Text

Amends 118 & 107 to Licenses NPF-10 & NPF-15,respectively. Amends Revise TS to Divide Item 7 of Listed TS Tables Into Item 7a Addressing Existing Loss of Voltage Function & Item 7b Addressing Degraded Grid Voltage Function
	ML20081J708
Person / Time
Site:	San Onofre
Issue date:	03/17/1995
From:	Fields M; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML20081J713	List: ML20081J708; ML20081J715;
References
	NUDOCS 9503280134
	Download: ML20081J708 (32)
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UNITED STATES y

,g NUCLEAR REGULATORY COMMISSION

'2 WASHINGTON, D.C. 2008M001 49.....,o i

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 i

Amendment No.118 License No. NPF-10 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Southern California Edison Company, et al. (SCE or the licensee) dated September 30, 1993, as supplemented by letters dated November 16, 1993, January 18, 1995, and February 2, 1995, 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 provisions of the Act, and the rules and regulations of the Comission, l

I 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 i

conducted in compliance with the Comission'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, f

9503290134 950317 PDR ADOCK 05000361 P

PDR i

s r

, 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 Soecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 118, 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 completion of the current Cycle 8 refueling outage and must be fully implemented prior to returning SONGS Unit 2 to power.

FOR THE NUCLEAR REGULATORY COMMISSION y}l- / ll [

b' 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 Specifications Date of Issuance:

March 17, 1995 i

e f

li a

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J f

5 ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.11R 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.

l PEMOVE INSERT 3/4 3-16 3/4 3-16 3/4 3-19 3/4 3-19 3/4 3-23 3/4 3-23 3/4 3-26 3/4 3-26 3/4 3-29 3/4 3-29 3/4 3-30 3/4 3-30 3/4 3-32 3/4 3-32 3/4 3-40 3/4 3-40 l

)

TABLE 3.3-3 (Eontinurddl ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION

?

MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION i

4.

MAIN STEAM LINE ISOLATION a.

Manual (Trip 2/ steam 1/ steam 2/ operating 1, 2, 3 11 Buttons) generator generator steam generator b.

Steam Generator 4/ steam 2/ steam 3/ steam I, 2, 3 9*,

10*

Pressure - Low generator generator generator c.

Automatic Actuation 4/ steam 2/ steam 3/ steam I, 2, 3 9*,

10*

Logic generator generator generator w

5.

RECIRCULATION (RAS) a.

Refueling Water Storage Tank - Low 4

2 3

1, 2, 3, 4 9*,

10*

b.

Automatic Actuation Logic 4

2 3

1, 2, 3, 4 9*,

10*

6.

CONTAlfelENT COOLING (CCAS) a.

Manual CCAS (Trip Buttons) 2 sets of 2 1 set of 2 2 sets of 2 1, 2, 3, 4 8

E E

b.

Deleted intentionally E

E c.

Automatic Actuation Logic 4

2 3

1, 2, 3, 4 9*, 10*

5 O

.-.-......,e~-<,,--

,,w,,

-,.,,..-.,,,,n.--

.--,, ~, --,. - -.

.-,---<.+v a

~, -.. - -

g TABLE 3.3-3 (Continued) z g

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION O5 MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE

[

FUNCTIONAL UNIT OF CHANNELS TO TRIP.

OPERABLE MODES ACTION z

Z 7.

LOSS OF POWER (LOVS, SDVS, or DGVSS) ro a.

4.16 kV Emergency Bus Undervoltage (Loss l

of Voltage) 4/ Bus 2/ Bus 3/ Bus 1, 2, 3, 4 9*,

10*

l i

b.

4.16 kV Emergency Bus l

Undervoltage (Degraded Voltage) 4/ Bus 2/ Bus 3/ Bus 1,2,3,4(d) 9*,

10*

l

{

8.

EMERGENCY FEEDWATER (EFAS)

Y a.

Manual (Trip Buttons) 2 sets of 2 1 set of 2 2 sets of 2 1,2,3 11 per S/G per S/G per S/G

b. -Automatic Actuation Logic 4/SG 2/SG 3/SG 1, 2, 3 9*,

10*

c.

SG Level (A/B) - Low and AP (A/B) - High 4/SG 2/SG 3/SG 1, 2, 3 9*,

10*

d.

SG Level (A/B) - Low and No S/G Pressure -

,E Low Trip (A/B) 4/SG 2/SG 3/SG 1, 2, 3 9*,

10*

a a

E M

9

)

CD

~

p

+

TABLE 3.3-3-(Continued)

TABLE NOTATION l

(a) Trip function may be bypassed in this MODE when pressurizer pressure is

[

1ess than 400 psia; bypass shall be automatically removed when pressurizer pressure is greater than or equal to 400 psia.

(b) An SIAS signal is first necessary to enable CSAS logic.

(c) Actuated equipment only; does not result in CIAS.

(d) Applicability for SDVS is Modes 1, 2, 3, and 4 when the diesel generator l

circuit breaker is open.

1 The provisions of Specification 3.0.3 are not applicable.

The provisions of Specification 3.0.4 are not applicable.

With irradiated fuel in the storage pool.

ACTION STATEMENTS ACTION 8 - With the number of OPERABLE channels one less than the Total Number f

of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6

[

hours and in COLD SHUTD4WN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

L ACTION 9 - With the number of channels OPERABLE one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may continue provided I

the inoperable channel is placed in the bypassed or tripped condition within I hour.

If the inoperable channel is bypassed, l

the desirability of maintaining this channel in the bypassed condition shall be reviewed in accordance with Specification 6.5.1.6e.

