ML20005F731

Amends 82 & 72 to Licenses NPF-10 & NPF-15,respectively, Extending Surveillance Interval to Every 24 Months for Tech Specs Re ESFAS Instrumentation,Radiation Monitoring Instrumentation & Reactor Coolant Gas Vent Sys

ML20005F731
Person / Time
Site:	San Onofre
Issue date:	01/02/1990
From:	Knighton G Office of Nuclear Reactor Regulation
To:
Shared Package
ML20005F732	List: ML20005F731 ML20005F738 ML20005F742
References
NUDOCS 9001170201
Download: ML20005F731 (23)

Text

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'o UNITED STATES

-E" NUCLEAR REGULATORY COMMISSION o.

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WASHINGTON, D. C,20655

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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 NO. 2 l

AMENDMENT TO FACILITY OPERATING LICENSE l

Amendment No. 82 License No. NPF-10 1.

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

A.

The applications for amendment to the license for San Onofre Nuclear Generating Station, Unit 2 (the facility) filed by Southern California Edison Company (SCE) on behalf of.~itself and San Diego Gas and Electric Company, the City of Riverside, California and the City of Anaheim, California (licensees) dated December 19; 1988 and December. 30,'1988, which were-supplemented September 5, 1989; and April 7, 1989, which was supplemented November 6, 1989, comply 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-' applications, the-provisions of the Act, and the regulations of. the-Comission;

'y' 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.

i 9001170201 900102 w

PDR ADOCK 05000361 P

PDC

1 v

., V ' Fr. Harold B. Roy -

San Onofre Nuclear Generating i

Southern California Edison Company Station, Units 2 and 3 CC:

Charles R. Kocher, Esq.

Mr. F. B. Marsh, Project Manager James A. Beoletto, Esq..

Bechtel Power Corporation Southern California Edison Company P.O. Box 60860 Irvine Operations Center Terminal Annex 23 Parker Los Angeles,_ California 900.60 Irvine, California 92718 Mr. Robert G. Lacy Orrick Herrington & Sutcliffe Manager, Nuclear Department ATTN: David R. Pigott, Esq.

San Diego Gas & Electric Company 600 Noritgomery Street P. O. Box 1831 1

San Francisco, California 94111 San Diego, California 92112 Alan R. Watts, Esq.

Mr. Jchn Hickman Rourke & Wooaruff Senior Health Physicist i

701 S. Parker St. No. 7000 Environmental Radioactive Mgmt. Unit 1

Orange, California 92668-4702 Environmental Management Branch State Department cf Health Services Mr. Sherwin-Harris 714 P Street, Room 616 Resource Project Manager Sacramento, California 95814 Public Utilities Department City of Riverside Resident Inspector, San Oncfre NPS 3900.Nain Street c/o U.S. Nuclear Regulatory Comission 1

Riverside, California 92522 Post Office Box 4329 i

San Clemente, California 92672 Mr. Charles B. Brinkman Combustion Engineering, Inc.

Mayor, City of San Clemente

'l 12300 Twinbrook Parkway, Suite 330 San Clemente, California 92672 Rockville, Maryland 20852 Regional Administrator, Region V Mr. Phil Johnson U.S. Nuclear Regulatory Comission U.S. Nuclear Regulatory Comission 1450. Maria Lane / Suite 210 Regicn V Walnut Creek, California 94596 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 Chairman, Board of Supervisors San Diego County Mr. Den Womeldorf 1600 Pacific Highway, Room 335 l

Chief Environmental Management-Branch San Diego, California. 92101 California Department of Health 714 P Street, Room 616 Sacramento, California 95814 l

'(14) l t

V',

. 2.

Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendirent, and paragraph 2.C(2) of Facility Operating License No. NPF-10 is.hereby amended to read as follows:

(2) Technical Specification The Technical Specifications 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. SCE shall operate the facility in accordance with the Technical Specifications and the Environirental i

Protection Plan.

3.

This license amendment is effective as of the date of its issuance'and rust be fully implemented no later than 30 days from the date of issuance.

FOR THE NUCLEAR REGULA ORY COMMISSION

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George 7. Knighton,-

rector Project Directorate V Division of Reactor Projects - III, i

IV, V and Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical l

Specifications Date of Issuance:

January 2, 1990 6

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2.

