ML20070R019
| ML20070R019 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 01/07/1983 |
| From: | GILBERT/COMMONWEALTH, INC. (FORMERLY GILBERT ASSOCIAT |
| To: | |
| Shared Package | |
| ML20070Q941 | List: |
| References | |
| REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR 2329, 2329-R02, 2329-R2, NUDOCS 8301270238 | |
| Download: ML20070R019 (112) | |
Text
-. . -
h June 19, 1981 Revision 1:
CAI Report No. 2329. l September 28, 1981 ,'
Revision 2:
January 7, 1982
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CONTROL OF HEAVY LOADS STUDY 1
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THE CLEVELAND ELECTRIC ILLUMINATING COMPANY PERRY NUCLEAR POWER PLANT ,
UNITS 1 AND 2 ]
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Docket Nos. 50-440, 50-441
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! 8301270238 830114 '
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( TABLE OF CONTENTS Section Title Page INTRODUCTION 1 EXNIBIT 1 LOGIC DIAGRAM 2
SUMMARY
CONCLUSIONS 6 l I EVALUATION OF ALL HOISTS AND EMERGENCY SERVICE WATER IUMPHOUSE CRANE l IKiRODUCTION I-1 Key to Drawings Data Sheets Drawings 021-001 through 021-008, 318-651 through 318-656 II EVALUATION OF REACTOR BUILDING CRANE INTRODUCTION II-1 Dat. Sheets Drawing b21-00 .
III EVALUATION OF FUEL HANDLING BUILDING CRANE
() INTRODUCTION Data Sheet IIT 1 Drawing 021-010 i
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CONTRUL OF HEAVY LOADS STUDY PERRY NUCLEAR POWER PIANT UNITS 1 AND 2 INTRODUCTION This report presents an evaluation of the movement of heavy loads inside the Perry Nuclear Power Plant Units 1 and 2, and the effects that potential failures of lifting devices could have on plant safety. Consideration has been given to the consequences of crane or hoist failures causing radiological damage to fuel, the potential for criticality, and the effects on the ability of the plant to come to a safe shutdown and remain in a long term decay heat removal mode.
The first portion of the report identifies the hoists and cranes that can lift and transport loads ter vier than 1048 pounds (the weight of a fuel assembly with lifting tool). The crane and hoS t coverage areas have been identified, and where appropriate the specific load paths have been shown.
O Exhibit 1 (next page) provides the logic chart that was used as the basis for the evaluation and ant. lysis of the movement of heavy loads.
The rer Its of this evaluation are presented in three sections: Section I is the evaluation of hoiste and monorails in all buildings housing safety related equipment and/or fuel, and the emergency service water pus 9 house crane;Section II is the evaluation of the reactor building crane;Section III is de evaluation of the fuel handling building crane.
Information packets have been assembled for er-h elevation or section of the plant. The packets consist of general at:.angement drawings that show:
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- 1. Locations of equipment necessary for safe shutdown and continued decay heat-removal with the respective emergency power division.
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- 2. Coverage areas for the lifting devices.
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is fac telCI te A as SUILBise 50ustet a,E sac 0=e _ en EXHIBIT 1 QulrtEnf Os FUEL ILisEsf8 y ~.
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sets Tat LIFTist et MVICI MEAtt AatA leCLust SAFE seemleau es se
{ E9E 1lEET W IMstlFT LIFTies NVICE a fvEL tesutafles TAGLI 4 Sift t (IPL&aaT10e 808 e FutfilER Ae&L'$18 YES Eggiflh57 viu t leBlvleust et L*'38 II > YES saa0W Oassee. 3.5.
I 19U181EeY De FUEL pygg Y IF D80PM9
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EQUIPIERT la TREtt &
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\ P0ftsflaLLY Dase66tpl stasces Saft $sifftes 15 W JESPettilts i, <r 1r ir 8 Tut Pfftsfl&L 700 04setet 70 BMETIFIG IF 4 LIFT OCCURSES SINCTLY ,
tett t$3teil4L EgulflEsf te FUEL. Se GCCUsets a FLege (Lg1Afsm atest te SCCuesta le T4 Il0E31&ft flClelTT. , g 2
() 3. Individual transport paths, both as elevated lifts and along the floor on ,
dollies.
To facilitate the use of the arrangement (.:awings, a key correlating equipment tag number with the equipment name has been included. 7here necessary, piping composite drawings have been added to better show critical safety piping. The results of the heavy load movement study are listed in tables accompanying each packet.
The tables identify the cranes, hoists or other lifting devices that have the capacity to lift more than 1048 pounds in buildings housing fuel or safe shutdcan equipment. A separate table is presented for each lifting device; the table includes the impact area, the load or loads lifted by the device, safety related equipment that could be damaged by a load drop, floor elevation and the category for hazard elimination. The categories for hazard elimination (refer to NUREG-0612) are as folloss:
A. System redundancy and separation:
i l hany systems are provided with redundant trains or safety components and are i physically separated from each other. One train can be rendered useless from a load drop while the other train remains operrtional.
l B. Load drop will not damage safety-related equipmcat:
The basis of this hazard elimination category was that no safety-related equipment or critical piping is located in the load coverage path.
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C. Loads lifted only when reactor is in cold shutdown.
D. Site-specific considerations:
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Operational procedures limit load paths only over areas where no safety-related equipment is located.
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In addition to identification of equipment necessary for safe shutdown of the
)( )
reactor, an evaluation of the piping systems has been made to identify common lines between two redundant systems and areas where redundant system piping could l be damaged by a single load drop. The critical piping sections identified have been shown on the general arrangement drawings or, where necessary to reduce congestion, are shown on supplemental piping composite drawings.
