ML20206Q756
| ML20206Q756 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 06/20/1986 |
| From: | Rood H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20206Q762 | List: |
| References | |
| TAC-54726, TAC-54727, TAC-54860, TAC-54861, NUDOCS 8607030319 | |
| Download: ML20206Q756 (14) | |
Text
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reg UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
,I WASWNGTON, D. C. 20666
,...../
SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA THE CITY OF ANAHEIM, CALIFORNIA DOCKET NO. 50-361
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SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 2
[
AMENDMENT TO FACILITY OPERATING LICENSE.
e.
Amendment No. 49 License No. NPF-10 1.
The Nuclear Regulatory Comission (the Comission) has found that:
1 A.
The applications for amendment to the license for San Onofre Nuclear Generating Station, Unit 2 (the facility) filed by the Southern California Edison Company on behalf of itself and San Diego Gas and Electric Company, The City of Riverside and The City of Anaheim, 3
3.
California (licensees) dated April 2 and 27, 1984 comply with the
' l i
standards and requirements of the Atomic Energy Act of 1954, as 4; l amended (the Act) and the Commission's regulations as set forth in
^'l 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, as amended, the provisions of the Act, and the regulations of the Ccmission; C.
There is reasonable assurance:
(i)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 Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the
- common 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.
i 8607030319 860620 DR ADOCK 05000361 PDR
. 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 Th'e Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 49, 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 licensee shall adhere to the. Technical Specifications existing at the time.
The period of time during changeover shall be minimized.
4.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION t
Harry Rood, Senior Project Manager PWR Project Directorate No. 7 Division of PWR Licensing-B
Attachment:
Changes to the Technical Specifications, Date of Issuance: JUN 2 01986 i
JUN 2 01935 -
ATTACHMENT TO LICENSE AMENDMENT N0. 49 FACILITY OPERATING LICENSE NO. NPF-10 DOCKET NO. 50-361 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Also to be replaced are the following overleaf pages to the amended pages.
Amendment Pages Overleaf Pages 3/4 3-41 3/4 3-42 3/4 8-18 3/4 8-17 e
l
]
INSTRUMENTATION
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INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The incore detection system shall be OPERABLE with:
a.
At least 75% of all incore detector locations, and b.
A minimum of two quadrant symmetric incore detector locations per core quadrant.
An OPERABLE incore detector location shall consist of a fuel assembly containing a fixed detector string with a minimum of four OPERABLE rhodium detectors or an OPERABLE movable incore detector capable of mapping the location.
APPLICABILITY: When the incore detection system is used for monitoring:
a.
AZIMUTHAL POWER TILT, i
b.
Radial Peaking Factors, c.
Local Power Density, d.
DNB Margin.
ACTION:
With the incore detection system inoperable, do not use the system for the above applicable monitoring or calibration functions.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE. REQUIREMENTS 4.3.3.2 The incore detection system shall be demonstrated OPERABLE:
a.
By performance of a CHANNEL CHECK within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to its use if 7 or more days have elasped since the previous check and at least once per 7 days thereafter when required for monitoring the AZIMUTHAL POWER TILT, radial peaking factors, local power density or DNB margin:
b.
At least once per 18 months by performance of a CHANNEL CALIBRATION operation which exempts the neutron detectors but includes all electronic components.
The neutron detectors shall be calibrated prior to installation in the reactor core.
SAN ONOFRE-UNIT 2 3/4 3-41 AMENDMENT NO. 49
- ~.,. -
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INSTRUMENTATION SEISMIC INSTRUMENTATION l
LIMITING CONDITION FOR OPERATION I
e 3.3.3.3 The seismic monitoring instrumentation shown in Table 3.3-7 shall be OPERA 8LE.
APPLICA8ILITY:
At all times.
~
ACTION:
)
i a.
With one or more seismic monitoring instruments 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 a
i the cause of the malfunction and the plans for restoring the instrument (s) to OPERABLE status, b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
1 SURVEILLANCE REQUIREMENTS I
4.3.3.3.1 Each of the above seismic monitoring instruments shall be demonstrated OPERA 8LE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-4.
l 4.3.3.3.2 Each of the above seismic monitoring instruments which is accessible during power operation and which is actuated during a seismic event (one or more valid basemat accelerations of 0.05g or greater) shall be restored to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and a CHANNEL CALIBRATION performed within i
5 days.
