ML20028E585
| ML20028E585 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 01/17/1983 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20028E587 | List: |
| References | |
| NUDOCS 8301280031 | |
| Download: ML20028E585 (10) | |
Text
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4
.s SOUTHERN CALIFORNI A EDISON COMPAftY.
~
SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA' THE CITY OF ANAHEIH, CALIFORNIA ~
DOCKET N0. 50-362 SAN ONOFRE NUCLEAR GENERATING STATION,-UNIT 3 AMEN 0HENT TO FACILITY OPERATING LICENSE Amendnent-No. 1
. License No.~ NPF-15 1.
The Nuclear Regulatory Comission (the Comission).has found that:L A.
Pursuant to 10 CFR 50.12 of the Corsnission's regulations, the:
Comission has authorized an exempti_on from the requirements of-General Design Criteria 56 until March ~22,1983.
8.
The applications for-anendment for the San Onofre Nuclear Generating.
Station, Unit 3 (the facility) filed by the Southern California.
Edison Company on behalf of itself and. San Diego Gas;and' Electric Conpany, The City.of Riverside and The City of Anaheim, California:
(licensees) dated November 19,.1982 and ' January 7.1983, complies ;
with the standards and requirenents.of the Atomic Energy Act of 1954, as anended (the Act) and the Commission's regulations aslsett forth in 10 CFR Chapter I; C.
The facility will operate in conformity with the application, as anended, the provisions of the Act, and the regulations'of the Comission;
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D.
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 set' forth in '10 CFR Chapter I; E.
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; F.
The issuance of this amendnent is in'accordance with 10 CFR Part 51; of the Comission's regulations and all applicable requirements have been satisfied.
8301200031 830114 PDR ADOCK 05000362 P
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2.
Accordingly, the license.fs amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. ?!PF-15 is:herehy 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. 2, are hereby incorporated in the license.*
SCE shall operate the facility in accordance with the Technical Specifications and the Environnental Protection Plan.
l 3.
Witnin 30 days after the issuance of this amendment, or such other time:
as the Connission nay specify, SCE shall satisfy any appitcable requirement of P.L.97-425 related to pursuing an agreenent with the Secretary of Energy for the disposal of high-lensi radioactive waste and spent nuclear -
fuel.
4 The license eendment is effective as follows:
November 19, 1982 Tech Spec 3/4.3.2: January 14, 1983 FOR THE NUCLEAR REGULATORY C0tetISS10H Original signed by Robert A. Purple Darrell G. Eisenhut Director i
Division of Licensing Office of Nuclear Reactor Regulation Date of Issuance: JAN 141993 i
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3
- Amenonent No. 2 to NPF-15 was issued on December 30, 1982 and the changes -
made therein are to remain in effect.
- See previous concurrence, i
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, 2.
Accordingly, the license is amended by changes to the Technical S ciff-cations as indicated in the attachment to this license anendnen and-paragraph 2.C(2) of Facility Operating License No. NPF-15 is h 'reby anended to read as fOllows:
(2) Technical Specifications The Technical Specifications contained in Append) dix B, as revised A and the Environnental Protection Plan contained in Ap through Amendment No. 2, are hereby incorpor d in the license.*
SCE shall operate the facility in accordan with the Technical Specifications and the Environmental Prot tion Plan.
3.
Within 30 days after the issuance of this a.
ndment, or such other tine as the Cor. Mission May specify, SCE shall tisfy any applicable requirenent of P.L.97-425 related to pursuing an agyeccent with the Secretary of Energy for the disposal of high-level r dioactive waste and spent nuclear fuel.
4 The license anendnent is ef fective s follows:
Novemb7 19, 1982 Tech Spec 3/4.3.2: Janua y 14, 1983 FOR THE NUCLEAR REGULATORY COMMISSION 1
George W. Knighton, Chief Licensing Branch No. 3 Division of Licensing Date of Issuance:
- AN 14 E 1
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- Anendnent No. 2 to hPF-15 was issued on DeceriDirr 30, 1982 and the changes nade therein are to remain in effect.
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. ATTACriMENT TO LICENSE Al1ENDftENT NO. I FACILITY OPERATIriG LICENSE NO. NPF-15 DOCKET NO. 50-362 Replace thc. following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised pages are. identified by Amendnent number and contain vertical lines indicating the area of change. Also to be replaced are the following overleaf pages to the anendment pages.
