ML20092H105
| ML20092H105 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 09/13/1995 |
| From: | Fields M NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20092H108 | List: |
| References | |
| NUDOCS 9509200262 | |
| Download: ML20092H105 (14) | |
Text
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UNITED STATES 3
NUCLEAR REGULATORY COMMISSION E
f WASHINGTON, D.C. 20066 4 001
\\...../
SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY j
THE CITY OF RIVERSIDE. CALIFORNIA THE CITY OF ANAHEIM. CALIFORNIA DOCKET NO. 50-361 SAN ONOFRE NUCLEAR GENERATING STATION. UNIT NO. 2 A_MENDMENT TO FACILITY OPERATING LICENSE Amendment No.125 License No. NPF-10 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Southern California Edison Company, et al. (SCE or the licensee) dated May 20, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission'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 Commission'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.
P
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. 125, 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.
The license amendment is effective as of the date of issuance to be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION fhO f
Q Mel B. Fields, Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation l
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 13, 1995
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.125 TO FACILITY OPERATING LICENSE NO. NPF-10 DOCKET NO. 50-361 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE INSERT 3/4 7-11 3/4 7-11 B 3/4 7-3h B 3/4 7-3b
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I ELANT SYSTEMS
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3/4.7.3 COMPONENT COOLING WATER SYSTEM l
LIMITING CONDITION FOR OPERATION 3.7.3 At least two independent component cooling water loops shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
a.
With only one component cooling water loop OPERABLE, restore at least l
two loops 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 be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With either one or both trains of the Backup Nitrogen Supply (BNS) system inoperable, within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> restore the BNS system train (s) to OPERABLE status or declare the associated CCW loop (s) inoperable.
l SURVEILLANCE REOUIREMENTS l
4.7.3.1 At least two component cooling water loops shall be demonstrated i
OPERABLE:
a.
At least once per 31 days by verifying that each valve (manual, j
power operated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.
b.
At least once per refueling interval during shutdown, by verifying that each automatic valve servicing safety-related equipment actuates to its correct position and each component cooling water pump starts automatically on an SIAS test signal.
4.7.3.2 The BNS system shall be demonstrated OPERABLE:
a.
At least once per 7 days by verifying that at least nine nitrogen gas bottles are installed with a minimum average bottle pressure of 4232 i
psig.
b.
At least once per refueling interval by verifying that the third stage pressure regulator of the BNS system is set at 55 psig (i 1.5 psi).
4 1
SAN ON0FRE - UNIT 2 3/4 7-11 Amendment No. M,125 i
i
PLANT SYSTEM 5 3/4.7.4 SALT WATER COOLING SYSTEM LIMITING CONDIT10N FOR OPERATION t
3.7.4 At least two independent salt water cooling loops shall be OPERA 8LE.
APPLICABILITY: MODES 1, 2, 3 and 4 ACTION:
With only one salt water cooling loop OPERABLE, restore at least two loops 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 be in at least HOT STAND 8Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
i l
SURVEILLANCE REQUIREMENTS 1
4.7.4 At least two salt water cooling loops shall be demonstrated OPERABLE:
At least once per 31 days by verifying that each valve (manual, a.
power operated or automatic) servicing safety related equipment that is not locked, sealed or otherwise secured in position, is in its correct position.
b.
At least once per refueling interval during shutdown, by verifying that each automatic valve servicing safety-related equipment actuates to its correct positibn and each salt water cooling pump starts automatically on an SIAS test signal.
SAN ONOFRE-UNIT 2 3/4 7-12 AMENDMENT N0. 75 4
s
i PLANT SYSTEMS BASES 2
3/4.7.1.6 ATMOSPHERIC DUMP VALVES (Continued) l The provisions of Specification 3.0.4 in MODES 2, 3, and 4 do not apply j
when only one ADV is inoperable, and the ADV can be made OPERABLE within the allowed action times. However, with two inoperable ADVs the plant must be 1.
placed on shutdown cooling.
Therefore, the provisions of Specification 3.0.4
]
do apply with two inoperable ADVs.
3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION
/<
The limitation on secondary side steam' generator pressure and temperature ensures that the pressure induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits. The limitations of 70*F and 200 psig are based on a steam generator RT, of 40*F and are sufficient to prevent brittle fracture.
