ML20070K643
| ML20070K643 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 07/18/1994 |
| From: | Berkow M Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20070K647 | List: |
| References | |
| NUDOCS 9407270068 | |
| Download: ML20070K643 (8) | |
Text
_
E UNITED STATES
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8 NUCLEAR REGULATORY COMMISSION
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WASHiNOTON, D.C. 2055!MXo1 DilKE POWER COMPANY DOCKET NO. 50-369 McGUIRE NUCLEAR STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 144 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 (licensee) dated February 25, 1994, 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.
9407270068 94071g DR ADOCK 05000369 PDR
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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-9 is hereby amended to read as follows:
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 144, are hereby incorporated into this license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection j
Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
]
1 6
y erbert N. Ber ow, Director Project Directorate 11-3 l
Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
July 18, 1994
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WASHINGT ON, D.C. 20555-0001 DUKE POWER COMPANY DOCKET N0. 50-370 McGUIRE NUCLEAR STATION. UllIT 2 AMENDMENT TO FACILITY OPERATIll6 LICENSE Amendment No. 126 License No. NPF-17 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment to the kGuire Nuclear Station, Unit 2 (the facility), Facility Operating License No. NPF-17 filed by the Duke Power Company (licensee) dated February 25, 1994, 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 dnd 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.
t
~._.
, J 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:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 126, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection
- Plan, i
3.
This license amendment is effective as of its date of issuance.
i FOR THE NUCLEAR REGULATORY COMMISSION l
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j'
/
rbert N. Berkow, Director roject Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: July 18, 1994 E
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ATTACHMENT TO LICENSE AMENDMENT N0.144 FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 8!iD TO LICENSE AMENDMENT NO.126 FACILITY OPERATING LICENSE NO. NPF-17 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.
Remove Paaes Insert Paaes 3/4 3-55 3/4 3-55 3/4 3-56 3/4 3-56 3/4 3-57 3/4 3-57 u
INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.6 The accident monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, and 3.
ACTION:
a.
With the number of OPERABLE accident monitoring instrumentation channels less than the Required Number of Channels shown in Table 3.3-10, restore the inoperable channel (s) to OPERABLE status within 7 days, or be in at least H0T SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, b.
With the number of OPERABLE accident monitoring instrumentation channels less than the Minimum Channels OPERABLE requirements of Table 3.3-10, restore the inoperable channel (s) to OPERABLE status according to b.1 or b.2 below:
l b.1 Instruments 1-15: within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least H0T SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.2 Instruments 16 and 17:
according to Technical Specification 3.7.4.a.
c.
The provisions of Specification 3.0.4 are not applicable.
i SURVEILLANCE REQUIREMENTS 4.3.3.6 Each accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-7.
McGUIRE - UNITS I and 2 3/4 3-55 Amendment No. 144 (Unit 1)
Amendment No. 126 (Unit 2)
1 TABLE 3.3-10 g
o5 ACCIDENT MONITORING INSTRUMENTATION i
\\
i REQUIRED MINIMUM NO. OF CHANNEL
! INSTRUMENT CHANNELS OPERABLE a
1.
Containment Pressure 2
1 2.
Reactor Coolant Temperature - T, and T (Wide Range) 2/T, 2/T,
1/T, 1/T m,
3.
Reactor Coolant Pressure - Wide $ange 2
1 j
m 4.
Pressurizer Water Level 2
1 5.
Steam Line Pressure 2/ steam generator 1/ steam generator 6.
Steam Generator Water Level - Narrow Range 2/ steam generator 1/ steam generator 7.
Refueling Water Storage Tank Water Level 2
1 8.
Auxiliary Feedater Flow Rate 2/ steam generator 1/ steam generator l
9.
Reactor Coolant System Subcooling Margin Monitor 2
1 10.
Containment Water Level (Wide Range) 2 1
11.
In Core Thermocouples 4/ core quadrant 2/ core quadrant t'
- 12. Containment Atmosphere - High Range Monitor 1
(EMF-51a or 51b)
Y 13. Reactor Vessel Level Instrumentation a.
Dynamic Head (D/P) Range 2
1 l
b.
Lower Range 2
1
- 14. Neutron Flux - Wide Range 2
1
- 15. Containment Hydrogen Concentration 2
1 k k 16. Diesel Generator Cooling Water Heat Exchanger RN Flow
- 1/ diesel generator 1/ diesel generator
&R 17. Containment Spray Heat Exchanger RN Flow
- 1/ train 1/ train 53 EE b
EE C.
4 cn 22 S. E.
ee
- Not applicable if the associated outlet valve is set to its flow balance position with power removed or if the associated outlet valve's flow balance position is fully open.
M TABLE 4.3-7 8
ACCIDENT MONITORING INSTRL'.lENTATION SURVEILLANCE RE0UIREMENTS Im' CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION C
1.
Containment Pressure M
R 2.
Reactor Coolant Temperature - T, and T (Wide Range)
M R
[
3.
Reactor Coolant Pressure - Wide Range M
R 4.
Pressurizer Water Level M
R 5.
Steam Line Pressure M
R 6.
Steam Generator Water Level - Narrow Range M
R 7.
Refueling Water Storage Tank Water Level M
R 8.
Auxiliary Feedwater Flow Rate M
R 9.
Reactor Coolant System Subcooling Margin Monitor M
R w
- 10. Containment Water Level (Wide Range)
M R
l w
11.
In Core Thermocouples M
R l
- 12. Containment Atmosphere - High Range Monitor M
R l
((
(EMF-Sla or 51b) l o=
@{
13.
Reactor Vessel Level Instrumentation m
a.
Dynamic Head (D/P) Range M
R b.
Lower Range M
R 55 LL
- 14. Neutron Flux - Wide Range M
R
$2
- 15. Containment Hydrogen Concentration M
R
- 16. Diesel Generator Cooling Water Heat Exchanger RN Flow M
R g
- 17. Containment Spry Heat Exchanger RN Flow M
R
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