The channel shall be returned to OPERABLE status no later than during the next COLD SHUTDOWN.

i With a channel process measurement circuit that affects multiple i

functional units inoperable or in test, bypass or trip all associated functional units as listed below.

Process Measurement Circuit Functional Unit Bypassed l

1.

Containment Pressure - High Containment Pressure - High (ESF)

Containment Pressure - High (RPS) l 2.

Steam Generator Pressure -

Steam Generator Pressure - Low l

Low Steam Generator AP 1 and 2 (EFAS) 3.

Steam Generator Level Steam Generator Level - Low l

Steam Generator Level - High Steam Generator AP (EFAS)

SAN ONOFRE - UNIT 2 3/4 3-19 Amendment No. 4,118

..s-a g

TABLE 3.3-4 (Continued) 9 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES

?

ALLOWABLE FUNCTIONAL UNIT TRIP VALUE VALUES c5 6.

CONTAINMENT COOLING (CCAS) a.

Manual CCAS (Trip Buttons)

Not Applicable Not Applicable b.

deleted intentionally c.

Automatic Actuation Logic Not Applicable Not Applicable 7.

LOSS OF POWER (LOVS, SDVS, or DGVSS) l a.

4.16 kV Emergency Bus Undervoltage (Loss of Voltage) 3675 V 3554 - 3796 V l

b.

4.16 kV Emergency Bus Undervoltage 4228 V 4181 - 4275 Y (Degraded Voltage) w ro 8.

EMERGENCY FEEDWATER (EFAS) a.

Manual (Trip Buttons)

Not Applicable Not Applicable b.

Steam Generator (A&B) level-Low 2 21% (3) 2 20% (3) c.

Steam Generator AP-High (SG-A > SG-B) s 125 psi s 140 psi d.

Steam Generator AP-High (SG-B > SG-A) s 125 psi s 140 psi e.

Steam Generator (A&B) Pressure - Low 2 741 psia (2) 2 729 psia (2)

}

f.

Automatic Actuation Logic Not Applicable Not Applicable E.

en

_,, _ ~ ___

TABLE 3.3-4 (Continued)

U

[

ENGINEERED _ SAFETY FEATURE ACTUATI0fLSYSTEM INSTRUMENTATION TRIP VALUES 2

%5 ALLOWABLE i

FUNCTIONAL UNIT TRIP VALUE VALUES-9.

CONTROL ROOM ISOLATION (CRIS) a.

Manual CRIS (Trip Buttons)

Not Applicable Not Applicable b.

Manual SIAS (Trip Buttons)

Not Applicable Not Applicable c.

Airborne Radiation 1.

Particulate / Iodine s 5.7 x 10' cpm **

s 6.0 x 10' cpm **

11. Gaseous s 3.8 x 10* cpm **

s 4.0 x 10' cpm **

y d.

Automatic Actuation Logic Not Applicable Not Applicable

10. T0XIC GAS ISOLATION (TGIS) a.

Manual (Trip Buttons)

Not Applicable Not Applicable b.

Chlorine - High s 14.3 ppe s 15.0 ppe c.

Ammonia - High 5 97 ppe s 100 ppa d.

Butane / Propane - High s 193 ppe s 200 ppe e.

Automatic Actuation Logic Not Applicable Eat Applicable h2

e,=

,. e e

v' E

TABLE 3.3-4 (Continued) c35jj ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES E

ALLOWABLE 21 FUNCTIONAL UNIT TRIP VALUE VALUES n

11.

FUEL HANDLING ISOLATION (FHIS) a.

Manual (Trip Buttons)

Not Applicable Not Applicable b.

Airborne Radiation 1.

Gaseous (8)

(8) w 30 c.

Automatic Actuation Logic Not Applicable Not Appilcable

12. CONTAINMENT PURGE ISOLATION (CPIS) a.

Manual (Trip Buttons)

Not Applicable Not Applicable b.

Airborne Radiation 1.

Gaseous (6)(7)

(6)(7) 11.

Particulate (6)(7)

(6)(7) 111. Iodine (6)(7)

(6)(7) h!

c.

Containment Area Radiation (Gamma)

< 325 mR/hr (M00ES 1-4)

< 340 mR/hr (MODES 1-4) is 7 2.4 mR/hr (M00E 6)

_ 2.5 mR/hr (M00E 6) i

'5 d.

Automatic Actuation Logic Not Appilcable Not Applicable

,Es w.--

v

l i

TABLE 3.3-4 (Continued)

TABM NOTATION E?

El (1)

Value may be decreased manually, to a minimum of greater than or equal to 300 psia, as pressurizer pressure is reduced, provided the margin between the pressurizer and this value is maintained at e

less than or equal to 400 psia;* the setpoint shall be increased automatically as pressurizer pressure c5 is increased until the trip setpoint is reached. Trip may be manually bypassed below 400 psia;

[

bypass shall be automatically removed whenever pressurizer is greater than or equal to 400 psia.

(2)

Value may be decreased manually as steam generator pressure is reduced, provided the margin between the steam generator pressure and this value is maintained at less than or equal to 200 psi;* the setpoint shall be increased automatically as steam generator pressure is increased until the trip setpoint is i

l reached.

l l

(3)

% of the distance between steam generator upper and lower level instrument nozzles.

1 (4)

Deleted.

g (5)

Actuated equipment only; does not result in CIAS.

ES (6)

The trip setpoint shall be set sufficiently high to prevent spurious alarms / trips yet sufficiently low i

to assure an alarm / trip should an inadvertent release occur.

