ML20206B684

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Amends 100 & 100 to Licenses NFP-72 & NPF-77,respectively, Changing TS Tables 3.3.1-1 & 3.3.2-1,to Revise Allowable Values for 12 Functions of RTS & Efsas
ML20206B684
Person / Time
Site: Byron, Braidwood  Constellation icon.png
Issue date: 04/23/1999
From: Anthony Mendiola
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20206B549 List:
References
NUDOCS 9904300032
Download: ML20206B684 (13)
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UNITED STATES y

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P; NUCLEAR REGULATORY COMMISSION waswiworow, o.c. sees.4eet COMMONWEALTH EDISON COMPANY DOCKET NO. STN 60-456 BRAIDWOOD STATION. UNIT NO.1 AMENDMENY TO FACILITY OPERATING LICENSE Amendment No.100 License No. NPF-72

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1.

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

A.

The application for amendment by Commonwealth Edison Company (the licensee) dated December 29,1998, 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 pnvisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assu;ance (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 amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The lasee=e of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfed.

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) :J Facility Operating License No. NPF-72 is hereby amended to read as follows:

i 9904300032 990423 PDR ADOCK 05000454 p

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Technical Soecifications The Technical Specifications contained in Appendix A as revised through Amendment No.100 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this-license. The licensee 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 shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION i

Anthony Mendiola, Chief, Section 2 Project Directorate ill Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date ofissuance: April 23, 1999

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t UNITED STATES g

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NUCLEAR REGULATORY COMMISSION o

WASHINGTON, D.C. SDe86 00M COMMONWEALTH EDISON COMPANY M

BRAIDWOOD STATION. UNIT NO. 2 AMENDMENT TO FACILITY Ofg8^ JING LICENSE Amendment No.100 License No. NPF-77 1.

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

A.

The application for amendment by Commonwealth Edison Company (the licensee) dated December 29,1998, 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 ths 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 *5is 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 satisfed.

2.

Accordingly, the license ir emended by changes to the Technical Specifications as indicated in the attachme.,u to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-77 is hereby amended to read as follows:

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Imphnical Soecificet; ens The Technical Specifications contained in Appendix A as revised through Amendment No.100 and the Environmental Protection Plan contained in Appendix B, both of which were attached to License No. NPF-72, dated July 2, 1987, are hereby incorporated into this license. The licensee 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 if its issuance and shall be imp e,nented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION g

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Anthony Me diola, Chief, S ion 2 j

Project Directorate lll Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date ofIssuance: April 23,'1999 l

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r-1 ATTACHMENT TO LICENSE AMENDMENT NOS.100 AND 100 FACILITY OPERATING LICENSE NOS. NPF-72 AND NPF-77 DOCKET NOS. STN 50-456 AND STN 50457 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

Remove Pages insert Panes 3.3.1-14 3.3.1-14 3.3.1-15 3.3.1-15 3.3.1-16 3.3.1-16 3.3.1-18 3.3.1-18 3.3.1-19 3.3.1-19 3.3.2-9 3.3.2-9 3.3.2-12 3.3.2-12 3.3.2-14 3.3.2-14

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.1 RTS Instrumentation 3.3.1 Table 3.3.1 1 (page 1 of 6)

Reactor Trip Syste:n Instrumentation APPLICABLE H0 DES OR OTHER SPECIFIED RE001 RED SURVEILLANCE ALLOWABLE FUNCTION.

CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE 1.

Manual Reactor Trip 1.2 2

B SR 3.3.1.13 NA 3(a), 4(a). 5(a) 2 C

SR 3.3.1.13 NA 2.

Power Range Neutron Flux l

a.

High 1.2 4

D SR 3.3.1.1 s 110.81 SR 3.3.1.2 RTP SR 3.3.1.7 SR 3.3.1.11 SR 3.3.1.15 b.

Low 1(b) 2 4

E SR 3.3.1.1 s 27.01 l

SR 3.3.1.8 RTP SR 3.3.1.11 SR 3.3.1.15 3.

