NUREG/CR-2913, Amend 181 to License DPR-72,incorporating Changes to GL 87-01, Relaxation in Arbitrary Intermediate Pipe Rupture Requirements, & NUREG/CR-2913, Two-Phase Jet Loads,
| ML20210G154 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 07/27/1999 |
| From: | Peterson S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20210G158 | List: |
| References | |
| RTR-NUREG-CR-2913 GL-87-01, NUDOCS 9908030017 | |
| Download: ML20210G154 (2) | |
Text
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NUCLEAR REGUL/. TORY COMMISSION I f WASHINGTON, D.C. 20555-0001
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FLORIDA POWER CORPORATION CITY OF ALACHUA CITY OF BUSHNELL CITY OF GAINESVILLE i
CITY OF KISSIMMEE l
CITY OF LEESBURG CITY OF NEW SMYRNA BEACH AND UTILITIES COMMISSION.
CITY OF NEW SMYRNA BEACH CITY OF OCALA ORLANDO UTILITIES COMMISSION AND CITY OF ORLANDO SEMINOLE ELECTRIC COOPERATIVE. INC, CITY OF TALLAHASSEE t>0CKET NO. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.181 License No. DPR-72 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Florida Power Corporation, et al. (the licensees), dated May 28,1998, 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 facility will operate in conformity with the application, tho provisions of the Act, and the rules and regulations of the Commission; j
C.
There is reasonable assurance (i) that the activities authorized by this i
l 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; and
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9900030017 990727 PDR ADOCK 05000302 P
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The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been setisfied.
2.
Accordingly, changes to the updated Final Safety Analysis Report (FSAR) to incorporate the criteria contained in Generic Letter (GL) 87-11 and NUREG/CR-2913 as part of the Crystal River, Unit 3 licensing basis, as set forth in the application for
- amendment by Florida Power Corporation dated May 28,1998, are authorized subject to the following limitations:
The use of the criteria in GL 87-11 for postulating breaks in piping located inside the containment and analyzed to the provisions of United States of America Standards B31.1-1967 shall be subject to the conditions specified in the staff's September 28,1989, letter to Florida Power Corporation, " Crystal River Unit 3 -
High Energy Line Break (HELB) Criteria for Analysis of Piping Outside Containment".
The NUREG/CR-2913 criteria will be used to evaluate jet loads 1 safety-related structures, systems and components due to postulated ruptures in the reactor coolant system (RCS), within the temperature and pressure limitations specified in the report for applicability of the jet model, at distances of greater than 10 pipe diameters from the postulated RCS rupture.
The licensee shall submit the revised description authorized by this amendment with the next update of the FSAR in accordance with 10 CFR 50.71(e).
3.
- This license amendmens is effective as of its date of issuance and shall be implemented as specified in (2) above.
FOR THE NUCLEAR REGULATORY COMMISSION hv Sheri R. Peterson, Chief, Section 2 Project Directorate 11 Division of Project Licensing Management Office of Nuclear Reactor Regulation Date of lasuance:
July 27, 1999