ML20059C450

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Amends 104 & 97 to Licenses NPF-2 & NPF-8,respectively, Changing TS to Eliminate Low Feedwater Reactor Trip & Reduce ST low-low Water Level Reactor Trip Safeguard Actuation Setpoint from 17% to 15% Narrow Range Span
ML20059C450
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 12/29/1993
From: Bajwa S
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20059C453 List:
References
NUDOCS 9401050217
Download: ML20059C450 (18)
v • d • e


Text

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UNITED STATES

[ g.)f )%i

,j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 s, w /

SOUTHERN NUCLEAR OPERATING COMPANY. INC, DOCKET NO. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 104 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 September 13, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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.

Thcre 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 license 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 satfor md.

2.

Accordingly, the license is amended oy 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:

1 i

i 9401050217 931229 PDR ADOCK 05000348 P

PDR i

b

. (2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 104, 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 startup from refueling outage 12.

FOR THE NUCLEAR REGULATORY COMMISSION S. Singh Bajwa, Acting Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

December 29, 1993 l,

1 I

o ATTACHMENT TO LICENSE AMENDMENT NO 104 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 Paoes Insert Paacs 2-6 2-6

-1 8 2-6 B 2-6 j

i 3/4 3-3 3/4 3-3 3/4 3-11 3/4 3-11 i

3/4 3-13 3/4 3-13 3/4 3-28 3j4 3-28

.l i

1 1

~

TABLE 2.2-1 (Continued) f REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES EE

13. Steam Generator Water 15% of narrow range instrument 2: 14.4% narrow range instrument l

El leve?.--Low - Low span - each steam generator span - each steam generator

14. Deleted l
15. Undervoltage - Reactor at 2680 volts - each bus 2: 2640 volts - each bus Coolant Pumps
16. Underfrequency - Reactor 2: 57.0 Hz - each bus 2: 56.9 HZ - each bus Coolant Pumps
17. Turbine Trip A.

Low Auto Stop at 45 psig at43 psig n.

Pressure i

B.

Turbine Stop Valve Not Applicable Not Applicable o,

closure

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

ha 5

h

,s

o LIMITING SAFETY SYSTEM SETTINGS BASES 2.2.1 (Continued) latter trip will ensure that the DNB design criterion is met during normal operational transients and anticipated transients when 2 loops are in i

operation and the Overtemperature delta T trip setpoint is adjusted to the i

value specified for all loops in operation. With the'0vertemperature delta T trip setpoint adjusted to the value specified for 2 loop operation, the P-8 trip at 66% RATED THERMAL POWER will ensure that the DNB design criterion is met during normal operational transients and anticipated transients with 2 loops in operation.

Steam Generator Water Level The Steam Generator Water Level Low-Low trip provides core protection by preventing operation with the steam generator water level below the minimum volume required for adequate heat removal capacity.

The specified setpoint provides allowances that there will be sufficient water inventory in the steam generators at the time of trip to allow for starting delays of the auxiliary feedwater system.

Undervoltace and Underfrecuency - Reactor Coolant Pumo Busses The Undervoltage and Underfrequency Reactor Coolant Pump bus-trips provide reactor core protection against DNB as a result of loss of voltage or.

underfrequency to more than one reactor coolant pump.

The specified setpoints assure a reactor trip signal is generated before the low flow trip setpoint FARLEY - UNIT 1 B2-6 AMENDMENT NO. 26,92,104

TABLE 3.3-1 (CONTINUED)

REACTOR TRIP SYSTEM INSTRUMENTATION MINIMUM s

FUNCTIONAL UNIT TOTAL NO.

CHANNELS CHANNELS APPLICABLE i2 0F CHANNELS TO TRIP OPERABLE MODES ACTION O

11.

Pressurizer Water level--High 3

2 2

1 7'

12.

A.

Loss of Flow - Single Loop 3/ loop 2/ loop in 2/ loop in I

7'

~

(Above P-8) any oper-each oper-ating loop ating loop B.

