ML20206B545
| ML20206B545 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 04/23/1999 |
| From: | Anthony Mendiola Office of Nuclear Reactor Regulation |
| To: | Commonwealth Edison Co |
| Shared Package | |
| ML20206B549 | List: |
| References | |
| NPF-37-A-107, NPF-66-A-107 NUDOCS 9904290287 | |
| Download: ML20206B545 (13) | |
Text
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[pengk UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30seHOM
'+4*****
COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-454 RY.RON STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.107 License No. NPF-37 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 het 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 (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 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-37 is hereby amended to read as follows:
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9904290287 990423 PDR ADOCK 05000454 P
PDR NO N2 j
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. j (2) Technical Soecifications The Technical Specifications contained in Appendix A as revised through Amendment No.107 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 Spocifications 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, i
FOR THE NUCLEAR REGULATORY COMMISSION i
Anthony Mendiola, Chief, Se ion 2 Project Directorate lli Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date oflasuance: April 23, 1999 i
t 70%k UNITED STATES ef j
NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 30006 0001 COMMONWEALTH EDISON COMPANY DOCV.ET NO. STN 50-455 BYRON STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.107 License No. NPF-66 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
Thn 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 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 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 satisfMxl.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendrnent, and paragraph 2.C.(2) of Facility Operating License No. NPF-66 is hereby amended to read as follows:
i
- f i (2)
Technical Soecifications The Technical Specifications contained in Appendix A (NUREG-1113), as revised through Amendment No.lo?
and revised by Attachment 2 to NPF-66, and the Environmental Protection Plan contained in Appendix B, both of which were attached to License No. NPF-37, dated February 14,1985, are hereby incorporated into this license. Attachment 2 contains a revision to Appendix A which is 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
/
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 of lasuance: April 23, 1999
<i ATTACHMENT TO LICENSE AMENDMENT NOS.107 AND 1n7 FACILITY OPERATING LICENSE NOS. NPF-37 AND NPF-66 DOCKET NOS. STN 50-454 AND STN 50-455 Revise the Appendix A Technical Specifications by removing the pages identifed below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
Remove Paaes insertEanes 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 i
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RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 1 of 6)
Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REOUIREMENTS VALUE 4
1.
Manual Reactor Trip 1.2 2
B SR 3.3.1.13 NA 3(a), 4(a), $(a) 2 C
SR 3.3.1.13 NA 1
l 2.
Power Range Neutron Flux a.
High 1.2 4
0 SR 3.3.1.1 s 110.8%
{
SR 3.3.1.11 J
SR 3.3.1.15 i
b.
Low 1(b) 2 4
E SR 3.3.1.1' s 27.01 l
Power Range Neutron Flux Rate a.
High Positive Rate 1.2 4
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 see j
4.
Intermediate Range 1(b). 2(C) 2 F.G SR 3.3.1.1 s 30.01 RTP l
Neutron Flux SR 3.3.1.8 SR 3.3.1.11 l
S.
Source Range Neutron 2(d) 2 H.!
SR 3.3.1.1 s 1.42 E5 cps Flux SR 3.3.1.8 SR 3.3.1.11 SR 3.3.1.15 3(a), 4(a). 5(a) 2 1.J SR 3.3.1.1 s 1.42 E5 cps SR 3.3.1.7 3
SR 3.3.1.11 i
SR 3.3.1.15
]
l (continued)
/
(a) With Rod Control System capable 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.
BYRON - UNITS 1 & 2 3.3.1 - 14 Amendment.107 & 107 I
1 1
l' RTS Instrumentation 3.3.1 Table 3.3.1 1 (page 2 of 6)
Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE l
FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE 6.
Overtemperature AT 1.2 4
E SR 3.3.1.1 Refer to SR 3.3.1.3 Note 1 (Page l
SR 3.3.1.6 3.3.1 18) l SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.15 7.
Overpower AT 1.2 4
E SR 3.3.1.1 Refer to 4
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 II 'I 4
K SR 3.3.1.1 a 1875 psig l
a.
Low SR 3.3.1.7 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 SR 3.3.1.15 9.
Pressurizer Water 1(8) 3 K
SR 3.3.1.1 s 93.5% of Level - High SR 3.3.1.7 Instrument SR 3.3.1.10 span I 'I 3
= 89.3% of I
- 10. Reactor Coolant Flow - Low (per loop)
SR 3.3.1.7 loop minimta SR 3.3.1.10 measured flow SR 3.3.1.15 I ')
4 K
SR 3.3.1.13 NA I
- 11. Reactor Coolant Pump (RCP) Breaker Position (per train)
(continued)
(e) Above the P-7 (Low Power Reactor Trips Block) interlock.
