ML20010J614
| ML20010J614 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 09/28/1981 |
| From: | CLEVELAND ELECTRIC ILLUMINATING CO. |
| To: | |
| Shared Package | |
| ML20010J608 | List: |
| References | |
| REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR 2329, 2329-R01, 2329-R1, NUDOCS 8110060231 | |
| Download: ML20010J614 (10) | |
Text
r June 19, 1981 GAI Report No. 2329 Revision 1 September 28, 1981 CONTROL OF HEAVY LOADS STLTY THE CLEVELAND ELECTRIC ILLUMINATING COMPANY PEhRY NUCLEAR POWER PLANT UNITS 1 AND 2 Docket Nos. 50-440, 50-441 0110060231 810928 PDR ADOCK 05000440 A
- PDR,
SUMMARY
CONCLUSIONS The Perry Nuclear Power Plant, in general, has been designed to avoid potentially damaging drop ~s of heavy loads.
Areas of the plant housing fuel or safe shutdown equipment have been evaluated and have been found to be free of hazards due to heavy loads, as defined by NUREG-0612, except the following:
Heavy Load Movements Requiring Administrative Procedures l R1 Loads lifted in the steam tunnel must be made only during cold shutdown a.
since damage to both main steam and feedwater lines can be caused simultaneously (refer to Drawing 021-003).
b.
The movement of _eavy loads in the emergenc'y ' service water pump house, i
especially one of the emergency service water pumps over the redundant system components, must be controlled by adelaistrative procedures (refer to Drawing 021-008).
The refueling chute must be moved within the reactor building by an c.
appropriate procedure so that it is not moved over the reactor vessel (refer to Drawing 021-009).
Analyses have been perfcrmed of the consequences of load drops over the reactor pressure vessel and in the spent fuel pool area. The postulated load drops do not t+sult in damage to the fuel in the core, jeopardize the vessel's ability to keep the core floaded, nor degrade the spent fuel pool leakage integrity.
R1 1
Reference:
" Structural Analysis of Reactor Pressure Vessel and Internals for Vessel Head Drop, Shroud Head Assembly Drep, and Steam Dryer Assembly brop Conditions," April 1977, (NEDC-23566).
6
TO BE USED IN CONJUNCTION WITil DRAWING 021-009 LIFTING DEVICE Iteactor Building Crane PERRY HEAVY LOADS STUDY BUILDING: Iteactor tiuilding ELEVATIofi: 721'-0" IMPACT AREA:
COLUMff LIf1E (see Drawing 021-009)
Hazard Safety Related Floor Elimination Remarks Load Equipment Elevation Category 1.
I rywell IIcad Iteactor Vessel and l>89'-6" E
1.
Analysis has shown that drop over reactor would r.ot cause 130,000 lbs Fuel R1 damage to the vessel and I-ternals, including fuel.
l i
S E
rione 489'-6" E
2.
The load path from the re.setor to the storage location does
~
not pass over safety-related equipment at this elevation 90:ae L>64 '-7 "
E 3.
There is no safety-related equipment in the impact area j
at this elevation j
l litandby Liquid L>4 2 ' - 0" F
4.
Systems are not need during cold shutdown
- ontrol Tank IC41-A001 2C41-A001 litandby I.fquid
(:ontrol l' umps IC41-C001/., B 2C41-C002A, B fiafety itelief ADS Valve Air
,\\ccumul a t o rs im g
10 HE USEI)
IN C0h.10NCTION 1.llTING DEVICE Reactor Building Crane WITil 1)RAWING 021-009 lillli. DING:
Reactor Building PERRY llEAVY I.0 ADS STtIDY El.EVAT iota :
721'-0" lill'ACr AREA: COI.lititi I.I NE _ (see Drawing _021-00'.;)
llaza rd Salcty Related Floor Elimination Eigniiment Elevation Category Remaiks l.na d t
2.
Vessel llend Reactor Vessel and 689'-6" E
1.
Drop over reactor wm:Id not l'iping thindle Fuel dar age reactor and internals, RI 1300 lbs Including fuel.
None 689'-6" E
2.
The load path from the reactor to storage area does not pass 8
over any safety-related equipment at this elevation None 664'-7" E
3.
There is no safety-related equipment in the impact area at this elevation Safety Relief ADS 642'-0" F
4.
Operability is not required Valve Air during cold shutdown
~
Accumulators IB21-A003 A, D
21121-A003 A, B Corstrol Rod Drive 620'-6" F
5.
Operability is tot required Ilydraulic Control after rod insertion.
lini t s ICla-D001 2Cl1-D001
TO IlE USED IN CONJUNCTION I.llTING llEVICE Reactor Building Crane WITil llRAWING 021-009 f.Illi.DI NG:
Reactor Bailding l'ERRY IfEAVY I.0 Alls STUDY El.Eva rlon:
721'-0" IllPACI AREA: COI.lillN 1.INE (see Drawing 021-009) llaza rd Safety itelated Floor Elimination 1.oa d Epipment Elevation Category Remarks 2.
Vessel llead RilR (loop B) 617'-0" to F, B 6.
The RilR system will be in the Piping Ilundle Piping - E12 RilR 630'-0" shutdown cooling mode during this lift.
If loop A piping (cont'd)
I is damaged, loop B system can l
be used for core cooling B
7.
If loop A piping is damaged, RilR/Feedwater 625'-0" g
loop B system can be used for y
Piping - N27 FW core cooling s-None 599'-0" E
8.