Loss of Flow - Two Loops 3/ loop 2/ loop in 2/ loop in 1

7' (Above P-7 and B ;w P-8) two oper-each oper-ating loops ating loop 13.

Stear Generator Water Level--

3/ loop 2/ loop in 2/ loop in 1,2 7'

Low-Low any oper-each oper-ating loops ating loop w1 14.

Deleted l

15.

Undervoltage - Reactor Coolant 3-2/ bus 2

2 1

7' Pumps w

16.

Underfrequency - Reactor Coolant 3-2/ bus 2

2 1

7' Pumps l

l L2

5 Eq TABLE 3.3-2 (Continued)

E REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES Z

FUNCTIONAL UNIT RESPONSE TIME 12.

A.

Loss of Flow - Single Loop s 1.0 seconds (Above P-8)

B.

Loss of Flow - Two Loops s 1.0 seconds (Above P-7 and Below P-8) 13.

Steam Generator Water Level--Low-Low s 2.0 seconds y

14. Deleted l

7

15. Undervoltage - Reactor Coolant Pumps s 1.2 seconds C
16. Underfrequency - Raactor Coolant Pumps s 0.6 seconds
17. Turbine Trip A.

Low Auto Stop 011 Pressure Not Applicable B.

Turbine Throttle Valve Closure Not Applicable 18.

Safety Injection Input from ESF Not Applicable 19.

Reactor Coolant Pump Breaker Position Trip loot Applicable 20.

Reactor Trip System Interlocks Not Applicable 21.

Reactor Trip Breakers Not Applicable "i

22. Automatic Trip Logic Not Applicable g

n

m TABLE 4.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS N

r-O CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNTIONAL UNIT CHECK CALIBRATION TEST REQUIRED s

C5 13.

Steam Generator Water S

R M

1, 2

[

-Level--Low-Low r

14. Deleted l
15. Undervoltage --Reactor N.A.

R M.

1 Coolant Pumps

16. Underfrequency - Reactor N.A.

R M

1 Coolant Pumps

17. Turbine Trip

.w A.

Low Auto Stop 011 N.A.

N.A.

S/U(9)(1)

N.A.

4 Pressure w

B.

Turbine Throttle Valve N.A.

N.A.

S/U(9)(1).

N.A.

Closure

18. Safety Injection Input from ESF N.A.

N.A.

M(4) 1, 2 19.

Reactor Coolant Pump Breaker N.A.

N.A.

R 1

Position Trip 20.

Reactor Trip System Interlocks N.A.

R S/U(8)-

1 21.

Reactor Trip _ Breaker N.A.

'N.A.

M(5)(14)(15),

I 2 S/U(1)(14)(15) 3,, 4,,

5 g

s

'm' 22.

Automatic Trip Logic N.A.

N.A.

M(5).

3,, 4,,- 5

+

1 2 l

g 23.

Reactor Trip Bypass Breaker N.A.

N.A.

(13),R(ll)

I 8

3*, 4,, S'

'hx

L TABLE 3.3-4 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES m

7 6.

AUXILIARY FEEDWATER E

a.

Automatic Actuation N.A.

N.A.

U Logic b.

Steam Generator Water 215% of narrow range instrument 214.4% of narrow range instrument l Level--Low-Low span each steam generator span each steam generator c.

Undervoltage - RCP 2 2680 volts a 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 a.

4.16 kv Emergency Bus 2 3255 volts bus voltage

  • 2 3222 volts bus voltage
  • co b.

4.16 kv Emergency Bus 2 3675 volts bus voltage

  • 2 3638 volts bus voltage
  • 8.

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INTERLOCKS a.

Pressurizer Pressure, s 2000 psig s 2010 psig P-ll E

b.

Low-Low T (Increasi$), P-12 E

544*F s 547*F k

(Decreasing) 543*F 2 540*F 5

c.

Steam Generator Level, (See 5. Above) g.

P-14 a;.

d.

Reactor Trip, P-4 N.A.

