ML20126F094
| ML20126F094 | |
| Person / Time | |
|---|---|
| Site: | San Onofre |
| Issue date: | 12/24/1992 |
| From: | SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML20126F039 | List: |
| References | |
| NUDOCS 9212300108 | |
| Download: ML20126F094 (16) | |
Text
_ _ _ _ _ _ _ _ _ _ _ _
ATTAcitMENT A Existing Specifications Unit 2 9212300108 921224 PDR ADOCK 0b000361 P
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REFUELING OPERATIONS 3/4.9.7' FUEL NAHOLING MACHINE - SPENT FUEL STORAGE PCOL BUlt0!NG y
i l!HITING CON 0! TION FOR OPERATICN 3.9.7 leads in excess of 2000 pounds shall be prohibited from travel over fuel assemblies in the storage pool except for the following four cases:
Spent fuel pool gates shall not be carried at a height greater than a.
30 inches (elevation 36' 4") over the fuel racks.
b.
Test equipment skid (4500 pounds) shall not be carried a~f. a height greater than 72 inches (elevation 39' 10") over rack cells which contain Unit 2 fuel assemblies or greater than 30 feet 8 inches (elevation 64' 6") over rack cells which contain Unit 1 fuel-assemblies, Installation or removal of the cask pool cover over the cask pool c.
with fuel in the cask pool.
The cover, fuel, and racks will be removed from the cask pool on co=pletion of the raracking proces,s.
d.
The lift of construction loads, including the teeporary gantry crane and the old and the new fuel storage racks (including lif ting n
equipment and rigging), above the cask pool with the cask poof. cover
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in place and fuel in the cask pool.
This includes tesporary storage of these construction loads on-the cask pool cover:during cons'truction.
These lifts are prohibited prior to a minimum fuel decay tirce of 88 days for all stored spent fuel assemblies.
APPLICABIl!TY:
With fuel assemblies in the storage pool.
ACTION:
With the requirements of the above specification not satisfied, place the fuel.
handling machine in a safe condition.
_ SURVEILLANCE REQUIREMENTS 4.9.7 Fuel handling sachine interlocks and physical stops which prevent-fuel handling machine travel with loads in excess of 2000 pounds over fuel assemblies shall be demonstrated OPEP).SLE within 7 days prinr to fuel handling machine use and at least:ence per 7 days thereafter during fuel handling machine operation, i
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a SAN ONOFRE-UNIT 2 3/4 9-7 MENOMENT Hot 87-
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REFUELING OPERATIONS
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MTt requirements for tne refueling machine ensure that:
(1) the refue; ira
? chine will be used for movement of all fuel assemblies; including those CEA inserted, (2) each machine has sufficient lead capacity to 4
lift _
J assembly including those with a CEA, and (3) the core internals a, ',
vessel are protected from excessive lifting force in the event they
-t tdvertently engaged during lifting operations.
Five finger CEAs are removed from the reactor _ vessel either along with the associated fuel bundle utilizing the refueling machine or can.be removed without the associated fuel bundle utilizing the refueling machine auxiliary hoist.
The four finger CEAs are inserted through the upper guide-structure with two fingers in each of the two adjacent fuel bundles in the periphery-of'the core.
The four finger CEAs are either reso'ved with the upper guide.
structure and lift rig or can be removed with separate tooling prior to upper guide structure removal utilizing the auxD'ery hoist of the polar crane
-er the refueling mach"- auxiliary hoist.
Coupling and uncoupling of the CEAs and the CEDM drive shaft extensions is accomplishto using one of the gripper operating tools.
The coupling and uncoupling is verified by weighing the drive shaft extensions.
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3/4.9.7 FUEL HANDLING MACHINE - SPENT FUEL STORAGE BUILDING, r
A.
Refueling Op s.t;ons
..1 The restriction on movement of loads in excess of the ncminal weight of a fuel r.ssembly, CEA. and associated handling tool over other fuel assemblies in the storage pool ensures that in the event, this load is dropped (1) the' activity release will be-limited to that contained in six fuel assemblies.. and (2) any possible distortion of fuel. in the storage racks will not result-in a-critical array. - This assumption is-based on the calculated results which desenstrate that, with crtdit-taken for thel fuel handling building filters,. the offsite doses would be well within (less than 21%) the 10 CFR 100 liatts.
