ML20067E767
| ML20067E767 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 02/11/1991 |
| From: | Dyer J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20067E768 | List: |
| References | |
| NUDOCS 9102180149 | |
| Download: ML20067E767 (14) | |
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1 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. 92 License No. NPF-10 1.
The Nuclear Regulatory Comission (the Comission) has' found thet:
A.
The applicatior, for amendment by Southern California. Edison Company, San Diego Gas and Electric Company, the City of Riverside California, and the City of Anaheim, Californic (licensees,) (the licensee)uatedNovember 14,-1990, 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 prWisions of the Act, and the rules and regulations of the Cr, mission; 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.
91021801499h2 161 PDR ADOCR O ppg P
. 2.
Accordingly, the license is amended by changes to the Technical Spect-
-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 t.ontained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 92, 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 I.-
j'
' James E. Dyer, Director Project Directorate V 1
Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications.
.Date of Issuance:
February 11, 1991 W
I
m ATTACHMENT TO LICENSE AMENDHENT NO. 92-FACILITY OPERATING LICENSE'NO. NPF-10 DOCKET NO. 50-361 di Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are. identified by
- the captioned amendment number and contain marginal lines indicating the areas of change.
REMOVE INSERT-3/4 7-10 3/4 7-10
. B 3/4-7-3b B 3/4.7-3b i
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I PLANT SYSTEMS' t-
- ATMOSPHERIC DUMP VALVES LIMITING CONDITION FOR OPERATION
- 3. 7.1. 6 Tne atmospheric dump valves shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3, and 4*.
ACTION:
With an atmospheric dump valve inoperable, restore the valve to a.
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 HOT SHUTDOWN and on shutdown cooling within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, b.
With both atmospheric dump valves inoperable, 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 HOT SHUTDOWN and on shutdown cooling within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
With the backup-nitrogen gas system capacity less than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, c.
restore-the backup nitrogen gas' system capacity within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or-declare the ADV inoperable.
d.-
The provisions of-Specification 3.0.4 are not applicable for MODES 2,13,Jand 4* with only one atmospheric dump valve inoperable, SURVEILLANCE REQUIREMENTS 4.7.1.6.1 Each atmospheric dump valve shall_ be determined OPERABLE at least once per REFUELING INTERVAL by:
Verifying that 'each atmospheric dump valve will open in modulate a.
mode using the _ backup nitrogen system, b.
Verifying that each atmospheric dump valve will close to its isolation position upon a MSIS test signal,
-Verifying that each atmospheric dump valve will open in
. c.
modulate / override mode with a MSIS test-signal present, and d..
Verifying that local manual operation will fully open.and close each atmospheric dump valve.
4.7.1.6.2 Verify at least once per 7 days' that the backup nitrogen' gas system capacity will provide a minimum of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of-pneumatic. operation for each=
atmospheric dump valve.
4.7.1.6.3 The at'mospheric dump valves shall be determined OPERABLE as requireu per-Specification 4.0.5.
- When steam generators are being used for decay heat removal.
SAN ONOFRE-UNIT 2 3/4 7-9a AMENDMENT NO. 89 JUL 10 990 l
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PLANT SYSTEMS 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION If!TINGCONDITIONFOROPERATION
= '3,7.2 The temperature of the secondary coolant.in the_ steam generators shall
-be greater than 70'F when the pressure of the secondary coolant in the steam generator is greater than 200 psig.
APPLICABILITY:
At all times.
ACTION:
With.the requirements of the above specification not satisfied:
LReduce 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 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.
SURVEILLANCE. REQUIREMENTS (4.7.21The pressure in the secondary side of-the steam generators shall be Jdetermined to be less than 200 psig at least once per hour when the: temperature.
'of the secondary coolant is less than =70'F.
SAN ONOFRE-UNIT 2 3/4 7-10 AMEN 0 MENT NO. 92 l
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PLANT SYSTEMS BASES 3/4.7.1.6 ATMOSPHERIC DUMP VALVES (Continued)
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 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 f 40'F and are sufficient to prevent brittle fracture.
HDT 3/4.7.3 COMPONENT COOLING WATER SYSTEM The OPERABILITY of the component cooling water system ensures that suf-ficient cooling capacity is available for continued operation of safety related-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.
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 nor-mal and accident conditions.
The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the acci-dent analyses.
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SAN ONOFRE-UNIT 2 B 3/4 7-3b AMENDMENT NO. 92 1.
