ML20196J444

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Amends 140 & 132 to Licenses NPF-2 & NPF-8,respectively, Changing TSs to Revise Intermediate Range Neutron Flux Reactor Trip Setpoint & Allowable Valus & Delete Ref to Reactor Trip Setpoints in TS 3.10.3
ML20196J444
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 12/08/1998
From: Berkow H
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20196J450 List:
References
NUDOCS 9812100068
Download: ML20196J444 (14)
v • d • e


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UNITED STATES j

j NUCLEAR REGULATORY COMMISSION t

WASHINGTON, D.C. ma "1

'44.....,o SOUTHERN NUCLEAR OPERATING COMPANY. INC.

ALABAMA POWER COMPANY DOCKET NO. 50-348 JOSEPH M. FA8tEY NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.140 License No. NPF-2

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

A. The application for amendment by Southern Nuclear Operating Company, Inc.

(Southern Nuclear), dated December 31,1997, as supplemented by letter dated September 11,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; A

B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 4

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 Commission's regulations; D. The issuance of this license amendment will not be inimical to the common defense and l

security or to the health and safety of the public; and l

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.

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

9812100068 481208 i

PDR ADOCK 05000348 P

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(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through j

Amendment No.140, are hereby incorporated in the license. Southern Nuclear shall i

operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days ofissuance.

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FOR THE NUCLEAR REGULATORY COMMISSION i

rt N. Berkow, Director roject Directorate 11-2 Division of Reactor Projects - 1/11 i

Office of Nuclear Reactor Regulation 1

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Attachment:

Changes to the Technical Specifications Date ofissuance:

December 8, 1998

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ATTACHMENT TO LICENSE AMENDMENT NO. 140 TO FACILITY OPERATING LICENSE NO. NPF-2 i

L DOCKET NO. 50-348 i

Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.

i Remove inand 2-5 2-5 i

B24 B24 l

3/4 10-3 3/4 10-3 3/4104 3/4 10-4 l

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TAB 2,E 2.2-1 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS hp E11NCTIONAL UNIT-TRIP SETPOINT ALLOWABLE VALUES 0

1.

Manual Reactor Trip Not Applicable Not Applicable by 2.

Power Range, Neutron Flux Low Setpoint - s 25% of RATED Low Setpoint - 5 25.4% of RATED THERMAL POWER THERMAL POWER g

High Setpoint - 5 109% of RATED High Setpoint - s 109.4% of RATED THERMAL POWER THERMAL POWER 3.

Power Range, Neutron Flux, s 5% of RATED THERMAI. POWCP. with 5 5.4% of RATED THERMAL POWER High Positive Rate a time constant 2 2 seconds with a time constant 2 2 seconds 4.

Power Range, Neutron Flux, s 5% of RATED THERMAL POWER with s 5.4% of RATED THERMAL POWER High Negative Rate a time constant 2 2 seconds with a time constant 2 2 seconds 5.

Intermediate Range, Neutron s 35% of RATED THERMAL POWER s 40% of RATED THERMAL POWER l

Flux g

e" 6.

Source Range, Neutron Flux 5 105 counts per second s 1.3 X 105 counts per second 7.

Overtemperature AT See Note 1 See Note 3 8.

Overpower AT See Note 2 See Note 6 9.

Pressurizer Pressure--Low 2 1865 psig 2 1862 psig 10.

Pressurizer Pressure--High s 2385 psig s 2388 psig

11. Pressurizer Water s 92% of instrument span s 92.4% of instrument span Level--High 9O
12. Loss of Flow 2 90% of minimum measured flow 2 89.7% of minimum measured flow z

per loop

  • per loop *

=

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  • Minimum measured flow is 88,100 gpm per loop.

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LIMITING SAFETY SYSTEM SETTINGS BASES Intermediate and Source Rance. Nuclear Flux The Intermediate and Source Range, Nuclear Flux trips provide reactor core protection during reactor startup. These trips provide redundant protection to the low setpoint trip of the Power Range, Neutron Flux channels. The Source Range Channels will initiate a reactor trip at about 10+5 counts per second unless manually blocked when P-6 becomes active. The Intermediate Range Channels will initiate a reactor trip at a current level proportional to approximately 35 percent of RATED THERMAL POWER unless l

manually blocked when P-10 becomes active. No credit was taken for operation of the trips associated with either the Intermediate or Source Range Channels in the accident analyses; however, their functional capability at the specified trip settings is required by this specification to enhance the overall reliability of the Reactor Protection System.