Power Range Neutron Flux Rate a,

High Positive Rate 1.2 4

E SR 3.3.1.7 s 6.21 RTP l

SR 3.3.1.11 with time constant a 2 seC b.

High Negative Rate 1.2 4

E SR 3.3.1.7 s 6.21 RTP l

SR 3.3.1.11 with time SR 3.3.1.15 constant a 2 sec 4 Intermediate Range 1(b). 2(C) 2 F.G SR 3.3.1.1 s 30.01 RTP l

Nef.ron Flux SR 3.3.1.8 SR 3.3.1.11 5.

Source Range Neutron 2(d) 2 H.1 SR 3.3.1.1 s 1.42 E5 cps Flux SR 3.3.1.8 l

SR 3.3.1.11 SR 3.3.1.15 l

3(a),4(a). 5(a) 2 1.J SR 3.3.1.1 s 1.42 E5 cps SR 3.3.1.7 SR 3.3.1.11 SR 3.3.1.15 (continued)

(a) With Rod Control System capatie of rod withdrawal or one or more rods not fully inserted.

(b) Below the P-10 (Power Range Neutron Flux) interlock.

(c) Above the P-6 (Source Range Block Permissive) interlock.

(d) Below the P 6 (Source Range Block Permissive) interlock.

BRAIDWOOD - UNITS 1 & 2 3.3.1 - 14 Amendment 300 & 100

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RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 2 of 6)

Reactor Trip Syster. Instrumentation APPLICABLE H0 DES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE 6.

Overtemperature AT 1.2 4

E SR 3.3.1.1 Refer to 1

SR 3.3.1.3 Note 1 (Page SR 3.3.1.6 3.3.1-18) l SR 3.3.1.7 j

SR 3.J.1.10 i

SR 3.3.1.15 j

7.

Overpower AT 1.2 4

E SR 3.3.1.1 Refer to SR 3.3.1.7 Note 2 (Page SR 3.3.1.10 3.3.1-19)

SR 3.3.1.15 8.

Pressurizer Pressure I ')

4 K

SR 3.3.1.1 a 1875 psig l

I a.

Low SR 3.3.1.7 j

SR 3.3.1.10 SR 3.3.1.15 b.

High 1.2 4

E SR 3.3.1.1 s 2393 psig SR 3.3.1.7 SR 3.3.1.10 1

SR 3.3.1.15

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9.

Pressurizer Water 1(')

3 K

SR 3.3.1.1 s 93.51 of Level - High SR 3.3.1.7 instrument SR 3.3.1.10 span I

10. Reactor Coolant 1(')

3 K

SR 3.3.1.1 m 89.3% of Flow-Low (per loop)

SR 3.3.1.7 loop minimum SR 3.3.1.10 measured flow SR 3.3.1.15

11. Reactor Coolant Pump 1(')

4 K

SR 3.3.1.13 NA (RCP) Breaker Position (per train)

(continued)

(c) Above the P-7 (Low Power Reactor Trips Block) interlock.

BRAIDWOOD'- UNITS 1 & 2 3.3.1 - 15 Amendment-100 & 100 i

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RTS Instrumentation 3.5.1 Table 3.3.1-1 (page 3 of 6)

Reactor Trip System Instrimentation APPLICABLE MODES OR-OTHER SPECIFIED REQUIRED SURVE]LLANCE ALLOWABLE i

FUNCTION CONDITIONS CHANNELS COND1110NS REQUIREMENTS VALUE

12. Undervoltage 1(')

4 K

SR 3.3.1.9

= 4920 V RCPs (per train)

SR 3.3.1.10 SR 3.3.1.15

13. Uncerfrequency 1(')

4 K

SR 3.3.1.9 a 56.0B H2 RCPs (per train)

SR 3.3.1.10 fR 3.3.1.15 1

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14. Steam Generator (SG)

Water Level - Low Low (per SG) a.