(7)

Prior to the completion of DCP 53N, the setpoints for Containment Airborne Radiation Monitor 2RT-7804-1 shall be determined by the 00CM.

i' (8)

The trip setpoint shall be set sufficiently high to prevent spurious alare/ trips yet sufficiently low l

to assure an alarm / trip should a fuel handling accident occur.

Variable setpoints are for use only during normal, controlled plant heatups and cooldowns.

I j

- Above normal background.

8 a

?

' - y Table 3.3-5 (Continued)

INITIATING SIGNAL AND FUNCTION RESPONSE TIME (SEC) 5.

Steam Generator Pressure -' Low MSIS (1) Main Steam Isolation (HV8204, HV8205) 8.9 (2) Main Feedwater Isolation- (HV4048, HV4052) 10.9 1

(3) Steam, Blowdown and Sample. Isolation 20.9 (HV8419. HV8421)

(HV4053,HV4054,HV4057,HV4058)

(4) Auxiliary Feedwater Isolation (NOTE 7) 40.9 (HV4705,HV4713,HV4730,HV4731)

(HV4706, HV4712, HV4714, HV4715) l 6.

Refuelina Water Storace Tank - Low RAS (1) Containment Sump Valves Open 50.7*

(2)

ECCS Miniflow Isolation Valves Close 50.7* (Note 8) 7.

4.16 kV Emeroency Bus Undervoltaae

a. LOVS (loss of voltage,127F) (Note 9) 1.00+/-00.05

b. Degraded voltage, (1270) 2.00+/-00.20 1.

SDVS (Sustained Degraded Voltage)

(a)

Auxiliary Timing Relay 162D 110.00+/-22.00 11.

DGVSS (Degraded Grid Voltage with SIAS)

(a)

Auxiliary Timing Relay 162S 4.30+/-00.19 (b)

Auxiliary Timing Relay 162T 1.25+/-00.40 l

8.

Steam Generator Level - Low (and No Pressure-Low Trio)

EFAS (1) Auxiliary Feedwater (AC trains) 52.7*/52.7**

(2) Auxiliary Feedwater (Steam /DC train) 42.7 (NOTE 6) 9.

Steam Generator Level - Low (and AP - Hich)

EFAS (1) Auxiliary Feedwater (AC trains) 52.7*/52.7**

(2) Auxiliary Feedwater (Steam /DC train) 42.7 (NOTE 6) 10.

Control Room Ventilation Airborne Radiation CRIS (1) Control Room Ventilation - Emergency Mode Not Applicable 11.

Control Room Toxic Gas (Chlorine)

TGIS (1) Control Room Ventilation - Isolation Mode 16 (NOTE 5) 12.

Control Room Toxic Gas (Ammonia)

TGIS Control Room Ventilation - Isolation Mode 36 (NOTE 5)

SAN ONOFRE - UNIT 2 3/4 3-29 Amendment No. 60, 118

3 i

Table 3.3-5 (Continued)

INITIATING SIGNAL AND FUNCTION RESPONSE TIME (SEC) 13.

Control Room Toxic Gas (Butane / Propane)

TGIS Control Room Ventilation -

Isolation Mode 36 (NOTE 5) 14.

Fuel Handlino Buildino Airborne Radiation FHIS Fuel Handling Building Post-Accident Cleanup Filter System Not Applicable 15.

Containment Airborne Radiation CPIS Containment Purge Isolation 2 (NOTE 2) 16.

_ Containment Area Radiation CPIS Containment Purge Isolation 2 (NOTE 2)

NOTES:

I 1.

Response times include movement of valves and attainment of pump or blower discharge pressure as applicable.

2.

Response time includes emergency diesel generator starting delay (applicable to A.C. 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, MFIVs, and CCW Valves 2HV-6211, 2HV-6216, 2HV-6223 and 2HV-6236.

4a.

CCW noncritical loop isolation Valves 2HV-6212, 2HV-6213, 2HV-6218, and 2HV-6219 close.

4b.

Containment emergency cooler CCW isolation Valves 2HV-6366, 2HV-6367, 2HV-6368, 2HV-6369, 2HV-6370, 2HV-6371, 2HV-6372, and 2HV-6373 open.

5.

Response time includes instrumentation, logic, and isolation damper closure times only.

6.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.

7.

Include HV4762 and HV4763 following implementation of DCP 195J.

8 Prior to completion of DCP 6234, valve closure is manually initiated.

Following completion of DCP 6234, valves are to close automatically on a RAS coincident with a high-high containment sump signal.

9.

Response time is for step voltage loss from nominal voltage to 0.0 l

volts.

Emergency diesel generator starting delay (10 sec.) and sequence loading r

delays for SIAS are included.

Emergency diesel generator starting delay (10 sec.) is included.

SAN ON0FRE - UNIT 2 3/4 3-30 Amendment No. E,118 i

9 s..

TABLE 4.3-2 h

ENGINEERED SAFETY FEATURE ACTUATION SYSTEN INSTRUMENTATION SURVEILLANCE REQUI 8

CHANNEL MODES FOR WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE EUNCTIONAL UNIT CHECK-CALIBRATION TEST 11 REOUIRED E

1.

SAFETY INJECTION (SIAS) y a.

Manual (Trip Buttons)

N.A.

(6) 1, 2, 3, 4 b.

Containment Pressure - High S

(6)

Q 1, 2, 3 m

c.

Pressurizer Pressure - Low S

(6)

Q 1, 2, 3, d.

Automatic Actuation Logic M.A.

N.A.

Q(3),SA(4) 1, 2, 3, 4 2.

