ML20198E046
| ML20198E046 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 12/17/1998 |
| From: | Bill Dean NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20198E051 | List: |
| References | |
| NUDOCS 9812230325 | |
| Download: ML20198E046 (4) | |
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NUCLEAR REGULATORY COMMISSION i
UNITED STATES t
WASHINGTON, D.C. 206 4 0001
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l NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSE1TS ELECTRIC COMPANY DOCKET NO. 50-336 l
l MILLSTONE NUCLEAR POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 221 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 September 19,1995, complies with the standards ar.d 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; l
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.
9812230325 981217 PDR ADOCK 05000336 p
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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-65 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 221, 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 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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. r William M. Dean, Director Millstone Project Directorate Division of Reactor Projects.1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
December 17, 1998 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 221 FACILITY OPERATING LICENSE NO. DPR-65 DOCKET NO. 50-336 Replace the following page of the Appendix A, Technical Specifications, with the attached page.
The revised page is identified by amendment number and contains vertical lines indicating the areas of change.
Remove Insert 3/4 5-2 3/4 5-2 l
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t ENERGENCY CORE COOLING SYSTENS i
SAFETY INJECTION TANK 5 (Continued)
SURVEILLANCE REQUIREMENTS l
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4.5.1 Each SIT shall be demonstrated OPERABLE:
Verify each SIT isolation valve is fully open at least once per a.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.'"
b.
Verify borated water volume in each SIT is 21080 cubic feet and s 1190 ctabic feet at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. 2i c.
Verify nitrogen cover-pressure in each SIT is 2 200 psig and s 250 psig at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
d.
Verify boron concentration in each SIT is 21720 ppm at least once per 6 months, and once within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after each solution volume l
increase of 21% of tank volume that is not the result of addition from the refueling water storage tank.
Verify that the closing coil in the valve breaker cubicle is removed l
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at least once per 31 days.
f.
Verify that the SIT isolation valves open automatically before the Reactor Coolant System pressure exceeds 1750 psia and on a safety injection signal at least once per 18 months.
(1)
If one SIT is inoperable, except as a result of boron concentration not within limits p.t inoperable level or pressure instrumentation, surveillance is not applicable to the affected SIT.
i (2)
If one SIT is inoperable due solely to inoperable water level l
instrumentation, surveillance is not applicable to the affected SIT.
(3)
If one SIT is inoperable due solely to inoperable pressure l
instrumentation, surveillance is not applicable to affected SIT.
(4) Only required to be performed for affected SIT.
l MILLSTONE - UNIT 2 3/4 5-2 Amendment No. f), IIP 221 0429 8
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