ML20082G848
| ML20082G848 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 04/10/1995 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20082G852 | List: |
| References | |
| NUDOCS 9504140039 | |
| Download: ML20082G848 (4) | |
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UNITED' STATES c.
S-NUCLEAR REGULATORY COMMISSION If WASHINGTON, D.C. 2006H001
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BALTIMORE GAS'AND ELECTRIC COMPANY DOCKET NO. 50-318 i
CALVERT CLIFFS NUCLEAR POWER PLANT. UNIT NO. 2
. AMENDMENT TO FACILITY OPERATING LICENSE
' Amendment No. 183 License No.-DPR-69 i
l 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Baltimore Gas and Electric Company
-(the licensee) dated February 24, 1995,' complies with the standards and requirements of the Atomic Energy Act.of'1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR
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Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment,
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and paragraph 2.C.2. of Facility Operating License No. DPR-69 is hereby amended to read as follows:
t 9504140039 950410 PDR ADOCK 05000318 P
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. 2.
Technical-Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.103, 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 to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Ledyard B. Marsh, Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: April 10, 1995 J
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ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO.183 FACILITY OPERATING LICENSE NO. DPR-69 DOCKET NO. 50-318 Revise Appendix A as follows:
Remove Paae Insert Pace 3/4 6-2 3/4 6-2 a
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3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Containment Leakaae LIMITIM CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of:
1.
5 L. (346,000 SCCM), 0.20 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., 50 psig, or 2.
5 L, (44,600 SCCM), 0.042 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 a reduced pressure of P, 25 psig.
b.
A combined leakage rate of < 0.50 L (173,000 SCCM), for all penetrations and valves sublect to Iype B and C tests 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 (259.500 SCCM), or 0.75 L applicable, or (b) with the m,asured combined leakage ra. (33,400 SCCM), as e
te for all penetrations and valves subject to Types B and C tests exceeding 0.50 L,
restore the overall integrated containment leakage rate to less than or equal to 0.75 L or less than or equal to 0.75 L.,lves subject to Type B an as applicable, and the combined leakage rate for all penetrations and va C tests to less than or equal to 0.50 L, prior to increasing the Reactor Coolant System temperature above 200 F.
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$URV5ILLANCEREQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be detemined in confomance with the criteria, methods and provisions specified in 10 CFR Part 50 Appendix J:
a.
Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted during shutdown at either P, (50 psig) or at P (25 psig). The frequency of the Tyse A tests shall be in accordance with 10 CFR Part 50, Appendix J. as modified by approved exemptions.
i CALVERT CLIFFS - UNIT 2 3/4 6-2 Amendment No. 183
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