CONTAINMENT SPRAY (CSAS) a.

Manual (Trip Buttons)

N.A.

(6) 1, 2, ' 3 b.

Containment Pressure --

High - High S

(6)

Q 1, 2, 3 c.

Automatic Actuation Logic N.A.

M.A.

Q(3),SA(4)

I,2,3 3.

CONTAINMENT ISOLATION (CIAS)

Y a.

Manual CIAS (Trip Buttons)

N.A.

(6) 1, 2, 3, 4 5

b.

Manual SIAS (Trip Buttons)(S)

N.A.

(6) 1, 2, 3, 4 c.

Containment Pressure - High S

(6)

Q 1, 2, 3 d.

Automatic Actuation Logic N.A.

N.A.

Q(3),SA(4) 1, 2, 3, 4 4.

MAIN STEAP' ISOLATION (NSIS) a.

Manual (Trip Buttons)

N.A.

(6) 1, 2, 3 b.

Steam Generator Pressure - Low S

(6)

Q 1, 2, 3 Automatic Actuation Logic N.A.

N.A.

Q(3),SA(4) 1, 2, 3 c.

5.

RECIRCULATION (RAS) k Refueling Water Storage a.

Tank - Low S

R Q

1, 2, 3, 4 g

b.

Automatic Actuation Logic M.A.

N.A.

Q(3),SA(4) 1, 2, 3, 4 5

6.

CONTAllWIENT COOLING (CCAS) 5 Manual CCAS (Trip Buttons)

N.A.

(6) 1, 2, 3, 4 a.

b.

deleted intentionally Automatic Actuation Logic W.A.

N.A.

Q(3),SA(4)

I, 2, 3, 4 c.

5

l g

IABLE 4.3-2 (Continued) l ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS W

m CHANNEL MODES FOR l#1ICH m

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL DNIT

_ CHECK CALIBRATION TEST IS REQUIRED E

Z 7.

LOSS OF POWER (LOVS, SDVS, or DGVSS) w a.

4.16 kV Emergency Bus Undervoltage (Loss of Voltage)

S (6)

(6) 1, 2, 3, 4 b.

4.16 kV Emergency Bus Undervoltage (Degraded Voltage S

(6)

(6) 1, 2, 3, 4 8.

ENERGENCY FEEDWATER (EFAS) a.

Manual (Trip Buttons)

N.A.

(6) 1, 2, 3 b.

SG Level (A/B)-Low and AP (A/B) - High-S (6)

Q 1, 2, 3 w

c.

SG Level (A/B) - Low and No A

Pressure - Low Trip (A/B)

S (6)

Q 1, 2, 3 d.

Automatic Actuation Logic N.A.

N.A.

Q(3) SA(4) 1, 2, 3 wL N

9.

CONTROL ROOM ISOLATION (CRIS) a.

Manual CRIS (Trip Buttons)

N.A.

R N.A.

b.

Manual SIAS (Trip Buttons)

N.A.

R N.A.

c.

Airborne Radiation i

1.

Particulate / Iodine S

R M

All l

11. Gaseous S

R M

All d.

Automatic Actuation' Logic N.A.

N.A.

R(3)

All E

10. T0XIC GAS ISOLATION (TGIS) i y

a.

Manual (Trip Buttons)

N.A.

R N.A.

i b.

Chlorine - High S

R M

All i

c.

Ammonia - High.

S R

M All d.

Butane / Propane'- High S

R M

All e.

Automatic Actuation Logic N.A.

N.A.

R(3)

All

-6 g

l

. _,._ _..,,._..__-___,...-._.,--.__ -..-_. __ ____ _...__.-- _ _-.- _,-...~..-._-__.-....__-....,--.-.___ __ _ _ __._ _ _.

m 4

g iAIILE 4.3-3 h

RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 7

CHANNEL MODES FOR WilCH Q

CllANNEL CHANNEL FUNCTIONAL SURVEILLANCE

,1NSTRUMENT Cl!ECK CAllBRATION TEST IS REQUIRED u

PROCESS MONITORS (Continued) 3.

Noble Gas Monitors a.

Plant Vent Stack D

R Q

1, 2, 3, 4

.(2RT-7865-1,3RT-7865-1, 2/3RT-7808) b.

Condenser Evacuation System D

R Q

1,2,3,4(1)

{

(2RT-7870-1,2RT-7818-1)

Y O

NOTES:

In accordance with Table 4.3-2 surveillance requirements for these instrument channels.

With irradiated fuel in the storage pool.

g (1) With any main steam isolation valve and/or any main steam isolating valve bypass valve not fully closed.

M g

(2) At least once per refueling interval.

En 5

. ---.-.m

-.. ~

.~.

e.

=

i i

1 h

i h.i l

1 t

c i

i L

r f

DELETED INTENT 10NALLY' i

i t

i h

i i

i t

i i

l i

i t

?

SAN ONOFRE-UNIT 2 3/4 3-40 Amendment No. 118

o l

i paneug f*-

UNITED STATES i

j

,j NUCLEAR REGULATORY COMMISSION 2

WASHINGTON. D.C. N1

'4,.....,o I

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 ON0FRE NUCLEAR GENERATING STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.107 License No. NPF-15 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Southern California Edisen Company, et al. (SCE or the licensee) dated September 30, 1993, as supplemented by letters dated November 16, 1993, January 18, 1995, and February 2, 1995, 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 provisions of the Act, and the rules and 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 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.ind 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 6

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 Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised s

through Amendment No. 107, 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 completion of the Cycle 8 refueling outage and must be fully implemented prior to returning SONGS Unit 3 to power.

