ML20134C922
| ML20134C922 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 10/03/1996 |
| From: | Fields M NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20134C925 | List: |
| References | |
| NUDOCS 9610110128 | |
| Download: ML20134C922 (16) | |
Text
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t UNITED STATES j
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NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D.C. 2066Ho01 49.....,d SOUTHERN CALIFORNIA EDISON COMPANY i
l SAN D' EGO GAS AND ELECTRIC COMPANY 2
)
THE CITY OF RIVERSIDE. CALIFORNIA 4
THE CITY OF ANAHEIM. CALIFORNIA l
DOCKET NO. 50-361 i
SAN ONOFRE NUCLEAR GENERATING STATION. UNIT NO. 2 l
AMENDMENT TO FACILITY OPERATING LICENSE k
l Amendment No.131 4
License No. NPF-10 i
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Southern California Edison
]
Company, et al. (SCE or the licensee) dated December 6, 1995, as j
supplemented by letters dated August 30, 1996, and September 20, 1996, complies with the standards and requirements of the Atomic
}
Energy Act of 1954, as amended (the Act), and the Commission's 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 Commission; C.
There is reasonable assurance (i) 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 Commission's regulations; i
D.
The issuance of this amendment will not be inimical to the common i
defense and security or to the health and safety of the public; j
and i
E.
The issuance of this amendment is in accordance with 10 CFR i
Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
9610110128 961003 I
PDR ADOCK 05000361 i
PDR p
q
. 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-10 is hereby 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.131, 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 to be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULAT0RY COMMISSION ft' 'f ff'Y5 Mel B. Fields, Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 3, 1996
4 0
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.131 TO FACILITY OPERATING LICENSE NO. NPF-10 DOCKET NO. 50-361 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by Amendment number and contain marginal lines indicating the areas of change.
REMOVE JI1ERI 3.7-32 3.7-32 3.7-33 3.7-33 3.7-34 3.7-34 4.0-4 4.0-4 4.0-5 4.0-5 l
I e
Spent Fuel Assembly Storage 3.7.18
).
3.7 PLANT SYSTEMS 3.7.18 Spent Fuel Assembly Storage i
1 LCO 3.7.18 The combination of initial enrichment and burnup of each SONGS 2 and 3 spent fuel assembly stored in Region II shall be within the acceptable burnup domain of Figure 3.7.18-1 or i
Figure 3.7.18-2, or the fuel assembly shall be stored in accordance with Licensee Controlled Specification 4.0.100.
The burnup of each SONGS 1 uranium dioxide spent fuel assembly stored in Region II shall be greater than or equal to 18.0 GWD/T for interior locations of 5.5 GWD/T for peripheral locations, or the fuel assembly shall be stored in accordance with Licensee Controlled Specification j
4.0.100.
i i
f APPLICABILITY:
Whenever any fuel assembly is stored in Region II of the 1
fuel storage pool.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Requirements of the A.1
NOTE---------
LC0 not met.
LCO 3.0.3 is not applicable.
Initiate action to Immediately move the noncomplying fuel assembly from Region II.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY t
SR 3.7.18.1 Verify by administrative means the initial Prior to enrichment and burnup of the fuel assembly storing the is in accerdance with LCO 3.7.18.
fuel assembly l
in Region II SAN ONOFRE--UNIT 2 3.7-32 Amendment No. +N,131
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1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 Initial U-235 Enrichment (w/o)
MINIMUM BURNUP VS. INITIAL ENRICHMENT FOR UNRESTRICTED l
PLACEMENT OF SONGS 2 AND 3 FUEL IN REGION II RACKS j
FIGURE 3.7.18-1 SAN ONOFRE--UNIT 2 3.7-33 Amendment No. M7,131 r
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1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 Initial U-235 Enrichment (w/c)
MINIMUN BURNUP VS. INITIAL ENRICHMENT FOR PLACEMENT OF SONGS 2 AND 3 FUEL IN REGION 11 PERIPHERAL POOL LOCATIONS FIGURE 3 '.18-2 SAN ONCFRE--UNIT 2 3.7 4 Aner.dment No. 4N,131
Design Features 4.0 4.0 DESIGN FEATU"ES (continued) 4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:
a.
