ML20099G020
| ML20099G020 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 07/28/1992 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20099G023 | List: |
| References | |
| NUDOCS 9208140057 | |
| Download: ML20099G020 (4) | |
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UNITED STATES
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.E NUCLEAR REGULATORY COMMISSION
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W ASHINoTON, D.C. 20&4 g
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CONSUMERS POWER COMPA,NJ DOCKET N0_._50-255 EA )) MLS PLANT l
AMENQMENT 10 FA_C1LITY jf[ RATING LI(LNSl Amendment No.151 License No. DPR-20 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Consumers Power Company (the licensee) dated September 27, 1991 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 !;
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; 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; 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.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to the license amen 6nent and Paragraph 2.C.2 of Facility Operating License No. DPR-20 is hereby amended to read as follows:
9 9208140057 920728 PDR ADOCK 05000255 P
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_2 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.151
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment 1.s effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION M
04 Ledyard B. Marsh, Director Project Directnrate III-l Division of Reactor Projects Ill/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: Sily 28,1992 4
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ATTACHMENT TO LICENSE AMENDMENT NO.151 FACILITY OPERATINt LICENSE NO. DPR-20 DOCKET NO. 50-255 Revise Appendix A Technical Specifications by removing the page identified below and inserting the attached page.
The revised page is identified by the amendment number and contains vertical lines indicating the area of change.
REMOVE INSERT 5-2 5-2 l-ll
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5.2 CONTAINMENT DESIGN FEATURES (Cont'd) 5.2.2 Penetrations a.
All penetrations through the steel-?ined concrete structure for 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 a.
The containment air cooling system includes four separate self-contained units which cool the containment air during normal oper ation and limit the pressure rise in the event of a design accident. Three units, with a total cooling water flow of 5580 gpm with an inlet temperature of 85'F, will remove 230 x 106 Btu /hr of heat.
b.
The containment sproy system is capable of removing 233 x 106 Btu /hr (two pumps) from the containment atmosphcre 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 6 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.
5.3 NUCLEAR STFAM SUPPLY SYSTEM (NSSS1 5.3.1 Primary Coolant System Desian Pressure and Temperature The primary coolant system is designed, and shall be maintained:
- a. -In accordance with the Code requirements specified in Section 4.2 of the FSAR with allowance for normal degradation pursuant to the surveillance requirements, b.
For a pressure of 25L ) psia, c.
For a temperature of 650'F, except the pressurizer, which shall be 700*F, and d.
With a volume of approximately 10.0^9 cubic feet.
5-2 Amendment No. Jyy,151 9
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