ML20212G434
| ML20212G434 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 10/27/1997 |
| From: | Mckee P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20212G441 | List: |
| References | |
| NUDOCS 9711060180 | |
| Download: ML20212G434 (5) | |
Text
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NUCLEAR REGULATORY COMMISSION WAaHINGTON D.C. SOM64001 1
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NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY AND WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 209 License No. DPR-65 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment filed by Northeast Nuclear Energy Com)any, et al. (the licensees) dated Se)tember 2,1997, complies wit 1 the standards and requirements of tie Atomic Energy Act of 1954, is 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 Comission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducter 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.
9711060100 971027 DR ADOCK 05 36
. 2.
Accordingly, Facility Operating License No. DPR-65 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Opersting License No. DPR-65 is hereby amended to read as follows:
(2)
Technical Soecifications The Technical Specifications contained in Ap)endix A, as revised through Amendment No. 209, are here)y incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of its date of issuance to be implemented within 30 days from the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
=
Phillip F McKee Deputy Director for Licensing Special Projects Office Office of Nuclear Reactor Regulation
Attachment:
Changes to Technical Specifications Date of Issuance: October 27, 1997-t
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ATTACHMENT TO LICENSE AMENDMENT NO. 209 FACILITY OPERATING LICENSE NO. DPR-65 DOCKET NO. 50-336 Replace the following ) ages of the Operating License and Appendix A. Technical Specifications, with tie attached pages..The revised pages are identified by smendment number and c:,ntain vertical lines indicating the areas of change.
Remove Insert 3/4 6-8 3/4 6-8 8 3/4 6-2 B 3/4 6-2
D CONTAINMENT SYSTEMS INTERNAL PRES 5URE LINITING CONDITION FOR OPERATION 3.6.1.4 Primary containment internal pressure shall be maintained between
-12 inches Water Gauge and +1.0 PSIG.
l APPLICABILITY: HODES 1, 2, 3 and 4.
E110H:
With the containment internal pressure in excess of or below the limits above, restore the internal pressure to within the limits within I hour or be in HOT STANDBY W1 thin the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; go to COLD SHUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
SURVEILLANCE REQUIRENENTS 4.6.1.4 The primary containment internal prassure shall be determined to within the limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
MILL 5 TONE - UNIT 2 3/46-8 ktendment No. 209
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CONTAINMENT SYSTEMS BASES 2/4.6.1.4 INTERNAL PRES $1 E 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 LOCA conditions.
The maximum peak pressure is obtained from a MSLB event. The limit of 1.0 l psig for initial positive containment pressure will limit the total pressure to less than the design pressure and is conststent 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 28g'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 vassel will be maintained comparable to the original design standards for the life of the facility.
Structurel 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 surveillance 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."
o glSTONE-UNIT 2 B 3/4 6 2 Amendment No. JJ. 77, JJJ.- Jpp, 209
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