Unit 1 1.2 4

E SR 3.3.1.1

= 16.11 of SR 3.3.1.7 narrow range SR 3.3.1.10 instriment SR 3.3.1.15 span b.

Unit 2 1.2 4

E SR 3.3.1.1

= 34.B% of SR 3.3.1.7 narrow range SR 3.3 1.10 instrument SR 3.3.1.15 span

15. Turbine Trip a.

Emergency Trip lif) 3 L

SR 3.3.1.10 a 910 psig g

Header Pressure SR 3.3.1.14 (per train)

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b.

Turbine Throttle 1(I) 4 L

SR 3.3.1.10 a It open

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Valve Closure SR 3.3.1.14 (per train)

16. Safety injection (SI) 1.2 2 tratas M

SR 3.3.1.13 NA Input from Engineered Safety Feature Actuation System (ESFAS)

(continued)

(e) Above the P-7 (Low Power Reactor Trips Block) interlock.

(f) Above the P-B (Power Range Neutron Flux) interlock.

I BRAIDWOOD - UNITS 1 & 2 3.3.1 - 16 Amendment 100 & 100

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RTS Instrumentation 3.3.1 Table 3.3.1-l'(page 5 of 6)

Reactor Trip System Instrumentation

-Note 1-Overtemoerature AT The Overtemperature AT Function Allowable Value shall not exceed the following Trip Setpoint by more than 1.04% of AT span.

l A T(1+7 s)

K - K, ((1+ r,s) 3 1

1 T

-T' + K (P-P')- f (A I)

SAT' o

3 3

3 (1+ r,s) 1+rs 1+rs)

(1+ r,s) 3 s

Where: AT is measured Reactor Coolant System (RCS) AT. *F.

ATo is the indicated AT at RTP, 'F.

s is the Laplace transform operator, sec~2.

T,is the measured RCS average temperature, 'F.

T is the nominal T,, at RTP, s 588.4*F.

P,is the measured pressurizer pressure, psig.

P is the nominal RCS operating pressure. - 2235 psig.

K - 1.325 K, - 0.0297/*F K - 0.00181/psig 3

3

- 73 = 8 sec 7,= 3 se 7 s 2 sec 3

r,= 33 sec r - 4 set r s 2 sec s

s f (AI) = -3.35{24 + (q, - q )} when q, - q, < - 24% RTP 3

0% of RTP_

when -24% RTP s qt - q, s 10% RTP 4.11{(qt - q ) - 10}

when qt - q, > 10% RTP Where qt and q, are percent RTP in the upper and lower halves of the core, respectively, and_ qt + q, is the total THERMAL POWER in percent RTP.

BRAIDWOOD ' UNITS 1 & 2 3.3.1 - 18 Amendment,.100 & 100

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RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 6 of 6)-

Reactor Trip System Instrumentation Note 2-Overoower AT The Overpower AT Function Allowable Value shall not exceed the following Trip Setpoint by more than 3.60% of AT span.

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- A T (1+r s) 1 rs i

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y SAT' K,- K T-K, T

- T" - f,(A I) o 3

(1+ r,s) 1+r s 1 + r,s 1+ r,s 1+1,s a.

Where: AT is measured RCS AT. *F.

ATo is the indicated AT at RTP. *F.

s is the Laplace transform operator, sec.2,

T,,is the measured RCS average temperature.

F.

T is the nominal T., at RTP. 5 588.4*F.

K,= 1.072 K - 0.02/*F for increasing T,

Ks = 0.00245/*F when T > T" 3

0/*F for decreasing T,y 0/*F when T s T" 71 - 8 sec 72 = 3 sec T s 2 sec 3

is s 2 sec r, = 10 sec fr(AI) = 0 for all AI.

BRAIDWOOD - UNITS 1 & 2 3.3.1 - 19 Amendment 100 & 100

N ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 1 of 6)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE t.JJES OR 1

OTHER SPECIFIED REOU' RED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANh15 CONDITIONS REQUIREMENTS VALUE 1.

