ML20084Q311
| ML20084Q311 | |
| Person / Time | |
|---|---|
| Site: | Palisades  (DPR-20-A-166) |
| Issue date: | 05/22/1995 |
| From: | Kennedy J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20084Q313 | List: |
| References | |
| NUDOCS 9506080562 | |
| Download: ML20084Q311 (4) | |
Text
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w e ver pw t-UNITED STATES
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. NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. SO90M001 i
CONSUMERS POWER COMPANY DOCKET N0. 50-255 PALISADES PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.166 i
License No. DPR,
-1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Consumers Power Company (the licensee) dated October 20, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
l 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 Comission's regulations; l
D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health an1 safety of the public; j
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.
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to the license amendment and Paragraph 2.C.(2) of Facility Operating License No. DPR-20 is hereby
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amended to read as follows:
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9506080562 950522 PDR ADOCK 05000255 i
P PDR
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-2 Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 166, and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
& (.
Janet L. Kennedy, Project Manager Project Directorate Ill-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 22, 1995 W
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ATTACHMENT TO LICENSE AMENDMENT NO.166 FACILITY OPERATING LICENSE NO. DPR-20 DOCKET NO. 50-255 Revise fgpendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
REMOVE INSERT 5-2 5-2
I:
5.2 CONTAINMENT DESIGN FEATURES (Cont'd) 5.2.2 Penetrations All penetrations through the steel-lined concrete structure for a.
electrical conductors, pipe, ducts, air locks and doors are of the double-barrier design.
(
b.
The automatically actuated containment isolation valves are designed to close upon high radiation or high pressure in the containment structure.
No single component failure in the actuation system will prevent the isolation valves from functioning -
as designed.
5.2.3 Containment Structure Coolina Systems The containment air cooling system includes four separate self-a.
contained units which cool the containment air during normal operation and limit the pressure rise in the event of a design accident.
Three units, with a total cooling water flow gf 5580 gpm with an inlet temperature of 85'F, will remove 230 x 10 Btu /hr of heat.
1 b.
The containment spray system is capable of removing 233 x 10' Btu /hr (two pumps) from the containment atmosphere at 283'F by spraying the water from the 270,000-gallon SIRW tank.
Recirculation of spray water from the containment sump through heat exchangers into the containment atmosphere is also provided. Under this mode of operation, the heat removal capability is 167 x 10' Btu /hr based upon 4000 gpm of component cooling water flow with 114*F inlet temperature through the heat exchanger and 1420 gpm of spray water flow at 283*F inlet temperature.
i 5.3 NUCLEAR STEAM SUPPLY SYSTEM (NSSS) 5.3.3 Primary Coolant Systen Desian Pressure and Temoerature The primary coolant system is designed, and shall be maintained:
In accordance with the Code requirements specified in a.
Section 4.2 of the FSAR with allowance for normal degradation pursuant to the surveillance requirements, i
b.
For a pressure of 2500 psia, t
For a temperature of 650*F, except the pressurizer, which shall be c.
700'F, and d.
With a volume of approximately 10,900 cubic feet.
i S-2 AmendmentNo.JJE,fMf, l 166
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