Text

Amends 115 & 104 to Licenses NPF-10 & NPF-15,respectively, Revising TS Table 3.3-1, Reactor Protective Instrumentation, to Allow Use of Source Range Neutron Flux Monitors in Place of safety-related Excore Monitors
	ML20078Q389
Person / Time
Site:	San Onofre
Issue date:	02/13/1995
From:	Fields M; Office of Nuclear Reactor Regulation
To:	;
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ML20078Q391	List: ML20078Q389; ML20078Q410;
References
	NUDOCS 9502210231
	Download: ML20078Q389 (15)
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'o, UNITED STATES i

NUCLEAR REGULATORY COMMISSION

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WASHINGTON, D.C. 20E86-0001

,.P 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 Amendment No.115 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 December 30, 1993, as supplemented by letters dated June 3, 1994, August 25, 1994, and January 3, 19, and 30, 1995, complies 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;

i B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 Commission'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.

n**iB8u ? 4" 2.

P j

. 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 Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.115, 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 its issuance and must be fully implemented no later than 30 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMISSION 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:

February 13, 1995 i

~

i ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.115 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 the captioned 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 3-3 3/4 3-3 3/4 3-4 3/4 3-4 3/4 3-6 3/4 3-6

IABLE 3.3-1 REACTOR PROTECTIVE INSTRUNENTATION u,

E MINIMUM o

TOTAL NO.

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

=

1.

Manual Reactor Trip 2 sets of 2 1 set of 2 2 sets of 2 1, 2 1

[

2 sets of 2 1 set of 2 2 sets of 2 3*, 4*, 5*

7A zZ 2.

Linear Power Level - High 4

2 3

1, 2 2f,3#

~

3.

Logarithmic Power Level - High a.

Startup and Operating 4

2(a)(d) 3 1, 2 2#,3f 4

2 3

3*, 4*, 5*

7A b.

Shutdown 4

0 2**

3,4,5 4

l 4.

Pressurizer Pressure - High 4

2 3

1, 2 2f,3#

5.

Pressurizer Pressure - Low 4

2(b) 3 1, 2 2f,3f w

6.

Containment Pressure - High 4

2 3

1, 2 2f,3#

7.

Steam Generator Pressure - Low 4/SG 2/SG 3/SG 1, 2 2#,3#

'f 8.

Steam Generator Level Low 4/SG 2/SG 3/SG 1, 2 2f,3#

w 9.

Local Power Density - High 4

2(c)(d)(e) 3 1, 2 2f,3#

10. DNBR - Low 4

2(c)(d)(e) 3 1, 2 2f,3#

11. Steam Generator Level - High 4/SG 2/SG 3/SG 1, 2 28,3#

12. Reactor Protection System Logic 4

2 3

1, 2 2f,3#

3*, 4*, 5*

7A

13. Reactor Trip Breakers 4

2(f) 4 1, 2 5

3*, 4*, 5*

7A

14. Core Protection Calculators 4

2(c)(d)(e) 3 1, 2 2#,3f,7

15. CEA Calculators 2

1 2(e) 1, 2 6#,7 g

16. Reactor Coolant Flow - Low 4/SG 2/SG 3/SG 1, 2 2#,3#

m g

17. Seismic - High 4

2 3

1, 2 2#,38

18. Loss of Load 4

2 3

1(g) 2f,38 g

m l

ll v,

t TABLE 3.31 (Centinutd)

TABLE NOTATION

With the protective system trip breakers in the closed position, the CEA drive system capable of CEA withdrawal, and fuel in the reactor vessel.

- The source range neutron flux monitors may be used in Modes 3, 4, and 5 with the reactor trip circuit breakers open or the Control Element Assembly (CEA)

Drive System not capable of CEA withdrawal.

The provisions of Specification 3.0.4 are not applicable.

(a) Trip may be manually bypassed above lod' of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is less than or equal to 10** of RATED THERMAL POWER.

(b) Trip may be manually bypassed below 400 psia; bypass shall be automatically removed whenever pressurizer pressure is greater than or equal to 400 psia.

