ML20235Z083
| ML20235Z083 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 03/10/1989 |
| From: | SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML13303B064 | List: |
| References | |
| NUDOCS 8903150120 | |
| Download: ML20235Z083 (20) | |
Text
g--- w-w-ATTACHMENT C PROPOSED TECHNICAL SPECIFICATIONS SAN ONOFRE UNIT 2
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t EFZUELING O'ERATIONS P 3/4.9.7 FUEL HANDLING MACHINE - SPENT FUEL STORAGE POOL BUILDING b LIMITING CONDITION FOR OPERATION 3.9.7 Loads in excess of 2000 pounds shall be prohibited from l travel over fuel assemb7.ies in the storage pool except for the I following four 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 1 fuel assemblies.
- c. Installation or removal of the cask pool cover over the cask pool with fuel in the cask pool.
- d. The lift of construction loads, including the temporary gantry crane and the old and the new fuel storage racks (including lifting equipment and rigging), abovr the cask pool with the cask pool cover in place and Luel in the cask pool. This includes temporary storage of these construction loads on the cask pool cover during construction.
APPLICABILITY: 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 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 and at least once per 7 days thereafter during fuel handling machine operation.
SAN ONOFRE-UNIT 2 3/4 9-7
REFUELING OPERATIONS BASES 3/4.9.6 REEUELING 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 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 FUEL STORAGE BUILDING 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 l possible distortion of fuel in the storage racks will not result in a critical array. This assumption is based on the calculated results which demonstrate that, with credit taken for the FHB filters, the offsite doses would be well within the 10CFR100 limits.
3/4.9.8 SHUTDOWN 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 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.
SAN ONOFRE-UNIT 2 B 3/4 9-2 AMENDMENT NO.
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 complete 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.
SAN ONOFRE-UNIT 2 B 3/4 9-3 AMENDMENT NO.
DESIGN FEATURES VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 11,800 + 600/-0 cubic feet at a nominal Tavg Of 582.1*F.
5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
5.6 FUEL STORAGE CRITICALITY 5.6.1 The spent fuel storage racks are designed and shall be maintained with:
- a. A keff equivalent to less than or equal to 0.95 when flooded with unborated water, which includes a conservative allowance for uncertainties as described in the FSAR.
- b. A nominal 10.40 inch center-to-center distance between fuel assemblies placed in the Region I storage racks and a nom.inal 8.85 inch center-to-center distance between fuel assemblies placed in the Region II storage racks.
5.6.2 The enrichment-fuel assembly discharge burnup shall be above (greater than) the curves shown on Figure 5.6-1, for Unit 2 fuel assemblies, or Figure 5.6-2 for Unit 1 fuel assemblies.
These minimum levels shall be achieved prior to storing spent fuel assemblies in Region II spent fuel racks, or New or burned fuel which does not meet the enrichment versus discharge burnup criteria of Figures 5.6-1/5.6-2 may be stored in Region II if all the following conditions are met.
Fuel Type 1 = new or burned fuel which does n21 meet the criteria of Figures 5.6-1/5.6-2.
Fuel Type 2 = fuel which does meet the criteria of Figures 5.6-1/5.6-2.
- a. Fuel Type 1 shall have initial enrichment 4 4.1 v/o U-235.
SAN ONOFRE-UNIT 2 5-7 AMENDMENT NO.
i
A 1
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W b. '
1 Fuel; W lL shall be st'ored lin' Region II inleither:(not both simultaneously) a, checkerboard. pattern orlan;
t alternating row pattern.per Figure 5.6-3.
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, c.
Fuel Type .1 shall:- be ' separated from ' Fuel Type 2 by/ at:
J .
leastione (1)ccompletely: empty row of storage cells..
, - d. : Fuel Type'1:shall not'.be' stored in the'siame row'as. Fuel
-Type 2.
e-. - One1(1) ~ completely empty row of Region II storage . cells -
shall separate' Fuel Type 1 stored in Region.II fronc fuel storage' Region I.