Araendment Page Overleaf Page 3/4 3-28 3/4 3-27 3/4 3-30 3/4 3-29 3/4 9-9 3/4 9-10 orncep
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. ~;iLE 3.3-5 ENGINEERED SAFETY :EATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME (SEC) 1.
Manual i
a.
SIAS Safety Injection Not Applicable Control Room Isolation Not Applicable Containment Isolation (3)
Not Applicable Containment Emergency Cooling Not Applicable b.
CSAS a
Containment Spray Not Applicable c.
CIAS Containment Isolation Not Applicable d.
MSIS Main Steam Isolation Not Applicable e.
RAS Containment Sump Recirculation Not Applicable f.
CCAS Containment Emergency Cooling Not Applicable g.
EFAS l
Auxiliary Feedwater Not Applicable l
h.
CRIS
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Control Room Isolation Not Applicable i.
TGIS l
, Toxic Gas Isolation Not Applicable j.
FHIS
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Fuel Handling Buildfag Isolation Not Applicable m
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Containment Purge Isolation Not Applicable t
SAN ONOFRE-UNIT 3 3/4 3-27
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.3 SI2'3L AN: FL'NCTI C.'i RES ;N3E TIgE (SEC) 2.
Pressurizer Pressure-Low SIAS (1) Safety I'njection (a) High Pressure Safety Injection 31.2*
(b) Low Pressure Safety Injection 41.2*
(2) Control Room Isolation Not Applicable (3) Containment Isolation (NOTE 3) 11.2* (NOTE 2)
(4) Containment Spray (Pumps) 25.6*
(S) Containment Emergency Cooling (a) CCW Pumps 31.2*
(b) CCW Valves (NOTE 4b)-
23.2*
(c) Emergency Cooling Fans 21.2*
3.
Containment Pressure-Hioh a.
SIAS (1)
Safety Injection (a) High Pressure Safety Injection 41.0*
(b)
Low Pressure Safety Injection 41.0*
(2) Control Room Isolation Not'Appiicable (3) Containment Spray (Pumps).
25.48
'(4) Containment Emergency Cooling (a) CCW Pumps 31.0*
(b) CCW Valves (NOTE 4b) 23.0*
(c) Emergency Cooling Fans 21.0*
b.
CIAS (1) Containment Isolation 10.9* (NOTE 2)
(2) CCW Valves (Note 4a) 20.9 4.
Containment Pressure - High-High CSAS Containment Spray 21.0*
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SAN ONOFRE-UNIT 3 3/4 3-28 AMENDMENT ~NO. 1
. 9
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INITIATING SIGNAL AND FUNCTION RESPONSE TIME'(SEC) 5.
Steam Generator Pressure - Lcw
,.,51 S (1) Main Steam Isolation (MSIV) 1 20.9 (2) Main Feedwater Isolation 10.9 6.
Refueling Water Storage Tank - Low e
RAS (1) Containment Sump Valves Open 50.7*
(2) ECCS Miniflow Valves Shut 50.7*
7.
4.16 kV Emergency Bus Undervoltace LOV (loss of voltage and degraded voltage)
Figure 3.3-1 8.
Steam Generator Level - Low (and No Pressure-Low Tric)
EFAS (1) Auxiliary Feecwater (AC trains) 50.S"/40.9**
(2) Auxiliary Feedwater (steam /DC train)
'30.9 (NOTE 6) 9.
Steam Generator Level - Low (and AP - Hich)
EFAS l
(1) Auxiliary Feedwater (AC trains) 50.9*/40.9**
(2) Auxiliary Feedwater (Steam /DC train) 30.-9 (NOTE 6)
I 10.
Control Room Ventilation Airborne # Radiation CRIS l
Control Room Ventilation - Emergency i
- Mode, Not Applicable 11.
Control Room Toxic Gas (Chlorine)
TGIS,'
Control Room Ventilation - Isolation Mode 16 (NOTE 5)
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Control Room Toxic Gas (Ammonia)
TGIS Control Room Ventilation - Isolation Mode 36 (NOTE 5)
SAN ONOFRE-UNIT 3 3/4 3-29
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Table 2.I-5 (Contirted)
P.*~:; ::0 5* '::L 4'.J UNCTION RESPCNSE Tit'E (SEC) 13.