(c)

Trip may be manually bypassed below 10"' of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is greater than or equal to 10*' of RATED TIRMAL POWE4. During testing pursuant to Special Test Exception 3.10.2 or 3.10.3, trip may be manually bypassed below 5% of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is greater than or equal to 5% of RATED THERMAL POWER.

t (d)

Trip may be bypassed during testing pursuant to Special Test Exception 3.10.3.

(e)

See Special Test Exception 3.10.2.

(f)

Each channel shall be comprised of two trip breakers; actual trip logic-shall be one-out-of-two taken twice.

(

(g) Trip may be bypassed below 55% RATED THERMAL POWER.

ACTION STATEMENTS ACTION 1 With the number of channels OPERABLE one less than required by t

the Minimum Channels OPERABLE requirement, 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/or open the protective system trip breakers.

ACTION 2 With the number of channels OPERABLE one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may continue l

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

If the inoperable channel is bypassed, the desirability of inaintaining this channel in the bypassed condition shall be redewed 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 l

SAN ONOFRE - UNIT 2 3/4 3-4 AMENDMENT N0.-44 115 v-m-m w

wr

TABLE 3.3-1 (Continued)

ACTION STATEMENTS 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:

Proces2 Measurement Circuit Functional Unit Bypassed 1.

Linear Power Linear Power Level - High (Subchannel or Linear)

Local Power Density - High DNBR - Low l

2.

Pressurizer Pressure - High Pressurizer Pressure - High Local Power Density - High j

DNBR - Low 3.

Containment Pressure - High Containment Pressure - High (RPS)

Containment Pressure - High (ESF) 4.

Steam Generator Pressure -

Steam Generator Pressure - Low Low Steam Generator AP 1 and 2 (EFAS I and 2) 5.

Steam Ger.erator Level Steam Generator Level - Low

\\'

Steam Generator Level - High Steam Generator AP (EFAS) i 6.

Core Protection Calculator Local Power Density - High DNBR - Low l

ACTION 3 - With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement, 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 channel in the tripped condition within I hour, and b.

All functional units affected by the bypassed / tripped channel i

shall also be placed in the bypassed / tripped condition as i

listed below:

Process Measurement Circuit Functional Unit Bypassed / Tripped 1.

Linear Power Linear Power level - High (Subchannel or Linear)

Local Power Density - High DNBR - Low I

SAN ON0FRE - UNIT 2 3/4 3-5 1

TABLE 3.3-1 (Continued) j TABLE NOTATION 2.

Pressurizer Pressure -

Pressurizer Pressure - High High Local Power Density - High DNBR - Low 3.

Containment Pressure -

Containment Pressure - High (RPS)

High Containment Pressure - High (ESF) j i

4.

Steam Generator Steam Generator Pressure - Low i

Pressure - Low Steam Generator AP 1 and 2 (EFAS I and 2) f 5.

Steam Generator Level Steam Generator Level - Low I

Steam Generator Level - High i

Steam Generator AP (EFAS) 6.

Core Protection Local Power Density - High Calculator DNBR - Low STARTUP and/or POWER OPERATION may continue until the performance of the next required CHANNEL FUNCTIONAL TEST. Subsequent STARTUP and/or POWER OPERATION may continue if one channel is restored to OPERABLE status and the provisions of ACTION 2 are satisfied.

ACTION 4 - With the number of channels OPERABLE one or more less than required by the Minimum Channels OPERABLE requirement, immediately suspend all operations involving positive reactivity changes and within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter perform shutdown margin verification in accordance with Specification 4.1.1.1.1 if T is greater than 200*F or Specification 4.1.1.2 if T, is less ten or equal to 200*F.

ACTION 5 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 6 -

a.

With one CEAC inoperable, operation may continue for up to 7 days i

provided that at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , each CEA is verified to be within 7 inches (indicated position) of all other CEA's in its group. After 7 days, operation may continue provided that Action 6.b is met.*

If the exemption to Specification 3.0.4 is used, Action 6.b must be met.

b.

With both CEACs inoperable, operation may continue provided that:*

1.

Within I hour the DNBR margin required by Specification 3.2.4.b (COLSS in service) or Specification 3.2.4.d (COLSS out of service) is satisfied.

f

Note:

Requirements for CEA position indication given in Technical Specification 3.1.3.2.