FOR THE NUCLEAR REGULATORY, COMMISSION j

. ppy / K /: & & /e Mel B. Fields, Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation i

Attachment:

Changes to the Technical i

Specifications Date of Issuance:

March 17,1995 i

0 l

ATTACHMENT TO LICENSE AMENDMENT AMENQMENT NO. in7 TO FACILITY OPERATING LICENSE NO. NPF-15 DOCKET NO. 50-312 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 3-16 3/4 3-16 3/4 3-19 3/4 3-19 3/4 3-23 3/4 3-23 3/4 3-26 3/4 3-26 3/4 3-29 3/4 3-29 3/4 3-30 3/4 3-30 3/4 3-32 3/4 3-32 3/4 3-40 3/4 3-40 f

4 l

a o

TABtL3,3-3 (Continued 1 ENGINELRED_SAF_ETY IEAT.URES_ ACTUATION SYSTEM INSTRUMENTATION E

o2 MINIMUM i

TOTAL NO.

CHANNELS CHANNELS APPLICABLE 7

EUNCT10NAL UNIT Of CHANNLLS

.10 TR11 OPERABLE MODES ACTION E

4 MAIN STEAM LINE ISOLATION w

a.

Manual (Trip 2/ steam 1/ steam 2/ operating 1, 2, 3 11

' Buttons) generator generator steam generator b.

Steam Generator 4/ steam 2/ steam 3/ steam I, 2, 3 9*,

10*

Pressure - Low generator generator generator l

c.

Automatic Actuation 4/ steam 2/ steam 3/ steam I,2,3 9*,

10*

logic generator generator generator 1

5.

RECIRCULATION (RAS) a.

Refueling Water Storage Tank - Low 4

2 3

1, 2, 3, 4 9*,

10*

l b.

Automatic Actuation Logic 4

2 3

1, 2, 3, 4 9*,

10*

6.

CONTAlf81ENT COOLING (CCAS) a.

Manual CCAS (Trip Buttons) 2 sets of 2 1 set of 2 2 sets of 2 1, 2, 3, 4 8

5g b.

Deleted intentionally M

e, c.

Automatic Actuation 5

togic 4

2 3

1, 2, 3, 4 9*,

10*

i 5

3

1 y,

TABLE 3.3-3 (Continued)

E ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION c,

59 MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS ' TO TRIP OPERABLE MODES ACTION E

Z 7,

LOSS OF POWER (LOVS, SDVS, or DGVSS) a.

4.11,tV Emergency Bus Unlewitage (Loss o'i Voltage) 4/ Bus 2/ Bus 3/ Bus 1, 2, 3, 4 9*,

10*

I b.

4.16 kV Emergency Bus Undervoltage (Degraded Voltage) 4/ Bus 2/ Bus 3/ Bus 1,2,3,4(d) 9*,

10*

8.

EMGGENCY FEEDWATER (EFAS)

R a.

Manual (Trip Buttons) 2 sets of 2 1 set of 2 2 sets of 2 1,2,3 11 y

per S/G per S/G per S/G cn b.

Automatic Actuation Logic 4/SG 2/SG 3/SG 1, 2, 3 9*,

10*

c.

SG Level (A/B) - Low and AP (A/B) - High 4/SG 2/SG 3/SG 1, 2, 3 9*,

10*

d.

SG Level (A/B) - Low and No S/G Pressure -

M Low Trip (A/B) 4/SG

- 2/SG 3/SG 1, 2, 3 9*,

10*

2 S

aa g

a T

__~..-e

~_.,..,,,_,%.--+,c

,,.,,-.yr..--,.-.-o.,_,,,

,~..-..,..,,-..4,,

.,-c-.

-,,,om--,.,,

,,c,

-14

.y....

r,m.__,

-,,,...,..m..m_--%,--,%.,r, r.

y.-..

e, m

a o

TABLE 1.3-3 (Continued)

TABLE NOTATION (a) Trip function may be bypassed in this MODE when pressurizer pressure is less than 400 psia; bypass shall be automatically removed when pressurizer pressure is greater than or equal to 400 psia.

(b) An SIAS signal is first necessary to enable CSAS logic.

(c) Actuated equipment only; does not result in CIAS.

(d) Applicability for SDVS is Modes 1, 2, 3, and 4 when the diesel generator l

circuit breaker is open.

[

The provisions of Specification 3.0.3 are not applicable.

The provisions of Specification 3.0.4 are not applicable.

With irradiated fuel in the storage pool.

ACTION STATEMENTS ACTION 8 - With the number of OPERABLE channels one less than the Total Number i

of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 9 - With the number of channels OPERABLE one less than the Total Number

[

of Channels, STARTUP and/or POWER OPERATION may continue provided L

the inoperable channel is placed in the bypassed or tripped condition within I hour.

If the inoperable channel is bypassed, the desirability of maintaining this channel in the bypassed i

condition shall be reviewed in accordance with Specification 6.5.1.6e.

The channel shall be returned to OPERABLE status no later than during the next COLD SHUTDOWN.

With a channel process measurement circuit that affects multiple functional units inoperable or in test, bypass or trip all associated functional units as listed below.

Process Measurement Circuit Functional Unit Bypassed 1.

Containment Pressure - High Containment Pressure - High (ESF)

Containment Pressure - High (RPS) 2.

Steam Generator Pressure -

Steam Generator Pressure - Low l

Low Steam Generator AP 1 and 2 (EFAS) 3.

