ML20214M159
| ML20214M159 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 08/20/1986 |
| From: | Rood H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20214M162 | List: |
| References | |
| TAC-60718, TAC-60719, NUDOCS 8609100561 | |
| Download: ML20214M159 (10) | |
Text
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hg UNITED STATES y'
g NUCLEAR REGULATORY COMMISSION 5
l WASHINGTON, D. C. 20555
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SOUTHERN CALIFORNIA EDIS0N 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 ON0FRE NUCLEAR GENERATING STATION, UNIT 2 AMENDMENTTbFACILITYOPERATINGLICENSE Amendment No. 53 License-No. NPF-10 1.
The Nuclear Regulatory Conunission (the Comission) has found that:
A.
The application 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 California (pany, The City of Riverside and The City of Anaheim, licensees) dated February 7, 1986 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission;
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C.
There is reasonable assurance:
(i) that the activities authorized l
by this amendment can be conducted without endangering the health l
and safety of the public, and (ii) that such activities will be l
conducted in compliance with the Commission's regulations set j
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 Commission's regulations and all applicable requirements have been satisfied.
8609100561 860820 PDR ADOCK 05000361 P
i 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-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. 53, 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 change over shall be minimized.
4.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION m
0 jCh' --
Harry Rood, Senior Project Manager PWR Project Directorate No. 7 Division of PWR Licensing-B
Attachment:
Changes to the Technical Specifications D. ate of Issuance:
August 20, 1986 l
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August 20, 1986 ATTACHMENT TO LICENSE AMENDMENT NO. 53 FACILITY OPERATING LICENSE NO. NPF-10 DOCKET NO. 50-361 1
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 Page Overleaf Page 3/4 5-4 3/4 5-3 O
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EMERGENCY CORE COOLING SYSTEMS GREkTERTHANOREQUALTO350*F 3/4.5.2 ECCS SUBSYSTEMS - T,yg LIMITING CONDITION FOR OPERATION 3.5.2 Two independent Emergency Core Cooling System (ECCS) subsystems shall be OPERASLE with each subsystem comprised of:
a.
One OPERA 8LE high pressure safety injection. pump, b.
One OPERABLE low-pressure safety injection pump, and One OPERABLE charging pump capable of taking suction from either the c.
boric acid makeup tank or the refueling water storage tank.
d.
An independent OPERABLE flow path capable of taking suction from the refueling water tank on a Safety Injection Actuation Signal and automatically tr'ansferring suction to the containment sump on a Recirculation Actuation Signal.
APPLICABILITY: MODES 1, 2 and 3".
ACTION:
With one ECCS subsystem inoperable, restore the inoperable subsystem a.
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 /> hnd in HOT SHUT 0OWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, b.
In the event the ECCS is' actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumsta6ces of the actuation and the total accumu-lated actuation cycles to date. The current value of the usage factor for'each affected safety injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.
With pressurizer pressure greater than tr equal to 400 psia.
l SAN ONOFRE-UNIT 2 3/4 5-3 AMEN 0 MENT NO. 16
s EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:
a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the following valves are in the indicated positions with power to the valve operators removed:
Valve Number Valve Function Valve Position a.
HV9353 SDC Warmup CLOSED b.
HV9359 SDC Warmup CLOSED c.
HV8150 SDC(HX) Isolation CLOSED d.
HV8151 SDC(HX) Isolation CLOSED e.
HV8152 SOC (HX) Isolation CLOSED f.
HV8153 SDC(HX) Isolation CLOSED g.
HV0396 SQC Bypass Flow Control CLOSED h.
HV8161 SDC(HX) Bypass Flow OPEN 1
Isolat. ion 1.
HV9420 Hot Leg Injection CLOSED Isolation J.
HV9434 Hot Leg Injection CLOSED Isolation k.
HV8160 SDC Bypass Flow Control OPEN 1.
HV8162 LPSI Miniflow Isolation OPEN m.
HV8163 LPSI Miniflow Isolation OPEN l
b.
At least once per 31 days by:
1.
Verifying that the ECCS piping is full of water by venting the ECCS pump casings and accessible discharge piping high points, and 2.
Verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position.
c.
By a visual inspection which verifies that no loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions.
This visual inspection shall be performed:
1.
For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and 2.