115 l

SAN ONOFRE - UNIT 2 3/4 3-6 AMENDMENT N0.-647

m pne,u f

UNITED STATES j

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 205864001 4...*$

SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE. CALIFORNIA THE CITY OF ANAHEIM. CALIFORNIA DOCKET NO. 50-362 SAN ONOFRE NUCLEAR GENERATING STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 104 License No. NPF-15 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 December 30, 1993, as supplemented by letters dated June 3, 1994, August 25, 1994, and January 3, 19, and 30, 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 (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the 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.

1

- 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 through Amendment No. 104, 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 its issuance and must be fully implemented no later than 30 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMISSION k

h 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:

February 13, 1995 s

b

{

i

ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.104 TO 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 the captioned 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 3-3 3/4 3-3 3/4 3-4 3/4 3-4 3/4 3-6 3/4 3-6 m

l l

l

TABLE 3.3-1 REACTOR PROTECTIVE INSTRUMENTATION MINIMUM g

TOTAL NO.

CHANNELS CHANNELS APPLICABLE

g FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION m

1.

Manual Reactor Trip 2 sets of 2 1 set of 2 2 sets of 2 1, 2 1

g 2 sets of 2 1 set of 2 2 sets of 2 3*, 4*, 5*

7A

[

2.

Linear Power Level - High 4

2 3

1, 2 2f,3f 3.

Logarithmic Power Level - High a.

Startup and Operating 4

2(a)(d) 3 1, 2 2#,3#

4 2

3 3*, 4*, 5*

7A b.

Shutdown 4

0 2**

3,4,5 4

l 4.

Pressurizer Pressure - High 4

2 3

1, 2 2f,3#

5.

Pressurizer Pressure - Low 4

2(b) 3 1, 2 2f,3#

w1 6.

Containment Pressure - High 4

2 3

1, 2 2#,3#

7.

Steam Generator Pressure - Low 4/SG 2/SG 3/SG 1, 2 2#,3#

w 4,

8.

Steam Generator Level Low 4/SG 2/SG 3/SG 1, 2 2f,3#

9.

Local Power Density - High 4

2(c)(d)(e) 3 1, 2 2#,3f

10. DNBR - Low 4

2(c)(d)(e) 3 1, 2 2f,3f

11. Steam Generator Level - High 4/SG 2/SG 3/SG 1, 2 2f,3f

12. Reactor Protection System logic 4

2 3

1, 2 2#,3#

3*,

4*, 5*

7A

13. Reactor Trip Breakers 4

2(f) 4 1, 2 5

3*, 4*, 5*

7A g

14. Core Protection Calculators 4

2(c)(d)(e) 3 1, 2 2f,3f,7 g

15. CEA Calculators 2

1 2(e) 1, 2 6f,7 g

16. Reactor Coolant Flow - Low 4/SG 2/SG 3/SG 1, 2 2f,3#

17. Seismic - High 4

2 3

1, 2 2f,3#

m5

18. Loss of Load 4

2 3

1(g) 2#,37 5

W

TABLE 3.3-1 (Continued)

TABLE NOTATION

With the protective system trip breakers in t.ie cloud position, the CEA drive system capable of CEA withdrawal, and fuel in de reactor vessel.

- The source range neutron flux monitors may be el in Modes 3, 4, and 5 with the reactor trip circuit breakers open or the Contrui Element Assembly (CEA)

Drive System not capable of CEA withdrawal.

The provisions of Specification 3.0.4 are not applicable.

(a) Trip may be manually bypassed above 10% of RATED THERMAL POWER; bypass shall pe automatically removed when THERMAL POWER is less than or equal to 10% of RATED THERMAL POWER.

(b) Trip may be manually bypassed below 400 psia; bypass shall be automatically removed whenever pressurizer pressure is greater than or equal to 400 psia.

(c) Trip may be manually bypassed below 10% of RATED THERMAL POWER; bypass to 10'p% of RATED THERMAL POWER.e automatically removed when THERMAL POW shall During testing pursuant to Special Test i

Exception 3.10.2 or 3.10.3, trip may be manually bypassed below 5% of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is greater than or equal to 5% of RATED THERMAL POWER.