Steam Generator Level Steam Generator Level - Low i

Steam Generator Level - High Steam Generator AP (EFAS) i i

SAN ON0FRE - UNIT 3 3/4 3-19 Amendment No.107

TABLE 3.3-3 (Continued)

TABLE NOTATION ACTION 10 -

With the number of channels OPERABLE one less than the Minimum i

Channels OPERABLE, STARTUP and/or POWER OPERATION may continue provided the following conditions are satisfied:

a.

Verify that one of the inoperable channels has been bypassed and place the other inoperable channel in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

[

t b.

All functional units affected by the bypassed / tripped channel shall also be placed in the bypassed / tripped i

condition as listed below:

Process Measurement Circuit Functional Unit Bypassed / Tripped 1.

Containment Pressure Circuit Containment Pressure - High (ESF)

Containment Pressure - High (RPS) 2.

Steam Generator Pressure -

Steam Generator Pressure - Low Low Steam Generator AP 1 and 2 (EFAS) l 3.

Steam Generator Level - Low Steam Generator Level - Low i

Steam Generator Level - High Steam Generator AP (EFAS)

+

STARTUP and/or POWER OPERATION may continue until the performance i

of the next required CHANNEL FUNCTIONAL TEST.

Subsequent STARTUP i

and/or POWER OPERATION may continue if one channel is restored to OPERABLE status and the provisions of ACTION 9 are satisfied.

ACTION 11 -

With the number of OPERABLE channels one less than the Total I

Number of Channels, restore the inoperable channels to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 12 -

With the number of OPERABLE channels one less than the Total Number of Channels, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ;-

however, one channel may be bypassed for up to I hour for surveillance testing provided the other channel is OPERABLE.

i-i SAN ONOFRE-UNIT 3 3/4 3-20 i

.=

TABLE 3.3-4 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES z?

E ALLOWABLE FUNCTIONAL UNIT TRIP VALUE VALUES E

Z 6.

CONTAINMENT COOLING (CCAS) a.

Manual CCAS (Trip Buttons)

Not Applicable Not Applicable b.

deleted intentionally c.

Automatic Actuation Logic Not Applicable Not Applicable 7.

LOSS OF POWER (LOVS, SDVS, or DGVSS) l a.

4.16 kV Emergency Bus Undervoltage (Loss of Voltage) 3675 V 3554 - 3796 V l

b.

4.16 kV Emergency Bus Undervoltage 4228 Y 4181 - 4275 V

[

m A

(Degraded Voltage) i 8.

EMERGENCY FEEDWATER (EFAS) a.

Manual (Trip Buttons)

Not Applicable Not Applicable b.

Steam Generator (A&B) Level-Low 2 2U,(3) 2 20% (3) c.

Steam Generator & -High (SG-A > SG-B) s 125 psi s 140 psi y

d.

Steam Generator M -High (SG-B > SG-A) s 125 psi s 140 psi

$g e.

Steam Generator (A&B) Pressure - Low 2 741 psia (2) 2 729 psia (2)

N f.

Automatic Actuation Logic Not Applicable Not Applicable 5

TABLE 3.3-4 (Continued)

Y ENGINEERED SAFETY F.EATU_RES ACTUATION SYSTEN INSTRUMENTATION TRIP VALU U

?g ALLOWA8tE FUNCTIONAL UNIT TRIP VALUE VALUES E

9.

CONTROL ROOM ISOLATION (CRIS) a.

Manual CRIS (Trip Buttons)

Not Appilcable Not Appilcable w

l b.

Manual SIAS (Trip Buttons)

Not Applicable Not Applicable c.

Airborne Radiation 1.

particulate / Iodine s 5.7 x 10' cpm **

s 6.0 x 10' cpm **

11. Gaseous s 3.8 x 10' cpm **

s 4.0 x 10' cpm **

1 d.

htomatic Actuation Logic Not Appilcable Not Appilcable b

10. T0XIC MS ISOLATION (TG15) a.

Manual (Trip Buttons)

Not Applicable Not Appitcable b.

Chlorine - High s 14.3 ppa s 15.0 ppe c.

Ammonta - High 5 97 ppe s 100 ppe d.

Butaw/ propane - High s 193 ppe s 200 ppm g

e.

Automatic Actuation Logic Not Appilcable Not Appilcable w

~

5 E

A i 4

O N

9useusP w

.. +.

r

-. - ~.,

.=

m E

TABLE 3.3-4 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES

=

ALLOWABLE FUNCTIONAL UNIT TRIP VALUE VALUES w 11. FUEL HAN0 LING ISOLATION (FHIS) a.

Manual (Trip Buttons)

Not Applicable Not Applicable b.

Airborne Radiation 1.

Gaseous (8)

(8) l c.

Automatic Actuation Logic Not Applicable Not Applicable w 12. CONTAINNENT PURGE ISOLATION (CPIS)

~*

a.

Manual (Trip Buttons)

Not Applicable Not Applicable i

b.

Airborne Radiation 1.

Gaseous (6)(7)

(6)(7) 11.

Particulate (6)(7)

(6)(7) 111. Iodine (6)(7)

(6)(7) c.

Containment Area Radiation (Gamma)

< 325 mR/hr (MODES 1-4)

< 340 mR/hr (MODES 1-4) i2.4mR/hr(Mode 6) 52.5mR/hr(MODE 6)

E d.

Automatic Actuation Logic Not Applicable Not Appilcable m*

e 5

3

-=

tg TABLE 3.3-4 (Continued) a g

TABLE NOTATION

?