Lifting devices and loads that have the potential to cause fuel. damage,-a criticality accident or less of safe shutdown capability art separately identified in the summary portion of this report.
4 The inspection and preventative maintenance instructions for all of the overhead cranes are being written under the guidelines of ANSI B30.2-1976 and the vendor service manuals. For those cases where requirements differ, the more stringent is being applied.
One local instruction will apply to the Polar, Fuel Handling and Emergency Service Water Pumphouse (ESW) crane, and a second instruction to all remaining-cranes.
An Overhead Crane Operator qualification guide is being written. This guide will follow the requirements of ANSI B30.2-1976 for qual *'ication of operators and contain reference to NUREG-0612 for operation of the Polar, Fuel Handling and ESW cranes. The following general guidelines from NUREG-0612 are listed in the qualification guides:
i a. Definition of Safe Load Pathr..
- b. Procedures for Handling of Heavy Loads.
- c. Qualification of Operators to ANSI B30.2 '.976.
- d. ANSI N14.6-1978 for 3pecial Lifting Devices.
- e. ANSI B30.9 for Slings and Other Lif ting Devices.
- f. Crane Inspection and Testing in accordance with ANSI B30.2-1976.
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() Operator qualification will requir_ familiarity with the PNPP Equipment Removal Scheme and specia handling / safe load path procedures. Knowledge will be checked by interview, written exam and a practical demonstration.
Completion of these requirements will be documented on a qualification card which will be retained in the ,perators' training file.
The ensure that safe load p3ths are followed, crane operators and maintenance personnel involved in supervising load handling will be familiar with all requirements prior to lifts. Information will be presented thraugh on-site training and referenced in maintenance instructions and procedures.
All cranes identified in this report that handle loads in' safety-related buildings are designed to CMAA Specification 70 and ANSI B30.2-1976. The cranes were supplied by Harnischfeger, Inc'., and the serial numbers are as follrws:
A. Reactor Buildi J Crane (Unit 1) - CN 25588 Reactor Building Crane (Unit 2) - CN 25589
' (}
B. Emergency Service Water Pumphouse Crane - CN 03951 C. Fuel Handling Building Crane - CN 25590 l
(_)\ -
5
SUMMARY
CONCLUSIONS The Perry Nuclear Power' Plant, in general, has been designed to avoid potential ly damaging drops of heavy loads. Areas of the plant housing fuel or safe shutdrm equipment have been evaluated and have been found to be free of hazardsduetoheavyloads,asdefine[byNUREC-0612,exceptthefollowing:
Heavy Load Movements Requiring Administrative Procedures
- a. Loads lifted in the steam tunnel can be made only during hot or cold shutdown. During hot shutdown the Main 4 team Isolation Valves must be closed (refer to Drawing 021-003).
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- b. The movement of heavy loads in the emergency service water pump house especially one of the emergency service water pumps over the redun. ant system components, must be controlled by administrative proedures (refer to Drawing 021-008).
- ' O c. The refueling chute must be moved within the reactor bui' ding by an appropriate procedure s, that it is not moved over the reactor vessel (refer to Drawing 021-009).
Analyses have been performed of the consequen;es of load drops over the l reactor pressure vtssel l and in the spent fuel pool area. The postulated load-1 drops do not result in damage to the fuel in the core, jeopardize the vessel's ability to keep the core flooded, nor degrade the spect fuel pool leakage integrity.
Alternative load paths need not be considered since all problem areas may be addressed through administrative prneedures.
1
Reference:
" Structural Analysis of Reactor Pressure Vessel and Internals for Vessel Head Drop, Shroud Head Assembly Drop, and Steam Dryer Assembly Drop p Conditions," April 1977, (NEDC-23566).
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.m.. . _ . . _ - . _ . - _ _ y - m ._. m . -.. _ m k
SECTION I l
EVALUATION OF ALL HOISTS AND EMERGENCY
(
SERVICE WATER PUMP HOUSE CRANE I
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_). INTRODUCTION The hoists and monorail used for handling and monitoring equipment in all safety buildings are itemized in the tables provided with this section. Also included-in this section are the loads handled by the emergency service water pump house cr ne.
Since heavy loads can be handled in all buildings during normal operation except the reactor building, consideration has-been'given to potential damage to all safe shutdown equipment and piping as well as damage to fuel, i
The. report summary identifies all potentially bazardous lifts.
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KEY TO DRAWING 021-001 E'. 568'-6", 574'-10" 577-6", 580-6" EQUIP.%NT TAG NUMBER Emergency Closed Cooling Pumps IP42-C001A 2P42-C001A 1P42-C001B 2P42-C001B Emergency Closed Cooling Hx IP42-B001A 2P43-B001A IP42-B001B 2P42-B001B Control Complex Chilled Water Chillers P47-B001A P47-B001C P47-B001B Control Complex Chilled Wat.er Pumps P47-C001A P47-B001C P47-C001B Emergency CC Pump Area Cooling M28-B001A M28-B001B System Air Handling Unit Emergency Closed Cooling / Chilled H51-P193 H51P194 Water Instrument Racks A,B,C H51-P195 ECC Pump Area Air Handling H51-P036A H51-P036B Panel O Control Complex Chilled Water H51-P318 H51-P319 Control Panel A,B,C H51-P320 Auxiliary Building Residual Heat Removal Heat Ex. IE12-B001A 2E12-B001A 1E12-B001B 2E12-B001B Residual Heat Removal Pumps 1E12-C002A 2E12-C002A 1E12-C002B 2E12-C002B IE12-C002C 2E12-C002C Reactor Core Isolation Cooling IE51-C001 Pump 2E51-C001 RCIC Lube Oil Cooler IE51-B002 2E51-B002 Reactor Core Isolation Cooling IE51-C002 Turbine Drive 2E51-C002 RCIC Pump Room Air Handling Units IM39-B004 2M39-B004 Residual Heat Removal Pump Room IM39-B001A 2M39-B001A Cooling Air Handling Units IM39-B001B 2M39-C001B
() IM39-B002 2M39-B002 001-1
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Drawing 021-001 Cont'd.
