
, '_i[: .
.( swa .^ w...
- " v d ' ". s" *.*,
"- = g ,- - 9 = = ,y =Gl ce=
0]
- , eax t:x.,x mxx l0 y '
l
'MN '
i'
( ,
MW RN-N W ,N
.y. _
gsg+;,Q 4-26
A FIGURE 4-6 k.)
CWCR-1 SAFE LOAD PATH SKETCH -
NORMAL NSSW OPERABLE o } l 8 I \\k \\ \ \ \N f f .
I
.s\\\ \\ \ \ 1, ,
l _ _ .}
_y . ,
lN\ l
.p
- ' y\
'N .
N ORN\AL 9J- lb N MNN NSSW INuwt 'l l,_ _'_ ._ _' _ al N .0 r N "3 L b emus-Ams dx Q qs c_..c,-. (NW s\ s: A L's'NN\
D+ 'N+O sv. s .
lC' W :~3 C *"
- ~A ~ Q ' x 8%' , :
~
.44*-(
- 13 ' t" NJ' 9
Q \\ .h. >
< .'sm_.b._
g l} \
'\\/ \
IN
- '~ = ?.
- k. ; \ ,5 . ,s 4 ,t
'Y
., . im. ..
l j
- s. . , e ... _
m '
, y s.!
- Ba t t Estv. 9 9 57 kmE -? wk
' jl C3C-f-a O I ,
l b ,
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4 *
- VT E
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l c 4 :
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ex: ::::, e r : m m: cc.2 -
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1
.a
(]
v t us v. 9 e -*
c.
2
. ~ - _n 4-27 l
tx (j FIGURE 4-7 CWC R-1 SAFE LOAD PATH SKETCH -
ALTERNATE NSSW OPERABLE
, , 1
- i ( X \ \ \ \. \\\
g l \ \\ \\\\ '
i \\
,qt--
i
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I i
s j , ', I
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h "3,^ I ALTERM ATE N o NU NS$W N' 4 5 1
INTAKE . L.-}
5 6
c t o n.~ c cie rvs s . \
\ 's .
\
i.
+ 'N+O '
\
xx\.
lC ~ iM ~: 3 tr ~ '=R ^ : A'
- _ \
K 1 N
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. 4 4* - c. * < 13 '- P. ~ C - [ _5 '- 7._'
4' M -5~ = y + ii '
,3, i; , s
'" ' M +
OM , ,or7 44 ; N- .
8 a,
F E_ _ i#3 lC ~ _~_ _ __M ,
e, - ,
b{
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o\
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i , ,
--7 A~- h, , pg; 9,,,
l
?==___ t. : : .,. - _-1[. b gd I gg g] Exct_usion av_: ::::, ca e as xu N AREA
'S$$$N'x N u
' " g
'D'sNN'N3 o _
=mmw
= g = = 4 I+_28
m en NOTE: Exclusion areas are shown heavy black or cross-hatched.
Exclusion areas shall be avoided during modes 1 through 4.
5- .
i i l l I "
g L. ~ ~ ~ = ~ I. i i
- .{_.
3 . _,/;
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/-
m g __ . . _. ;_.
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. - WS ?-- : _ - ^ "_ -
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.= ! !. !
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i t
-< l I
.-t_ _.. ti m 1.d -< 1 -< l -<
O e e e e e i i i 1 e ee e ** e FIGURE 4-8 TURBINE BUILDING SAFE LOAD PATli SKETCil
l\ .
1
< ( #
mE e o e
Tog
' p-
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i
- A
- *s [
%. 7.
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i i
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83 83 A 1
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. - . - - . - - - - . _ - - _ , . - . . _ . - _ . . _ _ . - . . - . - , . - , - . . . - . . . - - . . _ . ~ . - - - . _ . . . - _ - . - - . . , . . . . . . .
( .a ww. i L. A c c o-se i GCAGF j
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ll /- M J
ww.un t Uh*,5%,7, * ** .
IF Ek,,s er. 440 -se .
t se.mam h%
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1 .
- - 1
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- r-. a - a --s. -.r. -
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\ 9 4 4 g g 4 ,xw
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e s i.
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3 I 4 4 f $ $ $ l
.6
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t _*1 ~ 4 - TT" K- t_.
l 6L .
. Tom or roos.
O: _ -,
Nm* UOOER SN8ED- MACiG-==-$ 4W
[ g.
et a-v. 1 e.N -4E". p - . _
e e. oar a vo r ca m .
l
- *'+ %* v,
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- s. A m os-e,
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l '
f , ,. I m u,v. s 1
-/
/.: -
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\ \ '-
~
~
FV _\.
