ML20236K099

Amend 4 to License DPR-21,lowering RWCU Sys Isolation Setpoint from Existing Group 3 Isolation Signal to Group 5 (Reactor Low Water Level to lo-lo Water Level)

ML20236K099
Person / Time
Site:	Millstone
Issue date:	07/17/1987
From:	Thomas C Office of Nuclear Reactor Regulation
To:
Shared Package
ML20236K088	List: ML20236K085 ML20236K099 ML20236K108
References
NUDOCS 8708060410
Download: ML20236K099 (6)

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NORTHEAST NUCLEAR ENERGY COMPANY DOCKET NO. 50-245 MILLSTONE NUCLEAR POWER STATION, UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.4 License No. DPR-21 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by the Northeast Nuclear Energy Company, (the licensee) dated February 13, 1987, complies with 1

the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commis.; ion'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 (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; 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.

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8708060410 870717 DR ADOCK 05000245 PDR

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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. DPR-21 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised l

• through Amendment No. 4, 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 its issuance.

FOR THE NUCLEAR' REGULATORY COMMISSION 0 :cs A 0 Y M

Ce~il'O. Thomas, Director c

Integrated Safety Assessment Project Directorate Division of Reactor Projects - III, IV,.V and Special-Projects

Attachment:

Changes to the Technical Specifications l

Date of Issuance: July 17, 1987 I

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1 ATTACHMENT TO LICENSE AMENDMENT NO. 4 FACILITY OPERATING LICENSE NO. OPR-21 J

DOCKET NO. 50-245 Revise Appendix A Technical Specifications by removing the page indentified I

below and inserting the enclosed page.

The revised page is identified by l

the captioned amendment number and contain marginal lines indicating the area of change; j

REMOVE INSERT 3/4 7-15*

3/4 7-15*

Table 3.7.1, 3/4 7-16 Table 3,7.1, 3/4 7-16 Table 3.7.1, 3/4 7-17 Table 3.7.1, 3/4 7-17 l

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• 0verleaf page provided to maintain document completeness.

No changes contained on this page.

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i LIMITING C6NDIT!0N FOR OPERATION l

I 3.7 CONTAINMENT SYSTEMS In the event any isolation valve specified in Table 3.7.1 becomes 3.7.0.2.

inoperable, reactor power operation may continue provided at least one valve in each line having an inoperable valve is in the mode corresponding to the isolated condition.

3., If Specification 3.7.0 cannot be met, initiate an orderly shutdown and have reactor in the COLD SHUTDOWN or REFUEL CONDITION withi 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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SURVEILLANCE REQUIREMENT l

Whe.never an isolation valve listed in Table 3.7.1 is inoperable, the j

4.7,0.2.

position of at least one other valve in each line having an inoperable valve shall be recorded daily.

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