RRR Instrument Panels 1H22-P021 no removal 1H22-P018 RCIC Instrument Panels IH22-P0017 no removal 2H22-P0017 Suppression Pool Level 1H51-P1046 2:I51-P104C Instrument Panels A,B 1H51-P1089 2H51-P1089 1451-P1173 2H51-P1173 1H51-P1111 2H51-P1111 IH51-P1121 2H51-P1121 Valves Flow Control after HX 1E12-F003A 0 2E12-F003A/B Suppression pool isulation 1F12-F004 A/B loop A/B 2E12-F004A/B Penetration #411 inboard isolation IE12-F009 valve 2E12-F009 O Shutdown suction to Loop A/B 1E12-F006A/B 2E12-E006A/B RHR Steam Cond, to RCIC Pump 1E12-F026A/B Suction Isolation 2E12-F026A/B Main Steam to RCIC Turbine 1E51-F045 2E51-F045 Suppression pool suction isolation 1E51-F031 for RCIC 2E51-F031 Condensate Storage Tank to RCIC 1E51-F010 Pump isolat.on 2E51-F010 RHR h-at Exchanger Isolation IP45-F068A/B 2P45-F068A/B 1P45-F014A/B 2P45-F014A/B l
l 001-2
O O O TO ItE llSED 1 IN CON.lllNCTION LIFTING I)EVICE Iloist 33-1, 33-2 (IL51-E035, 2L51-E035) WITil llRAWING 021-001 BUILDING: Auxiliary PERRY llEAVY I.OAllS STilDi ELEVATION: 594'-10" IH1'ACT AREA: COLtlHN LINE AX-4 to AX-5; AX-C to AX-B llazard Safety Related Floor Elimination
, .oa d Equipment Elevation Category Remaiks 16,000 lbs (max) RilR Pump Room 568'-4" A There are two other trains of lutR Air llandling Unit l IM39-B002 Capacity - 30,000 2H39-B002 8 lbs.
T RilR "C" Piping 574'-10" 4 There are two other redunilant trains of RllR
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() KEY TO DRAWING 021-002 El. 593'-6", 599'-0", 600'-6", 602'-6", 605'-6" 8.QUIPHS>r TAG NUMBER Instrument Air Receiver IP57-A001B Tank A 2P57-A001B HVAC Pump Room Control canel 1!!51-P037 :
, 2H51-P03/
Control Rod Drive Mechanism IB13-D008 2B13-D008 Valves ,
Penetration 421 Inboard IE12-F009 Isolation 2E12-F009 Pump test to suppression IE12-F024A/B Pool 2E12-F024A/B RHR to Heat Exchanger IE12-F047A/B Isolation 2E12-F047A/B
() RHR B' lancing Valve IE12-F048A/B 2E12-F048A/B RCK Turbine Exhaust to IE51-F068 Suppressi.a Pool Isolation 2E51-F068 i.
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O ~O O TO DE llSED IN CONll!NCTION LIFflNG DEVICE iloist 34-1, 34-2 (IL51-E039, 2L51-E039)
WITH DRAWING 021-002 BUILDING: Auxiliary PERRY llEAVY 1.0 ADS STUDY ELEVATION: 610'-1" IMPACT AREA: COLUMN LINE AX-4 to AX-6; AX-B to AX-C llazard Safety Related Floor Elimination Load Equipment Elevation Category Remark-Ilatch Cover 599-0" B Them is no safety-mlateil l 10,000 lbs (max) equipment in the impact area I on this elevation lil-AB-2 RilR Pump C 568'-4" A There are two other trains of RilR lil-AB-3 1E12-C002C l
211-AB 'e 2E12-C002C o
o 2ti-AB-3 h RllR "C" Piping A There are two other trains of RilR Capacity - 15,000 lbs.
4
O O O To llE IISI:11 IN CON.IllNCTION LIFTING DEVICE Iloist 35-1, 35-2 (IL51-E036, 2L51-E036) WITil DRAWINt; U21-002 IlUILDING: Auxiliary I'ERRY llEAVY 1.OAlpi. STUDY ELEVATION: 618'-1" IMPnCT AREA: COLUMN LINE AX-2 to AX-3; AX-B to AX-C lic.za rd Safety Related Floor Elimination Load Equipment Elevation Category Remarks flatch removal and None 599'-0" B There is no safety-relar'.d high-pressure equipment in the impact area at core spray this elevation 28,000 lbs (max) High-pressure enre 568'-4" A If IIPCS is damaged, there is lil-AB-7 spray pump LPCS, RCIC, and RilR remaining o 211-AB-7 1E21-C001 S 2E21-C002 f,. Capacity - 30,000 and associated piping lbs.
