ML20058A658
| ML20058A658 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 06/18/1982 |
| From: | Miraglia F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20058A661 | List: |
| References | |
| NUDOCS 8207010126 | |
| Download: ML20058A658 (2) | |
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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. 50-361 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 3 License No. NPF-10 l
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The applications for amendment to the San Onofre Nuclear Generating Station, Unit 2 (the facility) Facility Operating License No. NPF-10 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 May 19, 20, 21 and 22, 1982, comply 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; i
B.
The facility will operate in confomity with the application, as amended, the provisions of the Act, and the regulations of the Comission; C.
There is reasonable assurance:
(1) that the activities authorized by this amendment can be conducted without endangering the health and ll safety of the public, and (11) 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.
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Accordingly, the license is amended by changes to the Technical Specifica-tions 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 Environ-mental Protection Plan contained in Appendix B, as revised through Amendment No. 3, are hereby incorporated in the license. SCE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
On May 20, telephonic approval was given for changes to Technical Specifi-cation 3.3.2, Table 3.3-5, Items 8.a(1), 9.a(1), 8.a(2), 9.a(2) and associated footnotes; and Technical Specification 3.3.3.6, Table 3.3-10, Item 23. These changes are effective as of that date. On May 22, telephonic approval was given for changes to Technical Specification 3.3.2, Table 3.3-5, Items 2.a(5)(b) and 3.a(4)(b) and associated NOTE 4.
These changes are effective as of that date. Confirmatory letters were issued on May 21 and May 26, 1982, respectively, for the May 20, and May 22, 1982 changes.
l FOR THE NUCLEAR REGULATORY COMMISSION Original signed by Frank J. Miraglia Frank J. Miraglia, Chief Licensing Branch No. 3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
JUN 181982
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AMENDMENT TO LICENSE AMENDMENT NO. 3 FACILITY OPERATING LICENSE NO. NPF-10 DOCKET NO. 50-361 P, solace the following pages of the Accendix A Technical Specifications with tne en:lesed pages. The revised cages are identified by Amendment number and ccntain vertical lines indicating the area of change.
The corresponding over-leaf pages are' also provided to maintain document completeness.
Overleaf Amended page Pace 3/4 3-27 3/4 3-28 3/4 3-29 3/4 3-30 3/4 3-54 3/4 3-53
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TABLE 3.3-5
/Ia ENGINEERED SAFETY FEATURES RESPONSE TIMES
-Q INITIATING SIGNAL AND FUNCTION RESPONSE TIME (SEC) 1.
Manual a.
SIAS Safety Injection Not Applicable Control Rocm Isolation Not Applicable Containment Isolation (3)
Not Applicable Containmer.: Emergency Cooling Not Applicable b.
CSAS.
Containment Spray Not Applicable c.
CIAS Containment Isolation Not Applicable d.
MSIS Main Steam Isolation Not Applicable e.
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Containment Sump Recirculation Not Applicable _.
f.
CCAS Containment' Emergency Cooling Not Applicable g.
EFAS Auxiliary Feedwater Not Applicable h.
CRIS Control Room Isolation Not Applicable i.
TGIS Toxic Gas Isolation Not Applicable j.
FHIS Fuel Handling Building Isolation Not Applicable k.
CPIS Containment Purge Isolation Not Applicable SAN ONOFRE-UNIT 2 3/4 3-27
Table 3.3-5 (continued)
INITIATING SIGNAL AND FUNCTION RESPONSE TIME (SEC) 2.
Pressurizer Pressure-Low a.
'(1)
Safety Injection (a)
High Pressure Safety Injection 31.2*
(b)
Low Pressure Safety Injection 41.2*
(2)
Control Room Isolation Not Applicable (3)
Containment Isolation (N0iE 3) 11.2" (NOTE 2)
(4)
Containment Spray (Pumps) 25.6*
(5) Containment Emergency Cooling (a)
CCW Pumps '
31.2*
21.2 (b) CCW Valves-(Note 4a)
(c) CCW Valves'(Note 4b) 23.2*
(d)
Emergency Cooling Fans 21.2*
3.
Containment Pressure-Hioh a.
SIAS (1)
Safety Injection
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(a) High Pressure Safety Injection 41.0*
(b)
Low Pressure Safety Injection 41.0*
(2) Control Room Isolation Not Applicable (3) Containment Spray (Pumps) 25.4*
(4) Containment Emergency Cooling (a) CCW Pumps 31.0*
l (b) CCW Valves (Note 4a) 21.0 l
(c) CCW Valves (Note 4b) 23.0*
(d)
Emergency Cooling Fans 21.0*
b.
CIAS Containment Isolation 10.9" (NOTE 2) l 4.
Containment Pressure - High-High l
CSAS f
Containment Spray 21.0*
i SAN ONOFRE-UNIT 2 3/4 3-28 AMENDMENT NO. 3 1
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Table 3.3-5 (Continued)
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INITIATING SIGNAL AND FUNCTION RESPONSE TIME (SEC)
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5.