Accordingly, the license is anended by changes to the Technical Speci-fications as indicated in the attachnent to this license amendnent, and paragraph 2.C(2) of Facility Operating License No.-NFF-15 is hereby amended to read as follows:

(2) Technical Specification The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 72, are hereby incorporated in the license._ SCE 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.

4 FOR THE NUCLEAR REGULATORY COMMISSION

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' **V deorge,W. Knighton>,

irector Project Directorate V Division of Reactor Projects - III, IV,il and Special Projects Office of Nuclear Reactor Regulation

Attachment:

- l Changes to the Technical Specifications i

Date of Issuance:

January 2,1990 I

1

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v, TABLE 4.3-2 (Continued) o 5

lj ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS T

g CHANNEL MODES FOR WHICH CHANNEL CHANNEL FUNCTIONAL

. SURVEILLANCE y

CHECK CALIBRATION TEST IS REQUIRED FUNCTIONAL UNIT w

11. FUEL HANDLING ISOLATION (FHIS)

N.A.

a.

Manual (Trip Buttons)

N.A.

N.A.

R b.

Airborne Radiation

i. Gaseous S

R M

ii. Particulate / Iodine S

R M

c.

Automatic Actuation Logic N.A.

N.A.

R(3) i

12.. CONTAINMENT PURGE ISOLATION (CPIS) t>-

a.

Manual (Trip Buttons)

N.A.

N.A.

R N.A.

b.

Airborne Radiation y

i..

Gaseous-S R

M 1,2,3,4,6 O

ii. Particulate W

R M.

1,2,3,4,6 iii. Iodine W

R M

6 c.

Containment' Area Radiation (Gama) 5 (6)

M 1,3,3,4,6 l

'd.

Automatic Actuation Logic N.A.

N.A.

R (3) 1,2,3,4,6 TABLE NOTATION (1) Each train or logic channel shall be tested at least every 62 days' on a STAGGERED TEST BASIS.

f (2)-Deleted.

(3) Testing of Automatic Actuation Logic shall include energization/de-energization of each initiation relay and verification of the OPERABILITY of each' initiation relay.

k (4) A subgroup relay test shall be performed.which shall -include the energization/de-energization of each g

subgroup relay and verification of the OPERABILITY of each subgroup relay. Relays' exempt from' testing I

g during plant operation shall be-limited to'only those relays associated with plant equipment which l-g cannot be operated during plant: operation. Relays not testable during plant operation shall be tested 4

during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless tested during the previous 6 months.

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(5) ~ Actuated equipment only; does not result'in CIAS.

. W (6) At least once per refueling interval.

With irradiated fuel in the storage pool.

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INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alarm / trip setpoints within the specified limits.*

l APPLICABILITY:

As shown in Table 3.3-6, ACTION:

a.

With a radiation monitoring channel alarm / trip setpoint exceeding the value shown in Table 3.3-6, adjust the setpoint to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare. the channel inoperable, b.

With one or more radiation monitoring channels inoperable, take the:

ACTION shown in Table 3.3-6.

1 c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

~

SURVEILLANCE REQUIREMENTS

4. 3. 3.1 Each-radiation monitoring instrumentation channel shall be-demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL I

CALIBRATION and' CHANNEL FUNCTIONAL TEST operations 1for the MODES and at-the frequencies shown in Table 4.3-3.

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• Continuous monitoring.and sampling of the containment purge exhaust directly from-the purge stack shall.be provided for the-low and high volume (8-inch and 42-inch) containment purge prior to startup following the -first refueling outage.

Containment airborne monitor 3RT-7804-1 or 3RT-7807-2 and. associated sampling media shall perform these functions prior to initial criticality.

From initial criticality to the startup following the. first refueling outage i

containment airborne monitor 3RT-7804-1 and associated sampling media shall perform the above required functions.

SAN ON0FRE-UNIT 3 3/4 3-34 AMENOMENT N0. 20

t l l l

TABLE 3.3-6 (Continued)

ACTION STATEMENTS l

ACTION 13 With the number of channels OPERABLE less than required by the minism channels OPERABLE requirement, within I hour initiate and maintain operation of the control room emergency air i

cleanup system in the emergency (except as required by ACT!0FS 14,'15) mode of operation.

ACTION 16 With the number of channels OPERABLE less than required by the minimum channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.12.

ACTION 17 With the number of channels OPERABLE less than required by the

. minimum channels OPERABLE requirement,. operation may continue provided that the purge valves are maintained closed.

