ML20195J185
| ML20195J185 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 06/14/1999 |
| From: | Peterson S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20195J189 | List: |
| References | |
| NUDOCS 9906180119 | |
| Download: ML20195J185 (4) | |
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g NUCLEAR REGULATORY COMMISSION
%,,,,, ***g WASHINGTON, D.C. 2055W1 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 BEACB 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 I
Amendment No.179 License No. DPR-72 l
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Florida Power Corporation, et al. (the i
licensees), dated September 30,1998, 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, the provisions of the Act, and the rules and regulations of the Commission; e
C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the s
public, and (ii) that such activities will be conducted in compliance with the l
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 9906190119 990614 5
PDR ADOCK 05000302 P
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2-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, changes to the updated Final Safety Analysis Report (FSAR) and associated Technical Specification Bases, to state that the gaseous radioactivity monitor would require approximately 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> to detect a 1 gallon per minute leak from the reactor coolant system, as set forth in the application for amendment by Florida Power Corporation dated September 30,1998, are authorized. The licensee shall submit the revised description authorized by this amendment with the next update of the FSAR and Technical Specification Bases in accordance with 10 CFR 50.71(e).
3.
This license amendment is effective as of its date of issuance and shall be implemented as specified in (2) above.
FOR THE NUCLEAR REGULATORY COMMISSION fofC~ kl.
$3l wl, Sheri R. Peterson, Chief, Section 2 Project Directorate ll Division of Project Licensing Management Office of Nuclear Reactor Regulation Date of issuance:
June 14, 1999 I
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ATTACHMENT TO LICENSE AMENDMENT NO. 179 TO FACILITY OPERATING LICENSE NO. DPR-72 DOCKET NO. 50-302 l
l Replace the following page of the Appendix "A" Technical Specifications with the enclosed i
I page. The revised page is identified by amendment number and contains a vertical line indicating the area of change.
1 Remove Paae Insert Paae
' B 3.4-65 B 3.4-65 1
e l
l P
1
E RCS Leakage Detection Instrumentation l
B 3.4.14 I
B 3.4 REACTOR COOLANT SYSTEM (RCS)
B 3.4.14 RCS Leakage Detection Instrumentation BASES i
BACKGROUND 10 CFR 50, Appendix A, GDC 30, (Ref. 1) requirec means be provided for detecting and, to the extent practical, l
identifying the location of the source of RCS LEAKAGE.
j Regulatory Guide 1.45 (Ref. 2) describes acceptable methods for selecting leakage detection systems.
Leakage detection systems must have the capability to detect reactor coolant pressure boundary (RCPB) degradation as soon after occurrence as practical to minimize the potential for propagation to a gross failure.
Thus, an early indication or warning signal is necessary to permit proper evaluation of all unidentified LEAKAGE.
The containment sump collects unidentified LEAKAGE and is instrumented to alarm on increasing level and has the capability to detect a leakage rate of I gpm in less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. This sensitivity is acceptable for detecting increases in unidentified LEAKAGE.
The reactor coolant contains radioactivity that, when released to the containment, can be detected by radiation monitoring instrumentation.
Reactor coolant radioactivity levels will be low during initial reactor startup and for a few weeks thereafter until activated corrosion products have been formed and fission products appear from fuel element claddingcontaminatipnorcladdingdefects.
Instrument sensitivities of 10' monitoring and of 10~,gCi/cc radioactivity for particulate j
pCi/cc radioactivity for gaseous monitoring are adequate for these leakage detecticn systems.
The particulate monitoring channel is capable of detecting a change in RCS leak rate of 1 gpm within one hour based on activity levels assumed in the environmental report (0.1%
i failed fuel).
The predominant nuclide of detection for the particulate channel is Rb-88. The gaseous channel requires significantly more time to detect the same change in RCS leak rate (approximately 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />). This is due to the relatively long half-life of its predominant nuclide of detection, Xe-133.
Other installed instrumentation such as RB pressure and Containment Cooling Fan condensate flow also indicate leakage into containment.
These are potentially valuable (continued) l Crystal River Unit 3 B 3.4-65 Amendment No. 179