Of the areas affected within containment at the completion of containment entry when CONTAINMENT INTEGRITY is established.
'd.
At least once per 18 months by:
1.
Verifying automatic isolation of the shutdown cooling system from the Reactor Coolant System when RCS pressure is simulated greater than or equal to 715 psia, and that the interlocks prevent opening the shutdown cooling system isolation valves when simulated RCS pressure is greater than or equal to 376 psia.
SAN ONOFRE-UNIT 2 3/4 5-4 AMENDMENT NO. 53
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- s UNITED STATES e+
't, NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20555
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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 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 42 License No. NPF-15 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment to the license for San Onofre Nucle'ar Generating Station, Unit 3 (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, California (licensees) dated February 7, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the 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 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 Commission's regulations and all applicable requirements have been satisfied.
i:
s 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 i
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. 42, 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 removal of the internals of valve number 10-068.
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 change over shall be minimized.
4.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Harry Rood, Senior Project Manager PWR Project Directorate No. 7 Division of PWR Licensing-B
Attachment:
Changes to the Technical Specifications Date of Issuance: August 20, 1986 e
e "i'
August 20, 1986
, ATTACHMENT TO LICENSE AMENDMENT NO. 42
~
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 following overleaf pages to the amended pages.
Amendment Page Overleaf Page 3/4 5-4 3/4 5-3 e
i I
e 9
-),
1 EMERGENCY CORE COOLING SYSTEMS 3/4.5.2 ECCS SUBSYSTEMS - T GREATER THAN OR EQUAL TO 350 F avg LIMITINGCONDITIONFOROPERdTION 3.5.2 Two independent Emergency Core Cooling System (ECCS) subsystems shall be OPERABLE with each subsystem comprised of-a.
One OPERABLE high pressure safety injection pump, b.
One OPERABLE low pressure safety injection pump, and c.
One OPERABLE charging pump capable of taking suction from either the boric acid makeup tank or the refueling water storage tank.
d.
An independent OPERABLE flow path capable of taking suction from the refueling wa.ter tank on a Safety Injection Actuation Signal and automatically transferring suction to the containment sump on a Recirculation Actuation Signal.
APPLICABILITY:
MODES 1, 2 and 3*.
ACTION:
(
a.
With one ECCS subsystem inoperable, restore the inoperable subsystem 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 HOT SHUTOOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special-Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumu-lated actuation cycles to date.
The current value of the usage factor for each affected safety injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.
With pressurizer pressure greater than or equal to 400 psia.
SAN ONOFRE-UNIT 3 3/4 5-3
k EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:
+
a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the following valves are in the indicated positions with power to the valve operators removed:
Valve Number Valve Function Valve Position a.
HV9353 SDC Warmup CLOSED b.
HV9359 SDC Warmup CLOSED c.
HV8150 SDC(HX) Isolation CLOSED d.
HV8151 SDC(HX) Isolation CLOSED e.
HV8152 SDC(HX) Isolation CLOSED f.
HV8153 SDC(HX) Isolation CLOSED g.
HV0396 SDC Bypass Flow Control CLOSED h.
HV8161 SDC(HX) Bypass Flow OPEN Isolation i.
Deleted j.
Deleted k.
HV9420 Hot Leg Injection CLOSED Isolation 1.
HV9434 Hot Leg Injection CLOSED Isolation m.
HV8160 SDC Bypass Flow OPEN Control n.
HV8162 LPSI Miniflow OPEN Isolation o.
HV8163 LPSI Miniflow OPEN i
Isolation b.
At least once per 31 days by:
1.
Verifying that the ECCS piping is full of water by venting the
^
ECCS pump casings and accessible discharge piping high points, and 2.
Verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position.
By a visual inspection which verifies that no loose debris (rags, trash, c.
clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions.
This visual inspection shall be performed:
1.
For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and 2.
Of the areas affected within containment at the completion of containment entry when CONTAINMENT INTEGRITY is established.
d.
At least once per 18 months by:
1.
Verifying automatic isolation of the shutdown cooling system from the Reactor Coolant System when RCS pressure is simulated greater than or equal to 715 psia, and that the interlocks prevent opening the shutdown cooling system isolation valves when simulated RCS pressure is greater than or equal to 376 psia.
SAN ONOFRE - UNIT 3 3/4 5-4 AMENDMENT NO. 42
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