B.
Spent Fuel' Fool-Reracking Construction Activities The restriction on movement of heavy. loads over spent-fuel ensures-that in the event a heavy lead is dropped:
. SAN ONONFRE-- UNIT ?.-
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.I REFUELING OPERATION 5 8ASES 3/4.9.7 FUEL HANDLING MACHINE - SPENT FUEL STORAGE BUILDING (Continued) 1.
The radiological consequences due to complete rupture of all spent I
fuel assemblies in the spent fuel poot and the cask pool (480 maximum), will remain belev (less than 25% of) the exposure limits of 10 CFR 100 for offsite doses as long as spent fuel has received a minimum of 88 days decay time.
This analysis takes no credit for fuel handling buil hatches are open) ding filters (i.e., the fuel handling building f
2.
Any possible distortion of all fuel assemblies and racks will not p'~
result in a critical array and X will ree.ain less than 0.95, as Q,
long as fuel is stored per TechnIN1 Specifications 5.6, " Fuel l9 Storage," and 3.9.13, " Spent Fuel Pool Boron Concentration."
1 3/4.9.8 SHUT 00VN COOLING AND COOLANT CIRCULATION The requirement that at least one shutdown cooling train be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140'F as required during the REFUELING H00E, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boren dilution incident O.
and prevent b ron stratification.
9 The requirement to have two shutdown cooling trains OPERABLE when there is less than 23 feet of water above the reactor pressure vessel flange, ensures that a single failure of the operating shutdown cooling loop will not result in a ecm-plate loss of decay heat removal capacity.
With the reactor vessel head re-moved and 23 feet of water above the reactor pressure vessel flange, a large heat sink is available for core cooling, thus in the event of a failure of the operating shutdown cooling train, adequate time is provided to initiate emer-gency procedures to cool tha core.
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l SAH ONONFRE --UNIT 2 B 3/4 9-2a (ENCHENT HO. 37
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l Existing Specifications Unit 3 O
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E REFUEL NG CPERATICHS 3/a. 9. '7 FUEL HANDLING 94tstNg - SPENT FUEL STORAGE 700L' BUILO!NG y-
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.a LIMITING CCH0! TION FOR CPGAt!0N 3.9.7 t.cacs in excess of 2000 pounds shall be prohibited from travel over fuel assecoltes in the storage pool except for the following four cases:
Scent fuel pool gates shall not be carried at a height greater than a.
30 inches (elevati'on 36' a") over the fuel racks.
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b.
Test equipment skid (4500 pounds) shall not be carried at a neignt greater than 72 inches (elevation 39' 10") over rack cells wnicn contain Unit 3 fuel assemblies or greater than 30 feet 8 inch,es (elevation 64' 5") ' ver rack calls wnich'contain Unit 1 fuel o
assemblies, Installation or removal of the cask pool cover over the cask pool c.
with fuel in the cask pool.
y
.The cover, fuel, and racks will_be removed from the cask pool on' cogletion of the raracking process.
d.
The lift of construction loads, including the tegorary gantry crane and the old and the new fuel storage racks (including lif ting
- ]
equipment and rigging), above the ca.sk pool with the cask pool cover-L in place and fuel in the cask pool.
This includes temporary storage of these construction loads on the cask pool cover' during construction.
These lifts are prohibited prior to a minimum decay time of 88 days for all stored fuel assemblies.
APPLICABILITY: Vith fuel assemblies-in the stcrage pool.
ACTION:
With the requirements of the above specification not satisfied, place the fuel handling machine in a safe condition.
SUEEILLANCEREQUIREMEN'is 4.9.7 Fuel handling-machine interlocks u.: physical stops which prevent fuel handling machine travel-with loads in excess of 2000 pounds over fuel assem-blies shall be deecnstrated OPERABLE within 7 days prior to fuel handling machine use and at least once per:
g machine operation.