(1)

Value may be decreased manually, to a minimum of greater than or equal to 300 psia, as pressurizer pressure is reduced, provided the margin between the pressurizer and this value is maintained at c;

less than or equal to 400 psia;* the setpoint shall be increased automatically as pressurizer pressure O

is increased until the trip setpoint is reached. Trip may be manually bypassed below 400 psia;

[

bypass shall be automatically removed whenever pressurizer is greater than or equal to 400 psia.

(2)

Value may be decreased manually as steam generator pressure is reduced, provided the margin between the steam generator pressure and this value is maintained at less than or equal to 200 psi;* the setpoint shall be increased automatically as steam generator pressure is increased until the trip setpoint is reached.

(3)

% of the distance between steam generator upper and lower level instrument nozzles.

(4)

Deleted.

l 5

(5)

Actuated equipment only; does not result in CIAS.

w A

(6)

The trip setpoint shall be set sufficiently high to prevent spurious alams/ trips yet sufficiently low to assure an alarm / trip should an inadvertent release occur.

(7)

Prior to the completion of DCP 53N, the setpoints for Containment Airborne Radiation Monitor 3RT-7804-1 shall be determined by the ODCM.

(8)

The trip setpoint shall be set sufficiently iiigh to prevent spurious alarm / trips yet sufficiently low to assure an alarm / trip should a fuel handling accident occur.

Variable setpoints are for use only during normal, controlled plant heatups and cooldowns.

,Ei

- Above normal background.

I a

if

i b ble 3.3-5 (Continued)

INITIATING SIGNAL AND FUNCTION RESPONSE TIME (SEC) l 5.

Steam Generator Pressure - Low MSIS (1) Main Steam Isolation (HV8204, HV8205) 8.9 (2) Main Feedwater Isolation (HV4048,HV4052) 10.9 (3) Steam, Blowdown and Sample Isolation 20.9 (HV8419,HV8421)

(HV4053, HV4054, HV4057. HV4058)

(4) Auxiliary Feedwater Isolation (NOTE 7) 40.9 (HV4705, HV4713 HV4730, HV4731)

(HV4706, HV4712, HV4714, HV4715) 6.

Refuelina Water Storace Tank - Low

a. RAS (1) Containment Sump Valves Open 50.7*

(2) ECCS Miniflow Isolation Valves Close 50.7* (Note 8) 7.

4.16 kV Emeraency Bus Undervoltaae

a. LOVS (loss of voltage,127F) (Note 9) 1.00+/-00.05 i

b. Degraded voltage, (1270) 2.00+/-00.20 1.

SDVS (Sustained Degraded Voltage)

(a)

Auxiliary Timing Relay 162D 110.00+/-22.00 11.

DGVSS (Degraded Grid Voltage with SIAS)

(a)

Auxiliary Timing Relay 162S 4.30+/-00.19 (b)

Auxiliary Timing Relay 162T 1.25+/-00.40 8.

Steam Generator level - Low (and No Pressure-Low Trio)

a. EFAS (1) Auxiliary Feedwater (AC trains) 52.7*/52.7**

(2) Auxiliary Feedwater (Steam /DC train) 42.7 (NOTE 6) 9.

Steam Generator level - Low (and P - Hiah)

a. EFAS (1) Auxiliary Feedwater (AC trains) 52.7*/52.7**

(2) Auxiliary feedwater (Steam /DC train) 42.7 (NOTE 6) 10.

Control Room Ventilation Airborne Radiation

a. CRIS (1) Control Room Ventilation - Emergency Mode Not Applicable i

11.

Control Room Toxic Gas (Chlorine)

a. TGIS (1) Control Room Ventilation - Isolation Mode 16 (NOTE 5) 12.

Control Room Toxic Gas (Ammonia)

a. TGIS (1) Control Room Ventilation - Isolation Mode 36 (NOTE 5)

SAN ON0FRE - UNIT 3 3/4 3-29 Amendment No. 49,107

i Table 3.3-5 (Continued)

INITIATING SIGNAL AND FUNCTION RESPONSE TIME (SEC) 13.

Control Room Toxic Gas (Butane /Procane)

'I TGIS Control Room Ventilation -

t Isolation Mode 36 (NOTE 5) 14.

futl_.liAndlina Buildina Airborne Radiation FHIS Fuel Handling Building Post-Accident 1

Cleanup Filter System Not Applicable 15.

Containment Airborne Radiation CPIS Containment Purge Isolation 2 (NOTE 2) 16.

Containment Area Radiation CPIS Containment Purge Isolation 2 (NOTE 2) i NOTES:

1.

Response times include movement of valves and attainment of pump or blower discharge pressure as applicable.

l 2.

Response time includes emergency diesel generator starting delay (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.

I 3.

All CIAS-Actuated valves except MSIVs, MFIVs, and CCW valves 3HV-6211,

[

3HV-6216, 3HV-6223 and 3HV-6236.

L l

4a.

CCW noncritical loop isolation valves 3HV-6212, 3HV-6213, 3HV-6218 and 3HV-6219, 4b.

Containment emergency cooler CCW isolation valves 3HV-6366, 3HV-6367, 3HV-6368, 3HV-6369, 3HV-6370, 3HV-6371, 3HV-6372 and 3HV-6373 open.

5.

Response time includes instrumentation, logic, and isolation damper i

closure times only.

6.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.

7.

Include HV4762 and HV4763 following implementation of DCP 195J.

8 Prior to completion of DCP 6234, valve closure is manually initiated.

Following completion of DCP 6234, valves are to close automatically on a RAS coincident with a high-high containment sump signal.

9.

Response time is for step voltage loss from nominal voltage to 0.0 l

volts.