Fuel assemblies having a maximum U-235 enrichment of 4.8 weight percent; l
b.
K s 0.95 if fully flooded with unborated water, WNchincludesanallowanceforuncertaintiesas described in Section 9.1 of the UFSAR; c.
A nominal 8.85 inch center to center distance between fuel assemblies placed in Region II; d.
A nominal 10.40 inch cente-to center distance between fuel assemblies >
' in Region I; e.
Units 1, 2, and 3 fuel assemblies may be stored in l
Region I with no restrictions; j
f.
Units 2 and 3 fuel assemblies with a burnup in the
" acceptable range" of Figure 3.7.18-1 are allowed unrestricted storage in Region II; g.
Units 2 and 3 fuel assemblies with a burnup in the
" acceptable range" of Figure 3.7.18-2 are allowed unrestricted storage in the peripheral pool locations with I or 2 faces toward the spent fuel pool walls of Region II; h.
Fuel assemblies with a burnup in the " unacceptable r:nge" of Figure 3.7.18-1 or Figure 3.7.18-2 will be stored in compliance with Licensee Controlled Specification 4.0.100; and i.
The burnup of each SONGS 1 uranium dioxide spent fuel assembly stored in Region II shall be greater than or equal to 18.0 GWD/T for interior locations or 5.5 GWD/T for peripheral locations, or the fuel assembly shall be stored in accordance with Licensee Controlled Specification 4.0.100.
(continued)
SAN ONOFRE--UNIT 2 4.0-4 Amendment No. +N,131
Design Features 4.0
)
{.
4.0 DESIGN FEATURES i
I 4.3 Fuel Storage (continued) 4.3.1.2 The new fuel storage racks are designed and shall be maintained with:
a.
Fuel assemblies having a maximum U-235 enrichment of 4.8 weight percent; l
b.
K s 0.95 if fully flooded with unborated water, wNfch includes an allowance for uncertainties as described in Section 9.1 of the UFSAR; K 'ludes an allowance for uncertainties ass 0.98 if moderated by aq c.
iNc described in Section 9.1 of the UFSAR; and d.
A minimum 29 inch center to center distance between fuel assemblies placed in the storage racks.
4.3.2 Drainaae The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below Technical Specification 3.7.16 value (23 feet above the top of irradiated fuel assemblies seated in the storage racks).
4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1542 fuel assemblies.
SAN GN0FRE--UNIT 2 4.0-5 Amendment No. W,131 a
S atog y =-
UNITED STATES g
.g NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D.C. 2056tW001
%***,*/
l SOUTHERN CALIFORNIA EDIS0N COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE. CALIFORNIA THE CITY OF ANAHEIM. CALIFORNIA DOCKET NO. 50-362 4
SAN ON0FRE NUCLEAR GENERATING STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 120 License No. NPF-15 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 6,1995, as supplemented by letters dated August 30, 1996, and September 20, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the
~
provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) 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 common defense and security or to the health and safety of the public; and 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.
1 l
1 2.
Accordingly, the license is amended by changes to the Technical Spect-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:
(2)
Technical Soecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 120, 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 to be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMM SSION A
Mel B. Fields, Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 3, 1996
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 120 TO 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 Amendment number and contain marginal lines indicating the areas of change.
REMOVE INSERT 3.7-32 3.7-32 3.7-33 3.7-33 1
3.7-34 3.7-34 4.0-4 4.0-4 4.0-5 4.0-5 l
l l
_ _ _ _ _.. _. _ _. _ _ _ _ _ _ _ _ _ _ _ ~. _ _
Spent Fuel Assembly Storage 3.7.18 3.7 PLANT SYSTEMS 3.7.18 Spent Fuel Assembly Storage, LCO 3.7.18 The combination of initial enrichment and burnup of each SONGS 2 and 3 spent fuel assembly stored in Region II shall be within the acceptable burnup domain of Figure 3.7.18-1 or Figure 3.7.18-2, or the fuel assembly shall be stored in accordance with Licensee Controlled Specification 4.0.100.