7 days thereafter during feel handling SAN OH0FRE - UNIT 3 3/4.9-7 AMENOMENT Ho. 77 g
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.4 FEFUELING OPERAT!0h>
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B_ASES 3/4.9.6 REFUEllM MACHINE The OPERA 31tITf requirements for the refueling machine ensure that: - (1) the refueling machine will be used for movement of all fuel assemblies including those witha a CEA inserted, (2) each machine has sufficient _ load capacity to lif t a fuel assembly including those with a CEA, and (3) the core Tinternals and pressure vessel are protected free excessive lifting. force in the event-they are inadvertently engaged during lifting operations.
+
Five finger CEAs are removed from the reactor vessel either along with the associated fuel bundle-utilizing the refueling nachine or can be removed without the associated fuel bundle utilizing the refueling.sachine auxiliary.
hoist.
The four finger CEAs are inserted through the upper-guide structure with two fingers in each of the two adjacent fuel bundles in the' periphery df the core.
The-four finger CEAs are either reeoved with the upper. guide structure and lif t rig or can be-remove.d with separate t4oling_ prior to' u guide structure removal utilizing the auxiliary hoist of the polar crane pper-the refueling nachine auxiliary hoist.
or-Coupling and uncoupling of the CEAs and the CEDM drive shaft extensions.is-O accomplished using one of the gripper operating tools.
The coupling and LI uncoupling is verified by weighing the drive shaft extensions.
3/4.9.7 FUEL HANDLING KACHINE - SPENT ~ FUEL STORAGE SUILDING A.
Refueling Operation The restriction on movement of -loads in axesss of the nominal wight of.
A fuel assembly - CEA and associated handling tool over_.other fuel assemblies in the storage pool ensures that in the event this'iond is dropped (1) the-activit and (2)y release will be limited to that contained in six fuel asseabites, any possible distortion of fuel.in the storage racks will not: result -
in a critical array.
This asstaption is based on the calculated results which demonstrate that, with credit taken for the fuel-handling building fj_1ters. the-offsite doses would be well within (less than 25%) the -
10.CFR 100 liatts.
B.
Spent Fuel Pool Raracking Construction Activities The restriction on movement of heavy loads over spent fuel ensures that in the event a heavy load is dropped:
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REFUELING OPERATIONS BASES ij 3/4.9.7 FUEL HANDLING MACHINE - SPENT FUEL STORAGE BUILDING (Continued) 7 1.
The radiological consequences due to complete rupture of all spent fuel' assemblies in the spent fuel pool-and the cask pool s
(480 maximum), will remain below (less than 25% of) the exposure limits of 10 CFR 100 for of fsite doses.
This analysis takes no credit for fuel handling butiding filters (i.e., the fuel handling building hatches are open).
2, Any possible distortion of all fuel assemblies and racks will not result-in a critical array and K will remain less than 0.95,'as longasfuelisstoredperTechnIN1 Specification 5.5,"Fue)
Storage," and 3. 9.13, " Spent Fuel Pool Soren Concentration.".
3/4.9.8 SHUT 00VH COOLING AND COOLANT CIRCUL.ATION The requirement that at leart one shutdown cooling train be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and main-i<
tain the. water in the reactor pressure vessel below 140*F as required during the REFUELING H00E, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron dilution incident and p.revent Q,
boron stratification.
The requirement to have two shutdown cooling trains OPERABLE when there is less than 23 feet of water above the reactor pressure vessel flange, ensures that a single failure-of the operating shutdown cooling loop wi.11 not result in a com-plate loss of decry heat removal ~ capacity.
With the reactor vessel head re-moved and 23 feet of.' water above the reactor pressure vessel flange, a large heat sink is available for core cooling, thus in the event of a failure of the coorating shutdown cooling train,. adequate time is provided to initiate emer-gency procedures to cool the core.
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SAH ONOFRE - UNIT 3' S 3/4 9-2a_
ANENOMENT-No. 77
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ATTACHMENT C Proposed Specifications Unit 2 b
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REFUEllNG OPERAT10t(1 3/4.9.7 FUEL HANDLING MACHINE - SPENT FUEL STORAGE POOL BUILDING llMITING CONDITION FOR OPERATION 3.9.7 Loads in excess of 2000 pounds shall be prohibited from travel over fuel assembliesinthestoragepoolexceptforthefollowingfourtwo{ cases:
a.
