IR 05000302/1993014
| ML20045J150 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 06/16/1993 |
| From: | Decker T, Mcneil N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20045J142 | List: |
| References | |
| 50-302-93-14, NUDOCS 9307230103 | |
| Download: ML20045J150 (11) | |
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L'g UNITED STATES
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WUCLEAR REGULATORY COMMISSION
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Report No.: 50-302/93-14 Licensee: Florida Power Corporation 3201 34th Street, South St. Petersburg, FL 33733 Docket No.:
50-302 License No.:
DPR-72 Facility Name: Crystal River 3 Inspection Co ducted: May 17-ZL, 1993 Inspector:
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N. G. W Neill'
, y Date Sig6ed Approved by:
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brL 6[# /75 ct T. R. Decker, Chief Date Signed Radiological Effluents and Chemistry Section Radiological Protection and Emergency Preparedness Branch Division of Radiation Safety and Safeguards SUMMARY Scope:
This routine, announced inspection was conducted in the areas of program l
organization, the Meteo'cological Tower data, effluent monitors, the Annual I
Radiological Environmental Operating Report, changes to the Off<ite Dose Calculation Manual (00CM), the results of Audits, Technical Specification (TS)
chemistry parameters, the Semiannual Radioactive Effluent Release Report for 1992, and Transportation of Radioactive Materials.
Results:
The licensee had not made any changes to their organization which would adversely affect the ability to control radiation exposures or radioactive material (Paragraph 2).
The Meteorological Tower had been maintained within required specifications and the operability of the system met the minimum requirements of the TSs (Paragraph 3).
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The Annual Radiological Environmental Operating Report (ARE0R) for 1992 was I
reviewed and results were compared against the Florida Office of Radiation
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Control's Radiological Surveillance of the Crystal River site report. No significant environmental effects attributable to the Unit 3 operation were detected (Paragraph 4).
9307230103 930617 PDR ADOCK 05000302-G PDR
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The results of audits performed by the licensee were reviewed and found to be comprehensive and thorough (Paragraph 5).
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Radioactive Waste Handling and Transportation areas were toured and activities related to the processing, sorting, and the offsite shipment of radiological wastes were reviewed. The emergency telephone number listed on the manifest of a shipment in transit was called and the ability of the licensee to answer questions relative to emergency handling of the shipment was found to be adequate and timely (Paragraph 6).
TS chemistry parameters were reviewed for the previous six months and all
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parameters were found to be maintained within requirements and the trends well analyzed and documented (Paragraph 7).
Changes which were made to the ODCM to include several TSs in the Methodologies Section were reviewed and found to present no significant
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changes to the methodologies or calculations previously used (Paragraph 8).
r Calibration and operability records for effluent monitors were reviewed and found to be adequate. One monitor was found to be inoperable for greater than thirty days, for which the licensee was taking additional samples and performing additional analyses as required by TSs (Paragraph 9).
The Semiannual Radioactive Effluent Release Report for 1993 was reviewed and totals for various pa:ameters were compared with previous years totals and found to be similar. Some evidence of elevated activation and fission products were detected in the first half of 1992 due to demineralyzer upsets and low decontamination factors (Paragraph 9).
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REPORT DETAILS 1.
Persons Contacted Licensee Employens P. Ezell, Environmental Chemistry
- E. Froats, Manager, Nuclear Compliance
- S. Johnson, Manager, Chemistry and Radiation Protection
- T. Lehman, Manager, Nuclear Chemistry
- D. McCullough, Supervisor, Radiochemistry P. McKee, Director, Quality Programs
- B. McLaughlin, Nuclear Regulatory Specialist
- W. Rossfield, Manager, Site Nuclear Services
- R. Widell, Director, Nuclear Operations Site Support
- D. Wilder, Manager, Radiation Protection Other licensee employees contacted during this inspection iacloded engineers, technicians, and administrative staff.
- Attended Exit Interview Acronyms and Initialisms used throughout this report are listed in the last paragraph.
2.
Organization (84750)
Technical Specification (TS) 6.2.1 describes the licensee's organization.
The inspector reviewed the licensee's organization, staffing levels, and lines of authority as they related to radiation protection and radioactive material control to verify that the licensee had not made organizational changes which would adversely affect the ability to control radiation exposures or radioactive material.
The inspector determined that there had been one major change to the organizational structure. The Nuclear Waste Technicians had been removed from Nuclear Chemistry and Radiation Protection. The section was now under the Manager of Nuclear Building Services Shop. The personnel had been transferred in whole to the new area.
Staffing levels and training requirements for the technicians.had not changed. The licensee representative was advised that the change in this area, which had been in operation less than a month at the time of the inspection, would be reviewed during future inspections to assess the impact on the program.
Based on this review, the inspector determined that the licensee had not made any changes to the organization which would adversely affect the ability to control radiation exposures or radioactive material.
No violations or deviations were identifie.
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3.
Meteorological Tower Data (84750)
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TS 3.3.3.4 requires that meteorological monitoring instrumentation channels, including instrumentatien for wind speed, wind direction and air temperature, be operational. lhese instrument readings are used to generate data which is used in dose projections for routine releases;
and would be used to evaluate appropriate protective actions for onsite and offsite personnel during abnormal releases.
Pursuant to these requirements, the inspectors reviewed talected portions of procedures covering the surveillance requirements and calibration of these instruments, reviewed the operability logs for the various instruments, and determined that the instruments readouts in the
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control room were functioning within the guidelines established by the TSs.
The inspector reviewed a small portion of the weekly calibration
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of the Back-up Tower and reviewed the following procedura:
SP-157B, " Surveillance Procedure - Meteorological System
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Surveillance (Weekly)," Revision 10 i
Within the scope of the review, the inspector determined that the
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meteorological instrumentation was being maintained as required.
