ML20072Q095
| ML20072Q095 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 11/20/1990 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20072Q104 | List: |
| References | |
| NUDOCS 9011300187 | |
| Download: ML20072Q095 (8) | |
Text
'
((on esaw'h, UNITED states g
NUCLEAR REGULATORY COMMISSION i
.5
.l WASHINGTON, D. C. 20656
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DUKE POWER COMPANY DOCKET NO. 50-36,9 McGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 116 License No. NPF-9 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The app (lication 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 4,1990, complies with the standards and re Act of 1954, as amended (the Act) quirements of the Atomic Energy 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 Comission; C.
There is reasonable assurance (1) that the activities authorized by thia amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance witi the Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not'be inimical to the common defense and seedrity or to the health and safety of the public; and E.
The issuance af this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
9011300187 901120 PDR ADOCK 05000349 P
. 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-9 is hereby en: ended to read as follows.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.116, 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
\\
fgn David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
November 20, 1990 l
l 1
UNITED STATES NUCLE AR REGULATORY COMMISSION i
a l
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wAsHiNorow, o. c. 2006s
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DUKE POWER COMPANY l
DOCKET NO. 50-370 McGUIRE NUCLEAR STATION, UNIT 2 1
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 98 License No. NPF-17 1.
The Nuclear Regulatory Connission (the Connission) has found that:
A.
The app (lication for amendment to the McGuire Nuclear Stationthe facilityi Unit 2 by the Duke Power Company (the licensee) dated September 4, 1990, i
complies with the standards and re Act of 1954, as amended (the Act) quirements of the Atomic Energy and the Consission'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 (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 Connission'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 an'd safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Conaission's regulations and all applicable requirements ha'se been satisfied.
l 1
--- -,- ~-
I e
e.
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 Fecility Operating License No. NPF-17 is hereby amended to read as follows:
Technical Spccifications The Technical Specifications contained in Appendix A, as revised thrnugh Amendment No. 98, 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 d
ced David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects-1/II Office of Nuc1 car Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
November 20, 1990
I ATTACHMENT TO LICENSE AMENDMENT NO.116 fACILITYOPERATINGLICENSENO.NPF0 DOCKET NO. 50 369 AND TO LICENSE AMENDMENT NO.
98 FACILITY OPERATING LICENSE NO. NPF-17 DOCKET NO. 50-370 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
Tae ~ 9yised pages are identified by Amendment number and contain vertical lines int **.ating the areas of change.
Remove Pages Insert Pages 2-ta 2-2a 2-5 2-5 2-9 2-9 i
1
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i i
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i i
i m-FLOW PER LOOP = 96250 gom m.
UNACCEPTABLE Efog OPERATION
}
EESo sq.
Ds t, nt-E000 A
f l te lat -
i I??
$ *s te
~
s,,.
I 400 -
ACCEPTABLE OPERATION 090-t 4
i 4
i 4
i 4
3 n
E ln ln POWER (PERCENTAGE OF NOMINAL)
FIGURE 2.1-1 UNITS 1 AND 2 REACTOR CORE SAFETY LIMIT - FOUR LOOPS IN OPERATION-McGUIRE - UNITS 12nd 2 2-2a Amenoment No.11(Unit 1)
Amenement ho,98(Unit 2)
TABLE 2.2-1 z
E>5 REACTOR TRIP SYSTEM INSTRUMENTATION 1.11P SETPOINTS
~
x 7
FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES
- 1. Manual Reactor Trip N.A.
N.A.
[
- 2. Power Range, Neutron Flux Low Setpoint 1 25% of RATED Low Setpoint 1 26% of RATED THERMAL POWER THERMAL POWER
,o
[
High Setpoint 1 109% of RATED High Setpoint 1 110% of RATED THERMAL POWcR THERMAL POWER
- 3. Power Range, Neutron Flux, 5 5% of RATED THERMAL POWER with
< 5.5% of RATED THERMAL POWER High Positive Rate a time constant > 2 seconds with a time constant > 2 seconds
- 4. Power Range, Neutron Flux, 5 5% of RATED THERMAL POWER with
< 5.5% of RATED THERMAL POWER High Negative Rate a time constant > 2 seconds with a time constant > 2 seconds "4
- 5. Intermediate Range, Neutron i 25% of RATED THERMAL POWER 1 30% of RATED THERMAL POWER Flux
- 6. Source Range, Neutron Flux i 105 counts per second i 1.3 x 105 counts per second
- 7. Overtemperature AT See Note 1 See Note 3 1
((
- 8. Overpower AT See Note 2 See Note 4 I
- 9. Pressurizer Pressure--Low
> 1943 psig
> 1935 psig
- 10. Pressurizer Pressure--High 1 2385 psig i 2395 psig
~OO L 11. Pressurizer Water Level--High i 92% of instrument span i 93% of instrument span
$5
- 12. Low Reactor Coolant Flow
> 90% of minimum measured
> 88.8% of minimum measured I
jj T10w per loop
- Tiow per loop
- ee y
- Minimum measured flow is %,250 gpm per loop.
~
7 TABLE 2.2-1 (Continued)
~
c)
C REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS E
NOTATION (Continued)
C it.i NOTE 1:
(Continued)
M Time constant utilized in the measured I,,g lag compensator, is 5 2 sec
=
g Ts e.g T'
$ 588.2*F Reference T,yg at RATED THERMA.L POWER,
=
to K
=
O M 095, 3
P
=
Pressurizer pressure, psig, P'
2235 psig (Nominal RCS operating pressure),
=
Laplace transform operator, sec 1, S
=
and fg(AI) is a function of the indicated difference between top and bottom detectors of the pov " range nuclear ion chambers; with gains to be selected based on measured instrument response during plant startup tests such that:.
(i) for q
~A between -29% and +7.0%; f (AI) = 0, where q 8"d U are percent RATED I
t b
y t
b THERMAL POWER in the top and bottom halves of the core respectively, and qt
- 9b is total THERMAL POWER in percent of RATED THERMAL POWER; aa ll (ii) for each percent that the magnitude of q g exceeds -29%, the AT Trip Setpoint b
l
((
shall be automatically reduced by 3.151% of its value at RATED THERMAL POWER; and
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(iii) for each percent that the magnitude of q
~9 exceeds +7.0%, the AT Trip Setpoint l
w s--
t b
shall be automatically reduced by 1.50% of its value at RAlED THERMAL POWER.
EE 11 ee 4
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