ML20045C149

From kanterella
Jump to navigation Jump to search
Amends 107 & 96 to Licenses NPF-10 & NPF-15 Respectively, Revising TS 3/4.8.1 to Provide one-time Exception to TS 4.8.1.1.1.9 to Allow Replacement of 480 Volt Transformers BO4X/BO6X During Cycle 7 Refueling Outages
ML20045C149
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 06/05/1993
From: Quay T
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20045C150 List:
References
NUDOCS 9306220134
Download: ML20045C149 (8)


Text

_

8 f' M C ug UNITED STATES f'ik;;/y

[

NUCLEAR REGULATORY COMMISSION gg WASHINGTON. D C 20555 0001 "q'...

j 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 NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.107 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 April 13, 1993, 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 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.

9306220134 930615 DR ADOCK 0500 1

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.107, 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 x6 b M Theodore R. Quay, Director Project Directorate V Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: June 15, 1993 i

ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.107TO FACILITY OPERATING LICENSE NO. 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.

REMOVE INSERT 3/4 8-2 3/4 8-2 f

ELECTRICAL POWER SYSTEM SURVEILLANCE RE0VlREMENTS 4.8.1.1.1 Each of the above required independent circuits between the offsite transmission network and the onsite Class IE distribution system shall be:

a.

Determined OPERABLE at least once per 7 days by verifying correct breaker alignments and indicated power availability.

If tie breakers 3A0416 or 3A0603 are used to provide a source of power, the following busses are required.

for 3A0416 for 3A0603 3A04 3A06 3B04**

3B06**

3D1 3D2 b.

Demonstrated OPERABLE at least once per refueling interval during shutdown by transferring (manually and automatically) unit power from the normal offsite power source to the alternate offsite power source. The provisions of Technical Specification 4.0.2 are not applicable.

4.8.1.1.2 Each diesel generator shall be demonstrated OPERABLE:

a.

In accordance with the frequency specified in Table 4.8-1 on a STAGGERED TEST BASIS by:

1.

Verifying the fuel level in the day fuel tank, 2.

Verifying the fuel level in the fuel storage tank, 3.

Verifying the fuel transfer pump can be started and transfers fuel from the storage system to the day tank, 4.

Verifying the diesel generator starts from ambient conditions and accelerates to at least 900 rpm.*

The generator voltage and frequency shall be 4360 i 436 volts and 60 1.2 Hz after reaching 900 rpm.

The diesel generator shall be started for this test by using one of the following signals:

  • A diesel generator start (in less than 10 seconds) from ambient conditions shall be performed at least once per 184 days. All other engine starts for the purpose of this surveillance testing may be preceded by an engine pre-lube period and/or other warmup procedures recommended by the manufacturer so that mechanical stress and wear on the diesel engine is minimized.
    • During Unit 3 Cycle 7 refueling outage, for the replacement of transformers 3B04X and 3B06X, tie breakers 3A0416 and 3A0603 may be considered OPERABLE with busses 3B04 or 3B06 IN0PERABLE provided that Unit 3 enters TS 3.8.2.2 ACTION b for the affected battery charger.

SAN ON0FRE - UNIT 2 3/4 8-2 AMENDMENT NO -75,107

f *Ec o

,?t UNITED STATES

[.lh/_J [ }

NUCLEAR REGULATORY COMMISSION j

f W ASHINGTON. D C. 20555-0001

1,,.....f SOUTHERN CALIFORNIA EDIS0N 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. 96 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 April 13, 1993, 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.

I

l

  • 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 Soecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 96, 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

/ bu.h ucy s

Theodore R. Quay, Director Project Directorate V Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

June 15,1993

ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 96 TO FACILITY OPERATING LICENSE N0. NPF-15 DOCKET NO. 50-362 Revise Appendix A Technical Specifications by recoving 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.

l REMOVE INSERT 3/4 8-2 3/4 8-2

ELECTRICAL POWER SYSTEMS SURVEILLANCE RE0VIREMENTS 4.8.1.1.1 Each of the above required independent circuits between the offsite transmission network and each Class lE 4 kV Bus shall be:

a.

Determined OPERABLE at least once per 7 days by verifying correct breaker alignments and indicated power availability.

If tie breakers 2A0417 or 2A0619 are used to provide a l

source of power, the following busses are required, for 2A0417 for 2A0619 l

2A04 2A06 2B04**

2B06**

l 2D1 2D2 b.

Demonstrated OPERABLE at least once per refueling interval during shutdown by transferring (manually and automatically) unit power from the normal offsite power source to the alternate offsite power source.

The provisions of Technical Specification 4.0.2 are not applicable.

4.8.1.1.2 Each diesel generator shall be demonstrated OPERABLE:

a.

In accordance with the frequency specified in Table 4.8-1 on a STAGGERED TEST BASIS by:

1.

Verifying the fuel level in the day fuel tank, 2.

Verifying the fuel level in the fuel storage tank, 3.

Verifying the fuel transfer pump can be started and trans-fers fuel from the storage system to the day tank, 4.

Verifying the diesel generator starts from ambient condi-tions and accelerates to at least 900 rpm.* The generator voltage and frequency shall be 4360 i 436 volts and 60 i 1.2 Hz after reaching 900 rpm. The diesel generator shall be started for this test by using the manual start signals:

a)

Manual b)

Simulated loss of offsite power by itself c)

Simulated loss of offsite power in~ conjunction with an ESF actuation test signal

  • A diesel generator start (in less than 10 seconds) from ambient conditions shall be performed at least once per 184 days. All.other engine starts for the purpose of this surveillance testing may be preceded by an engine pre-lobe period and/or other warmup procedures recommended by the manufacturer so that mechanical stress and wear on the diesel engine is minimized.
    • During Unit 2 Cycle 7 refueling outage, for the replacement of transformers 2B04X and 2B06X, tie breakers 2A0417 and 2A0619 may be considered OPERABLE with busses 2B04 or 2B06 IN0PERABLE provided that Unit 2 enters TS 3.8.2.2 ACTION b for the affected battery charger.

SAN ONOFRE - UNIT 3 3/4 8-2 AMENDMENT N0. O, 96