ML20077N984
| ML20077N984 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 08/12/1991 |
| From: | Dyer J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20077N988 | List: |
| References | |
| GL-88-16, NUDOCS 9108150185 | |
| Download: ML20077N984 (8) | |
Text
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- *too O[}x )~gf[*n LUNITED STATES A. EL NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 20666 -
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-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 ONOFRE NUCLEAR GENERATING STATION; UNIT N0'. 2
_ AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 97 License No. NPF-10 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The' a, plication for amendment by Southern California Edison Company, San Diego Gas and Electric Company,-the-City of Riverside,) (the -
California, and-the City of Anaheim,_ California (licensees licensee) dated April-15,11991 and1 supplemented May 7, 1991, 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_
Commission; C.
Thereis~reasonableassurance(1)thattheactivitiesauthorized 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; D.
- The issuance of this amendment will not b'e 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 Commission's regulations-and all applicable requirements have been satisfied.
4
'DR ADOCK 05000361 PDR
4 2.
Accordingly, the: license is amended by changes to the Technical Speci-fications 'as indicated in the attachment to this license amendment, and para' graph 2.C(2) of Facility Operating License No. NPF-10 is hereby amended to read as follows:
(2) Te'chnical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 97
, are hereby incorporated in the license.
Southern California Edi:,on Company sha n operate the facility in accordance with the Technical Specific, ions and the Environmental P rotection' Plan.
3.
This license amendme ' is effective as of the date of its issuance and must be fully implemented no later than 30 days from the d6te of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION t.Q James E. Dyer, Director Project Directorate V Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
' Changes to_the Technical Specifications 4
Date of Issuance: August-12, 1991 i
a J-
4 ATTACHMENT TO LICENSE AMEdDMENT AMENDMENT NO. 97 TO FACILITY OPERATING LICENSE NC. NPF-10 DOCKET N0. 50-361 Revise Appendix A Technical Specificatians by removing the page identified below and inserting the enclosed page.
The revised page is identified by the captioned amendment number and contain marginal lines indicating the ereas of change.
REMOVE INSERT 3/4 5-4 3/4 5-4 w
__m
EMERGENCY CORE COOLING SYSTEMS
-SURVEILLANCE REQUIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the following valves are a.
in the indicated positions with power to the valve operators removed:
Valve Number Valve Function Valve Position a.
HV9353 SDC Warsup CLOSED b.
HV9353 SDC Warmup CLOSED c.
HV815D SDC(HX) Isolation CLOSED d.
HV8151-SDC(HX) Isolation CLOSED e.
HV8152 SDC(HX) Isolation CLOSED f.
HV8153 SDC(HX) Isolation CLOSED g.
HV0396 SDC Bypass Flow Control CLOSED h.
HV8161 SDC(HX) Bypass Flow OPEN Isolation i.
HV9420 Hot Leg Injection CLOSED Isolation j.
HV9434 Hot Leg Injection CLOSED Isolation k.
HV8160 SDC Bypass Flow Control OPEN 1.
HV8162 LPSI Miniflow Isolation OPEN m.
HV8163 LPSI Miniflow Isolation OPEN b.
At least once per 31 days by:
1.
Verifying that the ECCS piping is full of water by venting the ECCS pump casings and accessible discharge piping high points, and 2, -
Verifying.that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position.
By a visual inspection which verifies that no loose debris (rags, c.
trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions.
This visual inspection shall be performed:
1.
For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and 2.
Of the areas affected within containment at the completion of containment entry when CONTAINMENT INTEGRITY is established, d.
At least'once per refueling interval by:
1.
Verifying automatic interlock action of the shutdown cooling system with the Reactor Coolant System by ensuring that when simulated RCS pressure is greater than or equal to 376 psia, the interlocks prevent opening the shutdown cooling system isolation valves.
SAN ONOFRE-UNIT 2 3/4 5-4 AMENDMENT NO. 97
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UNITED STATES
- ?
1-NUCLEAR: REGULATORY COMMISSION WASHINoToN. D.C; 20566 o
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=
SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE,-CALIFORNIA THE CITY OF ANAHEIM, CALIFORNIA i
DOCKET NO. 50-362 SAN-ONOFRE NUCLEAR GENERATING STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendwnt No. 86 License No. NPF-15 1.
The Nuclear-Regulatory Commission (the Commission) has found that:
A._
The application for amendment by Southern California Edison Company,:
= San Diego-Gas and Electric Company, the City of Riverside,) (the California, and-the City of Anaheim, California (licensees
-licensee) dated April 15, 1991 and supplemented May 7,1991,- 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 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 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 Commission's ' regulations and all applicable requirements have been satisfied.
l.
e-
. 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:
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix 0, as revised through Amendment No. 86, 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 REGutATORY COMMISSION
{.
J.A-.
James E. Dyer, Director Project Directorate V Division of Reactor Projects Ill/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August ]? 1991
ATTAChMLNT TO LICENSE AMENDMENT AMENDMENT-NO. 86-TO FACILITY OPERATING LICENSE NO. NPF-15 DOCKET NO. 50-362 Revise Appendix A Technical Specifications by removing the page identified below and inserting-the enclosed page. The revised page is identified by the-captioned amendment number and contain marginal lines indicating-the _
areas of. change.
REMOVE INSERT 3/4 5-4 3/4 5-4 I
a
aw EME'RGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS 4.5,2 Each ECCS subsystem shall be demonstrated OPERABLE:
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the following valves are a.
in the indicated positions with power to the valve operators removed:
Valve Number Valve Function Valve Position a.
HV9353 SDC Warmup CLOSED b.
HVo359 SDC Warmup CLOSED c.
HV8150 SDC(HX) Isolation CLOSED d.
HV8151 SDC(HX) Isolation CLOSED e.
HV8152 SDC(HX) Isolation CLOSED f.
HV8153 SDC(HX) Isolation CLOSED g.
HV0396 SDC Bypass Flow Control CLOSED h.
HV8161 SDC(HX) Bypass Flow OPEN Isolation i.
Deleted j.
Deleted k.
HV9420 Hot Leg Injection CLOSED Isolation 1.
HV9434 Hot Leg Injection CLOSED Isolation m.
HV8160 SDC Bypass Flow OPEN Control n.
HV8162 LPSI Miniflow OPEN Isolation o.
HV8163 LPSI Miniflow OPEN Isolation b.
At least once per 31 days by:
1.
Verifying that the ECCS piping is full of water by venting the ECCS pump casings and accessible discharge piping high points, and 2.
-Verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position.
By a visual inspection which verifies that no loose debris (rags, trash, c.
clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions.
This visual inspection shall be performed:
1.
For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and 2.
Of the areas affected within containment at the completion of :
containment entry when CONTAINMENT INTEGRITY is established.
d.
At least once per refueling interval by:
1.
Verifying automatic interlock action of the shutdown cooling system with the Reactor Coolant System by ensuring that when simulated RCS pressure is greater than or equal to 376 psia, the interlocks prevent opening the shutdown cooling system isolation valves.
SAN ONOFRE-UNIT 3 3/4 5-4 AMENDMENT NO. 86