I j
3/4.7.3 COMPONENT COOLING WATER SYSTEM The OPERABILITY of the Component Cooling Water (CCW) system ensures that l
sufficient cooling capacity is available for continued operation of safety 5
related equipment during normal and accident conditions. The redundant cooling i
capacity of this system, assuming a single failure, is consistent with the l
assumptions used in the accident analyses.
The CCW system is normally pressurized to maintain the CCW system water-i solid using nitrogen gas supplied to the CCW surge tank by the non-safety i
related Auxiliary Gas system. Makeup water to the surge tank is normally provided by the non-safety related, Nuclear Service Water system to compensate for normal system leakagp.
F Following a Design Basis Event, both the non-safety related Auxiliary Gas System and Nuclear Service Water system are assumed to be unavailable. A postulated Design Basis Event could result in CCW system voiding and a subsequent water hammer. The Backup Nitrogen Supply (BNS) system is an independent, safety related, Seismic Category I source of pressurized nitrogen i
for both CCW surge tanks.
The BNS system is designed to minimize CCW system high-point voiding by maintaining the CCW critical loops water-solid during Design Basis Event mitigation.
BNS system OPERABILITY ensures that both CCW surge tanks will be pressurized for at least seven days following a Design Basis Event without bottle changeout. The BNS system is required to be OPERABLE whenever the associated train of CCW is required to be OPERABLE. The BNS system surveillance requirements provide adequate assurance that BNS system j
OPERABILITY will be maintained.
i 3/4.7.4 SALT WATER COOLING SYSTEM The OPERABILITY of the salt water cooling system ensures that sufficient cooling capacity is available for continued operation of equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the accident analyses.
SAN ON0FRE - UNIT 2 B 3/4 7-3b Amendment No. 93,125 i
l l
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PLANT SYSTEMS BASEJ
)
3/4.7.5 CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM i
The OPERK8ILITY of the control roca emergency air cleanup system ensures that 1) the ambient air temperature does not exceed the allowable temperature i
for continuous dut this system and 2)y rating for the equipment ahd instrimentation cooled by the control room will remain habitable for operations 1
personnel during and following all credible accident conditions.
The 0FenABILITY of this system in conjunction with control room design provisions i
)
1.s based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent. This limitation is i
consistent with the requirements of General Design Criteria 19 of Appendix A, 10 CFR 50.
)
Cumulative operation of the system with the heaters on for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over a 31 day period is sufficient in reduce the buildup of moisture on the adsorbers and HEPA filters.
4 i
1 1
/
SAN ONOFRE-UNIT 2 8 3/4 7-4
pMtv UNITED STATES p!
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON. D.C. 2064 6 4001
'+9....
96 SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE. CALIFORNIA THE CITY OF ANAHEIM. CALIFORNIA DOCKET N0. 50-362 SAN ON0FRE NUCLEAR GENERATING STATION. UNIT N0. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.114 License No. NPF-15 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Southern California Edison Company, et al. (SCE or the licensee) dated May 20, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as ame'nded (the Act), and the Commission'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 Commission'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.
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. 114, 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.
The license amendment is effective as of the date of issuance to be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 9
/
Q Mel B. Fields, Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifica'tions Date of Issuance:
September 13, 1995
i ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.114 TO FACILITY OPERATING LICENSE NO. NPF-15 DOCKET NO. 50-362 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.
The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE INSERT 3/4 7-12 3/4 7-12 B 3/4 7-3b B 3/4 7-3b i
l 1
i
i PLANT SYSTEMS
$/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATIO LIMITING CONDITION FOR OPERATION 4
j 3.7.2 The temperature of the secondary coolant in the steam generators shall i
be greater than 90*F when the pressure of the secondary coolant in the staam generator is greater than 200 psig.
i APPLICABILITY: At all times.
ACTION:
With the requirements of the above specification not satisfied:
i Reduce the steam generator pressure of the secondary side to less l
a.
than or equal to 200 psig within 30 minutes, and b.
Perform an engineering evaluation to determine the effect of the 1
overpressurization on the structural integrity of the steam generator.
Determine that the steam generator remains acceptable for continued operation prior to increasing its temperatures above 200*F.
i l
SURVEILLANCE REQUIREMENTS.
i 4.7.2 The pressure in the secondary side of the steam generators shall be determined to be less than 200 psig at least once per hour when the temperature i
of the secondary coolant is less than 90'F.
s 1
SAN ONOFRE-UNIT 3 3/4 7-11 AMENDMENT N0. 82 i
PLANT SYSTEMS 3/4.7.3 COMPONENT COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.3 At least two independent component cooling water loops shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With only one component cooling water loop OPERABLE, restore at least I
a.
two loops 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 be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, b.