- f. Except for tha purposes of a fuel reconstitution . ,
station desartoed below (g) , Fuel Type 1 and Fuel. Type 2 storage arrays shall not alternate in Region II.
i g '. For. purposes of fuel reconstitution / inspection work',-it is permissible to have the three (3) row (empty - every J other Fuel Type 1 ~ empty) arrangement of Figure 5.6-4' E ' any where in the Fuel Type 2 storage array.. Additional ~
empty rows are allowed. This three (3). row pattern may be repeated in the Fuel. Type 2 storage array if at-least eight (8) rows separate repetitions..
DRAINAGE 5.6.3 The spent fuel-storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation:60'6".
CAPACITY
- 5. 6. 4 - The spent fuel storage pool is designed and'shall be maintained with a" storage capacity limited to no more than 1572 ]
fuel assemblies.
l
. 5.7 COMPONENT CYCLIC OR TRANSIENT LIMITS 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.
SAN ONOFRE-UNIT 2 5-8 AMENDMENT NO.
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SAN ONOFRE NUCLEAR GENERATING STATION Units 2 & 3 UNITS 2 & 3 FUEL MINIMUM BURNUP VS INITIAL ENRICHMENT FOR REGION 11 RACKS FIGURE 5.61 -
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SAN ONOFRE-NUCLEAR GENERATING STATION Units 2 & 3 UNIT 1 FUEL MINIMUM BURNUP VS INITIAL ENRICHMENT FOR REGION 11 RACl(S FIGURE 5.6 2
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g X Type 2 Fuel O Type 1 Fuel SAN ONOFRE NUCLEAR GENERATING STATION Units 2 & 3
_ Empty Storage Location F L ST R^ E p g pOR REG ON ll RACKS FIGURE 5.6-3
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X y X X X X X % TYPE 2 FUEL X X X X X X X X O O O O RECON STATION
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0 0 0 0 O O O O TYPE 1 FUEL 0 0 0 O y ARRAY IN REGION ll y = TYPE 2 FUEL l SAN ONOFRE l0 l = TYPE 1 FUEL NUCLEAR GENERATING STATION l Units 2 & 3
- EMPTY FUEL STORAGE PATTERNS FOR REGION 11 RACKS RECONSTITUTION STATION FIGURE 5.6-4 1 -- - - - - - - - - - - - _ - - . _ _ . _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _
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ATTACHMENT 0 PROPOSED TECHNICAL SPECIFICATIONS SAN ONOFRE UNIT 3
.A
.I REFUELING OP'ERATIONS 3/4.917 FUEL HANDLING MACHINE - SPENT FUEL STORAGE POOL 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 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 1 fuel assemblies.
- c. Installation or removal of the cask pool cover over the cask pool with fuel in the cask pool.
- d. The lift of construction loads, including the temporary gantry crane and the old and the new fuel storage racks (including lifting equipment and rigging), above the cask pool with the cask pool cover in place and fael in the cask pool. This includes temporary storage of-these construction loads on the cask pool cover during construction.
APPLICABILITY: 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 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 and at least once per 7 l
days thereafter during fuel handling machine operation.
1 i
SAN ONOFRE-UNIT 3 3/4 9-7
l i
REFUELING OPERATIONS l
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 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 FUEL STORAGE BUILDING 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 I possible distortion of fuel in the storage racks will not result in a critical array. This assumption is based on the calculated results which demonstrate that, with credit taken for the FHB filters, the offsite dosas would be well within the 10CFR100 limits.
3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION The rewirement 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 MODE, and (2) sufficient coolant circulation is maintained through the reactor core tc minimize the effects of a boron dilution incident and prevent boron stratification.
