ML20064E615
| ML20064E615 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 03/09/1994 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20064E619 | List: |
| References | |
| NUDOCS 9403140381 | |
| Download: ML20064E615 (9) | |
Text
-
~
p s
- r, e.
O i
UNITED STATES i gg; #[fl NUCLEAR REGULATORY COMMISSION wAssiscion, o c 20sss-coci 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 NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 111 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 Octcber 16, 1992, complies with the standards and requirensents of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I; 8.
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 comon 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.
9403140381 940309 PDR ADOCK 05000361 P
v l
) i 2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and l
paragraph 2.C(2) of Facility Operating License No. NPF-10 is hereby i
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. 111, 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 COPHISSION i
4 7 U M w d 2-
^p
^^
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:
tiarch 9, 1994 j
t 2
n.~
--,. ~.
w
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.111 TO FACILITY OPERATING LICENSE N0. NPF-10 DOCKET NO. 50-361 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.
The corresponding overleaf page is also provided to maintain document completeness.
REMOVE INSERT 3/4 3-76 3/4 3-76 p
t t
INSTRUMENTATION LOOSE-PART DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.10 The loose-part detection system shall be OPERABLE.
APPLICABILITY: MODES 1 and 2.
ACTION:
a.
With one or more loose part detection system channels inoperable for more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERABLE status.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.10 Each channel of the loose-part detection system shall be demonstrated OPERABLE by performance of a:
a.
CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.
CHANNEL FUNCTIONAL TEST at least once per 31 days, and c.
CHANNEL CALIBRATION at least once per refueling interval.
I 1
H
)
SAN ON0FRE - UNIT 2 3/4 3-75 AMENDMENT NO. 75
i
~
INSTRUMENTATION 3/4.3.4 TURBINE OVERSPEED PROTECTIQB LIMITING CONDITION FOR OPERATION 3.3.4 At least one turbine overspeed protection system shall be OPERABLE.
APPLICABILITY: MODES 1, 2* and 3.*
ACTION:
a.
With one stop valve or one control valve per high pressure turbine steam lead inoperable and/or with one reheat stop valve or one reheat intercept valve per low pressure turbine steam lead inop-erable, restore the inoperable valve (s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or close at least one valve in the affected steam lead or isolate the turbine from the steam supply within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With the above required turbine overspeed protection system otherwise inoperable, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> isolate the turbine from the steam supply.
SURVEILLANCE REQUIREMENTS 4.3.4 The above required turbine overspeed protection system shall be demonstrated OPERABLE:
a.
Deleted.
b.
At least once per 31 days by direct observation of the movement of each of the following valves through one complete cycle from the running position.
1.
Four high pressure turoine stop valves.
2.
Four high pressure turbine control valves.
3.
Six low pressure turbine reheat stop valves.
4.
Six low pressure turbine reheat intercept valves.
c.
At least once per refueling interval by performance of a CHANNEL CAllBRATION on the turbine overspeed protection systems, d.
At least once per 40 nonths by disassembling at least one of each of the above valves and performing a visual and surface inspection of valve seats, disks aad stems and verifying no unacceptable flaws or corrosion.
- With any main steam line isolation valve and/or any main steam line isolation valve bypass valve not fully closed.
SAN ONOFRE-UNIT 2 3/4 3-76 AMENDMENT NO. 79,111
a t**"'%f d'p
'c 7;jjf[f
\\
~
UNITED STATES NUCLEAR REGULATORY COMMISSION W ASHINGTON, D.C. 20555-0001 SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE. CALIFORNIA THE CITY OF ANAHEIM. CALIFORNIA DOCKET NO. 50-362 SAN ONOFRE NUCLEAR GENERATING STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.100 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 October 16, 1992, 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 (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 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.
i
- - ~ - -
-~
i 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 R, as revised through Amendment No.100, 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 glcw M
- 'y Theodore R. Quay, Director 3
Project Directorate V i
Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical j
Specifications Date of Issuance:
March 9, 1994 1
1 i
~
j I
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 100 TO FACILITY OPERATING LICENSE NO. NPF-15 DOCKET NO. 50-362 Revise Appendix A Technical Specifications by removing the., age 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 3-77 3/4 3-77
=
INSTRUMENTATION 3/4.3.4 TURBINE OVERSPEED PROTECTION LIMITING CONDITION FOR OPERATION i
3.3.4 At least one turbine overspeed protection system shall be OPERABLE.
APPLICABILITY:
MODES 1, 2* and 3.*
ACTION:
a.
With one stop valve nr one control valve per high pressure turbine steam lead inoperable and/or with one reheat stop valve or one reheat intercept valve per low pressure turbine steam lead inop-erable, restore the inoperable valve (s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or close at least one valve in the affected steam lead or isolate the turbine from the steam supply within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With the above required turbine overspeed protection system otherwise inoperable, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> isolate the turbine from the steam supply.
SURVEILLANCE REQUIREMENTS 4.3.4 The above required turbine overspeed protection system shall be demonstrated OPERABLE:
a.
Deleted.
b.
At least once per 31 days by direct observation of the movement of each of the following valves through one complete cycle frca the running position.
1.
Four high pressure turbine stop valves.
2.
Four high pressure turbine control valves.
3.
Six low pressure turbine reheat stop valves.
4.
Six low pressure turbine reheat intercept valves.
c.
At least once per refueling interval by performance of a CHANNEL CALIBRATION on the turbine overspeed protection systems.
d.
At least once per 40 months by disassembling at least one of each of the above valves and performing a visual and surface inspection of valve seats, disks and stems and verifying no unacceptable flaws or corrosion.
- With any main steam line isolation valve and/or any main steam line isolation valve bypass valve not fully closed.
SAN ONOFRE-UNIT 3 3/4 3-77 AMENDMENT NO.-frP,100