(d) Trip may be bypassed during testing pursuant to Special Test Exception 3.10.3.

(e) See Special Test Exception 3.10.2.

4 (f)

Each channel shall be comprised of two trip breakers; actual trip logic shall be one-out-of-two taken twice.

(g) Trip may be bypassed below 55% RATED THERMAL POWER.

ACTION STATEMENTS With the number of channels OPERABLE one less than required by AC110N 1 the Minimum Channels OPERABLE requirement, restore the inoper-able channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in tt least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and/or open the pro-tective system trip breakers.

ACTION 2 -

With the number of channels OPERABLE one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may continue provided 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 condition shall be reviewed in accordance with Specifi-cation 6.5.1.6e.

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

SAN ON0FRE - UNIT 3 3/4 3-4 AMENDMENT NO. % 104

i TABLE 3.3-1 (Continued) i i

ACTION STATEMENTS 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.

Linear Power Linear Power Level - High (Subchannel or Linear)

Local Power Density - High DNBR - Low 2.

Pressurizer Pressure - High Pressurizer Pressure - High Local Power Density - High DNBR - Low 3.

Containment Pressure - High Containment Pressure - High (RPS)

Containment Pressure - High (ESF) 4.

Steam Generator Pressure -

Steam Generator Pressure - Low Low Steam Generator AP 1 and 2 (EFAS I and 2) 5.

Steam Generator Level Steam Generator level - Low Steam Generator Level - High Steam Generator AP (EFAS) 6.

Core Protection Calculator Local Power Density - High DNBR - Low ACTION 3 - With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement, 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 channel in the tripped condition within I hour, and b.

All functional units affected by the bypassed / tripped channel shall also be placed in the bypassed / tripped condition as listed below:

Process Measurement Circuit Functional Unit Bypassed / Tripped 1.

Linear Power Linear Power Level - High (Subchannel or Linear)

Local Power Density - High DNBR - Low SAN ON0FRE - UNIT 3 3/4 3-5

r

~

TABLE 3.3-1 (Continued)

TABLE NOTATION 2.

Pressurizer Pressure -

Pressurizer Pressure - High High Local Power Density - High DNBR - Low

]

3.

Containment Pressure -

Containment Pressure - High (RPS)

High Containment Pressure - High (ESF) 4.

Steam Generator Steam Generator Pressure - Low Pressure - Low Steam Generator AP 1 and 2

)

(EFAS I and 2) 5.

Steam Generator Level Steam Generator Level - Low Steam Generator Level - High Steam Generator AP (EFAS) 6.

Core Protection Local Power Density - High Calculator DNBR - Low STARTUP and/or POWER OPERATION may continue until the performance of the next required CHANNEL FUNCTIONAL TEST.

Subsequent STARTUP and/or POWER OPERATION may continue if one channel is restored to OPERABLE status and the provisions of ACTION 2 are satisfied.

ACTION 4 - With the number of channels OPERABLE one or more less than required by the Minimum Channels OPERABLE requirement, immediately suspend all operations involving positive reactivity changes and within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter perform shutdown margin verification in accordance with Specification 4.1.1.1.1 if T is greater than 200*F or Specification 4.1.1.2 if T is less tEan or equal to 200*F.

y ACTION 5 - With the number of channels OPERABLE one less than required by the Minimum Channels OPFRABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 6 -

a.

With one CEAC inoperable, operation may continue for up to 7 days provided that at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , each CEA is verified to be within 7 inches (indicated position) of all other CEA's in its group. After 7 days, operation may continue provided that Action 6.b is met.*

If the exemption to Specification 3.0.4 is used, Action 6.b must be met.

b.

With both CEACs inoperable, operation may continue provided that:*

1.

Within I hour the DNBR margin required by Specification 3.2.4.b (COLSS in service) or Specification 3.2.4.d (COLSS out of service) is satisfied.

Note: Requirements for CEA position indication given in Technical Specification 3.1.3.2.

SAN ONOFRE - UNIT 3 3/4 3-6 AMENDMENT NO. +3,104

-

ML20078Q389

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