Spent fuel pool. gates shall not be carried at a height greater than 30 inches (elevation 36' 4") over the fuel racks.
b.
Test equipment skid (4500 pounds) shall not be carried at a height greater than 72 inches (elevation 39' 10") over rack cells which contain Unit 2 fuel assemblies or greater than 30 feet 8 inches (elevation 64' 6") over rack cells which contain Unit I fuel assemblies, c.
InsteMet4en-er--eemoval of the-eask-pool ccver evee-the cask 2001 wRh-fuel in the-eask pccl. _ The-coveer-fuel r-and rack; will ac removed-from-the-e+sk-pool-on-eemp1etien cf thc rereek4*g-procc :.
d.
The lift of-const+uet4en=1 cad;, inc4uding-the tempoeary-9antry crane and the old-and-the-c.cw fuel steeage-eaeks--(4nc4ud4n9-44+t4eg equipment-and-e49Mngh-above the cask pocl with the-eesk pocl cover 4n-place and fuel in the cask pocl. This include: tempeeavy-sterage of=the:c-construet4en leads-on the cask-pool-eevee-due4e9 eenstruet4eHtese-4+f1+-are-proh4hHed-peler tc : =iaimum fuel decay time of-88-days-fer all :tered-spent fuel ;;;cmbliesr APPLICABILITY: With fuel assemblies in the storage pool.
ACTIO_N:
With the requirements of the above specification not satisfied, place the fuel handling machine in a safe condition.
SURVElllANCE REQUIREMENTS 4.9.7 Fuel handling machine interlocks and physical stops which prevent fuel handling machine travel with loads in excess of 2000 pounds over fuel assemblies shall be demonstrated OPERABLE within 7 days prior to fuel handling machine use j
and at least once per 7 oays thereafter during fuel handling machine operation.
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I SAN ON0FRE-UNIT 2 3/4 9-7 AMENDMENT N0.
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REFUELING OPERATIONS l
1
-BASES 3/4.9.6 REFUELING MACHINO The OPERABILITY requirements for the refueling machine ensure that: (1) the refueling machine will be used for movement of all fuel assemblies including those with a CEA inserted, (2) each machine has sufficient load capacity to lift a fuel assembly including those with a CEA, and (3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.
Five finger CEAs are removed from the reactor vessel either along with the associated fuel bundle utilizing the refueling machine or can be removed without the associated fuel bundle utilizing the refueling machine _ auxiliary hoist. The four finger CEAs are inserted through the upper guide structure with two fingers in each of the two adjacent fuel bundles in the periphery of the core. The four finger CEAs are either removed with the upper guide structure and lift rig or can be removed with separate tooling prior to upper guide structure removal utilizing the auxiliary hoist of the polar crane or the refueling machine auxiliary hoist.
Coupling and uncoupling of-the CEAs and the CEDM drive shaft extensions is accomplished using one of the gripper operating tools. The coupling and uncoupling is verified by weighing the drive shaft extensions.
3/4.9.7 FUEL HANDLING MACHINE - SPENT FV_EL STORAGE BUILDif{G A.
The restriction on movement of loads in excess of the nominal weight of a fuel assembly, CEA and associated handling tool over other fuel assemblies in the storage pool ensures that -in the event this load -is dropped (1)- the:
activity release will.be limited to that contained in six fuel assemblies, and (2) any possible distortion of fuel in.the storage racks will not result in a critical array. 'This assumption is based on the calcul_ated results which demonstrate that, with credit taken for the fuel handling building filters, the offsite doses would be well~ within (less than 25%)
the 10 CFR 100 limits.
B.
Spent-F uel-PooM ecack4 ng-Gons truet4 on-Aet4 v414es The-rest N et4 oun-movement-o f-hea vy--loads-over--spent-feel-ensures--t4ta t4 n
_ the--event-a-heavy-4oad-4s-dropped +
1 SAN ON0FRE - UNIT 2 B'3/4 9-2 AMENDMENT NO.
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-REFUELING OPERATIONS BASES 3/4.9.7 FUEL HANDl4NG-MAGH114E--SPENT-FUE4-STORAGE-BUIM)ING-f&ont4nuedi 1.