Data shall be retrieved from the accessible actuated instruments and analyzed to determine the magnitude of the vibratory ground motion.
A Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 10 days describing the magnitude, frequency spectrum and resultant effect upon facility features important to safety.
Each of the above seismic monitoring instruments which is actuated during a seismic event (one or more valid basemat accelerations of 0.05g or greater) but is not accessible during power operation shall be restored to OPERABLE status i
and a CHANNEL CALIBRATION performed the next time the plant enters MODE 3 or below.
A supplemental report shall then be prepared and submitted to the Commission within 10 days pursuant to Specification 6.9.2 describing the additionas data from these instruments.
i SAN ONOFRE-UNIT 2 3/4 3-42
ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
(c) For each circuit breaker found inoperable during these functional tests, an additional representative sample of at least 10% of all the circuit breakers of the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type i
have been functionally tested.
2.
By selecting an functionally testing a representative sample of at least 10% of each type of lower voltage circuit breakers.
Circuit breakers selected for functional testing shall be i
selected on a rotating basis.
Testing of these circuit j
breakers shall consist of injecting a current in excess of the breakers' nominal setpoint and measuring the response time.
The measured response time will be compared to the manufacturer's j
data to insure that it is less than or equal to a value specified i
by the manufacturer.
Circuit breakers found inoperable during functional testing shall be restored to OPERABLE status prior to resuming operation.
For each circuit breaker found inoperable jl during these functional tests, an additional representative sample of at least 10% of all the circuit breakers of the i
inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested.
b.
At least once per 60 months by subjecting each circuit breaker to an inspection and preventive maintenance in accordance with procedures prepared in conjunction with its manufacturer's recommendations.
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SAN ONOFRE-UNIT 2 3/4 8-17 AMENDMENT NO. 2
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!g TABLE 3.8-1 i
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CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES
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- o 7
Primary Device Backup Device Number Number Service Description c
280106 2BLP0101 Containment Normal Cooling Fan E-397 N
280107 2BLP0102 CEDM Cooling Supply Fan E-403B l
280109 2BLP0103 CEDM Cooling Supply Fan E-403A 280111 2BLP0104 Standby Containment Normal Cooling Fan E-393 l
2B0209 2BLP0201 Containment Normal Cooling Fan E-394 2B0406 2BLP0301 Hydrogen Recombiner E-145 Power Panel L-180 2C0409 2BLP0302 Upper Dome Air Circulator A-071 2B0410 2BLP0303 Containment Emergency Fan E-399 200411 2BLP0304 Containment Emergency Fan E-401 j
200419 2BLP0305 Standby Upper Dome Air Circulator A-074
,s I
2B0606 2BLP0401 Hydrogen Recombiner E-146 Power Panel L-181 T
2B0609 2BLP0402 Upper Dome Air Circulator A-072 o$
2B0610 2BLP0403 Containment Emergency Fan E-400 j
2B0611 2BLP0404 Containment Emergency Fan E-402 2B0619 2BLP0405 Standby Upper Dome Air Circulator A-073 280809 2BLP0501 Containment Normal Cooling Fan E-396 2B0811 2BLP0601 Containment Normal Cooling Fan E-398 280903 2BLP0701 Containment Recirculation Unit A-353 2B0906 2BLP0702 Polar Crane (Containment) R001 (C) g 280907 2BLP0703 Standby Control Element Drive Mechanism Cooling g
Supply Fan E-404A 4
e i
R 280909 2BLP0704 Standby CEDM Cooling Supply Fan E-404B 4
280911 2BLP0705 Containment Recirculating Unit Heater E-568 1;
g 2BA02 2BLP0812 CCW from RCP P-001 Seal Heat Exchanger TV-9144 2BA03 2BLP0813 CCW from RCP P-003 Seal Heat Exchanger TV-9154 2BA04 2BLP0801 CEDM Cooling Supply Fan E-403A (2BA04-A)
(Enclosure Heater) l I
/
o UNITED STATES g
8 g
NUCLEAR REGULATORY COMMISSION 1
h j
WASHINGTON, D. C. 20555
)
SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY l
THE CITY OF RIVERSIDE, CALIFORNIA j
THE CITY OF ANAHEIM, CALIFORNIA DOCKET NO. 50-361 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 2
. [j AMENDMENT TO FACILITY OPERATING LICENSE
[
Amendment No. 38 License No. NPF-10 1
]
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The applications for amendment to the license for San Onofre Nuclear Generating Station, Unit 2 (the facility) filed by the Southern California Edison Company on behalf of itself and San Diego Gas and Electric Com l-California (pany, The City of Riverside and The City of Anaheim, licensees) dated April 2 and 27, 1984 comply with the a
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 i
amended, the provisions of the Act, and the regulations of the l
Commission; i
i i
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 set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the common 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.
