ML20082G423

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Amends 114 & 105 to Licenses NPF-2 & NPF-8,respectively, Allowing Mods to Be Made for Both Units to Relocate Lower Level SG Water Level Taps During Upcoming Refueling Outages
ML20082G423
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 04/07/1995
From: Berkow H
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20082G426 List:
References
NUDOCS 9504130246
Download: ML20082G423 (12)
v • d • e


Text

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,s UNITED STATES j

NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 205MWm01 d

4.....s SOUTHERN NUCLEAR OPERATING COMPANY. INC.

DOCKET NO. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 114 License No. NPF-2 1.

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

A.

The application for amendment by Southern Nuclear Operating Company, Inc. (Southern Nuclear), dated June 10, 1995, complies with the standards and requirements of the Atcmic 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 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 Commission's regulations; D.

The issuance of this license amendment will not be inimical to the common defense and se:urity 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.

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:

p 9504130246 950407 PDR ADOCK 05000348 P

PDR

, (2)

Technical Soecifications

.The Technical Specifications contained in Appendices A and B, as 1

revised through Amendment No. 114, are hereby incorporated in the license.

Southern Nuclear shall 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 prior to restart from the next refueling outage.

FOR THE NUCLEAR REGULATORY COMMISSION erbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - I/II-Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: April 7, 1995 I

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ATTACHMENT TO LICENSE AMENDMENT NO.114 TO FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO. 50-348 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.

Remove Paaes Insert Paagt 2-6 2-6 3/4 3-27 3/4 3-27 3/4 3-28 3/4 3-28 n.

M TABLE 2.2-1 (Continued) a 8

k REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT AT T AlalARLR VALUES w

13. Steam Generator Water 2 25% of narrow range 2 23.3% of narrow range instrument

[

Level--Low-Low instrument span - each.

span - each steam generator steam generator

14. Deleted i
15. Undervoltage - Reactor 2 2680 volts-- each bus 2 2640 volts - each bus Coolant Pumps i
16. Underfrequency 2.57.0 Hz - each bus 2 56.9 Hz - each. bus Reactor Coolant Pumps
17. Turbine Trip A. Low Auto Stop 2 45 psig 2 43 psig i

Pressure B. Turbine Stop Valve Not Applicable Not Applicable Closure

18. Safety Injection Input Not Applicable Not Applicable from ESF
19. Reactor Coolant Pump Not Applicable Not Applicable Breaker Position Trip

,E B

M 5

w

.;. ~.

v TABLE 3.3-4 icontinued).

Np ENGINEERED SAFETY FEA'n.1RE ACTUATION SYSTEM TNvrutIMNPATION TRIP SETPOINTS M

7 FUNCTIONAL UNIT TRIP SETPOIFP ALIINABLE_ VALUES siy 4.

STEAM LINE ISOLATION a.

Manual Not Applicable Not applicable b.

Automatic Actuation Not Applicable Not Applic@le -

Logic c.

Containment Pressure--

5 16.2 psig 5 17.5 psig High-High d.

Steam Flow in Two S A function defined S A function defined Steam Lines--High, as follows:

defined as_follows:

Coincident with A Ap corresponding to A Ap corresponding to 44t' Tavg--Low-Low 40% of full steam of full steam flow between flow between On and 04 and 20% load and then-20% load and then a ap a Ap increasing linearly:

R increasing linearly to to a Ap corresponding to a Ap corresponding to 111.5% of full steam-flow at y

110% of full steam full load with T vg 2 540*F a

w flow at full load with T 2 543'F avg e.

Steam Line Pressure--Low 2 585 psig.

2 575 psig-5.

TURBINE TRIP AND FEED WATER ISOLATION

.l a.

Steam Generator Water 5 79.2% of narrow range 5-80.5% of narrow range l-g Level--High-High instrument span each instrument span each steam generator steam generator 8

met

=

~

~

~~

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM h

INSTRUM13FPATION TRIP SETPOINTS g

FUNCTIONAL UNIT TRIP SETPOINT M

Ar rmant.r VAT.rfEs 7

6.

AUXILIARY FEEDWATER liy.

a.

Automatic Actuation N.A.

Logic N.A.

b.

Steam Genarator Water 2 25% of narrow range 2 23.3% of narrow range

.l Level--Low-Low instrument span each instrument. span each steam steam generator

~

generator c.

Undervoltage - RCP 2 2680 volts 2 2640 volts d.

S.I.

See 1 above (all SI setpoints) e.

Trip of Main:Feedwater N.A.

Pumps N.A.

4 7.

LOSS OF POWER w

a.

4.16 kv Emergency Bus 2 3255 volts bus 2 3222. volts. bus voltage

. voltage

  • O Voltage) 5 3418 volts bus voltage
  • n b.

4.16 kv Emergency Bus 2 3675 volts bus 2 3638 volts bus voltage

  • 5 3749 volts bus voltage
  • Voltage) 8.

i.

ENGINEERED. SAFETY-FEATURE ACTUATION SYSTEM INTERLOCK 3 y

a.

Pressurizer Pressure,,P-ll 5 200,0 psig..

5 2010 psig b.

