ML20044E043
| ML20044E043 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 05/17/1993 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20044E044 | List: |
| References | |
| NUDOCS 9305210215 | |
| Download: ML20044E043 (12) | |
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t UNITED STATES l
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['*,j NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 2066EK1001 I
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SOUTHERN CALIFORNIA EDISON COMPANY l
SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE. CALIFORNIA i
THE CITY OF ANAHEIM. CALIFORNIA 1
DOCKET NO. 50-361 SAN ONOFRE NUCLEAR GENERATING' STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.104
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License No. NPF-10 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Southern California Edison Company, et al. (SCE or the licensee) dated December 24,-1992,
.l complies with the standards-and requirements of the Atomic Energy l
Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter 1, B.
The facility will operatt in conformity with the application, the.
I provisions of the Act, and the rules and regulations of the.
Comission; i
C.
There is reasonable assurance (i) that the activities authorized 7
by this amendment can be conducted.without endangering the health.
l and safety of the public, and (ii) _that such activities will be conducted in compliance with the Comission's. regulations; j
D.
The issuance of this amendment will not be-inimical to the comon-defense and security or to the health and safety of the public;
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and E.
The issuance of this amendment is in accordance with 10 CFR-1 Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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9305210215 930517-1 gDR ADDCK0500g1
2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and i
paragraph 2.C(0) of Facility Operating License No. NPF-10 is hereby J
amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.104, are hereby incorporated in the license. Southern California Edison Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance and must be fully implemented no later than 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Theodore R. Quay, Director Project Directorate V i
Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 17, 1993 1
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e ATTACHMENT TO LICENSE AMENDMENT i
s AMENDMENT NO.104TO FACILITY OPERATING LICENSE NO. NPF-10 l
DOCKET NO. 50-361
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i Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by i
the captioned amendment number and contain marginal lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE INSERT 3/4 9-7 3/4 9-7 i
B 3/4 9-2 B 3/4 9-2 l
B 3/4 9-2a B 3/4 9-2a l
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REFUELING OPERATIONS 3/4.9.7 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 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 2 fuel assemblies or greater than 30 feet 8 inches (elevation 64' 6") over rack cells which contain Unit 1 fuel assemblies.
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 RE0VIREMENTS 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 assem-olies 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 ON0FRE-UNIT 2 3/4 9-7 AMENDMENT NO. 104 l
R'EFUELING 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.
j 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 struc-ture 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 A.
Refueling Operations The restriction on movement of loads in excess of the nominal weight of a r
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 l
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 demonstrate that, with credit taken for the fuel handling building filters, the off:ite doses would be well within (less than 25%)
the 10 CFR 100 limits.
t SAN ONOFRE - UNIT 2 B 3/4 9-2 AMENDMENT NO. C7,104
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i REFUELING OPERATIONS
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BASES 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION The requirement that at least one shutdown cooling train be in operation ensures that (I) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactcr 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 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 emer-gency procedures to cool the core.
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SAN ON0FRE - UNIT 2 B 3/4 9-Za AMENDMENT NO. fd5 104 L
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UNITED STATES l
-f 'I rN i E NUCLEAR REGULATORY COMMISSION Efg j
WASHWGToN. 0.C. 20566-021 j
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SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY i
THE CITY OF RIVERSIDE. CALIFORNIA t
i THE CITY OF ANAHEIM. CALIFORNIA l
DOCKET NO. 50-362 SAN ONOFRE NUCLEAR GENERATING STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 93 I
License No. NPF-15 l.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Southern California Edison Company, et al. (SCE or the. licensee) dated December 24, 1992, i
complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's l
regulations set forth in 10 CFR Chapter I; i
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; l
C.
There is reasonable assurance (1)'that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon t
defense and security or to the health and safety.of the public; and t
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
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2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and
-paragraph 2.C(2) of Facility Operating License No. NPF-15 is hereby amended to read as follows:
l (2)
Technical Specifications i
The Technical Specifications contained in Appendix A'and the
}
Environmental Protection Plan contained in Appendix B, as revised j
through Amendment No. 93, are hereby incorporated in the'
-l license. Southern California Edison Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance and must be fully implemented no later than 30 days from the date of issuance.
'I
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FOR THE NUCLEAR REGULATORY COMISSION
-l S-Theodore R. Quay, Directo Project Directorate V Division of Reactor Projects III/IV/V.
f Office of Nuclear Reactor Regulation i
Attachment:
Changes to the Technical 1
Specifications Date of Issuance:
May 17, 1993 l
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ATTACHMENT T0 LICENSE AMENDMENT AMENDMENT NO. 93 10 FACILITY OPERATING LICENSE NO. NPF-15 DOCKET NO. 50-362 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned ari.andment number and contain marginal lines indicating the areas of change.
The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE INSERT 3/4 9-7 3/4 9-7 B 3/4 9-2 B 3/4 9-2 B 3/4 9-2a B 3/4 9-2a 9
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REFUEll.NG OPERATIONS 3/4.9.7 FUEL HANDLING MACHINE - SPENT FUEL STORAGE POOL BUllDING 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 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 73' 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.
APPLICABILITY:
With fuel assemblies in the storage p031.
ACTION:
With the requirements of the above specification not satisfied, place the fuel handling rachine in safe condition.
5J.E'Lt W E REGUIREMENTS 4.9.7 fuel handling machine interlocks and physical stops which prevent fuel handling machine travel with loads in excess of 200^ pounds over fuel assem-blies shall be demonstrated OPERABLE within 7 days prior to fuel handling 4
machine use and at least once per ! days thereafter during fuel handling machine operation.
SAN ONOFRE - UNIT 3 3/4 9-7 AMENDMENT NO. 7; 93
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R'EFUEt1NG' OPERATIONS
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BASES j
I 3/4.9.6 REFUELING MACHINE The OPERABILITY requirements for the refaeling 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 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 with-out 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 feel bundles in the periphery of the ccre.
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 utilizii.3 the auxiliari hoist of the polar crane or the --#ueling 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 unceupling is verified by weighing the drive shaft extensions.
3/4.9.7 FUEL HANDLING 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 futi assem-blies 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 cal-culated 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.
SAN ONOTRE - UNIT 3 B 3/4 9-2 lA1NDMENT NO.-m 93, 4 -
c-I REFUELING OPERATIONS 1
BASES 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 th* 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 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 ir, 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, thur 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.
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L SAN ON0FRE - UNIT 3 B 3/4 9-2a AMENDMENT NO. 77,- 93