ML20111B084
| ML20111B084 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 02/28/1985 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20111B089 | List: |
| References | |
| NUDOCS 8503120739 | |
| Download: ML20111B084 (8) | |
Text
/
4 UNITED STATES
[*O)5, b NUCLEAR REGULATORY COMMISSION 5*
/a E WASHINGTON. D. C. 20555 k
DUKE POWER COMPANY DOCKET NO. 50-369 McGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 40 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 July 31, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance:
(i) that the activities authorized by this amendment can be conducted without endangering the healtn and safety of the public, and (ii) that su,ch activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 i
of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-9 is hereby amended to read as follows:
8503120739 850228 PDR ADOCK 05000369 P
.?_
(2) Technical Specifications The Technical Specifications contained in Apnendix A, as revised through Amendment No.
40, are hereby incorggrated into this license.
The licensee shall operate the facility intaccordance with the Tech-nical Specifications and the Environmentbl Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION M
Elinor G. Adensam, Chief' Licensing Branch No. 4 Division of Licensing
Attachment:
Technical Specification Changes Date of Issuance: February 28, 1985 i
f 1
i
)
,(ga rto w
'o UNITED STATES g
y ' s.c g
NUCLEAR REGULATORY COMMISSION
- *~
-p WASHINGTO N, D. C. 20555
\\...../
DUKE POWER COMPANY DOCKET NO. 50-370 McGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 21 License No. NPF-17 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application fo r amendment to the McGuire Nuclear Station, Unit 2 (the facility) Facility Operating License No. NPF-17 filed by the Duke Power Company (licansee) dated July 31, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR
~
Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance:
(i) that the activities authorize'd 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 license amendment will not b'e inimical to the common defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfief.
2.
Accordinn y, the license is hereby amended by page changes to the Technical
~
Specifications as indicated in the attachments to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-17 is hereby amended to read as follows:
l\\ (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 21, are hereby incorporated into this license.
The licensee shall operate the facility in accordance with the Tech-nical Specifications and the Environmental Protection Plan.-
I 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION N
Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing
Attachment:
Technical Specification Changes Date of Issuance:
February 28, 1985 e
i l
l
y i
ATTACHMENT TO LICENSE AMENDMENT NO. 40 FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND TO LICENSE AMENDMENT NO. 21 FACILITY OPERATING LICENSE NO. NPF-17 DOCKET NO. 50-370 Replace the following p' ages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change. The corresponding over-leaf page is also provided to maintain document completeness.
Amended Overleaf
- f. age Page 3'
3-56
_3/4 3-55 3
3-57 h
/
b t
)
4 J'
.-._,7
._,.,.r.
_4y
4 a-4 INSTRUMENTATION ACCIDENT M3NITORING 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 HOT SHUTOOWN 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 OPERR8LE requirements of y
Table 3.3-10, restore the inoperable channel (s) to OPERABLE status 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 HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
c.
The provisions of Specification 3.0.4 are not applicable.
3 SURVEILLANCE REQUIREMENTS 4.3.3.6 Each accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL l
CALIBRATION operations at the frequencies shown in Table 4.3-7.
l l'
~
McGUIRE - UNITS 1 and 2 3/4 3-55
c i
TABLE 3.3-10 W
ACCIDENT MONITORING INSTRUMENTATION REQUIRED MINIMUM m
NO. OF CHANNELS INSTRUMENT CHANNELS OPERABLE C5 1.
Containment Pressure 2
1 d
~3.-
ReactorCoolantPressure-WideQInge COLD (Wide Range) 2 1
2.
Reactor Coolant Temperature - T and T H
2 1
g' 4.
Pressurizer Water Level 2
1 R
5.
Steam Line Pressure.
2/ steam generator 1/ steam generator 6.
Steam Generator Water Level - Narrow Range 2/ steam generator 1/ steam generator m
7.
Refueling Water Storage ~6ank Water Level 2
1 8.
Auxiliary Feedater Flow Rate 2/ steam generator 1/ steam generator 9.
Peactor Coolant System Subcooling Margin Monitor 2***
1 l
10.
PORV Position Indicator
- 2/ valve 1/ valve 11.
PORV Block Valve Position Indicator **
1/ valve 1/ valve 12.
Safety Valve Position Indicator 2/ valve 1/ valve 13.
Containment Water Level (Wide Range) 2 1
,w 3
14.
In Core Thermocouples 4/corequadrant 2/ core quadrant 15.
Unit Vent - High Range Noble Gas Monitor 1
1 wa (High-High Range - EMF-36) m 16.
Steam' Relief - High Range Monitor 1/ steam line 1/ steam line (Unit 1 - EMF-24, 25, 26, 27)
(Unit 2 - EMF-10, 11, 12, 13) 17.
Containment Atmosphere - High Range Monitor 1
1 (EMF-Sla or 51b)
(
18.
Reactor Vessel Level Instrumentation ****
a.
Wide Range 2
1 FF b.
Narrow Range 2
1 EE eE yy "Not applicable if the associated block valve is in the closed position.
- Not applicable if the associated block valve is in the closed position and power is removed.
- 0nly one channel per unit is required until the end of the first refueling outage following 1/86 for each unit.
i
'4
- Not applicable until the beginning of Cycle 4 for Unit 1 and Cycle 3 for Unit 2.
oe bb EE i
nn N
f
s TABLE 4.3-7
{
ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 5
CHANNEL CHANNEL M
INSTRUMENT CHECK CALIBRATION l.
Containment Pressure N
R E
]
2.
Reactor Coolant Temperature - T and TCOLD (Wide Range)
M R
H0T 3.
Reactor Coolant Pressure - Wide Range M
R 9l
-4.
Pressurizer Water Level M
R o.
5.
Steam Line Pressure M
R m
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 g
10.
PORV Position Indicator M
R 11.
PORV Block Valve Position Indicator M
R 9
1",
12.
Safety Valve Position Indicator M
R 13.
Containment Water Level (Wide Range)
M R
14.
In Core Thermocouples M
R 15.
Unit Vent - High Range Noble Gas Monitor i
M R
(High-High Range - EMF-36) gg 16.
Steam Relief - High Range Monitor M
R gy (Unit 1 - EMF-24, 25, 26, 27) gg (Unit 2 - EMF-10, 11, 12, 13) 17.
Containment Atmosphere - High Range Monitor M
R (EMF-51a or 51b) x,,
??
18.
Reactor Vessel i.evel Instrumentation gy a.
Wide Rangs M
R b.
Narrow Range W
R E?
WW
-m vv