ML20129D217
| ML20129D217 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 10/21/1996 |
| From: | Mckee P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20129D224 | List: |
| References | |
| NUDOCS 9610240232 | |
| Download: ML20129D217 (5) | |
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g-UNITED STATES j
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2066tM001
.....,o 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 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 204 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 November 21, 1995, 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 compliance with the Commission's regulations; i
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.
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9610240232 961021 PDR ADOCK 05000336 P
. 2.
Accordingly, the license is amended by changes to the Technical Specifica+. ions 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 Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 204, 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.
I FOR THE NUCLEAR REGULATORY COMMISSION
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Phillip F.
cKee, Director l
Northeast Utilities Project Directorate Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 21, 1996 j
4 I
ATTACHMENT TO LICENSE AMENDMENT N0.204 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 5-4 5-4 l
B 3/4 6-2 B 3/4 6-2 l
l I
l l
l l
l
l l.'
DESIGN FEATURES i
DESIGN PRESSURE AND TEMPERATURE i
5.2.2 The reactor containment building is designed and shall be maintained j
for a maximum internal pressure of 54 psig and an equilibrium liner l j
temperature of 289'F.
PENETRATIDNS 4
5.2.3 Penetrations through the reactor containment building are designed and shall be maintained in accordance with the original design provisions j
contained in Section 5.2.8 of the FSAR with allowance for normal degradation j
pursuant to the applicable Surveillance Requirements.
5.3 REACTOR CORE 1
4 FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 217 fuel assemblies with each fuel assembly containing 176 rods. Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 4.5 weight percent of U-235.
CONTROL ELEMENT ASSEMBLIES 5.3.2 The reactor core shall contain 73 full length and no part length control element assemblies.
The control element assemblies shall be designed and maintained in accordance with the original design provisions contained in Section 3.0 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.
5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:
a.
In accordance with the code requirements specified in Section 4.2.2 of the FSAR with allowance for normal degradation pursuant of the applicable Surveillance Requirements, b.
For a pressure of 2500 psia, and c.
For a
temperature of 650'F except for the pressurizer which is 700'F.
MILLSTONE - UNIT 2 6-4 Amendment No. 77 177. Jff. 204 0230
-=... _ _.,.. - -
CONTAINMENT SYSTEMS BASES 3/4.6.1.4 INTERNAL PRESSURE The limitations on containment internal pressure ensure that the contain-ment peak pressure does not exceed the design pressure of 54 psig during MSLB or l LOCA conditions.
The maximum peak pressure is obtained from a MSLB event. The limit of 2.1 l psig for initial positive containment pressure will limit the total pressure to less than the desi p pressure and is consistent with the accident analyses.
3/4.6.1.5 AIR TEMPERATURE The limitation on containment air temperature ensures that the contain-ment air temperature does not exceed the worst case combined LOCA/MSLB air temperature profile and the liner temperature of 289'F. The containment air and liner temperature limits are consistent with the accident analyses.
3/4.6.1.6 CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment vessel will be maintained comparable to the original design standards for the life of the facility. Structural integrity is required to ensure that the vessel will withstand the design pressure of 54 psig in the event of a LOCA or MSLB. The measurement of containment tendon lift off force, the visual and metallurgical examination of tendons, anchorages and liner and the Type A leakage tests are sufficient to demonstrate this capability.
The surveillar.ce requirements for demonstrating the containment's struc-tural integrity are in compliance with the recommendations of Regulatory Guide 1.35 " Inservice Surveillance of Ungrouted Tendons in Prestressed Concrete Containment Structures."
MILLSTONE - UNIT 2 B 3/4 6-2 Amendment No. #, 77. J#,204 0231 e
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