PLANT SYSTEMS BASES
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3/4.7.5 CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM The OPEREBILITY of th' control room emergency air cleanup system ensures e
that 1) the ambient air temperature does not exceed the allowable temperature for continuous dut personnel during a)y rating for the equipment ahd instrume this system and 2 the control room will remain habitable for operations nd following all credible accident conditions.
The OPERABILITY of this system in conjunction with control room design provisions is 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 consistent with the requirements of General Design Criteria 19 of Appendix A, 10 CFR 50.
Daulative 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 seriod is sufficient to reduce the buildup of moisture on the adsorbers and HE)A filters.
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l SAN ONOFRE-UNIT 2 B 3/4 7-4 1
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UNITED STATES
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SOUTHERN CALIFORNIA EDISON COMPANY SANDIEGOGASANDELECTRICCOMPANJ 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.82 L'icense No. NPF-15 1.
The Nuclear Regulatory Comission (the Comission)'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 November 14, 1990, conplies 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 1;-
B.
The facility will operate in confonnity with the application, the provisions of the Act,'and the rules and regulations of the Commission;-
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 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.
4
-2.
Accordingly, the license is amended by changes to the Technical Speci.
ficenns -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).TechnicalSpecifications The Technical Specif1 cations contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 82
, 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.
o 3.
This license amendment is effective-as of the date of its. issuance and
.i must be fully implemented no later than 30 days from the date of issuance..
l FOR TPE NUCLEAR REGULATORY COMMISSION
(
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'
'Date of Issuance:, February 11, 1991 t
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ATTACHMENT"TO LICENSE AMENDMENT NO. 82 i
' FACILITY OPERATING LICENSE NO. NPF-15 DOCKET NO. 50-362 I
Revise Appendix A Technical Specifications by removing the pages identified below and inserting:the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal. lines indicating the areas of change.
REMOVE :
INSERT 3/4 7-11 3/4 7-11 B 3/4 7-3b B 3/4.7-3b
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H PLANT SYSTEMS' 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION LIMITING' CONDITION FOR OPERATION 3.7.2 The temperature of the secondary coolant in the steam generators shall-be greater than 90'F when the pressure of the secondary coolant in the steam generator is greater than 200 psig.
APPLICABILITY:
At all timet.
ACTION:
With the requirements of the above specification not satisfied:
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 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.
SURVEILLANCE REQUIREMENTS 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 of the secondary coolant ^is less than 90'F.
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SAN ONOFRE-UNIT 3 3/4 7-11 AMENDMENT NO. 82
REISSUED 5/25/E9 PLANT SYSTEMS I
3/4.7.3 COMPONENT COOLING WATER SYSTEM i
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 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 />, l
SURVEILLANCE REQUIREMENTS 4.7.3 'At least two component coolina water loops shall be demonstrated OPERABLE:
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'l 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.
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correct position.
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- b.
At least once'per refueling interval during1 shutdown, by verifying that each automatic valve servicing safety-related equipment actuates to. its correct position and each component cooling water pump startt si automatically on'an SIAS test signal.
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SAM ONOFRE-UNIT 3 3/4 7-12 AMENDMENT NO. 63
PLANTSYSTfM{
BASES 3/4.7.1.6 ATg5PHERICDUMPVALVES(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.
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 do apply with two inoperable ADVs.
3/4.7.2 STEAM GENERATOR PRESSU_RE/ TEMPERATURE LIrlITATION Thel 11mitation 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 NDT to prevent brittle fracture.-
3/4.7.3 COMPONENT COOLING WATER SYSTEM The OPERABILITY of the component cooling water system ensures that suffi-cient cooling capacity is available for continued operation of safety related 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.
3/4.7.4-SALT WATER COOLING SYSTEM The OPERABILITY of the salt water cooling system ensures that sufficient cooling capacity is availab'ie.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
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SAN ONOFRE UNIT 3 B 3/4 7-3b-AMENDMENT NO. 82 y
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P1. ANT SYSTEMS BASES 3/4.7.5 CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM The OPERABILITY of the control rc3m emergency air cleanup systes ensures that 1) the ambient air temperature does not exceed the allowable temperature for continuous dut this system and 2)y rating for the equipment and instrumentation cooled by the control room will remain habitable for operations personnel during and following all rredible accident conditions.
The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 ran 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.
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SAN ONOFRE-UNIT 3 B 3/4 7-4 S
,-,