Steam Generator Pressure - Low a.
MSIS (1) Main Steam Isolation (MSIV) 20.9 (2) Main Feedwater Isolation 10.9 6.
Refueling Water Storane Tank - Low a.
RAS (1) Containment Sump Valves Open 50.7*
(2) ECCS Miniflow Valves Shut 40.7*
7.
4.16 kv Emergency Bus Undervoltage LOV (loss of voltage and degraded voltage)
Figure 3.3-1 a.
8.
Steam Generator Level - Low (and No Pressure-Low T rip) a.
EFAS (1) Auxiliary Feedwater (AC trains) 50.9*/40.9**
(2) Auxiliary Feedwater (steam /DC train) 30.9 (Note 6) 9.
Steam Generator Level - Low (and AP - High)'
a.
EFAS (1) Auxiliary Feedwater (AC trains) 50.9*/40.9**
(2) Auxiliary Feedwater (Steam /DC train) 30.9 (Note 6) 10.
Control Room Ventilation Airborne Radiation a.
CRIS (1) Control Room Ventilation - Emergency Mode Not Applicable 11.
Control Room Toxic Gas (Chlorine) a.
TGIS (1) Control Room Ventilation - Isolation Mode 16 (NOTE 5) i 12.
Control Room Toxic Gas (Ammonia) a.
TGIS
.g (1) Control Room Ventilation - Isolation Mode 36 (NOTE 5)
SAN ONOFRE-UNIT 2 3/4 3-29 AMENDMENT N0. 3
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Table 3.3-5 (Continu;d)
INITIATING SIGNAL AND FUNCTION RESPONSE TIME (SEC)-
13.
Control Room Toxic Gas (Butane /Procane)
TGIS Control Room Ventilation -
Isolation Mode 36 (NOTE 5) 14.
Control Room Toxic Gas (Caroon Dioxide)
TGIS Cor. trol Room Ventilation -
Isolation Mode 36 (NOTE 5) 15.
Fuel Handlinc Buildino Airborne Radiation FHIS s
Fuel Handling Building Post-Accident Cleanup Filter System Not Applicable 16.
Containment Airborne Radiadion CPIS Containment Purge Isolation 2 (NOTE 2) 17.
Containment Area Radiation
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CPIS Containment Purge Isolation 2(N0iE2)
NOTES:
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1.
. Response times include movement of valves snd attainment of pump or blower discharge pressure as applicable.
Response time includes emergency diesel generator starting delay 2.
(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.
4a.
CCW non-critical loop isolation valves 2HV-6212, 2HV-6213, 2HV-6218 and 2HV-6219 close.
4b.
Containment emergency cooler CCW isolation valves 2HV-6366, EHV-6367, 2HV-6368, 2HV-6369, 2HV-6370, 2HV-6371, 2HV-6372, and 2HV-6373 open.
5.
Response time includes instrumentation, logic, and isciatic, damper closure times only.
6.
The provisions of Specification 4.0.4 are not applicable fer entry into Mode 3.
Emergency diesel generator starting delay (10 sec.) and sequence loading delays for SIAS are included.
Emergency diesel generator starting delay (10 sec.) is included.
i SAN ONOFRE-UNIT 2 3/4 3-30 AMENOMENT NO. 3
TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION (CONTINUED)
- 1 REQUIRED MINIMUM E
NUMBER OF CHANNELS INSTRUMENT CHANNELS OPERABLE 19.
Containment Area Radiation - High Range 2
1 20.
Main Steam Line Area Radiation 1/ steam line N.A.
21.
Condenser Evacuation System Radiation Monitor -
1 N. A.
Wide Range 22.
Purge / Vent Stack Radiation Monitor - Wide Range
- 2 1
23.
Cold Leg HPSI Flow 1/ cold leg N.A 24.
Hot Leg HPSI Flow 1/ hot leg N.A.
T I
NOTES:
- The two required channels are the Unit." monitor and the Unit 3 monitor.
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5 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMfNIS o
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INSTRUMENT CllANNEL CilANNEL -
i CllECK CALIBRATION
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1.
Containment Pressure - Narrow Range e
M R
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Containment Pressure - Wide Range M
R 3.
Reactor Coolant Outlet Temperature - Tilot (Wide Range)
M R
4.
Reactor Coolant Inlet Temperature -TCold (Wide Range)
M R
5.
l Pressurizer Pressure (Wide Range)
M 6
Pressurizer Water Level R
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Steam Line Pressure
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Steam Generator Water Level (Wide Range) 1 M
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Refueling Water Storage Tank Water Level R
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T 10 Auxiliary Feedwater Flow Rate M
R 1
11.
l R
Reactor Coolant System Subcooling Margin Monitor M
12.
Safety Valve Position Indicator R
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13.
Spray Systdm Pressure R
M 14.
LPSI llearter lemperature R
M
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Containment Temperature R
1 M
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Containment Water Level (Harrow Range)
R M
17.
e Containment Water Level (Wide Range) l R
M 10.
Core Lxit Thermocouples R
M R
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