N.A.

e ca N

/

'g

  • Refer to appropriate relay setting sheet calibration requirements.

, l* *'S ig I

y.

Pg UNITED STATES f$

. j NUCLEAR REGULATORY COMMISSION

's WASHINGTJN, D.C. 20555 0001 o

....+

SOUTHERN NUCLEAR OPERATING COMPANY. INC.

DOCKET N0. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 97 License No. NPF-8 i

1.

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

A.

The application for amendment by Southern Nuclear Operating Company, Inc. (Southern Nuclear), dated September 13, 1993, 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; 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 (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 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:

'. (2)

Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 97, 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 startup from refueling outage 10.

FOR THE NUCLEAR REGULATORY COMMISSION S. Singh Bajwa, Acting Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

December 29, 1993

^

i ATTACHMENT TO LICENSE AMENDMENT NO. 97 TO FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 i

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 B 2-6 B 2-6 l

3/4 3-3 3/4 3-3 j

i 3/4 3-11 3/4 3-11 3/4 3-13 3/4 3-13 1

3/4 3-28 3/4 3-28 i

l 4

4 TABLE 2.2-1 (Continued) h REACTOR TRIP SYSTEN INSTRUNENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES E

13. Steam Generator Water 15% of narrow range instrument 2 14.4% narrow range instrument l

Z Level--Low - low span - each steam generator span - each steam generator m

I4. Deleted l

15. Undervoltage - Reactor 2 2680 volts - each bus 2 2640 volts - each bus Coolant Pumps
16. Underfrequency - Reactor 2 57.0 Hz - each bus a 56.9 HZ - each bus Coolant. Pumps
17. Turbine Trip A.

Low Auto Stop 2 45 psig a 43 psig Pressure m

i B.

Turbine Stop Valve Not Applicable Not Applicable m

Closure

18. Safety Injection Input Not Applicable Not Applicable from ESF
19. Reactor Coolant Pump Not Applicable Not Applicable Breaker Position Trip 3E Ew 5

=

LIMITING SAFETY SYSTEM SETTINGS BASES 2.2.1 (Continued) latter trip will ensure that the DNB design criterion is met during normal operational transients and anticipated transients when 2 loops are in operation and the Overtemperature delta T trip setpoint is adjusted to the value specified for all loops in operation, With the Overtemperature delta T trip setpoint adjusted to the value specified for 2 loop operation, the P-8 trip at 66% RATED THERMAL POWER will ensure that the DNB design criterion is met during normal operational transients and anticipated transients with 2 loops in operation.

Steam Generator Water level The Steam Generator Water Level Low-Low trip provides core protection by preventing operation with the steam generator water level below the minimum volume required for adequate heat removal capacity.

The specified setpoint provides allowances that there will be sufficient water inventory in the steam generators at the time of trip to allow for starting delays of the auxiliary feedwater system.

Undervoltaoe and Underfrecuency - Reactor Coolant Pumo Busses The Undervoltage and Underfrequency Reactor Coolant Pump bus trips provide reactor core protection against DNB as a result of loss of voltage or underfrequency to more than one reactor coolant pump.

The specified setpoints assure a reactor trip signal is generated before the low flow trip setpoint 1

4 FARLEY - UNIT 2 B2-6 AMENDMENT NO. 85,97

TABLE 3.3-1 (CONTINUED)

REACTOR TRIP SYSTEM INSTRUMENTATION MINIMUM s

FUNCTIONAL UNIT TO'AL NO.

CHANNELS CHANNELS APPLICABLE QF CHANNELS TO TRIP OPERABLE MODES ACTION 11.

Pressurizer Water Level--High 3

2 2

1 7'

12.

A.

Loss of Flow - Single Loop 3/ loop 2/ loop in 2/ loop in 1

7' (Above P-8) any oper-each oper-ating loop ating loop B.

Loss of Flow - Two Loops 3/ loop 2/ loop in 2/ loop in 1

7' (Above P-7 and Below P-8) two oper-each oper-ating loops ating loop 13.