No violations or deviations were identified.
4.
Annual Radiological Environmental Operating Report (84750)
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TS 6.9.1.5.c requires the submittal of a routine Radiological Environmental Operat!ng Report. This report summarizes the results of the Radiological Environmental Surveillance Program which measures accumulation of radioactivity in the environment and determines whether
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the radioactivity detected is due to the operation of the Unit 3 at Crystal River.
This program also assesses the doses to the offsite population due to plant operation Pursuant to these requirements, the inspector reviewed this report for the calendar year 1992. This data was compared with a similar report,
"the Radiological Surveillance of Florida Power Corporation's Crystal River Site," as supplied by the State of Florida Department of Health and Rehabilitative Services, Office of Radiation Control.
The inspector also reviewed the performance of the State of Florida in the l
Environmental Protection Agency's Interlaboratory Cross-Check Program.
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Examination of these records showed no abnormal elevated levels of radioactivity in the analyses performed. There were no unusually numerous missing samples or other anomalous data in the previous year.
The data appeared to fulfill the requirements of the TSs and supported the statement that Crystal River Unit 3's operation had minimal impact
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on the surrounding environment.
In summary, no significant radiological consequences attributable to the operation of the site in 1992, were noted from airborne, waterborne, aquatic, ingestion, or direct exposure environmental pathways.
No violations or deviations were identified.
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5.
Audits (84750 and 86750)
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TS 6.5.2.9 requires audits of facility activities to be performed including:
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The Radiological Environmental Monitoring program and the results
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thereof at least once per 12 months.
The ODCM and implementing procedures at least once per 24 months.
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The Process Control Program and implementing procedures for
solidification of radioactive wastes at least once per 12 months.
The performance of activities required by the Quality Assurance
Program.for effluent and environmental monitoring at least once per 12 months.
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The purpose of the audits was to ensure that the licensee effectively implemented the programs which controlled these various arcas, lhese programs ensured that the licensee effectively controlled, quantified, and monitored releases of radioactive materials; and that the Environmental Monitoring Program was effectively implemented.
Pursuant to these requirements, the inspector reviewed Audit
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Report 93-03-CREW, titled " Quality Assessments, Nuclear Chemistry, Radiation Protection, and Nuclear Waste."
The audit was performed in April 1993 and assessed the administration, control and implementation of the Nuclear Chemistry, Radiation Protection, Rad Waste, and Environmental Monitoring Program; and
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assessed the effectiveness of the interfaces among the organizations having responsibilities for these programs.
Audit findings were documented on six Problem Reports (prs) which were issued while the Audit was in progress. This allows for substantially
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reducing the identification to resolution cycle time. The inspector reviewed the audit findings, the prs associated with the audit findings, and the observations and recommendations associated with the concerns, in the areas pertinent to this inspection and determined that the licensee corrective actions were timely and technically acceptable.
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No violations or deviations were identified.
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6.
Radiological Waste Handling and Transportation (86750)
10 CFR 71.5(a) requires each licensee who transfers licensed materials outside of the confines of its plant or other place of use,- or who delivers licensed materials to a carrier for transport, shall comply with the applicable requirements of the regulations appropriate to the mode of transport of the DOT in 49 CFR parts 170 through 189. These requirements help ensure that the licensee effectively processes, packages, stores and ships radioactive solid materials.
10 CFR 20.311(d) requires that a shipment manifest be completed for each radioactive waste shipment sent to a licensed waste processor and that the manifest meet the requirements of Part 20.311(b) and (c) to include information concerning the physical description of the waste, the volume, radionuclide identity and quantity, the principle chemical form, and the total radioactivity.
Pursuant to these requirements, the inspector reviewed. selected portions of several procedures associated with the packaging and transportation of radioactive wastes, and reviewed the records of shipments made earlier in 1993. Through the review of these shipping records and discussions with the licensee, the inspector determined that the licensee was meeting the requirements for the above mentioned regulations.
The inspector also observed portions of the loading of four boxes containing Turbinc Valves being sent to Westinghouse Electric Company in Spartanburg, S.C. The inspector observed the transport vehicle inspection, portions of the Quality Control inspection, and radiation field measurements. The inspector also reviewed the paperwork associated with the shipment. This paperwork was identified as:
Radioactive Shipment and Verification Record for Shipment
No. 93-49 49 CFR 172.203(d)(i) requires, in part, that a shipping paper contain a 24-hour emergency telephone number, as prescribed in subpart G of Part 172 of this subchapter.
The inspector reviewed the waste shipment manifest for the shipment mentioned above, to determine compliance with the 24-hour emergency telephone requirements specified in 49 CFR 172.203(d). The insper. tor called the phone number while the shipment was in transit, and found the
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number to be properly listed and manned. The number' connected the caller with the Control Room and the Nuclear Shift Supervisor was asked for the manifest details. The Shift Supervisor was able to answer detailed questions about the identified shipment in approximately ten minute._
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Based upon review of the manifests and the performance of.the licensee concerning the emergency telephone number, it was determined that the radioactive materials shipment and transportation requirements were being met.
No violations or deviations were identified.
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Technical Specification Chemistry Parameters (84750)
TS 3.4.8.a requires that the specific activity of the primary reactor coolant be less than or equal to 1.0 microcurie per gram (uC1/g) dose equivalent iodine-131 (DEI-131). This ensures that resulting two hour doses at the site boundary will not exceed 10 CFR 100 limits following a steam generator tube rupture accident with a primary to secondary steam generator leak of 1.0 gallons per minute.
Water chemistry can have a major impact on component performance, availability, and expected life. