ML20235G863

Amend 11 to License DPR-21,revising Tech Spec Table 3.7.1, Primary Containment Isolation to Reflect Plant Mods & to Increase Scope of Table to Include Check Valves & Valves Opened During Operation for Testing

ML20235G863
Person / Time
Site:	Millstone
Issue date:	09/08/1987
From:	Thomas C Office of Nuclear Reactor Regulation
To:
Shared Package
ML20235G861	List: ML20235G859 ML20235G863 ML20235G868
References
NUDOCS 8709300266
Download: ML20235G863 (7)

Text

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NORTHEAST NUCLEAR ENERGY COMPANY DOCKET NO. 50-245 1 MILLSTONE NUCLEAR POWER STATION, UNIT N0. 1  ;

I AMENDMENT 10 FACILITY OPERATING LICENSE j Amendment No. 11 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,(thelicensee)datedApril 28, 1987, 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 1

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.

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2. Accordingly,'the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendmentandParagraph2.C.(2)ofFacilityOperatingLicense No. DPR-21 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.11 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 02 0 0. *V ,

Cecil 0. Thomas, Director Integrated Safety Assessment Project Directorate Division of Reactor Projects - III', IV, V and Special' Projects

Attachment:

Changes to the Technical j Specifications W Date'of Issuance: September 8, 1987 J I

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, ' ATTACHMENT TO LICENSE AMENDMENT NO.11 H FACILITY OPERATING LICENSE NO. DPR-21=

DOCKET N,0. 50-245 Revise Appendix A Technical Specification's by removing the pages indentified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.-

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4.7 CONTAINMENT SYSTEMS BASES i

In order to assure that the doses that may result from a steam line break l

' do not exceed the 10 CFR 100 guidelines, it is necessary that no fuel rod perforation resulting from the accident occur prior to closure of the main steam'line isolation valves. Analyses suggest that fuel rod cladding perforations would be avoided for main steam valve closure times, including instrument delay, as long as 10.5 seconds. However, for added macgin, the Technical Specifications require a valve closure time of not greater than five seconds.

Table 3 7.1, Primary containment Isolation, does not include all containment isolation valves. The table includes valves which receive a containment isolation signal, check valves and valves intermittently opened during power operation for testing and/or sampling purposes.

For reactor coolant system temperatures less than 2120F, the containment could not become pressurized due to a loss of coolant accident. These valves are highly reliable, have low service requirement and most are normally closed. The initiating sensors and associated trip channels are also checked to demonstrate the capability for automatic isolation. Ref.

Section V-2.7 and Table V-4 FSAR. The test interval of once per operating cyc}e for automatic initiation results in a failure probability of 1.1 X 10 that a line will not isolate. More frequent testing for valve operability results in a more reliable system.

The main steam line isolation valves are functionally tested on a more frequent interval to establish a high degree of reliability.

The containment is penetrated by a large number of small diameter instrument lines. A program for periodic testing and examination of the flow check valves in these lines is performed as described in Amendment No. 23 to the Provisional Operating License (See Specification 4.7.D.1.b).

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i Hillstone Unit 1 B 3/4 7-11 Amendment No.11 h.. .