O O O TO 11E USED IN CONJUNCTION LIFTING DEVICE Iloist 42-A, B (L51-E070) WITil DRAVING og i_oo ,
4 BUILDING: Fuel llandling PERRY 1!EAVY LOADS STUDY ELEVATION: 610'-0" l
IMPACT AREA: COLUMN LINE IB-9 to IB-8; IB-CC to Centerline Petween Units
! Hazard Safety Related Floor Elimire. ion Load Equipment Elevation Category Remarks
! CRD maintenance Less tlian 1048 lbs; t iie re f o re , does equipment not require consideration
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O O O f
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, LIFTING DEVICE Iloist 43 (2L51-E065) WITil 1)ltAWING H21-002 BUILDING: Unit 2 Reactor Building I'EHHY llEAVY I.OAI)S STUlly l
ELEVATION: 618'-6-1/4" IMPACT AREA: COLUMN LINE See Dwg. 0 1-002 llaza rd Safety Related Floor Elimination
- Load Erluipment Elevation Category Hemaiks CRD and cask None 604-11-1/4" There is no safety-related removal B 'C
. equipment in tlie Impact area 6000 lbs (max)
- at this elevation None 574'-10" B >c Suppression pool floor Capacity - 8,000 o lbs.
l3
O O O TO BE USED LIFTING DEVICE 11oist 44 (IL51-E040 A, B) g 021-002 BUILDING: Reactor Building Unit 1 PERRY llEAVY I.0 ADS STUDY ELEVATION: 619'-3-3/4" IMPACT AREA: COLUMN LINE See Dwg. 021-002 llaza rd Safety Related Floor Elimination Load Equipment Elevation Category Remarks Reactor None 604'-11-1/4" g,C There is no safety-related Ricirculation equipment in the impact area Pump Removal at this elevation 66,000 lbs (max)
None 574'-10" B .C Suppression pool floor o Capacity - 70,000 lbs.
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O O O TO IIE IISED IN CON.lllNCTION LIFTING DEVICE Iloist 45-1, 45-2 (IL51-Eo' 41 A, B; 2L51-E041 A, B) WITil DRAWING H21-002 BUILDING: Reactor Building Annulus PERRY llEAVY I.0 ADS STUDY ELEVATION: 619'-3/4" IMPACT AREA: COLUMN LINE See Dwg. 021-002 llaza rd Sa fety Related Floor Elimination Load Equipme7t Elevation Category Remarks Reaccor None 599'-9" B,C Recirculation There is no safety-related equipment In the impact area l Pump Hotor Remeval at this elevation 66,000 lbs (max; None 574'-10" Capacity - 70,000 B,C '.1:ere
- is no safety-related o equipment at this elevation o lbs.
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O O O TO IIE lif;EI)
IN CON.IllNCTION LIFTING DEVICE Iloist 49-1, 49-2 (IL51-E043, 2L51-E043) WITil 1)RAWING 021-002 BUILDING: Reactor Buildin8 PERRY llEAVY l.0AI)S STUDY ELEVATION: 607'-3" IHpACT AREA: COLUMN LINE See Dwg. 021-002 llaza rd Safety Related' Floor Elimination Load Equipment Elevation Category Remarks Drywell personnel None 604'-11-1/4" B,C There is no safety-related lock equipment equipment in the impact area removal at this elevation 6000 lbs (max)
None 574'-10" B,C There is no safety-related capacity - 6,000 equipment at this elevation o lbs. in the impact area O
t a
O O O TO CE IIPEll IN CONJUNCTlHN LIFTING DEVICE Iloist 50-1, 50-2 (iL51-E043, 2L51-E043) WITil DRAWINGll21-00?
BUILDING: Reactor Building and Intermediate Building PERRY llEAVV lfiAllS Silli)Y ELEVATION: 606'-3" IIIPACT AREA: COLUMN LINE (50-1) IB-C to IB-E; (50-2) IB-L to IB-N 18-5 to IB-2 IB-5 to 18-2 llazard Safety Related Floor Elimination Load Equipment i Elevation Category Remaiks CRD alternate None 604'-11-1/2" B,C There is no safety-related removal through equipment in the impact area personnel hatch to at this elevation Intermediate i Building None 574'-10" B,C There is no safety-related l equipment in the impact area 8 Capacity - 6,000 at this elevation
'j' lbs.
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O O O TO IIE IlSED IN CON.IllNCTluN
. LIFTING DEVICE Iloist 51-1, 52-2 (IL51-E044, 2L51-E044) WITil DRAWING 021-002 BUII, DING: Reactor Building PERRY llEAVY 1.0 Alls STUDY ELEVATION: 625'-0" IMPACT AREA: COLUMN LINE See Dwg. 021-002 I
Ilazard Safety Related Floor Elimination I.oa d Equipment Elevation Category Remarks , , _ .
CRD and cask None 599'-9" B,C There is no safety-related removal to drywell equipment in the impact area l
6000 lbs (max) at this elevation None 574'-10" B,C There is no safety-related Capacity - 10,000 equipment in the impact :rea o lbs. at this elevation O
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O O O TO BE IISEA IN CONJUNCTiph LIFTING I)EVICE Iloist 58 (L51-E050) WITH DRAWING 31-002 BUILDING: Control Complex PERHY llEWY IJ1 ADS STUDY ELEVATION: 612'-6" IMPACT AREA: COLUMN LINE CC-D to CC-C; CC-5 to CC-4 Hazard Safety Related Floor Elimination Load Equipment Elevation Category Remarks Nuclear Closed None 599'-0" B There is no safety-related Cooling Pump equipment in the impact area Maintenance at this elevation 6385 lbs (max) ECC lleat Exchangers IP42-B001B 574'-10" A Train A lleat Exchanger.. a re in Capacity - 8,000 2P42-B001B an adjacent cubicle and cannot g lbs. be damaged with this Ir,ad drop Y
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O O O TO EE ilSEli IN CON.IINCTinN LIFTING DEVICE Iloist 59 (L51-E050) WITil DHAWINt; 021-002 BUILDING: Control complex l'El(RY llEAVY I.0 Alls STllDY ELEVATION: 612'-("
IMPACT AREA: COLUMN LINE CC-D to CC-E; CC-5 to CC-4 llaza rd Safety Related Floor Elimination I.oad Equipment Elevation Category Remarks Nuclear Closed None 599'-0" B There is no safety-rela t eil Cooling Pump equipment in the impact area Maintenance at this elevation 6385 lbs (max) ECC lleat Exchangers JP42-B001B 574'-10" A Train A Ileat Exchany.ers are in Capacity - 8,000 2P42-B001B an ad.lacent cubicle g lbs.