ACTION 17a -

With the number of channels OPERA 8LE less than required by.the minimum channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.5.1 (Mode 1, 2, 3, 4 only)

ACTION 17b -

With the number of channels OPERABLE less than requirsd by the t

minimum channels OPERABLE requirement, close each of the con-I tainment purge penetrations'providing direct access from the

{

~ containment atmosphere to the outside atmosphere.

l' 1

ACTION 18 With the numbei of channels OPERABLE one less than Minimum j

Channels OPERABLE requirement, either restore the inoperable

(

)

channel to OPERABLE status within 30 days, or be in. HOT SHUTDOWN within the next 12. hours.

ACTION 18a -

With both channels inoperable, restore the-inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />,'or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

ACTION 19 With the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirement, either restore the.

inoperable Channel (s) 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:

1)

Initiate the preplanned alternate method of monitoring the appropriate parameter (s), and 2)

Prepare and submit a Special Report to the Commission.

pursuant to Specification 6.9.2 within 14-days.fo11owing initiation of the pre planned alternate outlining the action taken, the cause of the inoperability.and the plans and schedule for restoring the system to OPERABLE.

q status.

1. In accordance with Engineered Safety Feature trip value specified by Table 3.3-4.

A With irradiated fuel in the storage pool.

ACTIONS 13, 16, 17, 17a and 17b are repeated from Table-3.3-3 for reference.

SAN ONOFRE-UNIT 3 3/4 3-37 AMENDMENT.NO. 20 S

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= "g TABLE 4.3-3 E

RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL-MODES FC4t WHICH h

CHANNEL CilANNEL FUNCTIONAL SURVEILLANCE h

INSTRUMENT CHECK CALIBRATION TEST IS REQUIRED y

1.

Area Monitors

~

a.

Containment - High Range S

R M

1, 2, 3, 4 (3RT-7820-1,3RT-7820-2) b.

Containment - Purge Isolation S

(2)

M 1,2,3,4,6 (3RT-7856-1,3RT-7857-2) c.

Main Steam Line S

R M

1, 2, 3, 4 (3RT-7874A,3RT-7875A, R

3RT-78748,3RT-78758) y 2.

Process Monitors a.

Fuel. Storage Pool Airborne (3RT-7822-1,3RT-7823-2) i.

Gaseous

11. Particulate / Iodine b.

Containment Airborne (3RT-7804-1,3RT-7807-2) i.

Gaseous 1,2,3,4,6 ii.

Particulate 1,3,3,4,6 iii.

Iodine' 6

m c.

Control Room Airborne 5

(2/3RT-7824-1,-2/3RT-7825-2) i.

Particulate All 5

ii. Gaseous All N

.s.,-

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(f)

L l

E" TAfsLE 4.3-3 (Continued) o RADIATION MONITORING INSTRUMENTATION SURVEILLANCE _ REQUIREMENTS sc CHANNEL MODES FOR WHICH 3

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE

]'

IllSTRUMENT CHECK' CALIBRATION TEST IS REQUIRED-PROCESS MONITORS (Continued) 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) b.

Condenser Evacuation System D

R Q

1,2,3,4(1)

-(3RT-7818,3RT-7870-1) w z

s w

- b NOTES:

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

I

• With irradiatedifuel in the storage pool..

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

(2) At least once per refueling: interval.

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M i

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l 1

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i 1

t 36751110 VOLTS '

100 i

,8 a

ha P-o P

10 I

I

/

I

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F 2800 VOLTS

=l L

2.610.13 SECONOS j

O VOLTS 1.0 t.06 SECONDS j

I 1.0 I

2400 2800 3200 3600 4000~

i-BUS VOLTAGE 1

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Figure 3.3-1 l

DEGRADED BUS VOLTAGE TRIP SETTING

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i SAN ONOFRE-UNIT 3 3/4 3-40 4

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REACTOR COOLANT SYSTEN i

l 3/4.4.10 REACTOR COOLANT GAS VENT SYSTEM LIMITING CONDITION FOR OPERAT!0N 3.4.10 The Reactor Coolant Gas Vent System shall be OPERABLE with:

l At least one ef valves 3HV0296A er 3NV02968 capable of being powerec

(

a.

free an emergency bus and providing a vent path from the reactor i

vessel head; and, i

b.

At least one of valves 3HV0297A or 3NV02978 capable of being powered from an emergency bus and providing a vent path from the pressurizer stone space; and.