The-eadiologleal-consequences-due40-complete-ruptvee-of-al4 spen t-fu el-as sembl4 es-i n-the-spent-fuel-poobend-the-ca sk-pool
{480-ma x4 mumbr-w i44-eema 4 n-below-{4ess-t han-25%-of-}-the-ex posure 44mits-of-10-GFR-100-for-offs 44e-doses-es-long--as spent-fuel-has rece4ved-e-minimue-of-88-days-deeay-+4mer--Th4e-analysis tekes no-cred44-for-fuel-hand 14ng-build 4ng-f444ers. (i.e., the-fuel ha nd14 ng-bu H d ing-ha tc hes-are-open}r ih Any-poss4hle-44+toet4en-of-aH-fuel-essembHes and racA+-wf44 not-resu14-4 n-a-c ri t4 c a l-e reay-a nd-Km-will remain-less-than O rG 6r-a s-long-as-fu eb4 s-s tored-pee-4ech n4eal-Spee4 f4 ea t4 ens SrMFueb-Storager"-and-3r9r13, " Spent-Fue4-Pool-Boron Concent-rat 4end 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION The requirement that at least one shutdown ecoling train be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140*F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification.
The requirement to have two shutdown coolirig tr. ins OpEPABLE when there is les:.
l than 23 feet of water above the reactor pressure vessel flange, ensures that a single failure of the operating shutdown cooling loop will not result in a cam-i plete loss of decay heat removal capacity. With the reactor vessel head removed and 23 feet of water above the reactor pressure vessel flange, a large heat sink is available for core cooling, thus in the event of a failure of the operating shutdown cooling train, adequate time is provided to initiate emergency procedures to' cool the core.
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l-SAN ONOFRE - UNIT 2 B 3/4 9-2a AMENDMENT N0.
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-ATTACHMENT 0:
Proposed Specifications Unit 3 k
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=e R[fjjELING OPERATI0fLS 3/4.9.7 FUEL HANDLING MACHINE - SPENT FUEL STORAGE P0OL BUILDING LIMITING CONDITION FOR OPERATION 3.9.7 Loads in excess of 2000 pounds shall be prohibited from travel over fuel assemblies in the storage pool except for the following four two; cases:
a.
Spent fuel pool gates shall not be carried at a height greater than 30 inches (elevation 36' 4") over the fuel racks, b.
Test equipment skid (4500 pounds) shall not be carried at a height greater than 72 inches (elevation 39' 10") over rack cells which contain Unit 3 fuel assemblies or greater than 30 feet 8 inches (elevation 64' 6") over rack cells which contain Unit I fuel assemblies.
c.
I ns tem a t4en-oe-remove 4-o f-t he-eask-pool-covee-ovee-the-c+sk-pool I
with-fuel--4n-the-eask-p301.
The-covem-fueh-and-eaeks-wi+1-be removed-from-the-ca s k-pool-on-compet4en-ef-the-reeaek4 ng-processr d.
The-Mf4-o f-< ens tru e t4on-l oadsr-4nc4uding-the-temporary-ganl ey-eeane a nd-t he-old-a nd-the-new-fuel-storage-racks-tine-lud4eg-14-f44ng equ4pment-and-e4gg4ng)r-above-the-eask-poci.1th-the-eask-pool-coves 4n-place-and-fel--4 n-t he-eask-poolv --Th4s-4nc4edes--temporacy-s teeage of-these-construet4en-loads-on-the-eask-pccl ccier dueing constfuet4en--These-l+f4s are proh4Mted-peise-to-a-ein4eum-deeay 14mc of S8 days-for all stored-fuel-assembl4es r APPLICABILITY: With fuel assemblies in the storage pool.
ACTI0ti:
With the requirements of the aoove specification not satisfied, place the fuel handling machine in a safe condition.