Overtemperature AT The overtemperature delta T trip provides core protection to prevent DNB for all combinations of pressure, power, coolant temperature, and axial power distribution, provided that the transient in slow with respect to piping transit, thermowell, and RTD response time delays from the core to the temperature detectors (about 4 seconds), and pressure is within the range between the High and Low Pressure reactor trips. This setpoint includes corrections for changes in density and heat capacity of water with temperature and dynamic compensation for transport, thermowell, and RTD response time delays from the core to RTD output indication.

With normal axial power distribution, this reactor trip limit is always below the core safety limit as shown in Figure 2.1-1.

If axial peaks are greater than design, as indicated by the difference between top and bottom power range nuclear detectors, the reactor trip is automatically reduced according to the notations in Table 2.2-1.

Operation with a reactor coolant loop out of service below the 3 loop P-8 setpoint does not require reactor protection system setpoint modification because the P-8 setpoint and associated trip will prevent DNB during 2 loop operation exclusive of the overtemperature delta T setpoint.

Two loop operation above the 3 loop P-8 setpoint is permissible after resetting the K1, K2, and K3 inputs to the overtemperature delta T channels and raising the P-8 setpoint to its 2 loop value.

In this mode of operation, the P-8 interlock and trip functions as a High Neutron Flux trip at the reduced power level.

FARLEY-UNIT 1 B 2-4 AMENDMENT No. 26,87,140

SPECIAL TEST EXCEPTIONS 3/4.10.3 PHYSICS TESTS LIMITING CONDITION FOR OPERATION 3.10.3 The limitations of Specifications 3.1.1.3, 3.1.1.4, 3.1.3.1, 3.1.3.5 and 3.1.3.6 may be suspended during the performance of PHYSICS TESTS provided:

The THERMAL POWER does not exceed 5% of RATED THERMAL POWER, and a.

b.

The Reactor Coolant System lowest operating loop temperature (Tavg) is greater than or equal to 531*F.

APPLICABILITY:

MODE 2.

ACTION:

With the THERMAL POWER greater than 5% of RATED THERMAL POWER, a.

immediately open the reactor trip breakers.

b.

With a Reactor Coolant System operating loop temperature (Tavg) less than 531'F, restore T to within its limit within 15 minutes or be avg in at least HOT STANDBY within the next 15 minutes.

SURVEILLANCE REQUIREMENTS 4.10.3.1 The THERMAL POWER shall be determined to be less than or equal to 5%

of RATED THERMAL POWER at least once per hour during PHYSICS TESTS.

4.10.3.2 Each Intermediate and Power Range Channel shall be subjected to a CHANNEL FUNCTIONAL TEST within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to initiating PHYSICS TESTS.

l 4.10.3.3 The Reactor Coolant System temperature (Tav ) shall be determined to be greater than or equal to 531'F at least once per 30 minutes during PHYSICS TESTS.

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k FARLEY-UNIT 1 3/4 10-3 AMENDMENT NO.26,140

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SPECIAL TEST EXCEPTIONS 3/4.10.4 REACTOR COOLANT LOOPS LIMITING CONDITION FOR OPERATION 3.10.4 The limitations of Specification 3.4.1.1 may be suspended during the performance of start up and PHYSICS TESTS provided the THERMAL POWER does not exceed the P-7 Interlock Setpoint.

APPLICABILITY:

During operation below the P-7 Interlock Setpoint.

ACTION:

With the THERMAL POWER greater than the P-7 Interlock Setpoint, immediately open the reactor trip breakers.

SURVEILLANCE REQUIREMENTS 4.10 1.1 The THERMAL POWER shall be determined to be less than P-7 Interlock Setpoint at least once per hour during start up and PHYSICS TESTS.