Low-Low T P-12

avg, (Increasing)-

54 4 *F -

5-547'F (Decreasing) 543*F 2 540*F 2

,0 c.

Steam Generator Level, P-14 (See 5. above) m O

d.

Reactor Trip,-P-4 N.A.

N.A.

  • Refer to appropriate relay' setting sheet. calibration requirements.

f C' %3 j

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?*i UNITED STATES j

j NUCLEAR REGULATORY COMMISSION -.

2 WASHINGTON, D.C. 2006dMM01 gi

'+9..

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.e SOUTHERN NUCLEAR OPERATING COMPANY. INC.

DOCKET NO. 50-364 JOSEPH N. FARLEY NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment 'No.105 License No. NPF-8 1.

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

A.

The application for amendment by Southern Nuclear Operating

. Company, Inc. (Southern Nuclear), dated June 10,'1994, 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 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 license 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.

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-8 is hereby amended to read as follows:

- l

]

4'

, (2)

Technical Soecifications j

The Technical Specifications contained in Appendices A and' B, as I

revised through Amendment No.105, are hereby incorporated in the i

license.' Southern Nuclear shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall l

be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 1

2 -

Her ert N. Berkow, Director-Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor. Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: April 7, 1995 4

4 4

J

ATTACHMENT'TO LICENSE AMENDMENT NO. 105 TO FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.

. Remove Paaes Insert Paaes 2-6 2-6 3/4 3-27 3/4 3-27 3/4 3-28 3/4 3-28 1

i 5

y ww n-

,,, ~ - -

TABLE 2.2-1 fContinued)-

E Q

REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS E

N-FUNCTIONAL UNIT TRIP SETPOINT AT 71%IABLE VALUES u

13. Steam Generator Water 2 25% of narrow-range.

2 23.3% of narrow range inst rument -

l' Level--Low-Low instrument span - each span - each steam generator steam generator

14. Deleted
15. Undervoltage - Reactor 2 2680 volts - each bus 2 2640 volts - each bus Coolant Pumps
16. Underfrequency 2 57.0 Hz - each bus 2 56.9 Hz - each bus Reactor Coolant Pumps
17. Turbine Trip A. Low Auto Stop 2 45 psig 2 43 psig g

a Pressure B. Turbine Stop Valve Not Applicable Not Applicable Closure

18. Safety Injection Input Not Applicable Not Applicable from ESF
19. Reactor Coolant Ptmp -

Not Applicable Not Applicable Breaker Position Trip-O O

U1

TABLE 3.3-4 (Continued)

>p ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SacrPOINTS m

7 FUNCTIONAL UNIT TRIP SETPOINT E

Ar.71%IABLE VALUES y

4.

STEAM LINE ISOLATION w

a.

Manual Not Applicable Not applicable b.

Automatic Actuation Not Applicable Not Applicable Logic c.

Containment Pressure--

5 16.2 psig 5 17.5 psig High-High d.

Steam Flow in Two S A function defined 5 A function defined Steam Lines--High, as follows:

defined as follows:

Coincident with A Ap corresponding to A Ap corresponding to 44%

Tavg--Low-Low 40% of full steam of full steam flow between flow between 0% and 0% and 20% load and then 20% load and then a Ap a Ap increasing linearly Z

increasing linearly to to a Ap corresponding to a

a Ap corresponding to 111.5% of full steam flow at y

110% of full steam full load with T 2 540*F avg w

flow at full load with.T 2 543*F avg e.

Steam Line Pressure--Low 2 585 psig 2 575 psig 5.

TURBINE TRIP AND FEED WATER ISOLATION a.

Steam Generator Water 5 79.2% of narrow range S 80.5% of narrow range l

Level--High-High instrument span each instrument span each Q

steam generator steam. generator Bx 2O O

U1

~

._-_--n.

=;

)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS p

FUNCTIONAL UNIT TRIP SETPOINT M

A7.f f%IABLE VALUES 7

6.

AUXILIARY FEEDWATER

~

Ey a.

Automatic Actuation N.A.

N.A.

Log 1C b.

Steam Generator Water 2 25% of narrow range 2 23.3% of narrow range l.

Level--Low-Low instrument span each instrument ypan each steam steam generator generator c.

Undervoltage - RCP 2 2680 volts 2 2640 volts d.

S.I.

See 1 above (all SI setpoints) e.

Trip of Main Feedwater N.A.

N.A.

Pumps 7.

LOSS OF POWER u,

a.

4.16 kv Emergency Bus 2 3255 volts bus 2 3222 volts bus voltage

  • un O

Voltage) 5 3418 volts bus voltage

  • m b.

4.16 kv Emergency Bus 2 3675 volts bus 2 3638 volts bus voltage

  • Voltage) 5 3749 volts bus voltage
  • 8.

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INTERLOCKS a.

Pressurizer' Pressure, P-11 5 2000 psig 5 2010 psig.

b.

Low-Low T (Increasingf,P-12 av 544*F S 547'F (Decreasing) 543*F 2 540*F z

.O c.

Steam Generator Level, P-14 (See 5. above) d.

Reactor Trip. P-4

'N.A.

N.A.

  • Refer to appropriate relay setting sheet calibration requirements.

= - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _

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