ML20079A069

Amend 183 to License DPR-65,changing Table 3.3-9 of TS by Modifying Indicated Measurement Range for Neutron Flux Monitor on Remote Shutdown Panel

ML20079A069
Person / Time
Site:	Millstone
Issue date:	12/20/1994
From:	Mckee P Office of Nuclear Reactor Regulation
To:
Shared Package
ML20079A072	List: ML20079A069 ML20079A077
References
NUDOCS 9412300131
Download: ML20079A069 (5)

Text

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• 4 UNITED STATES g

NUCLEAR REGULATORY COMMISSION 4

WASHINGTON. D.C. 2066M)001

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2 NORTHEAST NUCLEAR EMERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION. UNIT NO. 2

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AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.183 License No. DPR-65 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 April 22, 1994, j

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; 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 i

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 i

E.

The issuance of this amendment is in accordance with 10 CFR Part i

51 of the Commission's regulations and all applicable requirements have been satisfied.

9412300131 941220 PDR ADOCK 05000336 P

PDR

. 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. DPR-65 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.183, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of issuance, to be implemented within 30 days of issuance.

FOR TH LEAR REGULATORY COMISSION

/

L Phillip F.

cKee, Director Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation a

j

Attachment:

Changes to the Technical Specifications j

Date of Issuance:

December 20, 1994 I

I I

ATTACHMENT TO LICENSE AMENDMENT NO.183 FACILITY OPERATING LICENSE NO. DPR-65 DOCKET NO. 50-336 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 Insert V

V 3/4 3-40 3/4 3-40 l

l i

I l

i l

l l

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6 E

l LINITING COM ITIONS FOR OPERATION A2 SURVEILLANCE REQUIREMENTS l

SECTION 3/4.2 POWER DISTRIBUTION LIMITS Egig i

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3/4.2.1 LINEAR HEAT RATE.................... 3/4 2-1 I

3/4.2.2 Deleted 3/4.2.3 TOTAL INTEGRATED RADIAL PEAKING FACT 0R - FT 3/4 2-9 7

l 3/4.2.4 AZIMUTHAL POWER TILT i

.................. 3/4 2-10 3/4.2.5 Deleted k

3/4.2.6 DNB MARGIN

....................... 3/4 2-13 i

i j

3/4.3 INSTRUMENTATION i

i 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION..........

3/4 3-1 1

3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM

[

i j

INSTRUMENTATION.................... 3/4 3-10 l

3/4.3.3 MONITORING INSTRUMENTATION 3/4 3-26 j

Radiation Monitoring

.................. 3/4 3-26 i

Incore Detectors

.................... 3/4 3-30 i

Seismic Instrumentation................. 3/4 3-32 4

Neteorological Instrumentation 3/4 3-36 I

Remote Shutdown Instrumentation............. 3/4 3-39 Fire Detection Instrumentation 3/4 3-43

}

Accident Monitoring................... 3/4 3-46 f

Radioactive Liquid Effluent Monitoring Instrumentation 3/4 3-50 j

Radioactive Gaseous Effluent Monitoring Instrumentation. 3/4 3-56 l

3/4.4 REACTOR COOLANT SYSTEM i

3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION.......... 3/4 4-1 4

Startup and Power Operation............... 3/4 4-1 Hot Standby.......................

3/4 4-la Shutdown

........................ 3/4 4-lb i

i NILLSTONE - UNIT 2 V

Amendment No. M, M. M. S.

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TABLE 3.3-9 m

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REMOTE SHUTDOWN MONITORING INSTRUMENTATION l

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MINiltM m

READOUT MEASUREMENT CHAIGIELS INSTRUMENT LOCATION RANGE OPERA 8LE 1.

Wide Range Logarithmic Neutron Flux Hot Shutdown Panel 10 % - 1005 1

Monitor (C-21) j 2.

Reactor Trip Breaker Indication Reactor Trip OPEN-CLOSE 1/ trip breaker Switchgear (Q03) w 3.

Reactor Cold Leg Temperature Hot Shutdown Panel 0-600*F 1

)

(C-21) w 8'

4.

Pressurizer Pressure Hot Shutdown Panel a.

Low Range (C-21) 0-1600 psia 1

b.

High Range 1500-2500 psia 1

5.

Pressurizer Level Hot Shutdown Panel 0-1001 1

(C-21) 6.

Steam Generator Pressure Hot Shutdown Panel 0-1200 psia 1/ steam generator (C-21) 7.

Steam Generator Level Hot Shutdown Panel 0-1005 1/ steam generator (C-21) f 3

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