4.10.4.2 Each Intermediate, Power Range Channel and P-7 Interlock shall be subjected to a CHANNEL FUNCTIONAL TEST within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to initiating start up and PHYSICS TESTS.

t FARLEY-UNIT 1 3/4 10-4 AMENDMENT NO. 26,140 j

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1 UNITED STATES

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NUCLEAR REGULATORY COMMISSION

  • A, f

wAsMWGTON. D.C. 30006 40M

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i SOUTHERN NUCLEAR OPERATING COMPANY. INC.

ALABAMA POWER COMPANY l

DOCKET NO. 50-364

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JOSEPH M FARLEY NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE j

i l

1 Amendment No. 132 i

License No. NPF-8 f

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

A. The application for amendment by Southern Nuclear Operating Company, Inc.

(Southern Nuclear), dated December 31,1997, as supplemented by letter dated

- September 11,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and f

the rules and regulations of the Commission-

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i C. There is reasonable assurance (i) that the activities authorized by this amendment can l

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; j

D. The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and j

i 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.

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2. Accordingly, the license is amended by changes to the Technical Specifications, as l

indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility l

Operating License No. NPF-8 is hereby amended to read as follows:

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! l (2) Technical Soecifications I

The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 132, are hereby incorporated in the license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications.

j

3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days ofissuance.

l FOR THE NUCLEAR REGULATORY COMMISSION

(

i

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H rt N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - 1/11 l

Office of Nuclear Reactor Regulation j

Attachment:

Changes to the Technical Specifications Date of Issuance:

December 8,1998 i

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1

a ATTACHMENT TO LICENSE AMENDMENT NO.132 TO FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 I

I Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginallines.

Remove Insert 2-5 2-5 B 2-4 B 2-4 3/4 10-3 3/4 10-3 3/4 10-4 3/4 10-4 l

l i

TABLE 2n2-1 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS h

FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES n

g 1.

Manusi Reactor Trip Not Applicable Not Applicable 2.

Power Range, Neutron Flux Low Setpoint - 5 25% of RATED Low Setpoint - s 25.4% of RATED THERMAL POWER THERMAL POWER t

High Setpoint - s 109% of RATED High Setpoint - s 109.4% of RATED THERMAL POWER THERMAL POWER 3.

Power Range, Neutron Flux, s 5% of RATED THERMAL POWER with 5 5.4% of RATED THERMAL POWER High Positive Rate a time constant 2 2 seconds with a time constant 2 2 seconds 4.

Power Range, Neutron Flux, 5 5% of RATED THERMAL POWER with s 5.4% of RATED THERMAL POWER High Negative Rate a time constant 2 2 seconds with a time constant 2 2 seconds 5.

Intermediate Range, Neutron 5 35% of RATED THERMAL POWER s 40% of RATED THERMAL POWER l

Flux g

I 6.

Source Range, Neutron Flux 5 105 counts per second s 1.3 K 105 counts per second 7.

Overtemperature AT See Note 1 See Note 3 8.

Overpower AT See Note 2 See Note 6 I

9.

Pressurizer Pressure--Low 2 1865 psig 2 1862 peig

10. Pressurizer Pressure--High 5 2385 pelg s 2388 psig
11. Pressurizer Water s 92% of instrument span s 92.4% of instrument span Level--High hg
12. Loss of Flow 2 90% of minimum measured flow 2 89.7% of minimum measured flow g

per loop

  • per loop
  • t N

5

  • Minimum measured flow is 88,100 gpm per loop.

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. ~.

4 8

t LIMITING SAFETY SYSTEM SETTINGS BASES Intermediate and Source Rance, Nuclear Flux The Intermediate and Source Range, Nuclear Flux trips provide reactor core protection during reactor startup. These trips provide redundant protection to the low setpoint trip of the Power Range, Neutron Flux channels.

The Source Range Channels will initiate a reactor trip at about 10+5 counts per second unless manually blocked when P-6 becomes active. The Intermediate Range Channels will initiate a reactor trip at a current level proportional to approximately 35 percent of RATED THERMAL POWER unless manually blocked when l

P-10 becomes active. No credit was taken for operation of the trips associated with either the Intermediate or Source Range Channels in the accident analyses; however, their functional capability at the specified trip settings is required by this specification to enhance the overall reliability of the Reactor Protection System.

