ML20045B801
| ML20045B801 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 06/11/1993 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20045B789 | List: |
| References | |
| NUDOCS 9306210105 | |
| Download: ML20045B801 (4) | |
Text
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UNITED STATES lQ ' /
NUCLEAR REGULATORY COMMISSION gj.,,
WASHINGTON. D.C. M55-0@1 CONNECTICUT YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-213 HADDAM NECK PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 159-License No. DPR-61 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Connecticut Yankee Atomic Power Company (the licensee), dated March 16, 1993, as supplemented on May 28, 1993, 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 author! zed 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 w be inimical to the common defense and security or to the.ht a' o d safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51-of the Commission's regelations and all applicable requirements have been satisfied.
i 9306210105 930611 PDR ADOCK 05000213 P
PDR a
. 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-61 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specificatior.s contained in Appendix A, as revised through Amendment No.159, 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 THE NUCLEAR REGULATORY COMMISSION
[
Jo F. Stolz, Direct Pr ject Directorate
-4 ivision of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 11, 1993
ATTACHMENT TO LICENSE AMENDMENT NO.159 FACILITY OPERATING LICENSE NO. OPR-61 DOCKET NO. 50-213 Replace the following page of the Appendix A Technical Specifications with 'he enclosed page. The revised page is identified by amendment number and contains vertical lines indicating the areas of change.
Remove Insert 3/4 6-2 3/4 6-2 R
1 J
l CONTAINMENT SYSTEMS s
CONTAINMENT LEAKAGE i
LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of less than or equal to La, 0.18 % by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at Pa, 39.6 psig, or b.
A combined leakage rate of less than 0.00 La for all penetrations
)
and valves subject to Type B and C tests, when pressurized.to Pa.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
With either the measured overall integrated containment leakage rate exceeding 0.75 La or the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 La, restore _ the overall integrated leakage rate to less than 0.75 La and the combined leakage rate for all penetrations subject to Type B and C tests to less than 0.6g La prior to increasing the Reactor Coolant System temperature above 200 F.
SURVEILLANCE RE0VIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule, and shall be determined in conformance with. the criteria specified in Appendix J of 10 CFR Part 50:
a.
Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40 10 month intervals during shutdown at a pressure not less than Pa, 39.6 psig during each 10-year service period.
The third test of each set shall be conducted during the shutdown for the 10-year plant inservice inspection; HADDAM NECK 3/4 6-2 Amendment No.,I5,159 0144