-SURVEILLANCE REQUIREMENTS 4.9.7 Fuel handling machine interlocks and physical stops which prevent fuel handling machine travel with loads in excess of 2000 pounds over fuel assemblies l
shall be demonstrated OPERABLE within 7 days prior to fuel handling machine use and at least once per 7 days thereafter during fuel handling machine operation.
l l
SAN ONOFRE - UNIT 3-3/4 9-7 AMENDMENT NO.
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P REFUELING OPERATIONS BASES 3/4.9.6 REFUELING MACHINE The OPERABILITY requirements for the refueling machine ensure that: (1) the refueling machine will be used for movement of all fuel assemblies including those with a CEA inserted, (2) each machine has sufficient load capacity to lift a fuel assembly including those with a CEA, and (3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during l'i.ing operations.
Five finger CEAs are removed from the reactor vessel either along with the associated fuel bundle utilizing the refueling machine or can be removed without the associated fuel bundle utilizing the refueling machine auxiliary hoist. The four finger CEAs are inserted through the upper guide structure with two fingers in each of the two adjacent fuel bundles in the periphery of the core. The four finger CEAs are either removed with the upper guide structure and lift rig or can be removed with separate tooling prior to upper guide structure removal utilizing the auxiliary hoist of the polar crane or the refueling machine auxiliary hoist.
I Coupling and uncoupling of the CEAs and the CEDM drive shaft extensions is accomplished using one if the gripper operating tools. The coupling and uncoupling is verified by weighing the drive shaft extensions.
3/4.9.7 FUEL HAND!ING MACHINE - SPENT FUEL STORAGE BUILDING A.
Refueling Operation The restriction on movement of loads in excess of the nominal weight of a fuel assembly, CEA and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped (1) the activity release will be limited to that contained in six fuel assemblies, and (2) any possible distortion of fuel in the storage racks will not i
result in a critical array. This assumption is based on the calculated L
results which demonstrate that, with credit taken for the fuel h-
' ng.
l building filters, the off site doses would be well within (less t!
~5%)
the 10 CFR 100 limits.
B.
Spent Fucl Poc! Rcracking-Genstruction Ac-t-i'.itics he restr4et-icn-on movement of heavy loads over spent fuel c,sures that in the evcnt a-heavy 4ead-h-dropped +
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SAN ON0FRE - UNIT 3 B 3/4 9-2 AMENDMENT NO.
o REFVELING OPERAIJONS BASFS 3/4.L 7 FUEL-44ANDL-lHG-MC_ HINE--SPENT 4UEl-STORACE BUILGl#G-(Gen 14nued) 1.
The-eadiolog4cabeensequences-due-to-cemplete-rupture-ef--all spent fuebassembM es-in-4 he-s pen t-poobend-the-eask-peel-(480-max 4 mumb wi11 rcmain-below-(4en-than-25% of) the-exposure-Mmits-ef-lO-CH 400-fee-eff+4te-doses.
Th4s-analys4s-takes ac credM -for fuel handHng-buHd4n9444ters (i. c., the-fuel-handMng building-hatches are-openh 2.
Any-pon4ble-distort 4en-of-aH-fue4-assembMes-and-eaeks will not-resuM-4n-a-ceH4eabarray-and-Km-will remain less-than=0.95, as long-as-fueb4s-stored-pee-Technleal-Spec 4f4 eat 4+n 5.S. " Fuel Storage," and--3-9.13
" S pen t-FuebPoobBoron-C+neentra t4sne i
3/4.9.8 SHUTDOWN COOL,lFG AND COOLAHT CIRCULATION The requirement that at least one shutdown cooling train be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and main-tain the water in the reactor pressure vessel below 140*F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron (i!ition incident and prevent boron stratification.
The requirement to have two shi'tdown cooling trains OPERABLE when there is less than 23 feet of water above the reactor pressure vessel flange ensures that a single failure of the operating shutdown cooling loep will not result in a com-plete loss of decay heat removal capability.
With the reactor vessel head re-
}
moved and 23 feet of water above the reactor pressure vessel flange, a large heat sink is available for core cooling, thus in-the event of a failure of the operating shutdown cooling train, adequate time is provided to initiate emer-gency procedures to cool the core, t.
SAN ON0FRE - UNIT 3 B 3/4 9-2a AMENDMENT NO.
j
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