The'burnup of each SONGS 1 uranium dioxide spent fuel assembly stored in Region II shall be greater than or equal to 18.0 GWD/T for interior locations or 5.5 GWD/T for peripheral locations, or the fuel assembly shall be stored in accordance with Licensee Controlled Specification 4.0.100.
APPLICABILITY:
Whenever any fuel assembly is stored in Region II of the fuel storage pool.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Requirements of the A.1
NOTE---------
LCO not met.
LCO 3.0.3 is not applicable.
Initiate action to Immediately move the noncomplying fuel assembly from Region II.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.18.1 Verify by administrative means the initial Prior to enrichment and burnup of the fuel assembly storing the is in accordance with LCO 3.7.18.
fuel assembly l
in Region II SAN ON0FRE--UNIT 3 3.7-32 Amendment No. 116,120
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O 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 Initial U-235 Enrichment (w/o)
MINIMUM BURNUP VS. INITIAL ENRICHMENT FOR UNRESTRICTED PLACEMENT OF SONGS 2 AND 3 FUEL IN REGION II RACKS FIGURE 3.7.18-1 SAN ONOFRE--UNIT 3 3.7-33 Amendment No. H4.120
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MINIMUM BURNUP VS. INITIAL ENRICHMENT FOR PLACEMENT OF SONGS 2 AND 3 FUEL IN REGION 11 PERIPHERAL POOL LOCATIONS FIGURE 3.7.18-2 SAN ONOFRE--UNIT 3 3.7-34 Amendment No. H6,120
Design Features 4.0 4.0 DESIGN FEATURES (continued) j 4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be j
maintained with:
a.
Fuel assemblies having a maximum U-235 enrichment j
of 4.8 weight percent; 1
b.
K s 0.95 if fully flooded with unborated water, wNchincludesanallowanceforuncertaintiesas i
described in Section 9.1 of the UFSAR;
)
c.
A nominal 8.85 inch center to center distance i
between fuel assemblies placed in Region II; i
d.
A nominal 10.40 inch center to center distance between fuel assemblies placed in Region I; t
l e.
Units 1, 2, and 3 fuel assemblies may be stored in l
Region I with no restrictions; i
f.
Units 2 and 3 fuel assemblies with a burnup in the l
" acceptable range" of Figure 3.7.18-1 are allowed j
unrestricted storage in Region II; g.
Units 2 and 3 fuel assemblies with a burnup in the
" acceptable range" of Figure 3.7.18-2 are allowed unrestricted storage in the peripheral pool locations with 1 or 2 faces toward the spent fuel i
j pool walls of Region II; h.
Fuel assemblies with a burnup in the "unacctptable range" of Figure 3.7.18-1 or Figure 3.7.18-2 will i
be stored in compliance with Licensee Controlled Specification 4.0.100; and i
i.
The burnup of each SONGS 1 uranium dioxide spent fuel assembly stored in Region II shall be greater i
than or equal to 18.0 GWD/T for interior locations or 5.5 GWD/T for peripheral locations, or the fuel l
assembly shall be stored in accordance with Licensee Controlled Specification 4.0.100.
l (continued)
SAN ON0FRE--UNIT 3 4.0-4 Amendment No. M4,120
Design Features 4.0 4.0 DESIGN FEATURES I
4.3 Fuel Storage (continued) 4.3.1.2 The new fuel storage racks are designed and shall be maintained with:
a.
Fuel assemblies having a maximum U-235 enrichment of 4.8 weight percent; l
b.
K s 0.95 if fully flooded with unborated water, wk[chincludesanallowanceforuncertaintiesas described in Section 9.1 of the UFSAR; K 'ludes an allowance for uncertainties ass 0.98 if moderated by a c.
iNc described in Section 9.1 of the UFSAR; and d.
A minimum 29 inch center to center distance between fuel assemblies placed in the storage racks.
4.3.2 Drainaae The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below Technical Specification 3.7.16 value (23 feet above the top of irradiated fuel assemblies seated in the storage racks).
4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1542 fuel assemblies.
SAN ON0FRE--UNIT 3 4.0-5 Amendment No. 4%,120