8 Emergency diesel generator starting delay (10 seconds) and sequence I

loading delays for SIAS are included.

l Emergency diesel generator starting delay (10 seconds) is included.

SAN ONOFRE - UNIT 3 3/4 3-30 Amendment No. 44,107

(

lABLE4.3d vi E

ENGINEERED SAFETY FEAlURES_ACIUATION SYSTEN INSTRU_ MENTATION SURVEILLANCE REQUIREMEN 9g CHANNEL.

MODES FOR WHICH g

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT C11EXCIL CAllBRATION TEST IS REQUIRED-1.

SAFETY INJECTION (SIAS) a.

Manual (Trip Buttons)

N.A.

(6) 1, 2, 3, 4 w

b.

Containment Pressure - High 5

(6)

Q 1, 2, 3 c.

Pressurizer Pressure - Low S

(6)

Q 1, 2, 3 d.

Automatic Actuation Logic N.A.

N.A.

Q(1)(3),SA(4) 1, 2, 3, 4 2.

CONTAINMENT SPRAY (CSAS) 1 a.

Manual (Trip Buttons)

N.A.

M.A.

(6) 1, 2, 3 b.

Containment Pressure --

High - High S

(6)

Q 1, 2, 3 c.

Automatic Actuation Logic N.A.

N.A.

Q(1)(3),SA(4) 1, 2, 3

.i 3.

CONTAINNENT ISOLATION (CIAS) w 4,

a.

Manual CIAS (Trip Buttons)

N.A.

(6) 1, 2, 3, 4 b.

Manual SIAS (Trip Buttons)(5)

N.A.

M.A.

(6)

I, 2, 3, 4 c.

Containment Pressure - High S

(6)

Q 1, 2, 3 d.

Automatic Actuation Logic M.A.

N.A.

Q(1)(3),SA(4) 1, 2, 3, 4 4.

MAIN STEAM ISOLATION (MSIS) a.

Manual (Trip Buttons)

N.A.

(6)

I, 2, 3 b.

Steam Generator Pressure - Low S (6)

Q 1, 2, 3 c.

Automatic Actuation Logic M.A.

N.A.

Q(1)(3),SA(4)

I, 2, 3 5.

RECIRCULATION (RAS) g a.

Refueling Water Storage g

Tank - Low S

R Q

1, 2, 3, 4 g

b.

Automatic Actuation Logic M.A.

N.A.

Q(1)(3),SA(4)

I, 2, 3, 4 E

6.

CONTAINMENT COOLING (CCAS) g a.

Manual CCAS (Trip Buttons)

N.A.

(6) 1, 2, 3, 4 b.

deleted intentionally l

g c.

Automatic Actuation Logic M.A.

N.A.

Q(1)(3),SA(4)

I, 2, 3, 4

-- ~

---av

..w,-

-~,

.---------m

o, TABLE 4.3-2 (Continued)

E ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS o5s CHANNEL MODES FOR WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST IS REQUIRED E

Z 7.

LOSS OF POWER (LOVS, SDVS, or DGVSS) l w

a.

4.16 kV Emergency Bus Undervoltage (Loss of Voltage)

S (6)

(6) 1, 2, 3, 4 b.

4.16 kV Emergency Bus Undervoltage (Degraded Voltage 5

(6)

(6) 1, 2, 3, 4 8.

EMERGENCY FEEDWATER (EFAS) a.

Manual (Trip Buttons)

N.A.

(6) 1, 2, 3 b.

SG Level (A/B)-Low and w2 AP (A/B) - High S

(6)

Q 1, 2, 3 w

c.

SG Level (A/B) - Low and No a

Pressure - Low Trip (A/B)

S (6)

Q 1, 2, 3 d.

Automatic Actuation Logic N.A.

N.A.

Q(3) SA(4) 1, 2, 3 9.

CONTROL ROOM ISOLATION (CRIS) a.

Manual CRIS (Trip Buttons)

N.A.

R N.A.

b.

Manual SIAS (Trip Euttons)

N.A.

R N.A.

c.

Airborne Radiation i.

Particulate / Iodine S

R M

All

11. Gaseous S

R M

All d.

Automatic Actuation Logic N.A.

N.A.

R(3)

All k

10.

T0XIC GAS ISOLATION (TGIS) a.

Manual (Trip Buttons)

N.A.

R N.A.

5!

b.

Chlorine - High S

R M

All S

c.

Ammonia - High 5

R M

All d.

Butane / Propane - High S

R M

All 2

P e.

Automatic Actuation Logic N.A.

N.A.

R(3)

All O

N

. _,, _ _ - _ _ _ - _ _ _ -. ~ _

e.

m E

TABLE 4.3-3 (Continued) k A

RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS m

CHANNEL MODES FOR WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE E

INSTRUNENT CHECK CAllBRATION TEST IS REQUIRED 4

PROCESS MONITORS (Continued) w 3.

Noble Gas Monitors a.

Plant Vent Stack D

R Q

1,2,3,4 (2/3 RT-7808, 2RT-7865-1, 3RT-7865-1) w b.

Condenser Evacuation System D

R q

1, 2, 3, 4(1) 1 (3RT-7818,3RT-7870-1)

Y M

l NOTES:

In accordance with Table 4.3-2 surveillance requirements for these instrument channels.

With irradiated fuel in the storage pool.

(1) With any main steam isolation valve and/or any maire steam isolating valve bypass valve not fully closed.

3 (2) At least once per refueling interval.

E" 9

E 9

_,m

n DELETED INTENTIONALLY SAN ONOFRE-UNIT 3 3/4 3-40 Amendment No. 107

-

ML20081J708

Text

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