ML20195J190
| ML20195J190 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 06/14/1999 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20195J189 | List: |
| References | |
| NUDOCS 9906180120 | |
| Download: ML20195J190 (4) | |
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NUCLEAR REGULATORY COMMISSION
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.179TO FACILITY OPERATING LICENSE NO. DPR-72 FLORIDA POWER CORPORATION 1
CRYSTAL RIVER UNIT 3 DOCKET NO. 50-302 1
1.0 INTRODUCTION
By [[letter::3F0998-11, Forwards LAR 238 to License DPR-72,correcting RCS Leakage Detection Capability of RB Atmosphere Gaseous Radioactivity Monitor Described in ITS Bases & FSAR|letter dated September 30,1998]] (Reference 1), Florida Power Corporation (FPC), the i
licensee, requested a license amendment change for Crystal River Unit 3. The license j
amendment would correct the description of the reactor coolant system (RCS) leakage detection capability of the reactor building atmosphere gaseous radioactivity monitor in the Improved Technical Specification (ITS) Bases and the Final Safety Analysis Report (FSAR).
The current description states that the gaseous radioactivity monitor can detect 1 gpm in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. According to the licensee event reports (LERs) (References 2 and 3), FPC personnel discovered that the gaseous radioactivity monitor was not capable of detecting a 1 gpm RCS leak within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> but rather 1 gpm in 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />. Therefore, the proposed change would stata i
that the Crystal River Unit 3 gaseous radioactivity monitor can detect a 1 gpm RCS leak in
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approximately 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />.
i 2.0 EVALUATION On July 30,1997, FPC personnel discovered that the RM-A6 particulate and gaseous radioactivity monitor's sensitivity was configured to iodine detection mode only and was incapable of detecting particulate radioactivity. On November 25,1997, FPC personnel also determined that the gaseous radioactivity monitor was not capable of detecting a 1 gpm RCS leak in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The Crystal River Unit 3 ITS 3.4.14 requires that the reactor building sump level and reactor building atmosphere radiation monitoring (particulate or gaseous) leakage detection systems be operable in modes 1,2,3, and 4. According to the licensee's LERs, a new RM-A6 particulate monitor has been installed. In addition, the RM-A6 gaseous radioactivity monitor has been entered into the Operation Equipment Out of Service log to ensure compliance with ITS 3.4.14.
In its license amendment submittal, the licensee stated that both the reactor building sump level and the particulate radioactivity monitor leakage detection systems are capable of detecting a 1 gpm leak within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. This assumes that the RCS radioactivity is equivalent to 0.1 percent failed fuel, as discussed in the Environmental Report (Reference 4) for the prticulate radioactivity monitor. The staff notes that normal RCS radioactivity levels are below 0.1 percent failed fuel. Based on this information, the staff concludes that ITS 3.4.14 is being met at l
Crystal River Unit 3.
9906180120 990614 PDR ADOCK 05000302 P
PDR ENCLOSURE 2
. in its submittal, the licensee proposed to change the ITS Bases B 3.4.14 and FSAR Section 4.2.3.8 to more accurately describe the capability of the gaseous radioactivity monitor. The proposed wording is as follows:
The particulate monitoring channelis capable of detecting a change in RCS leak rate of 1 gpm within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, based on activity levels assumed in the Environmental Report (0.1% failed fuel). The predominant nuclide of detection for the particulate channelis Rb-188. 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.
To support its request, the licensee described other diverse methods of leak detection available at Crystal River Unit 3. These include makeup tank level, cooler condensate flow from each reactor building cooling unit (RBCU), reactor building pressure, and RCS inventory balance.
The licensee stated that makeup tank level is displayed and recorded in the control room. The licensee has calculated that a decrease of 1.9 inches per hour of makeup tank level is equivalent to 1 gpm of RCS leakage. The RBCU condensate flow is also monitored and alarmed in the control room. The licensee stated that the RBCU condensate flow switches have a setpoint of 1133 cc/ min (0.3 gpm) and will provide indication of increasing humidity in the reactor building. The current alarm response procedures at Crystal River Unit 3 list RCS leakage inside containment as a potential cause of high condensate flow alarms.
Regulatory Guide (RG) 1.45 (Reference 5) provides the staff's position on reactor coolant pressure boundary leakage detection systems. In particular, regulatory positions 3 and 5, below, are applicable to the FPC request.
- 3. At least three separate detection methods should be employed and two of these methods should be (1) sump level and flow monitoring and (2) airborne particulate radioactivity monitoring. The third method may be selected from the following:
- a. Monitoring of condensate flow rate from air coolers,
- b. Monitoring of airborne gaseous radioactivity.
Humidity, temperature, or pressure monitoring of the containment atmosphere should be considered as alarms or indirect indication of leakage to the containment.
- 5. The sensitivity and response time of each leakage detection system in regulatory position 3 above employed for unidentified leakage should be adequate to detect a leakage rate, or its equivalent, of 1 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 />.
In addition, RG 1.45 states that it is acceptable to use the values in the plant environmental report in analyzing the sensitivity of airbome particulate or gaseous radioactivity leak detection system. Based on the discussion above, the staff concludes that Crystal River Unit 3 has met the ir: tent of RG 1.45. Regulatory position 3 is met by compliance with ITS 3.4.14 and monitoring the condensate flow from the RBCUs. Regulatory position 5 is met as long as the RCS activity is equivalent to 0.1 percent failed fuel. Additionally, the staff believes that changing the description of the gaseous radioactivity monitor's capabilities to the "as-is"
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, o RCS activity is equivalent to 0.1 percent failed fuel. Additionally, the staff believes that changing the description of the gaseous radioactivity monitor's capabilities to the "as-is" condition of detecting 1 gpm of RCS leakage in 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> is acceptable based on the diverse methods of leak detection that are available.
3.0 STATE CONSULTATION
Based upon a letter dated March 8,1991, from Mary E. Clark of the State of Florida, Department of Health and Rehabilitative Services, to Deborah A. Miller, Licensing Assistant, U.S. NRC, the State of Florida does not desire notification of issuance of license amendments.
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4.0 ENVIRONMENTAL CONSIDERATION
S The amendment changes requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration, and there has been no public comment on such finding (63 FR 64116). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
5.0 CONCLUSION
S The staff has reviewed FPC's submittal and supporting documentation. The staff has concluded that Crystal River Unit 3 has met the intent of RG 1.45 and ITS 3.4.14. Therefore, the staff finds that the proposed change in the description of the gaseous radioactivity monitor's capabilities in the ITS Bases 3.4.14 and FSAR is acceptable. The staff concludes that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: K.Ksvanagh Date:
June 14, 1999 l
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6.0 REFERENCES
1.
Terry, J.H., Florida Power Corporation, to USNRC," License Amendment Request #238, Revision to Licensing Basis for Reactor Coolant System Leakage Detection Instrumentation," September 30,1998.
2.
Rencheck, M.W., Florida Power Corporation, to USNRC, " Licensee Event Report (LER) 50-302/97-042-00," December 17,1997.
3.
Baumstark, J. S., Florida Power Corporation, to USNRC, " Licensee Event Report (LER) 50-302/97-042-01," June 15,1998.
4.
Rodgers, J. T., Florida P. c 1r Corporation, to USNRC, " Crystal River Unit 3 Environmental Report," Jr.dary 4,1972. US Atomic Energy Commission Regulatory Guide 1.45," Reactor Cooiant Pressure Boundary Leakage Detection Systems," May 1973.
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