ML20077C595
| ML20077C595 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 11/30/1994 |
| From: | Mckee P Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20077C596 | List: |
| References | |
| NUDOCS 9412050268 | |
| Download: ML20077C595 (4) | |
Text
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UNITED STATES
[
j NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 2055fHX)01
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NORTHEAST NUCLEAR ENERGY COMPANY. ET AL.
DOCKET NO. 50-423 MILLSTONE NUCLEAR POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 98 License No. NPF-49 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee), dated June 30, 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 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 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.
9412050268 941130 PDR ADOCK 05000423 P
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- 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-49 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 98
, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in 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 the date of its issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Phillip F. McKee, Director Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: November 30, 1994 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 98 FACILITY OPERATING LICENSE NO. NPF-49 DOCKET N0. 50-423
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Replace the following page of the Appendix A Technical Specifications with the enclosed page. The revised page is identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert 3/4 3-30 3/4 3-30 t
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33 TABLE 3.3-4 (Continued)
S ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS a
m SENSOR TOTAL ERROR i
g FUNCTIONAL UNIT ALLOWANCE fTA)
I (S)
TRIP SETPOINT AllDNRI VALE A
8.
Loss of Power a.
4 kV Bus Undervoltage N.A.
N.A.
N.A.
2 2800 2 2720 volts (Loss of Voltage) volts with with a s 2 a 5 2 second second time time delay.
delay.
b.
4 kV Bus Undervoltage N.A.
N.A.
N.A.
2 3730 volts 2 3706 volts l.
(Grid Degraded Voltage) with a 5 8 with a s 8 second time second time
$~
delay with ESF del y with ESF actuation or actuation or
< 300 second
< 300 second 8
ilme delay Timedelay without ESF without ESF actuation.
actuation.
9.
Engineered Safety Features Actuation System Interlocks a.
Pressurizer Pressure, P-Il N.A.
N.A.
N.A.
s 1985 psig s 1995 psig f
b.
Low-Low T,,g, P-12 N.A.
N.A.
N.A.
2 553*F 2 549.6*F g
c.
Reactor Trip, P-4 N.A.
N.A.
N.A.
N.A.
N.A.
,E
- 10. Emergency Generator Load N.A.
N.A.
N.A.
N.A.
N.A.
Sequencer y
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