SAN ONOFRE-UNIT 3 B 3/4 9-2 AMENDMENT NO.
l
The re Wirenent 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 complete loss of decay heat removal cape-ity. With the reactor vessel head removed and 23 feet of water iove the reactor pressure vessel flange, a large heat. sink . available for_ core cooling, thus in the event of a failure of tne operating shutdown cooling train, adequate ;
time is provided to initiate emergency procedures to cool the !
core. ;
l SAN ONOFRE-UNIT 3 B 3/4 9-3 AMENDMENT NO.
t
~
p- DESIGN FEATURES ~-
f VOLUME 5.4.2 -The-total water and steau volume of the reactor coolant.
system is 11,800-+ 600/-0 cubic' feet lat a nominal Tavg Of-582.1*F.
'5.5 METEORO h =5.5.1- The' meteorological tower shall be~ located as shown on' Figure 5.1-1.
- 5. 6' FUEL STORAGE.
CRITICALITY
- 5. 6.1 - The spent fuel storage racks are designed.and-shall be maintained with:
- a. Ak g equivalent to less'than or equal'to.0.95 when
.flo$bedwithunboratedwater,whichincludesa conservative allowance.for' uncertainties.as described in theLFSAR..
- b. A nominal 10.40 inch center-to-center distance between
-fuel assemblies placed=in the Region I storage racks
~
-and ainominal 8.85 inch center-to-center distance
.between fuel assemblies placed:in.the' Region II storage racks.
5.6.2 The enrichment-fueltassembly discharge burnup shall be above-(greater than) the curves shown on Figure 5.6-1,1for Unit.3 fuel assemblies,.or Figure-5.6-2 avr Unit 1 fuel assemblies.
These minimum levels shall be achieved prior to storing spent fuel assemblies.in Region II spent fuel racks,.or New or burned fuel which does not meet the enrichment versus discharge burnup criteria of Figures 5.6-1/5.6-2 may be stored in Region II if all the following~ conditions are met.
Fuel Type 1 = new or burned fuel which does Dat meet the criteria of Figures 5.6-1/5.6-2.
Fuel Type 2 = fuel which does meet the criteria of Figures 5.6-1/5.6-2.
- a. Fuel Type 1 shall have initial enrichment.5 4.1 w/o U-235.
-SAN ONOFRE-UNIT 3 5-7 AMENDMENT NO.
l 1
l
- b. . Fuel M e 1 shall be stored in Region II in either (not i both' simultaneously) a checkerboard pattern or an alternating row pattern per Figure 5.6-3.
I c. Fuel Type 1 shall be separated'frcm Fuel Type 2 by at I
least one (1) completely empty row of storage cells.
- d. Fuel Type 1 shall not be stored in the same row as Fuel Type 2.
e._ One (1) completely empty row of Region II storage cells shall separate Fuel Type'1 stored in Region II from fuel storage Region I.
- f. Except for the purposes of a fuel reconstitution station described below (g), Fuel Type 1 and Fuel Type 2 storage arrays shall not alternate in Region II.
- g. For pu noses of fuel reconstitution / inspection work, it is permissible to have the three (2) row-(empty - every other Fuel Type 1 - empty) arrangement of Figure 5.6-4 any where in the Fuel Type 2 storage array. Additional empty rows are allowed. This three (3) row pattern may be repeated in the Fuel Type 2 storage array if at least eight (8) rows separate repetitions. j DRAINAGE j 5.6.3 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 60'6".-
CAPACITY 5.6.4- The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1572 'l fuel assemblies.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMITS 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of
. Table 5.7-1.
SAN ONOFRE-UNIT 3 5-8 AMENDMENT NO.
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SAN ONOFRE NUCLEAR GENERATING STATION Units 2 & 3 UNITS 2 & 3 FUEL MINIMUM BURNUP VS INITIAL ENRICHMENT FOR REGION ll RACKS-FIGURE 5.61
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4 NUCLEAR GENERATING STATIOt' Units 2 & 3 UNIT 1 FUEL i MINIMUM BURNUP VS INITIAL ENRICHMENT FOR REGION ll RACKS FIGURE 5.6-2
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_ Empty Storage Location FU ST RAGE p pOR REG ON H RACKS FIGURE 5.6-3
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