ML20011E818
| ML20011E818 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 02/10/1990 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20011E819 | List: |
| References | |
| NUDOCS 9002220527 | |
| Download: ML20011E818 (8) | |
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UNITED STATES
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5 W ASHINGTON,0. C. 20555
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DUKE POWER COMPANY r
DOCKET NO. 50-369 McGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.102 License No. NPF-9 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the McGuire Nuclear Station.
Unit 1 (the facility) Facility Operating License No. NPF-9 filed by the Duke Power Company (the licensee) dated September 15, 1989,-
complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations as 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 set forth in 10 CFR i
Chapter I; 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.
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Accordingly, the license is hereby amended by page 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-9 is hereby L
amended to read as-follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.102, are hereby incorporated into the 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 its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION N
A David B. Matthews, Director r
Project Directorate II-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
. Technical Specification Changes Date of Issuance: February 10, 1990 b
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UNITED STATES
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DUKE POWER COMPANY DOCKET NO. 50-370 McGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING _ LICENSE Amendment No.84 L
License No. NPF-17 i
1.
The Nuclear Regulatory Commission (the Commission) has fount. that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 2 (the facility) Facility Operating License No. NPF-17 filed by the Duke Power Company (the licensee) dated September 15, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations as 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 set forth in 10 CFR Chapter I; 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.
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2.
Accordingly, the license is hereby amended by page 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-17 is hereby amended to read as follows:
i Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.84
, are hereby incorporated into the 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 its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION p David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes i
Date of Issuance: February 10, 1990 5
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j ATTACHMENT TO LICENSE AMENDMENT NO.102 i
FACILITY OPERATING LICENSE N0 NPF-9 DOCKET NO. 50-369 i
AND p
TO LICENSE AMENDMENT NO.84 FACILITY OPERATING LICENSE NO. NPF-17 l
DOCKET NO. 50-370 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Amended Page 3/4 3-27 3/4 3-30 3/4 3-31
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., o TABLE 3.3-4 (Continced) 8 c
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS A
FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES
=g 4.
Steam Line Isolation h
a.
Manual Initiation N.A.
N.A.
i b.
Automatic Actuation Logic N.A.
M.A.
and Actuation Relays c.
Containment Pressure--High-High
$ 2.9 psig 5 3.0 psig d.
Negative Steam Line
$ 100 psi with a 5 120 psi with a Pressure Rate - High rate / lag function rate / lag function m}
time constant time constant 3 50 seconds 1 50 seconds E
w e.
Steam Line Pressure - Low 1 585 psig 1 565 psig 5.
Turbine Trip and Feedwater Isolation a.
Automatic Actuation Logic N.A.
N.A.
and Actuation Relays
((
b.
Steam Generator Water level--
< 82% of narrow range
< 83% of narrow range gg High-High (P-14)
Instrument span each steam Instrument span each steam gg generator generator oo c.
Doghouse Water Level-High 12" 13"
((
(Feedwater Isolation Only) co -
M 6.
Containment Pressure Control System CC hh Start Permissive / Termination
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o TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONOS f
1.
Manual a.
Safety Injection (ECCS)
N. A.
b.
Containment Spray N.A.
c.
Containment Isolation Phase "A" Isolation N.A.
Phase "B" Isolation N. A.
Purge and Exhaust Isolation N. A.
d.
Steam Line Isolation N.A.
I e.
Feedwater Isolation N. A.
f.
Auxiliary Feedwater N. A.
g.
Nuclear Service Water N. A.
h.
Component Cooling Water N.A.
1.
Reactor Trip (from SI)
N.A.
j.
Start Diesel Generators N.A.
2.
Containment Pressure-Hiah a.
Safety Injection (ECCS) 5 27(1) b.
Reactor Trip (from SI) 52 c.
Feedwater Isolation
< 9 d.
Containment Isolation-Phase "A"(2) 5 1853)/28(4) e.
Containment Purge and Exhaust Isolation
( 4 f.
N.A.
g.
Nuclear Service Water 5 65(3)/76(4) h.
Component Cooling Water 5 65(3)/76(#)
1.
Start Diesel Generators 5 11 l
McGUIRE - UNITS 1 & 2 3/4 3-30 Amendment No.102 (Unit 1)
Amendment No.84 (Unit 2)
p TABLE 3.3-5 (Continued)
ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 3.
Pressurizer Pressure-Low-Low I
a.
Safety Injection (ECCS)
< 27(1)/12(3) b.
Reactor Trip (from SI)
$2 l
c.
Feedwater Isolation
<9 d.
Containment Isolation-Phase "A"(2)
}18(3)/28(4) l e.
Containment Purge and Exhaust Isolation 54 l
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f.
N.A.
g.
Nuclear Service Water System 5 76(1)/65(3) h.
Component Cooling Water 1 76(1)/65(3) i 1.
Start Diesel Generators 5 11 4.
Steam Line Pressure-Low
^
a.
Safety Injection (ECCS)
$ 12(3)/22(4) b.
Reactor Trip (from SI)
<2 c.
Feedwater Isolation
<9 d.
Containment Isolation-Phase "A"(2)
}18(3)/28(4) e.
Containment Purge and Exhaust Isolation
<4 f.
N.A.
g.
Nuclear Service Water 1 65(3)/76(4) h.
Steam Line Isolation
<7 1.
Component Cooling Water h65(3)/76(4) j.
Start Diesel Generators
< 11 5.
Containment Press _ure-High-High a.
Containment Spray 5 45
~ b.
Containment Isolation-Phase "B" N.A.
c.
Steam Line Isolation
<7 6.
Steam Generator Water Level-Hich-High a.
Turbine Trip N.A.
b.
Feedwater Isolation
<9 McGUIRE - UNITS 1 & 2 3/4 3-31 Amendment No.102(Unit 1)
Amendment No. 84 (Unit 2)
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