I

. At least one of valves 3NV0298, capable of being powered from an c,

i amargency bus and providing a vent path to the containment atmosphere, or 3NV0299, capable of being powered from an emergency bus and pro-viding a vent path to the quench tank; and L

d.

Valves 3NV0296A, 3NV02968, Mfv0297A, 3NYO2978, 3NV0299 and 3NV0298

$ closed.

APPLICABILITY: MODES 1, 2, 3 and 4 I

ACTION:

With any of valves 3HY0296A, 3NV02968, 3NVC297A, or 3HV02978 a.

inep table, operation may continue pecvided that.

i) power is removed from the inoperable valve (s) within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />;

and,

11) valves 3NV0299 and 3NV0298 are maintained closed end power is i

removed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; and, iii) the inoparable valve (s) is restored to OPERABLE status during the next COLD SHUTDOWN.

b.

With any of valves 3NYC299 or 3 40298 inoperable, operation may

-l continue provided that:

I i

1) power is removed free the inoperable valve (s) within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />;

and, j

I 11) valves 3NV0296A, 3HV02968, 3HV0297A and 3NV02978 are i

maintainedclosedandpowerisremovedwithin4 hours &

and h-l l

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$AN ON0FRE - UNIT 3-3/4 4 37 AMENONENT NO.53 f

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REACT 0R COOLANT SYSTEM l

LIMITING CONDITION FOR OPERATION 4

I 111) the inoperable valve (s) is restored to OPERABLE status during the next COLD SHUTDOWN.

c.

The provisions of 3.0.4 are not applicable for entry into MODES 3, 2 and 1.

SURVEILLANCE REQUIREMENTS i

l 4.4.10 Each reactor coolant system vent path shall be demonstrated OPERABLE at least once per refueling interval by:

1.

Verifying all manual isolation valves in each vent path are locked in the open position, j

2.

Cycling each valve in the vent path through at least one complete cycle of full travel from the control room during COLD SHUTDOWN or j

REFl'ELING.

3.

Verifying flow through the reactor coolant vent' system vent paths during venting during COLD SHUTDOWN.

t i

i SAN ONOFRE - UNIT 3 3/4 4 38 AMENDMENT NO. 72-

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l ATTACHMENT TO LICENSE AMENDMENT-NO. 72 FACILITY OPERATING LICENSE NO. NPF-15 DOCKET NO. 50-362 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 area of change.

l Also enclosed are the following overleaf pages to the amended pages.

(

AMENDMENT PAGE OVERLEAF PAGE 3/4 3-33 3/4 3-34 3/4 3-38 3/4 3-37 3/4 3-39 3/4 3-40 S/4 4-38 3/4 4-37

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v3 Facoq'o UNITED STATES NUCLEAR REGULATORY COMMISSION "g

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g WASHINGTON. D. C. 20556

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l SOUTHERN CALIFORNIA EDISON COMPANY

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i 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 NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE J

Amendment No. 72 l

License No. NPF-15 1.

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

A.

The applications for amendment to the license for San Onofre Nuclear Generating Station, Unit 3 (the facility) filed by Southern California Edison Company (SCE) on behalf of itself California and the, City of Anaheim, California (1.icensees) de,.

and San Diego Gas and Electric Company, the City of Riversi i

dated December 19, 1988 and December 30, 1988, which were supplemented September 5, 1989; and April 7,'1989, which w6s supplemented November 6, 1989, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with'the applicatinns, i

the provisions of the Act, and the regulations of the Comission; 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 wi.11 be conducted in compliance with the Commission's regulations; i

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'eccordance with 10 CFR Pert 51 of the Comission's regulations and all applicable requirements have been satisfied.

4

g TABLE 4.3-2 (Continued) i g

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

CHANNEL MODES FOR WHICH 7~

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE E

FUNCTIONAL UNIT CHECK CALIBRATION TEST IS REQUIRED e

11.

FUEL HANDLING ISOLATION (FHIS) w a.

Manual (Trip Buttons)

N.A.

N.A.

R N.A.

b.

Airborne Radiation

i. Gaseous S

R M

ii. Particulate / Iodine 5

R M

c.

Automatic Actuation Logic M.A.

N.A.

R(3)

12.. CONTAINMENT PURGE ISOLATION (CPIS) a.

Manual (Trip Buttons)

N.A.

N.A.

R N.A.

w b.