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O O O TO BE USED IN CONJUNCTION LIFTING DEVICE Iloist 60 (151-E050) WITil DRAWING 021-002 BUILDING: Control Complex l'ERRY llEAVY I.0 Alls STUDY ELEVATION: 612'-6" IMPACT AREA: COLUMN L?NE CC-D to CC-E; CC-5 to CC-4 Hazard Safety Related Floor Elimination Load Esinipment Elovation Catey ry Remarks Nuclear Closed None 599'-0" B There is no safety-related Cooling Pump l equipment in the impact area Maintenance at this elevation 6385 lbs (max) ECC Pumps IP42-C001B 574'-10" A Train A Pumps are in an adiacent Capacity - 8,000 2P42-C001B cubicle and cannot s,0 dams.se d in o lbs.
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KEY TO DRAWING 021-007 El. 689'-6" CONTROL COMPLEX TAG NUMBER MCC, Switchgear, and Battery H51-P0164 Room HVAC instrument H51-P0165 Rack H51-P0166 H51-P0167 Control Room HVAC and H51-P0152 Emergency Recirculation H51-P0153 Instrument Rack Control Room HVAC Supply M25-B001A Plenum M25-B001B Control Room HVAC Supply M25-C001A Fan M25-C001B Control Room HVAC Return M25-C002A Fan M25-C002B i
MCC, switchgear, and Electrical M23-B001A Equipment Area Supply Plenum M23-B001B MCC, Switchgear, and Electrical M23-C001A Equipment Area Supply Fan M23-C001B MCC, Switchgear, and Electrical M23-C002A Equipment Area Return Fan M23-C002B l
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O O O TO BE USED IN CONJUNCTION 1.1FTING DEVICE Holst 52 (L51-E045) WITli DRAWING 021-007 BUILDING: Control Complex PERRY HEAVY IBADS STUDY ELEVATION: 693'-6" IHpAct AltEA: COLUMN LINE CC-B to CC-C; CC-1 to CC-2 Hazard Safety Related Floor Elimination I,oad Equipment Elevation Category Remarks llatch and None 679'-6" B There is no safety-related Ventilation equipment in the impact area l Equipment Removal at this elevation 6000 lbs (max)
None 654'-6" B There is no safety-related equipment in the impact area l Capacity - 6,000 8 s. at this elevation 638'-6" B There is no safety-related equipment in the impact area at this elevation
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Emergency Service Water IP45-D002A 2P45-D002A Pump Discharge Strainer IP45-D002B. 2P45-D002B IPi5-D003 2P45-D003 Emergency Service Water P49-C002A Screen Wash Pump P49-C002B Emergency Service Weter P49-D001A Pumphouse Intake Screen P49-D001B Emergency Service Water P49-D003A Screen Wash Pump P49-D003B Discharge Strainer ESW Ventilation Fan IM32-C001A 2M32-C001A
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Control Panels for H51-P010A Intake Screens H51-P010B l
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llirt4 mso ) NON0lVl510NAL EQUIPuENT NUESIR i itse sma) O lH5Poloe} (@ (IP45 6008 *) O
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SECTION II I EVALUATION OF REACTOR BUILDING CRANE l I
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INTRODUCTION The reactor building crane is used extensively during refueling outager..
Drawing 021-009 depicts the laydown areas and the transit paths. Since all heavy loads are lif ted and transported by the reactor building crane when the reactor is in cold shutdown, damage to the residual heat removal system (in the shutdown cooling mode) is the only active safe shutdown system that stat be considered for heavy load drop damage inside containment. In addition to the RHR piping, the potential for damage to fuel due to a heavy load drop must be evaluated. A written description of the refueling procedurc is given in Section 9.1.4.2.10.2 of the Perry FSAR. The capacity of the Reactor Building Crane is 250,000 lbs.
Since the layout of Unit 2 containment is " opposite hand" to Unit 1, only Unit 1 is discussed; all findings for Unit I will apply to Unit 2.
The report summary identifies potentially hazardous lifts within containment as weil as the balance of plant.
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TO BE USED j IN CONJUNCTION l LIFTING DEVICE Reactor Building Crane WITil DRAWING o21-009 BUILDI!;G: Reactor Building PERRY llEAVY LOADS STUDY l EL3VATION: 72t '-0" IMPACT AREA: COLUMN LINE (see Drawing 021-009) ilaza rd Safety Related Floor Elimination Load Equipment Elevation Category Remarks
- 1. . Drywall llead Reactor Vessel and r>8 9 ' -6" See Renuarks 1. Analysis has shown that drop 130,000 lbs Fuel over reactor would not cause l damage to the vessel and internals, including fuel.
