ML20083A411
| ML20083A411 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 05/03/1995 |
| From: | Mckee P Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20083A413 | List: |
| References | |
| NUDOCS 9505100238 | |
| Download: ML20083A411 (4) | |
Text
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UNITED STATES j
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NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20065 4001
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NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION. UNIT NO. 2 i.
AMENDMENT TO FACILITY OPERATING LIC1]LSE Amendment No.187 License No. DPR-65 l
1.
The Nuclear Regulatory Commission (the Comission) has found that:
]
A.
The application for amendment by Northeast Nuclear Energy I
Company, et al. (the licensee) dated October 18, 1994, supplemented February 21, 1995, complies with the standards and requirements of the Atomic. Energy Act of 1954, as amended (the i
Act), and the Commission's rules and regulations set forth in 10 I
CFR Chapter I;
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B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; t.
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 E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
9505100238 950503 PDR ADOCK 05000336 P
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- 2.
Accordingly, the license is amended by changes to the Technical
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Specifications as indicated in the attachment to this license amendment, 1
h and paragraph 2.C.(2) of Facility Operating License No. DPR-65 is hereby amended to read as follows:
l (2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.187, 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.
l FOR THE NUCLEAR REGULATORY COP 911SSION r
WW Phillip F. McKee, Director Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation j
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 3,1995 t
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ATTACHMENT TO LICENSE AMENDMENT NO.187 FACILITY OPERATING LICENSE-NO. DPR-65 DOCKET NO. 50-336 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert 3/4 6-2 3/4 6-2 i
1 l
1 1
CONTAIMEN SYSTEMS CONTAIMENT LEAKAGE LIMITING COM ITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of 1 L 0.50 percent 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 P, 54 psig.
b.
A combined leakage rate of s 0.60 L for all penetrations andvalves,subjecttoTypeBandCIestswhenpressurizedto P,.
c.
A combined leakage rate of 5 0.017 L, for all penetrations i
identified in Table 3.6-1 as secondary containment bypass leakage paths when pressurized to P,.
APPLICABILITY: MODES 1,'2, 3 and 4.
ACTION:
With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L or (b with the measured combined leakage rate for all penetrations and,, valves ) subject to Types B and C tests exceeding 0.60 L, or (c) with the combined bypass leakage rate exceeding 0.017 L restoret$e leakage rate (s) to within the limit (s) prior to increasing t,he Reactor Coolant System temperature above 200*F.
SURVEILLANCE REQUIREMENTS 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 50.
a.
Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at approximately equal intervals during shutdown at P, h (54 psig) during each 10-year service period. The third test of eac set shall be conducted during the shutdown for the 10-year plant inservice inspection.
5 MILLSTONE - UNIT 2 3/4 6-2 Amendment No. 177, J)f,187 ouz