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A FIGURE 4-9 LOAD PATH k'
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DE ' . -'. l, , fi- r -t . j} w . y { l< ' , ! g - I ' -r - i t l t - t g t' ' O ; --- - ~ n . - >.' .s t- l . i u: + .n.~- o u . 6 ;). * ~' I,-. - '* .. . .i h' ~b. d -~ ' , L ilA ' ..u . . ;M d . . p'. 6 I , \ G . , j 3 . _ _ _ . . . . . t ._. . .I Section 5 1.if ting Device Compliance with ANSI N14.6-1973 and ANSI B30.9-1971 REQUESTED INFORM ATION: i Verification that lif ting devices identified in Section 4, co iply with the require. ments of ANSI N14.6-1978, or ANSI B30.9-1971 as appropriate. For lifting devices where these standards, as supplerrented by NUREG 0612, Section 5.1.l(4) or 5.1.l(5), are not met, describe any proposed alternatives and demonstrate their equivalency in terms of load-handling reliability.
RESPONSE
For the loads listed in the tables in Section 4 which utilize slings, the plant procedure governing the testing and use of slings is being _ revised to be in accordance with the requ:rements of ANSI B30.9-1971. Only two lif ting devices have been identified in the tables in Section 4. These are:
- 1. The reactor vessel head and internals lif ting device.
- 2. The spent fuel pool missile shield lif ting beam.
The requirements of ANSI N14.6 are not considered applicable to the spent fuel pool missile shield lifting device in that if the handled load, ie. a spent fuel pool missile shield,is dropped it will float in the spent fuel pool and it can not sink to a pool depth where it could impact the spent fuel (Section 9.6.1.5 of the Crystal i River FSAR). t O. 5-1
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W The reactor vessel head and internals lif ting device was designed and fabricated by b' the Babcock and Wilcox Company (B&W) using the B&W engineering practices in effect at the time. Since this preceded ANSI N-14.6-1978, it is difficult to make a strict interpretation of compliance with the standard in light of the fact that the lif ting device is in use and that the existing documentation was not originally intended to meet the requirements of the ANSI standard. Since the intent of NUREG-0612 is to verif y the load handling reliability of the lif ting device, our reviev ef the lif ting device's compliance to ANSI 10.6-1978 has been limited to specifically addressing those sections of the standard which have a direct bearing on the issue of load handling eliability. The fo!!owing paragraphs discuss compliance with Sections 3 through 6 of ANSI 14.6. Section 3 of ANSI N14.6, " Design", addresses the considerations made in for designing a new lif ting device. The reactor vessel head and internals lif ting device was designed to standard industry and B&W engineering and fabrication practices in effect at the time. Although no specific design specification was prepared and quality assurance requirements were not placed upon the design and fabrication of the device, B&W standard engineering and design practices plus B&W's knowledge of how the device would be used should adequately fulfill these requirements. P&W has stated that the tripod, handling extensions and load slings were all designed to be capable of lif ting three times the design capacity of the lif ting device, 180 tons, without exceeding the yield strength of the materials used. Dynamic loading was not considered in the original design, however the excess design margin in static loading should account for any dynamic loading. The stress design factors are therefore in compliance with the ANSI 14.6 standard as supplemented by NUREG 0612. Tht lif ting device slings are in accordance with ANSI B30.9-1971. With regards to Section 3.2.6 of ANSI N14.6, we have been F unable to retrieve any information on materials testing from the files. The reactor vessel head and internals lif ting device was designed specifically for handling the reactor vessel head and internals, therefore the design considerations of Sections
. 3.3,3.4,3.5 and 3.6 of ANSI N14.6 were all considered in the context of the design practices in use when the device was built.