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Monc fi8 9 ' -6" B 2. The load path from the reactor l to the storage location does not ps::s over safety-related equipment at this elevation li64 '-7 " 8 None 3. There is no safety-related equipment in the Impact area at this elevation fitandby Liquid !i4 2 ' -0" C 4. Systems are not used during Control Tank -
cold shutdown l IC41-A001 2C41-A001 litandby I.lquid Dontr01 Pumps -
IC41-C001A, H 2C41-C002A, B fiafety Relief ADS Valve Air Accumulators
O O O TO llE USED I;i CONJUNCTION f,IFTING DEVICE Reactor Building Crane WITH DRAWING 021-009 Ilull. DING: Reactor Building PERRY llEAVY LOADS STUDY ELEVATION: 721'-0" litPACI' AREA: Col.UHN LINE (see Drawing 021-009)
^11azard Safety Related Flcor Elimination 1.oad Equipment. Elevation Category Remarks
- 1. Drywell llead control Rod Drive 620'-6n C 5. Operability of these untia 130,000 lbs l
flydraulic Control are not required after scram-(cont'd) Units ICIl-D001 2Cl1-D001 8 RilR (Loop B) 617'-0" to C,A 6. The RilR system will he in the i
piping - E12 RilR 630'-0" shutdown cooling mode during this liit. If loop A piping is damaged, Loop B system can be used for core cooling RilR/Feedwater 625'-0" A 7. If Loop A piping is damaged, piping - N27 FW Loop B system can be used for core cooling None 599'-0" B 8. There is no safety-related equipment in the impact area l
at this elevation None 574'-10" B 9. There is no safety-related l equipment in the impact area
! at this elevation
O O O TO BE USEll IN CONJUNLTION IlFTING DEVICE Reactor Building Crane WITil DRAWING 021-009 Bull.IllNG: Reactor Building PERRY llEAVY 1.0 ADS STUDY ELEVATl0N: 721'-0" lHPAtil' AREA: Col,tRIN I.lHE (see Drawing 021-009) llaza rd Safety Related Floor Elimination I.na d Esinipment Elevation Category Remarks
- 2. Vessel llead Reactor Vessel and 689'-6" , See Remarks 1. Drop over reactor would not l Piping Bundle Fuel damage reactor and internals, 1300 lbs including fuel.
None 689'-6" B
- 2. Theloadpathfromthereactorl to storage area does not pass 8 over any safety-related y equipment at this elevation None 664'-7" B 3. There is no safety-related l equip mat in the impact area at this elevation Safety Relief ADS 642'-0" G 4. Operability is not required l Valve Air during cold shutdown Accumulators l
IB21-abo 3 A, B 1 2B21-A003 A, B l
l Control Rod Drive 620'-6" C 5. Operability is not required l
, flydraulic Control after rod insertion.
I Units ICIl-D001 2Cll-D001 I
O O O TO BE USED IN CONJUNCTION IlFTING DEVICE Reactor Building Crane WITil DRAWING 021-009 BullJIING: Reactor Building PERRY llEAVY I.0 ADS STUDY El.EVATION: 721'-0" IHrAcr AREA: COI.flHN I.lHE (see Drawing 021-009) llaza rd Safety Related Floor Elimination I.oad Equipment Elevation Category Remarks
- 2. Vessel llead RIIR (loop B) 617'-0" to C,A 6. TheRilRsystemwillbeinthel Piping Bundle Piping - E12 RilR 630'-0" shutdown cooling mode during (cont'd) -
this lift. If loop A piping is damaged, loop B sy.atem can be us:4 for core cooling g RilR/Feedwater 625'-0" A 7. If loop A piping is damaged. l Piping - N27 FW loop B system can be used for 7*- core cooling None 599'-0" B
- 8. There is no safety-related equipment in the impact area at this elevation None 574'-10" g 9. There is no safety-related l equipment in the impact area at this elevation
- 3. Thermal Reactor Vessel and 689'-6" See Remarks 1. Drop over reactor would not l
Insulation Fuel cause damage to fuel and RPV top llead vessel.
10,000 1ha None 689'-6" B 2. Theloadpathfromthereacted to the storage location d as not pass over any safety-related equipment at this elevatbn
O O O TO DE ilSED IN CONJUNCTION I,IFTING IIEVICE Reactor Euilding Crane WITil DRAWING 021-009 Bull.i;l NG: Reactor Building PERRY llEAVY 1.0 Alls STUDY EI.EVATION: 721'-0" IIIPALT AltEA: Col,UMN 1.INE (see Drawing 021-009)
Hazard Safety Related Floor Elimination I,oad Equipment Elevation Category Remarks
- 3. Thermal None 664'-7" B 3. There is no safety-related l Insulation equipment in the impact area RpV Top Ilead ,
at this elevation 10,000 lbs (cont'd) Safety Relief ADS 642'-0" C 4. Operability is not required l Valve Air during cold shutdown o Accumulators y IB21-A003 F.G,H un 2B21-A003 F.C.H Conrol Rod Drive 620'-6" C 5. Operability is not required l
Hydraulic Control after rod insertion.
Units ICIl-D001 2Cll-D001 RllR (Loop B) 617'-0" to C,A 6. TheRllRsystemwillbeinthel Piping - E12 RilR 630'-0" shutdown cooling mode during this lift. If loop A piping is damaged, loop B system can be used for core cooling RIIR/Feedwater 625'-O" A 7. If loop A piping is damaged, l t
Piping - 1127 FW loop B system can be used for l core cooling I
O O O TO BE tlSED IN CON.it!NCTION l.IFIING DEVICE Reactor Butiding Crane WITil DRAWING 021-009 llull. DING: Reactor Building PERRY llEAVY I.0AI)S STUDY ELEVATlHN: 721'-0"
- lilPACr AREA: Col,UHN I.INE (see Drawing 021-009)
. Hazard i Safety Related Floor Elimination I.uad EquipmenL ElevaLion Category Remarks
- 3. Thermal None 599'-0" 8. There is no sofety-related B
insulation RPV equipment in the ir pact area Top Ilead at this elevation -
10,000 lbs (cont'd) None 574'-10" B
- 9. There is no eifety-related g
l o equipment in the Impact area
'f' at this elevation cn
- 4. RPV Ilead and Reactor and Fuel 689'-6" ' i See Remarks 1. Drop o* er reactor would r>ot l O-Rings, and damage vessel and fuel.
