ML20207F802
| ML20207F802 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 08/10/1988 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20207F807 | List: |
| References | |
| TAC-68425, TAC-68426, NUDOCS 8808230226 | |
| Download: ML20207F802 (8) | |
Text
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UNITED STATES 1
8 NUCLEAR REGULATORY COMMISSION o
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WASHINGTON, D. C. 20555
%,..... p SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA THE CITY OF ANAHEIM, CALIFORNIA DOCKET NO. 50-361 SAN ON0FRE NUCLEAR GENERATING STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 65 License No. NPF-10 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the license for San Onofre Nuclear Generating Station, Unit 2 (the facility) filed by the Southern California Edison Company (SCE) on behalf of itself and San Diego Gas and Electric Company, The City of Riverside and The City of Anaheim, California (licensees) dated June 14, 1988, as supplemented July 13 and July 25, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisionc of the Act, and the regulations of the Comission; 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 Comaission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the comon defense and security or to the health and safety of the public; 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.
8808230226 880810 PDR ADOCK 05000361 P
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this 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. 65, are hereby incorporated in the license. SCE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The change in Technical Specifications is to become effective within 30 days of issuance of the amendment.
In the period between issuance of the amendment and the effective date of the new Technical Specifications, the licensees shall adhere to the Technical Speciffcations existing at the time. The period of time during change over shall be minimized.
4.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION sI, George W. Knighton, Director Project Directorate V Division of Reactor Projects - III, IV, V and Special Project, Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 10, 1988
.a ATTACHMENT TO LICENSE AMENDMENT NO. 65 FACILITY OPERATING LIF.E,NSE NO. NPF-10 DOCKET N0. 50-361 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert 3/4 1-20 3/4 1-20 e
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. REACTIVITY CONTROL SYSTEMS CEA DROP TIME LIMITING CONDITION FOR OPERATION 3.1.3.4 The individual full length (shutdown and regulating) CEA drop time, from a withdrawn position greater than or equal to 145 inches, shall be less than or equal to 3.2 seconds from when the electrical power is interrupted to
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the CEA drive mechanism until the CEA reaches its 90 percent insertion position with:
T,yg greater than or equal to 520 F, and a.
b.
All reactor coolant pumps operating.
APPLICABILITY:
MODES 1 and 2.
ACTION:
With the drop time of any full length CEA determined to exceed the above limit, be in at least HOT STANDBY within six hours.
SURVEILLANCE REQUIREMENTS 4.1.3.4 The CEA drop time of full length CEAs shall be demonstrated through measurement prior to reactor criticality:
a.
For all CEAs following each removal and reinsta11ation of the reactor vessel head, b.
For specifically affected individuals CEAs following any maintenance on or modification to the CEA drive system which could affect the drop time of those specific CEAs, and c.
At least once per 18 months.
SAN ONOFRE-UNIT 2 3/4 1-20 AMENDMENT NO. 65
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'o, UNITED STATES I
NUCLEAR REGULATORY COMMISSION E
wAsmNGTON, D. C. 20555
.....j SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA THE CITY OF ANAHEIM, CALIFORNIA DOCKET NO. 50-362 S_AN ONOFRE NUCLEAR GENERATING STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 54 License No. NPF-15 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the license for San Onofre Nuclear Generating Station, Unit 3 (the facility) filed by the Southern California Edison Company (SCE) on behalf of itself and San Diego Gas and Electric Company, The City of Riverside and The City of Anaheim, California (licensees) dated June 14, 1988, as supplemented July 13 and July 25, 1988, complies with the standards and. requirements oftheAtomicEnergyActof1954,asamended(theAct)andthe Comission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Comission; i
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 set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the comon defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements I
have been satisfied.
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. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this amendment and Paragraph 2.C(2) of Facility Operating License No. NPF-15 is hereby amended to read as follows:
(2) Technical 3pecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.
54, are hereby incorporated in the license. SCE shall operate the facility in accordance tith the Technical Specifications and the Environmental Protection Plan.
3.
The change in Technical Specifications is to become effective within 30 days of issuance of the amendment.
In the period between issuance of the amendment and the effective date of the new Technical Specifications, the licensees shall adhere to the Technical Specifications existing at the time. The period of time during change over shall be minimized.
4.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION t 7\\
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George W. Knighton, Director Project Directorate V Division of Reactor Frojects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 10, 1988 l
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ATTACHMENT TO LICEN_SE AMENDMENT NO. 54 FACILITY OPERATING LICENSE NO. NPF-15 DOCKET NO. 50-362
' Replace the following pages of the Appendix "A" Technical S)ecifications with the attached pages. The ravised pages are identified
)y Amendment number and contain vertical lines indicating the area of change.
Remove Insert 3/4 1-20 3/4 1-20 b
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d ei REACTIVITY CONTROL SYSTEMS CEA DROP TIME LIMITING C3NDITION FOR OPERATION
.n 3.1.3.4 The individual full length (shutdown and regulating) CEA drop time, from a withdrawn position greater than or equal to 145 inches, shall be less than or equal to 3.2 seconds from when the electrical power is interrupted to l
the CEA drive mechanism until the CEA reaches its 90 percent insertion position with:
a.
T greater than or equal to 520*F, and av0 b.
All reactor coolant pumps operating.
APPU CABILITY:
H0 DES 1 and 2.
ACTION:
a.
With the drop time of any full length CEA determined to exceed the above limit, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
_ SURVEILLANCE REQUIREMENTS 4.1.3.4 The CEA drop time of full length CEAs shall be demonstrated through measurement prior to reactor criticality:
a.
For all CEAs following esch removal and rainstallation of the reactor vessel head, b.
For specifically affected individuals CEAs following r,y maintenance on or modification to the CEA drive system which coul; affect the drcp time of those specific CEAs, and c.
At least once per 18 months.
SAN ONOFRE-UNIT 3 3/4 1-20 AMENDMENT NO. 54
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