ML20248B875
| ML20248B875 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 09/27/1989 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20248B878 | List: |
| References | |
| NUDOCS 8910030321 | |
| Download: ML20248B875 (5) | |
Text
{{#Wiki_filter:_ UNITED STATES NUCLEAR REGULATORY COMMISSION n y WASHINGTON, D. C. 20665 \\...../ PUBLIC SERVICE. ELECTRIC & GAS COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-354 HOPE CREEK GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 33 License No. NPF-57 1. The Nuclear Reguiatory Commission (the Commission or the NRC) has found that: A. The application for amendment filed by the Public Service Electric & Gas Company (PSE&G) dated August 21, 1989, and supplemented by letter dated September 11, 1989, 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 facFity will operate in conformity with the application, the provision; of the Act, and the rules and regulations of the Commissfoi; C. There is reasonable assurance: (1) 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 set forth in 10 CFR Chapter 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. 2. Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-57 is hereby amended to read as follows: d,. (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 33, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. PSE&G shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Pian. 8910030321 890927 'l PDR ADOCK 05000354 F P FDC _ _ -. _. - _ - - _ _, - _ - - - - - - - - - - - - - - - - - - - - ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
.} 1 3. This license amendment is effective as of its date of issuance. FOR THE NUCLEAR REGULATORY COMMISSION b~ Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technicai Specifications Date of Issuance: September 27, 1989 l -t i 9 . -. - _ _ _.. _.. _ - - - _ ~. - - _.. _ -.
l i ATTACHMENT TO-LICENSE AMENDMENT NO. 33 FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354 i Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised page is identified by Amendment number and contains vertical lines indicating the area of change. Overleaf page provided to maintain document completeness.* Remove Insert 5-3* 5-3* 5-4 5-4 6e s I l
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.n m. _,,,, ' L.. e., t 5 y s LOW POPULATION ZONE FIGURE 5.1.2-1 HOPE CREEK 5-3
~ DESIGN FEATURES s 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 764 fuel assemblies and shall be limited to those assemblies which have been approved for use in BWRs. CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 185 cruciform shaped control rod assemblies. The control material shall be boron carbide powder (B C) and/or 4 hafnium metal. The absorber material has a nominal absorber length of 143 inches.
- 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 5.2 of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements, b. For a pressure of: 1. 1250 psig on the suction side of the recirculation pump. 2. 1500 psig from the recirculation pump discharge to the jet pumps. c. For a temperature of 575 F. VOLUME 5.4.2 The total water and steam volume of the reactor vessel and recirculation system is approximately 21,970 cubic feet at a nominal steam dome saturation temperature of 547 F. 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1.1-1. I t HOPE CREEK 5-4 Amendment No. 33 _ _. _ _ _ _ _ _. _ _ _ _ _ _ _. _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _. _. _ _ _ _ _ _ _ _ _. _ _ _ _ _ _.}}