Steam Generator Water Level--

3/ loop 2/ loop in 2/ loop in 1,2 7'

Low-low any oper-each oper-ating loops ating loop w1 14.

Deleted l

15.

Undervoltage - Reactor Coolant 3-2/ bus 2

2 1

7' Pumps w

16.

Underfrequency - Reactor Coolant 3-2/ bus 2

2 1

7' Pumps s

.U e

t i

I

~

g 5k TABLE 3.3-2 (Continued) 4 E

REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES 4

~

FUNCTIONAL UNIT RESPONSE TIME 12.

.A.

Loss of Flow - Single Loop s 1.0 seconds (Above P-8) 8.

Loss of Flow - Two Loops s 1.0 seconds (Above P-7 and Below P-8) 13.

Steam Generator Water Level--Low-Low s 2.0 seconds

{

14.

Deleted l

7

15. Undervoltage - Reactor Coolant Pumps s i.2 seconds C

16.

Underfrequency --Reactor Coolant Pumps s 0.6 seconds 17.

Turbine Trip A.

Low Auto Stop 011 Pressure Not Applicable B.

Turbine Throttle Valve Closure Not Applicable 18.

Safety. Injection Input from ESF Not Applicable

19. -Reactor Coolant-Pump Breaker Position Trip Not Applicable-j

'20.

Reactor Trip System Interlocks Not Applicable 21.

Reactor Trip Breakers Not' Applicable j

22. Autom. tic 1,1,tosic set App m abie

s TABLE 4.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS

  1. O CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE i

FUNTIONAL UNIT CHECK CALIBRATION TEST REQUIRED C5 13.

Steam Generator Water 5

R H

1, 2

[

Level--Low-tow

14. Deleted l
15. Undervoltage - Reactor N.A.

R H

1 Coolant Pumps

16. Underfrequency - Reactor N.A.

R M

1 Coolant Pumps

17. Turbine Trip w

A.

Low Auto Stop 011 N.A.

N.A.

S/U(9)(1)

N.A.

Pressure w

B.

Turbine Throttle Valve N.A.

N.A.

S/U(9)(1)

N.A.

Closure 18.

Safety Injection input from ESF N.A.

N.A.

M(4) 1, 2 19.

Reactor Coolant Pump Breaker N.A.

N.A.

R 1

Position Trip 20.

Reactor Trip System Interlocks N.A.

R S/U(8) 1 21.

Reactor Trip Breaker N.A.

N.A.

M(5)(14)(15),

1 2 S/U(1)(14)(15) 3,, 4,,

5 g

22. Automatic Trip Logic N.A.

N.A.

M(5) 1 2

g 3,, 4,,

S g

Ey 23.

Reactor Trip Bypass Breaker N.A.

N.A.

(13),R(ll) 1 2

,o 3,, 4,,

S 5

E

'S

TABLE 3.3-4 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT All0WABLE VALUES 6.

AUXILIARY FEEDWATER E

a.

Automatic Actuation N.A.

N.A.

Q Logic m

b.

Steam Generator Water 215% of narrow range instrument 214.4% of narrow range instrunent l Level--Low-Low span each steam generator span each steam 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 a.

4.16 kv Emergency Bus 2 3255 volts bus voltage

  • 2 3222 volts bus voltage

E$

s 3418 volts bus voltage

  • b.

4.16 kv Emergency Bus 2 3675 volts bus voltage

  • 2 3638 volts bus voltage
  • 8.

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INTERLOCKS a.

Pressurizer Pressure, s 2000 psig s 2010 psig P-ll E

b.

Low-Low T

"),

P-12 (IncreastEg 544 F s 547 F 9

(Decreasing) 543*F 2 540 F

z:

[

c.

Steam Generator Level, (See 5. Above)

P P-14 d.

Reactor Trip, P-4 H.A.

N.A.

A*

  • Refer to appropriate relay setting sheet calibration requirements.

=

--

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