ML20215N421

Amend 86 to License DPR-61,clarifying Definition of Containment Integrity in Tech Spec 1.8.2.b to Permit Normally Closed Manual Isolation Valves SI-V-863 A,B,C & D to Be Opened for Periodic Surveillances

ML20215N421
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	10/30/1986
From:	Charemagne Grimes Office of Nuclear Reactor Regulation
To:
Shared Package
ML20215N412	List: ML20215N411 ML20215N421 ML20215N427
References
NUDOCS 8611050385
Download: ML20215N421 (4)

Text

1. 'o,, UNITED STATES 8 o NUCLEAR REGULATORY COMMISSION r,  ; WASHINGTON, D. C. 20655

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' CONNECTICUT YANKEE ATOMIC POWER COMPANY

. HADDAM NECK PLANT i DOCKET N0. 50-213 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 86 License No. DPR-61

1. The Nuclear Regulatory Connission (the Commission) has found that:

A. The application for amendment by Connecticut Yankee Atomic Power Company (the. licensee), dated August 29, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as l amended (the Act), and the Commission's rules and regulations as 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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8611050385 861030 PDR ADOCK 05000213 P PDR r

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2. Accordingly, the license is amended by changes to the technical specifications,1 s indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. DPR-61 is hereby a amended to read as follows:

(2) Technical Specifications

! The technical specifications contained in Appendix A, as revised through Amendment No. 86, 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 its date of issuance.

FOR THE NUCLEAR REGULATORY COMISSION W .L .

Christopher I. Grimes, Direc or Integrated Safety Assessment Project Directorate Division of PWR Licensing - B

Attachment:

Changes to the Technical Specifications Date of Issuance:. October 30, 1986 l

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ATTACHMENT TO LICENSE AMENDMENT NO. 86 FACILITY OPERATING LICENSE NO. DPR-61 DOCKET NO. 50-2I3

, Replace the following page of the Appendix A technical specifications with the enclosed page as indicated. The revised page is identified by the captioned amendment number and contains a vertical line indicating the area of change.

REMOVE INSERT 1-2 1-2 i

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DEFINITIONS i

CONTAINMENT INTEGRITY 1.8 CONTAINMENT INTEGRITY shall exist when:

1.8.1 The Eontainment automatic isolation valve system is OPERABLE.

• 1.8.2 All penetrations required to be closed during accident conditions are either:

a. Capable of being closed by OPERABLE containment automatic isolation valves, or

b. Closed by manual valves, blind flanges, or deactivated automatic valves secured and locked in their closed positions.

NOTE 1) Normally-closed isolation valves listed in Table 3.11-2, l which fail closed on loss of power and are capable of being closed within 60 seconds of a containment isolation ,

actuation signal (CIAS) by an operator utilizing norma! l control switches and normal position indication within the main control room may be opened for periodic testing.

NOTE 2) Normally-closed manual isolation valves SI-V-863A, B, C,. and D and SA-V-413 may be opened for periodic surveillances. In addition, SA-V-413 may be opened to

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allow for maintenance activities. While these valves are  ;

open, a locally stationed operator will be in direct  !

communication with the control room. This ensures that i the valves are capable of being closed within 60 seconds  !

of a containment isolation actuation signal.

1.8.3 All equipment hatches are closed and sealed, and 1.8.4 Each door in each air lock is closed and sealed except when the air lock is being used for normal transit entry and exit through the containment, then at least one air lock door shall be closed and sealed.

CHANNEL CALIBRATION 1.9 A CHANNEL CALIBRATION shall be the adjustment of channel output such that it responds, with acceptable range and accuracy, to known values of the parameter which the channel measures. Calibration shall encompass the entire channel, including equipment actuation, alarm, or trip.

CHANNEL CHECK 1.10 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication with other indications derived from independent instrument channels measuring the same parameter.

1-2 Amendment Nos. 86

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