Ilead Strong Back 56,000 +
180,000 = None 689'-6" B 2.
236,000 lbs The load path from the reactor (
to the storage location does not (total) pass over safety-related equipment None 664'-7" B 3. There is no s'afety-related l equipment in the impact area at this elevation Safety Relief ADS - 642'-0" C
- 4. Operability is not required l Valve Air during cold shutdown Accumulators .
IB21-A003 E,F,C 2B21-A003 E F,B
O O O TO DE IISED IN CONJIINCTION l.lF11NG DEVICE Reactor Building Crane WITil DRAWING 021-009 i
Bill t,DI NG: Reacto: Building PERRY llEAVY LDADS STUDY EI,EVATION: 721'-0" IrlpAcr AREA: COI.UNN I,INE (see Drawing 021-009) llazard SaIcty Related Floor Elimination I.oail Equipment Elevation Category Renarks
- 4. RpV llead and Control Rod Drive 620'-6" C 5. Operability is not required O-Rings, and Ilydraulic Control during cold shutdown l
llend Strong Units Back ICll-D001 56,000 + 2Cl1-D001 -
180,000 =
g 23o,000 lbs RilR (Loop A) 617'-0" to '^ 6. The RIIR system wt11 be in the g (total) Piping -- E12 RilR 630'-0" shutdown cooling mode during L this lift. If loop A piping is damaged, loop B syst m can be used for core cooling RilR/Feedwater 625'-0" A 7. If loop A piping is damaged, Piping - N27 FW loop B system can be used for core cooling Reactor Pressure and 620'-6" A 8. There are 3 other trains of -l Level Instrument instrumentation Rack A 11122 9004 A,B.C 21122-P004 A,B,C None 599'-0" B 9. There is no safety-related l equipment in the impact are.1 at this elevation B l None 574'-10" 10. There is no safety-related I-equipment in the impact area at this elevatton
O O O TO BE tiSED IN CONJUNCTION l.IFTING DEVICE Reactor Building Crane MITil DRAWING 021-009 Billi.DlHG: Reactor Building PERRY llEAVY 1. DADS STUDY El.EVATION: 721'-0" IHI'MT AREA: COI.UHN l.lHE (see Drawing 021-009)
Hazard SaIcty Related Floor Elimination I.oad Equipment Elevation Category Remarks
- 5. Dryer- Reactor Vessel and 689'-6" See Remarks 1. Drop over reector would not l Separator Fue; damage reactor vessel and Strong Back fuel.
8000 lbs None 689'-6" B 2. Theloadpathfromthestoragel area to the reactor do:.s not g pass over safety-related y equipment at this elevation m
Hone 664'-7" B 3. There is no safety-related l
equipment in the impact area at this elevation Standby 1.iquid 642'-0" C 4. Operability la not required control Tank during cold shutdown IC41-A001 2C41-A001 Standby 1.iquid Control Pumps IC41-C001 A, B 2C41-C001 A, B Safety Relief ADS Valve Air Accumulators IB21-A003 B.C.D 2B21-A003 B.C.D
TO IIE USED IN CONJUNCTION I,IITING llEVICE Reactor Building Crane WITil DRAWINt; 021-009 llull, DING: Reactor Building PEllRY IIEAVY 1.0AliS STilDY El.EVATION: 721'-0" lHPACT AREA: Col.lilIN 1.1NE (see Drawing 021-009) llazard Safety Related Floor Elimination 1.oad Equipment Elevation Categocy Rma rks
- 5. Dryer- Control Rod Drive 620'-6" C 5. Operability is not required Separator Ilydraulic Control during cold shutdown Strong Back Units 8000 lbs (cont'd) RIIR (Loop B) 617'-0" to C,A 6. The RilR systeta will be it. the l Piping - E12 RilR 630'-0" shutdown cooling mode during o this lift. If loop B piping y is damaged, loop A system can e be used for core cooling RIIR/ Feedwa ter '625'-0" A 7. If loop B piping is damaged, piping - N27 FW loop A system can be used for core cooling None 599'-0" 3 8. There is no safe ehutdown l
equipment in the impact area at this elevation None 579'-10" B 9. There is no safe shutdown l equipment in the impact area at this elevation
- 6. Steam Dryer Reactor Vessel and 689'-6" 1. Urop over the reactor could and Strong Fuel possibly cause damage to the Hack vessel and fuel. Further 8000 + 106,00( analysis is required
= 114,000 lbs
O O O TO IlE USEll IN CONJUNCTION tlFTING DEVICE Reactor. Building Crane WITil DRAWING 021-009 llUll. DING: Reactor Building PERRY llEAVY f.0 ADS STilDY EI,EVATION: 721'-0" lill'ACr AREA: 001,l#1N 1.INE (see Drawing 021-009)
~~
llazard Safety Related Floor Elimination I.oad Equipment Elevation Category Remarks
- 6. Steam Dryer None 689'-6" B 2. Theloadpathfromthereactorl and Strong to the storage area does not Back pass over safety-related 8000 + 106.000 equipment
= 114,000 lbs (cont'd) None 664'-7" B 3. There is no safety-related o equipment in the impact area y at this elevation Hone 642'-0" B 4. There is no safety-related l equipment in the impact area at this elevation Hainsteam isolation 620'-6" C
- E*#8 Y" N" #*
Valves, Relief Valves during cold shutdown RilR/Feedwater 617'-0" to A 6. If loop B piping is damaged, l (Loop B) Piping - 630'-0" loop A ayatem can be used for N27 FW core cooling None 574'-10" B 7. There is no safety-related l equipment in the impact area at this elevation
- 7. Separato'r and Reactor Vessel and 689'-6" See Remarks 1. Drop over the reactor would l Strongback Fuel not cause damage to the 8000 + 68,000 . vessel and fuel.
