ML20091E515
| ML20091E515 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 04/08/1992 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Northeast Nuclear Energy Co (NNECO), Connecticut Light & Power Co, Western Massachusetts Electric Co |
| Shared Package | |
| ML20091E518 | List: |
| References | |
| DPR-65-A-056 NUDOCS 9204140227 | |
| Download: ML20091E515 (5) | |
Text
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9'o, UNITED ST ATES t
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NUCLEAR REGULATORY COMMISSION 3
4 WASHINGTON O, C. 20555
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NORTHEAST NUCLEAR ENERGY COMPANY JJ1E CONNECTICVT LIGHT AND POWER COMP M IliE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 i
MILLSTONE NUCLEAR POWF1 JTATION. UNIT NO, 2 M1,NSMtNT TO FACitlTY CPERATING llCENSE N
Amendment No.156 License No. DPR-65 1.
The Nuclear Regulatory Comission (the Comission) has found that:
1.
The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee), dated February 7,1992, 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 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 (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 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 Slaof the Comission's regulations and all applicable requirements h ae been satisfied.
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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 _$gecifications The lechnical Specifications contained in Appendix A, as revised through Amendment No156
, 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 isstiance.
FOR THE NUCLEAR REGULATORY COMMISSION John F.
olz, Director Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 8,1992 e
l 1
ATTACHMENT TO LICENSE AMENDMENT NO.156 FACILITY OPERATING LICENSE NO. DPR-6.5 DOCKET NO. 50-336
. Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by amendment nu:aber and contain vertical lines ~ indicating the areas of change.
4 Remove Insert 3/4 6-2 3/4 6-2 3/4 6-4 3/4 6-4 1
4
CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITINC CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
An overall integrated leakage rate of 5 L, 0.50 percent by a.
weightofthecontainmentairper24hourlatP,,54psig, b.
A combined leakage rate of s 0.60 L for all penetrations and valves subject to Type B and C testl when pressurized to P.
3 A combined leakage rate of 5 0.017 L for all penetrations c.
identifiedinTable3.61assecondafycontainmentbypass leakage paths when pressurized to P,.
APPLICABillH: MODES I, 2, 3 and 4.
ACTION:
With either (a) the measured overall integrated containment leakage rate or (b) with the measured combined leakage rate for all exceeding 0.75 L*v,alves subject to Types B and C tests exceeding 0.60 L, or penetrations and (c) with the combined bypass leakage rate exceeding 0.017 L, restore tfle leakagerate(s)towithinthelimit(s)priortoincreasingtheReactorCoolant 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 confonnance with the criteria specified in Appendix J of 10 CFR 50.
Three Type A tests (Overall Integrated Containment Leakage Rate) a.
shall be conducted at 40110 month intervals
- during shutdown at P l
8 (54 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.
- The test interval for conducting a Type A test shall be extended to allow the second Type.A test, within the second ten-year service period, to be conducted during Cycle 11 refueling outage. This extension expires upon completion of Cycle 11 refueling outage.
l MILLSTONE - UNIT 2 3/4 6-2 Amendment No. JJ/,156 0054
9 4
CONTAINMENT SYSTEMS SURVEILLANCE REDUIREMENTS (Conti m.dl
-g.
- All test leakage rates shall be calculated using observed data converted to absolute values. Error analyses shall be perfomed to select an acceptable integrated leakage measurement system, h.
The provisions of Specification 4.0.2 are not applicable.
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l' MILLSTONE - UNIT 2 3/4 6-4 Amendment No. Jyp,156 0055 f-
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