Airborne Radiation S-1.

. Gaseous S

R M

1,2,3,4,6 w

11. Particulate W

R M

1,2,3,4,6 0

iii. Iodine -

W R

M 6

c.

Containment Area Radiation (Gansna) 5 (6)

M 1,2,3,4,6 l

d.

Automatic Actuation Logic N.A.

N.A.

R (3) 1,2,3,4,6 TABLE NOTATION (1) Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS.

(2)- Deleted.

l (3) Testing of Automatic Actuation Logic shall include energization/de-energization of each initiation l

g relay and verification of the OPERABILITY of each initiation relay.

E (4) A subgroup relay test shall be performed which shall include the energization/de-energization of each E'

subgroup relay an.d verification of the OPERABILITY of each subgroup relay. Relays exempt from testing E

during plant operation shall be limited to only those relays associated with plant equipment which cannot be operated during plant operation. Relays not testable during plant operation shall be tested 5

during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless tested during the previous 6 months.

g (5) Actuated equipment only; does not result in CIAS.

(6) ' At least once per refueling interval.

With irradiated fuel in the storage pool.

~

e INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RA61ATIONMONITORINGINSTRUMENTATION t

i LIMITING CONDITION FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alarm / trip setpoints within the specified limits.

APPLICABILITY:

As shown in Table 3.3-6.*

ACTION:

a.

With a radiation monitoring channel alarm / trip setpoint exceeding the value shown in Table 3.3-6, adjust the set oint to within the limit i

within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel inoperable.

b.

With one or more radiation monitoring channels inoperable, take the ACTION shown in Table 3.3-6.

t c.

The provisions uf Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel shall be demonstrated l

OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-3.

I "See.Special Test Exception 3.10.5.

l l

1 SAN ONOFRE-UNIT 2 3/4 3-34 AMENDMENT NO. 31

~

u; TABLE 3.3-6 (Continued)

ACTION STATEMENTS ACTION 13 With the number of channels OPERABLE less than required by the minimum channels OPERABLE requirement, within 1-hour initiate and maintain operation of the' control room emergency air cleanup i

system in the emergency (except as required by ACTIONS 14, 15) mode of operation.

ACTION 16 With the number of channels OPERABLE less than required by the minimum channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.12.

ACTION 17 With the number of. channels OPERABLE less than required by the 4

minimum channels OPERABLE requirement, operation may continue provided that the purge valves are maintained closed.

ACTION 17a -

With the number of channels OPERABLE less than required by the minimum channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.5.1.

(Mode 1, 2, 3, 4 only)-

ACTION 17b -

With the number of channels OPERABLE less than required by:the minimum channels OPERABLE requirement, close each of the contain-ment purge penetrations providing direct access from the contain-ment atmosphere to the outside atmosphere, i

ACTION 18 With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement, either restore the inoperable channel to OPERABLE status within 30 days, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

ACTION 1Ba -

With both chann'els inoperable, restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, or be in HOT SHUTOOWN within

,the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

ACTION 19 With the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirement, either restore the inoperable Channel (s) 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:

1)

Initiate the preplanned alternate method of monitoring the appropriate parameter (s), and 2)

Prepare and submit a Special Report to the Commission pur-l suant to Specification 6.9.2 within 14 days following initi-ation of the pre planned alternate outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

1. In accordance with Engineered Safety Feature trip value specified by Table 3.3-4.

• With irradiated fuel in the storage pool, t

ACTIONS 13,16,17,17a and 17b are repeated from Table 3.3-3 for reference.

g SAN ONOFRE-UNIT 2 3/4 3-37 AMENDMENT NO. 31

,m m...,

E TABLE 4.3-3

~

S; RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS El e

CHANNEL MODES FOR WHICH 5

H CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CALIBRATION TEST IS REQUIRED 1.

Area Monitors a.

Containment - High Range S

R M

1, 2, 3, 4 (2RT-7820-1,2RT-7820-2) b.

Containment - Purge Isolation 5

(2)

M 1,2,3,4,6 (2RT-7856-1,2RT-7857-2)

^

c.

Main Steam Line 5

R M

1, 2, 3, 4 t'

(2RT-7874A,2RT-7875A,.

2RT-78748,2RT-78758) i M 2.

Process Monitors a.

Fuel Storage Pool Airborne (2RT-7822-1,2RT-7823-2) 1.