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(\ V Section 4 of ANSI N14.6, Fabrication, is directed at new fabrication. Reviewing this section in retrospect to the standard B&W manufacturing practices is not considered practical. With regards to the owner's responsibilities in Section 5, " Acceptance Testing, Maintenance, and Assurance of Continued Compliance", the refueling and surveillance procedures address proper use and maintenance of the reactor head and internals device. Current inspection practices are carried 'out each rebeling outage. The tripod, handling extensions and load slings were initially subjected to an acceptance test of 255 tons. Considering that the critical lif ts as defined by NUREG 0612 are the lif t of the reactor head and lif ting fixture (160 tons) and the lift of the core plenum and handling fixture (53 tons), the acceptance test initially performed greatly exceeded ANSI N14.6 requirements. All load bearing welds were also subjected to nondestructive examination. Florida Power Corporation complies with Section 5.3," Testing to Verify Continuing Compliance". Annual load testing to 150% of the maximum load is not practical; NDE testing of the lifting device is required prior to use in accordance with Section 5.1.3(2) of ANSI 14.6. Additionally, plant procedures specify that when initially lif ting the head from the vessel, the load is held suspended I to 2 inches above the flange for several minutes while the rigging, the crane and the disconnection of control rod drives is checked. Following this, the reactor head is moved to its laydown area. Due to the inaccessability of containment, where the head and internals handling device is stored, inspections and testing requirements addressed in this section of the standard are interpreted as either a prior to use or refueling outage frequency and, not a specified number of months. t f(i s-3
i t O The applicability of Section 6, "Special Lif ting Devices for Critical Loads" can not be determined at this time. ANSI N14.6 defines a critical load as:
"Any lif ted load whose uncontrolled movement or release could adversely af fect any safety related system when such system is required for unit safety or could result in potential off site exposures comparable to the guidelines exposures outlined in Code of Federal Regulations, Title 10, Part 100".
4 I
- The structural, impact, etc. analyses required to make such a determination are scheduled to be completed for the 9 month report.
, in reviewing Section 6 against the reactor vessel head and internals lif ting device, j two problem areac are noted. Section 6.2.1 states that load-bearing members be designed with at least twice the normal stress design factor for handling a critical ; load. If this is interpreted to mean twice the requirements stated in Section 3.2.1.1, the reactor head and internals lifting device does not comply.
l Additionally, it would be extremely difficult to comply with the annual testing requirements stated in Section 6.3.1. i G 5-4
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a O Sect. ion 6 Verification of Testing and Inspection J REQUESTED INFORMATION: 4 4 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, sufficient information should be provided to demonstrate the equivalency , of proposed alternatives.
RESPONSE
The Florida Power Corporation is currenay in the process of upgrading the crane i inspection, testing and maintenance procedures to meet the intent of ANSI B30.2-1976, Chapter 2-2. It is anticipated that these procedures will be in effect prior to the third refueling outage.(Reference letter from Baynard to Eisenhut dated May 14, 1981). I e d l 0 6-1
I' ( Section 7 Verification of Crane Design REQUESTED INFORMATION: 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.
RESPONSE
The design of the Reactor Building Polar Crane (RCCR-1), the Auxiliary Building Crane (FHCR-5) and the intake Gantry Crane (CWCR-1) were reviewed with respect to the guidelines set forth in CMAA Specification 70 and Chapter 2-1 of ANSI B30.2-1976. All three cranes were built in 1969 prior to the issuance of the CMAA and ANSI standards in accordance with the governing industry standard and practices in effect at that time, the " Specifications of the Electric Overhead Crane Institute" (E.O.C.1), and the detailed crane procurement specification prepared by Gilbert Associates, Inc. From these specifications it has been determined that the cranes are in corhpliance with CMAA Specifications 70 and ANSI B30.2 with the following qualifications. Both ANSI and CMAA require that welding be performed in accordance with the latest edition of AWS D.I.1, " Structural Welding Code" and AWS D14.1, "Specifi-cations for Welding Industrial and Mill Cranes". These current standards are more recent and were not available at the time of construction of these crres. However the Whiting practices and procedures for the welding were in accordance with AWS standards in effect at the time of construction and are considered equivalent to the current standards. 7-1
4 The cranes structural members were fabricated from A-36 structural steel. The - E.O.C.! specifications to which the crane was built allowed the crane manufacturer to use a higher stress design factor than 16,000 psi for A-36 steel. In recent discussions with the Whiting Corporation, we have not been able to determine if, the 16,000 psi design stress was used, which would make the cranes conservatively designed under CMAA standards, or whether a higher stress factor was used, which' could possibly not be in full compliance with CMAA Specification 70. The Whiting Corporation has been contracted to review this aspect of the crane design. The results of their review will be incorporated into the 9-month report. Since the cranes were allload tested to 125% of the rated capacity prior to use and since the heavi ;t load of concern, the 160 ton reactor vessel head lif t, is less than rated crane capacity, the resolution of this ma ter will not adversely affect the load handling reliability of the cranes. i i i 9 O i 7-2
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- U Section 8 Operator Training, Qualification and Conduct REQUESTED INFORM ATION
! Exceptions, if any, taken to ANSI B30.2-1976 with respect to operator training, qualification, and conduct.
RESPONSE
Procedures and the training program for crane operators are being upgraded to meet the intent of ANSI B30.2-1976. It is anticipated that these procedures will be ; in ef fect prior to the third refueling outage (Reference letter from Baynard to Eisenhut dated May 14, 1981). 9
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