ML20205Q978
| ML20205Q978 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 04/14/1999 |
| From: | Clifford J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20205Q981 | List: |
| References | |
| NUDOCS 9904220141 | |
| Download: ML20205Q978 (7) | |
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NORTHEAST NUCLEAR ENERGY COMPANY l
THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.234 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 January 18,1999, 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 (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 complianca 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.
9904220141 990414 PDR ADOCK 05000336 P
. 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.234, 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
- <:. ; I L
James W. Clifford, Section Chief Project Directorate 1-2 Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: April 14, 1999 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 7u 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 verticallines indicating the areas of change.
Remove Insert j
3/4 6-2 3/4 6-2
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3/4 6-5 3/4 6-5 0
B 3/4 6-1 B 3/4 6-1 B 3/4 6-1a r
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CONTAIMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION l
3.6.1.2 Containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of <
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.
l b.
A combined leakage rate of < 0.60 L, for all penetrations and valves subject to Type B and C tests when pressurized to P,.
c.
A combined leakage rate of 0.0072 L, for all penetrations that are secondary containn:nt 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 0.0072 L,, restore the l
leakage rate (s) to within the limit (s) prior to increasing the Reactor Coolant System temperature above 200*F.
SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall te demonstrated in accordance with the Containment Leakage Rate Testing Program.
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MILLSTONE - UNIT 2 3/4 6-2 Amendment No. J M, J M, J77. 7 #. W o<u
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I This Page Intentionally Deleted.
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MILLSTONE - UNIT 2 3/4 6-5 Amendment No. 934 0439
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l' 3/4.6 CONTAINMENT SYSTEMS l
BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyses. This restriction, in conjunc-tion with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.
Primary CONTAINMENT INTEGRITY is required in MODES 1 through 4.
This requires an OPERABLE containment automatic isolation valve system.
In MODES 1, 2, and 3 this is satisfied by the automatic containment isolation signals generated by low pressurizer pressure and high containment pressure.
In MODE 4 the automatic containment isolation signals generated by low pressurizer pressure and high containment pressure are not required to be OPERABLE. Automatic actuation of the containment isolation system in MODE 4 is not required because adequate time is available for plant operators to evaluate plant conditions and respond by manually operating engineered safety features components.
Since the manual actuation (trip pushbuttons) portion of the containment isolation system is required to be OPERABLE in MODE 4, the plant operators can use the manual pushbuttons to rapidly position all automatic containment isolation valves to the required accident position. Therefore, the containment isolation trip pushbuttons satisfy the requirement for an OPERABLE containment automatic isolation valve system in MODE 4.
3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the accident analyses at the peak accident pressure of P,.
As an added conservatism, the measured overall integrated leakage rate is further limited to < 0.75 L, during performance of the periodic tests to account for possible degradation of the containment leakage barriers between leakage tests.
The surveillance testing for measuring leakage rates is in accordance with the Containment Leakage Rate Testing Program.
The Millstone Unit Ho. 2 FSAR contains a list of the containment penetrations that have been identified as secondary containment bypass leakage paths.
3/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and leak rate given in Specifications 3.6.1.1 and MI LSTONE - UNIT 2 8 3/4 6-1 Amendment No. //J, 797, /JJ, 23a
3/4.6 CONTAINMENT SYSTEMS BASE 3 3.6.1.2.
The limitations on the air locks allow entry and exit into and out of the containment during operation and ensure through the surveillance testing that air lock leakage will not become excessive through continuous usage.
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MILLSTONE - UNIT 2 B 3/4 6-1a Amendment No. p3a o44o