Safety Injection a.

Manual Initiation 1.2.3.4 2

B SR 3.3.2.9 NA b.

Automatic 1.2.3.4 2 trains C

SR 3.3.2.4 NA Actuation Logic SR 3.3.2.5 and Actuatio1 SR 3.3.2.7 Relays c.

Containment 1.2.3 3

D SR 3.3.2.1 s 4.6 psig Pressure - High 1 SR 3.3.2.6 SR 3.3.2.10 SR 3.3.2 12 d.

Pressurizer 1.2.3(a) 4 D

SR 3.3.2.1

= 1817 psig l

Pressure - Low SR 3.3.2.6 SR 3.3.2.10 SR 3.3.2.12 e.

Steam Line 1.2.3(a) 3 per steam D

SR 3.3.2.1

= 614 psig(b)

Pressure - Low line SR 3.3.2.6 SR 3.3.2.10 SR 3.3.2.12 2.

Containment Spray a.

Manual Initiation 1.2,3.4 2

B SR 3.3.2.9 NA b.

Automatic 1.2.3.4 2 trains C

SR 3.3.2.4 NA Actuation Logic SR 3.3.2.5 and Actuation SR 3.3.2.7 Relays c.

Containment 1.2.3 4

E SR 3.3.2.1 s 21.2 psig Pressure High - 3 SR 3.3.2.6 SR 3.3.2.10 SR 3.3.2.12 (continued)

(a) Above the P-11 (Pressurizer Pressure) interlock.

(b) Time constants ssed in the lead / leg contrc11er are t = 50 seconds and t, s 5 seconds.

i 1

BRAIDWOOD - UNITS 1 & 2

3. 3.2 - 9 Amendment 100 & 100

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Oc ESFAS Instrumentation 3.3.2 Table 3.3.2 1 (page 4 of 6)

Engineered Safety Feature Actuation System Instr oentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE 5.

Turbtne Trip and Feedwater Isolation a.

Automatic 1,2(h) 3(h) 2 trains G

SR 3.3.2.4 NA Actuation Logic SR 3.3.2.5 and Actuation SR 3.3.2.7 Relays b.

Steam Generator (SG) Water Level - High High (P 14)

1) Unit 1 1,2(h) 3(h) 4 per SG D

SR 3.3.2.1 s B9.9% of SR 3.3.2.4 narrow range SR 3.3.2.5 instroent SR 3.3.2.6 scan SR 3.3.2.7 SR 3.3.2.10 SR 3.3.2.12

2) Unit 2 1,2(h) 3(h) 4 per SG D

SR 3.3.2.1 s 81.51 of l

SR 3.3.2.4 narrow range SR 3.3.2.5 instro ent SR 3.3.2.6 span SR 3.3.2.7 SR 3.3.2.10 SR 3.3.2.12 c.

Safety injection Refer to Function 1 (Safety injection) for all initiation functions and requirements.

l (continued)

(h) Except when all feedwater Isolation Valves are closed or isolated by a closed manual valve, i

BRAIDWOOD - UNITS 1 & 2 3.3.2 - 12 Amendment 100 & 100

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ESFAS Instrumentation 3.3.2 Table 3.3.2 1 (page 6 of 6)

Engineered Safetygtcre Actuation System Instrunentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE

8. ESFAS Interlocks
a. Reactor Trip. P-4 1.2.3 2 per train F

SR 3.3.2.9 NA

b. Pressurizer Pressure.

1.2.3 2

L SR 3.3.2.6 s 1936 psig P-11 SR 3.3.2.10 l

c. T,- Low Low, P-12 1.2.3 3

L SR 3.3.2.6

= 548.0'F SR 3.3.2.10 i

BRAIDWOOD - UNITS 1 & 2 3.3.2 - 14 Amendment 100 & 100 2

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