= 76,000 lbs
- . J TO BE USEI)
IN CONJUNCTION LIFTING DEVICE Reactor Building Crane WITH DRAWING 021-009 IlUILDING: Reactor Building I'ERRY llEAVY I.0 ADS STUDY EI.EVATION: 721'-0" tilPACT AREA: Col,UHN l.lNE (see Drawing 021-009)
Hazard SaIcty Rel.sted Floor Elimination -
Ioad Equipment Elevationi Category Remarks
- 7. Separator and None 689'-6" B 2. The load path from the reactor l Strongback to the storage location does 8000 + 68,000 not pass over safety-related
= 76,000 lbs equipment at this elevation (cont'd)
None 664'-7" B 3. There is no safety-related l
o equipment in the impact area y at this elevation C B 642'-0" 4. There is no safety-related equipment in the impact area at this elevation Mainsteam Flow and 620'-6" ^ 5. There are 3 redundant trains Instrument Racks of instrumentation lil22-PO42 21I22-PO42 RilR Common Shutdown 625'-0" ^ 6. If the shutdown cooling node Suction Piping - E12 for the RIIR is jeopardized RilR due to piping damage, the core can be cooled by either RilR loop in the emergency core cooling mode
.m O a O TO BE USED IN CONJtlNCTION I,lFTING llEVICE Reactor Building Crane WITil DRAWING 021-009 pijlLDING: Reactor Building PERRY llEAVY I.0 ADS STUDY El.EVATION: 721'-0" IflPACT AREA: Col,UllN l.lNE _(pee Drawing _021-009) llazard Safety Related Floor Elimination I,oad Evin ipment Elevation Category Remarks
- 7. Separator and RilR/Feedwater pip 3ng 625'-0" A 7. If the shutdown cooling mode Strongback for the RilR is jeopardized l
8000 + 68,000 due to piping damage, the core
= 76,000 lbs can be cooled by either RilR (cont'd) loop in the emergency core cooling mode 8
y None 599'-0" B 8. There is not safety-related l g equipment in the impact area at t'ils elevation None 574'-10" B 9. There is no safety-related l equipment in the impact area at this elevation
- 8. Refueling Chute Reactor Vessel and 689'-6" D 1. Refueling pcocedure will 36,000 lbs Fuel preclude load path over reactor None 689'-6n B 2. The lond path from the chute to its storage location does not pass over safety-related equipment None 642'-0" B 4. There is no safety-related l equipment in the impact area at this elevation
O O O TO DE USED IN CONJtlNCTION l.lFTING DEVICE Reactor Building Crane WITil DRAWING 021-009 BUII. DING: Reactor Building PERRY llEAVY I0 ADS STUDY ELEVATION: 721'-0" 1HPACT AREA: COLUHN I.INE (see Drawinn 021-009)
Hazard Safety Related Floor Eliminatson Ioad Equipment Elevation Category Remarks
- 8. Refuelleg Chuto None 620'-6" 5. There is no safety-related 36,000 lbs equipment in the impact area at this elevation RilR (Inop A) Piping 617'-0" t . e H system will be in E12 RHR 630'-0" C'A the shutdown cooling mode o during this lift. If loop A O piping is damaged, loop B h system can be used for core cooling RIIR/Feedwa ter 625'-0" A 7. If loop A piping is damaged, Piping - N27 PW loop B system can be used for core cooling None 599'-0" B 8. There is no safety-related l equipment in the impact area at this elevation l
None 574'-10" B 9. There is no safety-related equipment in the impact area at this elevation
- 9. Refueling Gates None 689'-6" B No safety-related equipment in G41-E00lA 1670 lbs impact area l
G41-E001B G41-E002A 1565 lbs G41-E002B
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EVALUATION OF FUEL HANDLING BUILDING CRANE O
e 9
4 i
O s
-- - . _ _ _ _ = . - .
I t
.l
.A INTRODUCTION The fuel handling building crane is used primarily during spent fuel shipping ,
cask operations and new fuel receiving. Drawing 021-010 shows the operating floor elevation of the fuel handling building with the crane coverage area.
Since the spent fuel shipping cask is the heaviest load handled in the crane coverage area, the heavf loads evaluation considered only accidental drops of the cask.
No safe shutdown equipment is housed within the crane coverage area and the fuel handling building crare's coverage does not include any of the spent fuel pools.
The report susunary identifies potentially hazardous lifts in .the fuel handling building as well as the balance of plant.
l O
III-l
O O 10 llE USED o
l IN CONJUNCTl0N Fuel Handling Building Crane WITH DRAWIN(; 021-010 l
1.lFTING DEVICE IIHil.IllNG: Fuel llandling Building PERRY HEAVY I.0 ADS STUDY EI.EVATION: 661'-3" ,
IH1'ACT AREA: CUI.ttlN 1.lNE IB-8 to 18-10 l
i Hazard Safety Related Floor Elimination Elevation Category Remarks I.oad Eviuliment Fuel Shipping Cask None 620'-6" Note on Dwg. 021-010 that the crane 250,000 lbs (max) coverage area is not over the spent fuel pool or any area where (All other loado Hone 599'-0" spent fuel or safety-related handled by the Fuel equipment is housed ,
Ilandling Building o crane weigh less None 574'-10" See Remarks 1. Analysis has shown that a load l
drop at the west end of the -
p and have less crane coverage area will not
- sectional density so that evaluation degrade the spent fuel pool of other loads is leakage integrity.
not necessary)
See Remarks 2. Procedures and design l Capacity - 250,000 limitations prevent the cask Ibs. from being dropped swire than 1
30 feet so that the impact design of the cask is not exceeded e
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