Overtemperature AT The Overtemperature delta T trip provides core protection to prevent DNB for all combinations of pressure, power, coolant temperature, and axial power distribution, provided that the transient is slow with respect to piping transit, thermowell, and RTD response time delays from the core to the temperature detectors (about 4 seconds), and pressure is within the range between the High and Low Pressure reactor trips. This setpoint includes corrections for changes in density and heat capacity of water with temperature J

and dynamic compensation for transport, thermowell, and RTD response time i

delays from the core to RTD output indication. With normal axial power distribution, this reactor trip limit is always below the core safety limit as shown in Figure 2.1-1.

If axial peaks are greater than design, as indicated by the difference between top and bottom power range nuclear detectors, the reactor trip is automatically reduced according to the notations in Table 2.2-1.

Operation with a reactor coolant loop out of service below the 3 loop P-8 setpoint does not require reactor protection system setpoint modification because the P-8 setpoint and associated trip will prevent DNB during 2 loop i

operation exclusive of the overtemperature delta T setpoint.

Two loop operation above the 3 loop P-8 setpoint is permissible after resetting the K1, K2, and K3 inputs to the overtemperature delta T channels and raising the P-8 setpoint to its 2 loop value.

In this mode of operation, the P-8 interlock and trip functions as a High Neutron Flux trip at the reduced power level.

FARLEY-UNIT 2 B 2-4 AMENDMENT No.85,132

e a e SPECIAL TEST EXCEPTIONS 3/4.10.3 PHYSICS TESTS LIMITING CONDITION FOR OPERATION 3.10.3 The limitations of Specifications 3.1.1.3,.3.1.1.4, 3.1.3.1, 3.1.3.5 and 3.1.3.6 may be suspended during the performance of PHYSICS TESTS provided:

a.

The THERMAL POWER does not exceed 5% of RATED THERMAL POWER, and b.

The Reactor Coolant System lowest operating loop temperature (Tavg) is greater than or equal to 531'F.

APPLICABILITY:

MODE 2.

ACTION:

With the THERMAL POWER greater than 5% of RATED THERMAL POWER, a.

immediately open the reactor trip breakers.

i b.

With a Reactor Coolant System operating loop temperature (Tavg) less than 531*F, restore T to within its limit within 15 minutes or be avg in at least HOT STANDBY within the next 15 minutes.

r SURVEILLANCE REQUIREMENTS 4.10.3.1 The THERMAL POWER shall be determined to be less than or equal to 5%

of RATED THERMAL POW 1:R at least once per hour during PHYSICS TESTS.

4.10.3.2 Each Intermediate and Power Range Channel shall be subjected to a l

CHANNEL FUNCTIONAL TEST within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to initiating PHYSICS TESTS.

4.10.3.3 The Reactor Coolant System temperature (Tavg) shall be determined to l

be greater than or equal to 531'F at least once per 30 minutes during PHYSICS TESTS.

9 l

2 FARLEY-UNIT 2 3/4 10-3 AMENDMENT No.132 1

SPECIAL TEST EXCEPTIONS 3/4.10.4 REACTOR. COOLANT LOOPS LIMITING CONDITION FOR OPERATION j

i 3.10.4 The limitations of Specification 3.4.1.1 may be suspended during the i

performance of start up and PHYSICS TESTS provided the THERMAL POWER does not exceed the P-7 Interlock Setpoint.

l APPLICABILITY:

During operation below the P-7 Interlock Setpoint.

h,CTION:

With the THERMAL POWER greater than the P-7 Interlock Setpoint, immediately open the reactor trip breakers.

SURVEILLANCE REQUIREMENTS 4.10.4.1 The THERMAL POWER shall be determined to be less than P-7 Interlock

{

Setpoint at least once per hour during startup and PHYSICS TESTS.

i 4.10.4.2 Each Intermediate, Power Range Channel and P-7 Interlock shall be subjected to a CHANNEL FUNCTIONAL TEST within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to initiating start up and PHYSICS TESTS.

j i

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1 1

FARLEY-UNIT 2 3/4 10-4 AMENDMENT NO.

132

.

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