ML20206H273
| ML20206H273 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 05/05/1999 |
| From: | Peterson S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20206H276 | List: |
| References | |
| NUDOCS 9905110129 | |
| Download: ML20206H273 (4) | |
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j NUCLEAR REGULATORY COMMISSION WASHINOTON, D.C. 20555-0001 4 *****,o 9
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FLORIDA POWER CORPORATION CITY OF ALACHUA CITY OF BUSHNELL CITY OF GAINESVILLE CITY OF KISSIMMEE 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 DOCKET NO. 50 302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.176 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 January 27,1999, 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, 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 i
security or to the health and safety of the public; and 4
9905110129 990505 PDR ADOCK 05000302 P
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E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the l
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 this license amendment, and paragraph 2.C(2) of Facility l
Operating License No. DPR-72 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.176,are hereby incorporated in the license. Florida Power Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
%k Ib Sheri R. Peterson, Chief, Section 2 Project Directorate 11 Division of Project Licensing Management Office of Nuclear Reactor Regulation Date of issuance:
May 5, 1999 i
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O ATTACHMENT TO LICENSE AMENDMENT NO.176 TO FACILITY OPERATING LICENSE NO. DPR-72 DOCKET NO. 50-302 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by amendment number and contains a vertical line indicating the area of change.
Remove Paae insert Paae 5.0-15 5.0-15
e.
v
. Procedures, Programs and Manuals 5.6
-5.6 Procedures, Programs and Manuals 5.6.2.10
'OTSG Tube Surveillance Program (continued) 3.
The:above-required inservice inspections'of OTSG tubes.shall be performed at the following frequencies except, a one-time
- change for Cycle.11 is granted to modify the scheduled inspection frequency from'a calendar-based; interval to an interval of up to 21.6 months of operating time at a L
temperature of.500 F or above ~(measured at the hot leg side).
This;will allow the OTSG tube inspection to coincide with Refuel Outage 11R:
a.
Inservice. inspections shall be performed at intervals of not less than 12 nor more than 24 calendar months after the previous inspection.
If two consecutive inspections following service under all volatile treatment (AVT) conditions, not including the preservice inspection, result in all inspection results falling into the C-1 category, or if two consecutive inspections demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the inspection interval may be extended to a maximum of once per 40 months, b.
If the inservice inspection of an OTSG, conducted in accordance with. Table 5.6.2-2 or Table 5.6.2-3 requires a third sample inspection whose results fall in Category C-3, the inspection frequency shall be reduced to at least once per 20 months. The reduction in inspection frequency shall apply until a subsequent inspection demonstrates that a third sample inspection is not required.
J c.
Additional unscheduled inservice inspections shall be performed on each OTSG in accordance with the first sample inspection specified in Table 5.6.2-2 or Table 5.6.2-3 during the shutdown subsequent to any of the following conditions:
i 1.
Primary-to-secondary tube leaks (not including leaks originating from tube-to-tube sheet welds) in excess of the limits of Specification 3.4.12, 2.
A seismic occurrence greater than the Operating Basis Earthquake, 3.
A loss-of-coolant accident requiring actuation of the engineered safeguards, or 4.
A main steam line or feedwater line break.
(continued)
Crystal River Unit 3 5.0-15 Amendment No. 176
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