BYRON - UNITS 1 & 2 3.3.1 - 15 Amen'dment 107 & 107 a
.,*l r
RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 3 of 6)
Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUlREMENTS VALUE
\\
I ')
4 K
SR 3.3.1.9 a 4920 V I
- 12. Undervoltage RCPs (per train)
SR 3.3.1.10 l
]
SR 3.3.1.15 I ') '
4 K
SR 3.3.1.9 a 56.08 H2 I
- 13. Underfrequency RCPs (per train)
- 14. Steam Generator (SG)
Water Level - Low Low (per SG)-
a.
Unit 1 1.2 4
= 16.1% of SR 3.3.1.7 narrow range SR 3.3.1.10 instrument SR 3.3.1.15 span b.
Unit 2 1.2 4
E SR 3.3.1.1 a 34.81 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 1(f) 3 L
SR 3.3.1.10
= 910 psig l
Header Pressure SR 3.3.1.14 (per train) b.
Turbine Throttle 1(f) 4 L
SR 3.3.1.10 a 11 open Valve Closure SR 3.3.1.14 (per train)
- 16. Safety Injection ($1) 1.2 2 trains 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 8 (Power Range Neutron Flux) interlock.
i BYRON - UNITS 1 & 2 3.3.1 - 16 Amendment 107 & 107
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RTS Instrumentation 3.3.1 Table 3.3.1-1 (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+r s) 1 K - K (1+r,s) 1 i
SAT' T
-T' + K (P-P')- f (A I) o 3
3 2
(1+ r,s) 1+rs 2 (1+r s)
(1+ r,s) 3 3
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
2 a
71 = 8 sec T2 = 3 sec T s 2 sec 3
7,= 33 sec 75 - 4 sec r s 2 sec s
i f (AI) = -3.35{24+(qt - q,)} when qt - q, < - 24% RTP t
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.
i BYRON - UNITS 1 & 2 3.3.1 - 18 Amendment.107 & 107
If af RTS instrumentation 3.3.1 Table 3.3.1-1 (page 6 of.6)
Reactor Trip System Instrumentation Note 2-Overnower AT The Overpower. AT Function Allowable Value shall not exceed the following Trip Setpoint by more than 3.60% of AT span.
l
~
A T (1+r s) 3 i'
r,s i
i T-K, T
- T" - f,(A I) s a T, ' K,- K,1+ r,s 1+ r,s 1+r s (1+r,s) 1+rs 3
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. s 588.4*F.
K = 1.072 K = 0.02/*F for increasing T,,,
K, = 0.00245/ F when T > T" 4
3 0/*F for decreasing T,,,
0/*F when T 5 T" T1 = 8 sec 7,= 3 sec T s 2 sec 3
r,s 2 sec 7,= 10 sec f (AI) = 0 for all AI.
r BYRON - UNITS 1 & 2 3.3.1 - 19 Amendment.107 & 107
r i
ESFAS Instrumentation 3.3.2 Table 3.3.2 1 (page 1 of 6)
Engineered Safety Feature Actuation System Instrtmentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVE!LLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS 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 Actuation 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
= 1817 psig l
Pressure - Low SR 3.3.2.6 4
Steam Line 1.2.3(a) 3 per steam D
SR 3.3.2.1 a 614 psig(b)
Pressure - Low line SR 3.3.2.6 SR 3.3.2.10 SR 3.3.2.12 2.
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 (Pressurtzer Pressure) interlock.
(b) Time constants used in the lead / lag controller are t, a 50 seconds and t, s 5 seconds.
BYRON - UNITS 1 & 2
- 3. 3. 2 - 9 Amendment.107 & 107
i 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.
Turbine Trip and Feedwater Isolation a.
Automatic 1.2(h) 3(h3 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 89.9% of SR 3.3.2.4 narrow range SR 3.3.2.5 instroent SR 3.3.2.6 span 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 81.5% of l
SR 3.3.2.4 narrow range SR 3.3.2.5 instrument 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.
(continued)
(h) Except when all Feedwater Isolation Valves are closed or isolated by a closed manual valve.
I
(
l BYRON - UNITS 1 & 2 3.3.2 - 12 Amendment 107 & 107 e
o.
.l ESFAS Instrumentation 3.3.2 L
Table 3.3.2 1 (page 6 of 6)
Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIR*D SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDIT10NS REQUIREMENTS VALUE
- 8. ESFAS Inter 1.r.as
- a. Reactor Trip. N 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 193f rate P-11 SR 3.3.2.10 l
- c. T,- Low Low. P 12 1.2.3 3
L SR 3.3.2.6 a 548.0'F SR 3.3.2.10 1
1 l
l 1
l l
l l
BYRON - UNITS 1 & 2 3.3.2 - 14 Amendment 107 & 107
.