With either one or both trains of the Backup Nitrogen Supply (BNS) system inoperable, within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> restore the BNS system train (s) to OPERABLE status or declare the associated CCW loop (s) inoperable.
SURVE1LLANCE RE0VIREMENTS 4.7.3.1 At least two component cooling water loops shall be demonstrated l
OPERABLE:
At least once per 31 days by verifying that each valve (manual, a.
power operated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.
b.
At least once per refueling interval during shutdown, by verifying that each automatic valve servicing safety-related equipment actuates to its correct position and each component cooling water pump starts automatically on an SIAS test signal.
i 4.7.3.2 The BNS system shall be demonstrated OPERABLE:
At least once per 7 days by verifying that at least nine nitrogen gas a.
bottles are installed with a minimum average bottle pressure of 4232 psig.
b.
At least once per refueling interval by verifying that the third stage pressure regulator of the BNS system is set at 55 psig (i 1.5 psi).
SAN ONOFRE - UNIT 3 3/4 7-12 Amendment No. 63,114
PLANT SYSTEMS BASES 3/4.7.1.6 ATMOSPHERIC DUMP VALVES (Continued) the ADVs are subject to inservice testing per Surveillance 4.7.1.6.3, the frequency of Surveillance 4.7.1.6.1 is based on the length of a fuel cycle.
i The provisions of Specification 3.0.4 in MODES 2, 3, and 4 do not apply when only one ADV is inoperable, and the ADV can be made OPERABLE within the allowed action times. However, with two inoperable ADVs the plant must be placed on shutdown cooling. Therefore, the provisions of Specification 3.0.4 l
do apply with two inoperable ADVs.
3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION The limitation on secondary side steam generator pressure and temperature ensures that the pressure-induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits. The limitations of 90*F and 200 psig are based on a steam generator RT, of 60*F and are sufficient to prevent brittle fracture.
1 3/4.7.3 COMPONENT COOLING WATER SYSTEM s
The OPERABILITY of the Component Cooling Water (CCW) system ensures that l
i sufficient cooling capacity is available for continued operation of safety j
related equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the l
assumptions used in the accident analyses.
The CCW system is normally pressurized to maintain the CCW system water-solid using nitrogen gas supplied to the CCW surge tank by the non-safety related Auxiliary Gas System. Makeup water to the surge tank is normally provided by the non-safety related, Nuclear Service Water system to compensate for normal system leakage.
Following a Design Basis Event, both the non-safety related Auxiliary Gas system and Nuclear Service Water system are assumed to be unavailable.
A 4
i postulated Design Basis Event could result in CCW system voiding and a subsequent water hammer. The Backup Nitrogen Supply (BNS) system is an independent, safety related, Seismic Category I source of pressurized nitrogen i
for both CCW surge tanks.
The BNS system is designed to minimize CCW system j
high-point voiding by maintaining the CCW critical loops water-solid during Design Basis Event mitigation.
)
BNS system OPERABILITY ensures that both CCW surge tanks will be i
pressurized for at least seven days following a Design Basis Event without bottle changeout. The BNS system is required to be OPERABLE whenever the associated train of CCW is required to be OPERABLE. The BNS system j.
surveillance requirements provide adequate assurance that BNS system OPERABILITY will be maintained.
3/4.7.4 SALT WATER COOLING SYSTEM 4
The OPERABILITY of the salt water cooling system ensures that sufficient cooling capacity is available for continued operation of equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the accident analyses.
SAN ONOFRE - UNIT 3 8 3/4 7-3b Amendment No. 82,114
PLANT SYSTEMS BASES 3/4.7.5 CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM The OPERABILITY of the control room emergency air cleanup system ensures that 1) the ambient air temperature does not exceed the allowable temperature this system and 2) the control room will remain habitable personnel during and following all credible accident conditions.
The OPERABILITY of this system in conjunction with control room to 5 rem or less whole body, or its equivalent.
This limitation is consistent with the requirements of General Design Criterion 19 of Appendix A, 10 CFR 50.
Cumulative operation of the system with the heaters on for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over a 31-day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters.
I l
l SAN ONOFRE-UNIT 3 8 3/4 7-4