l
2-2.
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 Specifications The Technical Specifications contained in Appendix A and the l
Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 38, are hereby incorporated in the license.
SCE shall operate the facility in accordance with the Technical Specific'ations 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 licensee shall adhere to the. Technical Specifications, existing at the time. The period of time during changeover shall be minimized.
4.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Harry Road, Senior Project Manager PWR Project Directorate No. 7 Division of PWR Licensing-B
Attachment:
Changes to the Technical Specifications Date of Issuance:
JUN 2 01986
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,-,----w, 9------
JUN 2 01986 9 s ATTACHMENT TO LICENSE AMENDMENT NO. 38 FACILITY OPERATING LICENSE NO. NPF-15 DOCKET NO. 50-362 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Also to be replaced are the folleving overleaf pages to the amended pages.
l Amendment Pages Overleaf Pages 3/4 3-41 3/4 3-42 3/4 8-18 3/4 8-17 l
l l
I
.i
INSTRUMENTATION INCORE DETECTORS LIMITING CONDITION FOR OPERATION
- 3.3.3.2 The incore detection system shall be OPERABLE with:
a.
At least 75% of all incore detector locations, and b.
A minimum of two quadrant symmetric incore detector locations per core quadrant.
An OPERABLE incore detector location shall consist of a fuel assembly containing a fixed detector string with a minimum of four OPERABLE rhodium detectors or an OPERABLE movable incore detector capable of mapping the location.
APPLICABILITY: When the incore detection system is used for monitoring:
a.
AZIMUTHAL POWER TILT, b.
Radial Peaking Factors, c.
Local Power Density, d.
DNB Margin.
ACTION:
With the incore detection system inoperable, do not use the system for the above applicable monitoring or, calibration functions.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.2 The incore detection system shall be demonstrated OPERABLE:
a.
By performance of a CHANNEL CHECK within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to,its use if 7 or more days have elapsed since the previous check and at least once pei 7 days thereafter when required for monitoring the AZIMUTHAL POWER TILT, radial peaking factors, local power density or DNB margin:
b.
At least once per 18 months by performance of a CHANNEL CALIBRATION operation which exempts the neutron detectors but includes all electronic components.
The neutron detectors shall be calibrated prior to installation in the reactor core.
SAN ONOFRE - UNIT 3 3/4 3-41 AMENDMENT NO. 38
INSTRUMENTATION SEISMIC INSTRUMENTATION *
}
LIMITING CONDITION FOR. OPERATION I
i 3.3.3.3 The seismic monitoring instrumentation shown in Table 3.3-7 shall be j
APPLICA8ILITY: At all times.
ACTION:
With one or more seismic monitoring instruments inoperable for more a.
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 4
instrument (s) to OPERABLE status.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
1 SURVEILLANCE REQUIREMENTS J
~4.3.3.3.1 Each of the above seismic monitoring instruments shall be l
demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-4.
4.3.3.3.2 Each of the above seismic monitoring instruments which is accessible during power operation and which is actuated during a seismic event (one or 1
mo.re valid basemat accelerations of 0.05g or greater) shall be restored to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and a CHANNEL CALIBRATION performed within 5 days.
Data'shall be retrieved from the accessible actuated instruments and analyzed to determine the magnitude of the vibratory ground motion.
A Special Report shall be prepared and submitted to the Commission pursuant to 1
Specification 6.9.2 within 10 days describing the magnitude, frequency spectrum
)
and resultant effect upon facility features important to safety.