There is no safety-related equipment in the impact area at this elevation l
None 574'-10" E
9.
There is no safety-related equipment in the lupact area at this elevation 3.
Thermal Reactor Vessel and 689'-6" E
1.
Drop over reactor would not Insulation Fuet cause damage to fuel and R1 RPV top Ilead vessel.
10,000 lbs None 689'-6" E
2.
The load path from the reactor to the storage location does not pass over any safety-related equipment at this elevation
TO IlE tlSED IN CON.lUNCTION I.lFTING DEVIEE Reactor Building Crane WITil DRAWING 021-009 PERRY HEAVY I.0 ADS STUDY lillll.DI NG:
Reactor iluilding El.1;VA r lini:
721'-0" lilPACT ARE.
Col.litita 1.INE..(Hue _ Drawing _Il21-009)
Hazard Safety Related Floor Elimination 1.oa d Esgu i pment Elevation Category Remarks 3.
Thermal None 599'-0" E
8.
There is no selety-related Insulation RPV equipment ja the in. pact area Top Ilead at this elevation 10,000 1bs (cont'd)
None 574'-10" E
9.
There is no safety-related equipment in the impact area 8
at this elevation T*
4.
RPV llead and Reactor and Fuel 689'-6" E
1.
Drop over reactor would not 0-Rings, and damage vessel and fuel.
RI 11ead Strong Back 56,000 +
180,000 =
None 689'-6" E
2.
The load path from the reactor 236,000 lbs to the storage location does not l R1 (total)
, pass over safety-related equipment None 664'-7" E
3.
There is no safety-related equipment in the impact area at this elevation Safety Relief ADS 642'-0" F
4.
Operability'is not required Valve Air during cold shutdown Accumulators IB21-A003 E,F,G 2B21-A003 E,F,B
To llE ilSED IN CON.luNCTION Reac.nr Building Crane WITil DRAWING 021-009 e
l.lFTING DEVICE Illill.DI NG:
Reactor Buildinn PERRY llEAVY I.0 ADS STUDY El.EVATiori:
721'-0" lill'Mir Al:EA:
Col.tlHit I.l tlE (see lirawing 021-009) llazard SaIcty Related Floor Elimination 1.oa d Estu i pment Elevation Category Remarks 5.
Dryer-Reactor Vessel and 689'-6" E
1.
Drop over reactor would not Separator Fuel damage reactor vessel and fuel.
El Strong Back 8000 lha None 689'-6" E
2.
The load path from the storage area to the reactor does not pass over safety-related g
7 equipment at this elevation y
I m
None 664'-7" E
3.
There is no safety-related equipment in the impact area at this elevation Standby I.iquid 642'-0" F
4.
Operability is not required Control Tank durirg cold shutdown IC41-A001 2C41-A001 Standby Liquid Control Pumps 1C41-C001A, B 2C41-C00lA, B Safety Relief ADS Valve Air Accumulators lil21-A003 B,C,D 2B21-A003 B,C.D
TO IlE USED IN CONJUNCTION 1.lFTlHG DEVICE Iteactor. Building Crane WITil 1)RAWING 021-009 litill.DI NG:
Reactor Building PERRY IIEAVY I.0 ADS STUDY Ei.EVAT ion:
721'-0" lllPACT AHEA:
Col.UHil 1.I NE (see Drawing 021-009) llazard Safety Related Floor Elimination I.oa d Espa i pment Elevation Category Remarks 6.
Steam Dryer None 689'-6" E
2.
The load path from the reactor and Strong to the storage area does not Back pass over safety-related 8000 + 106,000 equipment 114,000 lbs
=
(c on t ' d)
None 664'-7" E
3.
There is no safety-related o
equipment in the impact area S
at this elevation None 642'-0" E
4.
There is no safety-related equipment in the impact area at this elevation Mainsteam Isolation 620'-6" F
5.
Operabiltty is not required Valves, Relief Valveti during cold shutdown RilR/ Feedwa ter 617'-0" to B
6.
If loop B piping is damaged, (loop B) Piping -
630'-0" loop A system can be used for N27 FW core cooling None 574'-10" E
7.
There is no safety-related equipment in the impact area at this elevation 7.
Separator and Reactor Vessel and 689'-6" E
1.
Drop over the reactor would l
Strongback Fuel not cause damage to the R1 8000 + 68,000 vessel and fuel.
= 76,000 lbs
TO IIE USED IN CONJUNCTION 1.IFTING DEVICE Fuel llandling Building Crane WITil DRAWilit; 021-010-PERRY llEAV1 1.0 ADS S'lullY lillil.Ill NG:
Fuel llandling Building El.EVAT i oN :
661'-3" Ifil'Acr AREA:
Col.llflN l.I NE IB-8 to IB-10 llazard Safety Related Floor Elimination 1.oa d Equipment Elevation Category Remarks Fuel Shipping Cask None 620'-6" Note na Dwg. 021-010 that the crane 250,000 lhs (max) coverage area is not over the spent fuel pool or any area where (All other loads None 599'-0" spent fuel or safety-related handIed Iv the Fue1 equipment is housed llandling ilullding o
crane weigh less None 574'-10" E
1.
Analysis has shown that a load o
and have less drop at the west end of the sectional density crane coverage area will not R1 so that evaluation degrade the spent fuel pool leakage integrity.
of other loads is not necessary) 2.
Procedures and design limitations prevent the cask from being dropped more than 30 feet so that the impact design of the cask is not exceeded l
1