ML20206D139
| ML20206D139 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 04/26/1999 |
| From: | Stephen Dembek NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20206D141 | List: |
| References | |
| NUDOCS 9905030312 | |
| Download: ML20206D139 (3) | |
Text
{{#Wiki_filter:. n raro g UNITED STATES l g j NUCLEAR REGULATORY COMMISSION j t WASHINGTON, D.C. 200SHe01 1 %.....f . SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE. CALIFORNIA THE CITY OF ANAHEIM. CALIFORNIA DOCKET NO. 50-361 \\ SAN ONOFRE NUCLEAR GENERATING STATION. U,41T NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.152 License No. NPF-10 1. The Nuclear Regulatory Commission (the Commission) has found that: A. The application for amendment by Southern California Edison Company, et al. (SCE cr the licensee) dated April 24,1999, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; j B. The facility will operats 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 Comm!ssion'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; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and al. applicable requirements have been satisfied. I 2. Accordingly, License No. NPF-10 is amended to approve changes to the Updated Final Safety Analysis Report Section 5.4.7.1.2 as indicated in the attachment to this license amendment. ~ 9905030312 990426 PDR ADOCK 05000361 P PDR
1 , 3. This license amendment is effective as of the date of its issuance and is applicable for 7 days from the date of issuance or until the check valve repair is completed, whichever 1 occurs first. I FOR THE NUCLEAR REGULATORY COMMISSION Stephen Dembek, Chief, Section 2 Project Directorate IV and Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the UFSAR Section 5.4.7.1.2 Date of issuance: April 26,1999
? UPDAYSb N M-MT/ A9 Aw sis RepoC l l periods from normal operating temperature to the refueling temperature. The initial phase of the cooldown is accomplished by heat rejection from the steam generators to the condenser or atmosphere. After the reactor coolant temperature and pressure have been reduced to approximately 350'F and 376 l lb /in.*a, the SCS is put into operation. l In their shutdown cooling function, the LPSI pumps take suction from one of the two RCS hot legs. Heat is removed by circulating this flow through the shutdown cooling heat exchangers (SCHXsi. The cooled flow returns to the RCS through four LPSI headers connectJd to the cold legs. Plant cool-down rate is controlled by flow control valves which permit proportioning the amount of shutdown cooling flow passing through the heat exchangers and heat exchariger bypass line. The SCS reduces reactor coolant temperature to refueling temperature and maintains this temperature during refueling operations. The SCHXs are also used during the recirculation mode following a loss-of-coolant incident for containment spray purposes, as discussed in subsections 6.2.2 and 6.5.2. l The SCS is used in conjunction with steam generator atmospheric dump and emergency feedwater to cool down and depressurize the RCS following a small j break LOCA (see section 6.3). No components of the SCS for Unit 2 are shared by Unit 3, 5.4.7.1.2 Design Criteria In addition to the functional requirements of paragraph 5.4.7.1.1, the following design requirements form the design basis for the SCS: A. The functional requirements defined in paragraph 5.4.7.1.1 must be met assuming the failure of a single active component. B. No single active failure will allow overpressurization of the SCS. l Positive isolation from the RCS is provided whenever the RCS is above the shutdown cooling initiation pressure of 376 lb/in.8a (pressurizer). Isolation valves with appropriate interlocks are provided on the SCS suction line for this purpose. The valves and interlocks are discussed in paragraph 5.4.7.2.2. Overpressure protectwn from the safety injection tanks is discussed in paragraph 6.3.2.2.1. i The SCS is provided with appropriate relief valves for overpressure protection. Design basis for pressure relief l capacity is discussed in paragraph 5.4.7.2.2. C.
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