Each of the
'above seismic monitoring instruments which is actuated during a seismic event j
(one or more valid basemat accelerations of 0.05g or greater) but is not accessible during power operation shall be restored to OPERABLE status and a CHANNEL CALIBRATION performed the next time the plant enters MODE 3 or below.
A supplemental report shall then be prepared and submitted to the Commission within 10 days pursuant to Specification 6.9.2 describing the additional data from these instruments.
Shared system with San Onofre - Unit 2.
i 1
SAN ONOFRE-UNIT 3 3/4 3-42
I i
i ELECTRICAL POWER SYSTEMS 4
(
SURVEILLANCE REQUIREMENTS (Continued)
(c)' For each circuit breaker found inoperable during these functional tests, an additional representative sample of at least 10% of all the circuit breakers of the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested.
2.
By selecting and functionally testing a representative sample of at least 10% of each type of lower voltage circuit breakers.
4' Circuit breakers selected for functional testing shall be selected on a rotating basis.
Testing of these circuit breakers shall consist of injecting a current in excess of the breakers' nominal setpoint and measuring the response time.
The measured response time will be compared to the manufacturer's data to insure that it is less than or equal to a value specified by the manufacturer.
Circuit breakers found inoperable during functional testing shall be restored to OPERABLE status prior to resuming operation.
For each circuit breaker found inoperable during these functional tests, an additional representative i
sample of at least 10% of all the circuit breakers of the l[
inoperable type shall also be functionally tested until no more
\\
failures are found or all circuit breakers of that type have been functionally tested.
j b.
At least once per 60 months by subjecting each circuit breaker to an inspection and preventive maintenance in accordance with procedures prepared in conjunction with its manufacturer's recommendations.
l I
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4 I
SAN ONOFRE-UNIT 3 3/4 8-17
TABLE 3.8-1 E
CONTAINMENT PENETRATION CON 00CTOR OVERCURRENT PROT'ECTIVE DEVICES E
i o
E Primary Device Backup Device Number Number Service Description E
280106 2BLP0101 Containment Normal Cooling Fan E-397 l
Z 2B0107 2BLP0102 CEDM Cooling Supply Fan E-4038 l
w 280109 2BLP0103 CEDM Cooling Supply Fan E-403A 280111 2BLP0104 Standby Containment Normal Cooling Fan E-393 l
2B0209 2BLP0201 Containment Normal Cooling Fsn E-394 j
2B0406 2BLP0301 Hydrogen Recombiner E-145 Power Panel L-180 2B0409 2BLP0302 Upper Dome Air Circulator A-071 i
2B0410 2BLP0303 Containment Emergency Fan E-399 2B0411 2BLP0304 Containment Emergency Fan E-401 2B0419 2BLP0305 Standby Upper Dome Air Circulator A-074 t
i M
200606 2BLP0401 Hydrogen Recombiner E-146 Power Panel L-181 2B0609 2BLP0402 Upper Dome Air Circulator A-072 I
T 200610 2BLP0403 Containment Emergency Fan E-400 i
M 280611 2BLPO404 Containment Emergency Fan E-402 2B0619 2BLP0405 Standby Upper Dome Air Circulator A-073 280809 2BLP0501 Containment Normal Cooling Fan E-396 i
280811 2BLP0601 Containment Normal Cooling Fan E-398 2B0903 2BLP0701 Containment Recirculation Unit A-353 l
4 280906 2BLP0702 Polar Crane (Containment) R001 (C) 280907 2BLP0703 Standby Control Element Drive Mechanism Cooling l
g Supply Fan E-404A m
E 280909 2BLP0704 Standby CEDM Cooling Supply Fan E-4048 3
280911 2BLP0705 Containment Recirculating Unit Heater E-568
'i 2BA02 2BLP0812 CCW from RCP P-001 Seal Heat Exchanger TV-9144 z
2BA03 2BLP0813 CCW from RCP P-003 Seal Heat Exchanger TV-9154 l
P 2BA04 2BLP0801 CEDM Cooling Supply Fan E-403A g
(2BA04-A)
(Enclosure Heater) i m