Gaseous

11. Particulate / Iodine b.

Containment Airborne (2RT-7804-1,2RT-7807-2) i.

Geseous 1,2,3,4,6 it.

Particulate 1,2,3,4,6 k

iii.

Iodine 6

El c.

Control Room Airborne (2/3RT-7824-1, 2/3RT-7825-2)

P i.

Particulate All z

ii. Gaseous All co n2 9

+

y

r TABLE 4.3-3 i

o

^

5 5

RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

'?

5 CHANNEL MODES FOR WHICH i.i.

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE

-INSTRUMENT CHECK CALIBRATION TEST IS REQUIRED w

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 r

4 i

NOTES:

1. n accordance with Table'4.3-2 surveillance requirements for these instrument channels.

I With irradiated fuel.in the storage pool.

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

5 (2) At least once per refueling interval.

56

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i 3675 i 110 VOLTS j

100

)

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1. 2800 VOLTS 2.6 t 0.13 SECONOS 0 VOLTS 1.0 t.05 SECONOS 3

1 1.0 2400 2000 3200 3600 4000 BUS VOLTAGE Figure 3.3-1 DEGRADED BUS VOLTAGE TRIP SETTING

\\

SAN ONOFRE-UNIT 2 3/4 3-40 e

-,s,

, - ~.. -

i j

MACTORCOOLANTSYSTEM 3/4.4.10 REACTOR COOLANT GAS VENT SYSTEM l

l LIMITING CONDITION FOR OPERATION 1

4 3.4.10 The Reictor Coolant Gas Vent System shall be OPERABLE with:

At least one of valves 2WC296A or 2WO2968 capable of being powered a.

free an emergency bus and providing a vent path from the reactor i

vessel head; and, I

b.

. At least one of valves 2WC297A or 2NV02978 capable of bding powered from an emergency bus and providing a vent path free the pressurizer i

steam space; and, c.

At least one of valves 2NV0294 capable of being powered from an, emergency bus and providing a v,ent path to the containment staosphere, or 2NV0299 capable of being powered from an emergency bus and providing a ven,t path to the quench tank; and d.

Valves 2WC296A, 2WC2968, 2NV0297A, 2WC2978, 2NY0299 and 2Nv0298 11J1, closed.

APPLICABILITY:

MODES 1, 2, 3'and 4 ACTION:

With any of valves 2NV0296A, 2HV0296b, 2NV0297A or 2NV02978 I

a.

(

inoperable, operation may continue provided that:

i) power is removed from the inoperable valve (s) within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; j

and, ii) valves 2HV0299 and 2WC298 are maintained closed and poe,er is removed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; and,

-iii) the inoperable valve (s) is restored to OPERABLE status during the next CMS SHUTDOWN.

b.

With any of valves 2WC299 or 2WC298 inoperable, operation may continue provided that:

)

1) power is removed free the inoperable valve (s) within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />;

and, 11) valves 2WC29&A, 2WO2968, 2WO297A and 2WO2978 are 3 i

maintained closed and power is removed within 4 heers;11, and l

i SAN ON0FRE - UNIT 2 3/4 4-35 AMENDMENT N0; $4 I

e

".. v REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION lii) the inoperable valve (s) is restored to OPERABLE status during the next COLD SHUTDOWN.

c.

The provisions of 3.0.4 are not applicable for entry into MODES 3, 2 and 1.

SURVEILLANCE REQUIREMENTS 4.4.10 Each reactor coolant system vent pa'th shall be demonstrated OPERABLE at least once per refueling interval by:

1.

Verifying all manual isolation valves in each vent path are locked in the open position.

2.

Cycling each valve in the vent path through at least one complete cycle of full travel from the control room during COLD SHUTDOWN or REFUELING. -

s 3.

Verifying flow through the reactor coolant vent system vent paths during venting during COLD SHUTDOWN.

4 e

e

' SAN ONOFRE - UNIT 2 3/4 4-36 AMEN 0 MENT NO. 82 f

i

~

i 3

l ATTACHMENT T0-LICENSE AMENDMENT NO. 82 i

f 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 area of change.

Also enclosed are the following overleaf pages to the amended pages.

AMENDMENT PAGE OVERLEAF PAGE 3/4 3-33 3/4 3-34 3/4 3-38 3/4 3-37 3/4 3-39 3/4 3-40 l

3/4 4-36 3/4 4-35 4

P

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t t

e v-

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