Ccr. rcl Roc Texic Gas (Eutane/Precane)
TGIS Control Room. Ventilation -
Isolation Mode 36 (NOTE 5) 14.
Control Room Toxic Gas (Carbon Dioxide)
TGIS l
Control Room Ventilation -
Isolation Mode t
36'(NOTE 5) i 15.
Fuel Handling Building Airborne Radiation FHIS Fuel Handling Building Post-Accident
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Cleanup Filter System Not Applicable 16.
Containment Airborne Radiation i
CPIS l
Centain ent Perge Isolation 2 (FOTE 2),
- t 17.
Containment Area Radiation CPIS l
i Containment Purge Isolation 2 (N0'TE 2)
NOTES:
l 1.
Response times include movement of valves and attainment of' pump or blower discharge pressure as applicable.
2.
Response time inclu' des. emergency diesel generator starting delap (applicable to AC motor operated valves other than containment purge valves), instrumentation and logic response only.
Refer to Table 3.6-1 for containment isolation valve closure times.
3.
All CIAS-Actuated valves except MSIVs and MFIVs and CCW valves 3HV-6211 and 3HV-6216.
4a.
CCW non-critical loop isolation valves 3HV-6212, 3HV-6213, 3HV-6218 and 3HV-6219 close.
4b.
Containm,ent emergency cooler CCW isolation valves 3HV-6366, 3HV-6367, 3HV-6368, 3HV-6360, 3HV-6370, 3HV-6371, 3HV-6372 and 3HV-6373 open.
5.
Response time includes instrumentation, logic, and isolation damper closure times only.
. 6.
The provisicns of Specification 4.0.4 are not applicable for entry into NODE 3.
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- Emergency diesel generator starting delay (10 sec.) and sequence loading delays for SIAS are included.
Emergency diesel generator starting delay (10 sec.) is included.
SAN ONOFRE-UNIT 3 3/4 3-30 AMENDMENT NO. 1 4
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( L'.MI]l'jG CON 31 TION FOR OPERATION f
/*l least one shutdown cooling train shall be in operation.ge OPERASL'E and at
.t.9.8.2 Two independent
- shutdown cooling trains shall APPLICABILITY:
HODE 6'when the water level above the top of the reactor pressure vessel flange is less than 23 feet.
ACTI0hv a'.'[WithlesnthantherequiredshutdowncoolingtrainsOPERABLE, immediately initiate corrective action to return the required shut-down ecoling trains to CPERA5LE status, or to establish greater than or equal to J3 "eet of water above the reactor pressure vessel flange as soVn ds possible, b.
With no shutdown' cooling train in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required shutdown cooling train to operation.
Close all containment censtrations providir.g direct access frca the cc..tti-snt st tr:tsre to tne ca:stce atmosphere within 4 neurs.
.URVEILLANCE REOUIREMENTS s
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4.9.8.2 At least one shutdown cooling train shall be verified to be.in operation and circulating reactor coolant at a flow rate of greater than or equal to 4000 gpm at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
i
- cth shutdoin cooling trains may be removed from operation for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 8
per 8-hour period during -the performance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs provided all operations involving a reduction in boron concentration of the RCS are suspended.
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SAN ONOFRE-UNIT'3 3/4 9-9 AtiEtIDriENT NO.1
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- 3 Eu LIF'.ITING CCNDITION FOR CFE~'. TION s
- 3. 9.' 9 The containment purge isolation system shall be OPERABLE.
4 APPLICABILITY:
During CORE ALTERATIONS or movement of irradiated fuel within tne containment.
ACTIOE With the i.cntainment purge isolation system inoperable, close each of the conteinn nt purge penetrations providing direct access from the containment atmospnere to the cutside atmosphere.
The provisions of Specification 3.0.4 are not applicable.
SUR.EfLLANCE REQUIREF'.ENTS 4.9.9 The containment purge isolation system shall be demonstrated OPERABLE '
within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to the start of and at least'once per 7 days during CORE ALTERATIONS by verifying that containment purge valve isolation occurs on manual initiation and on a high radiation test signal.
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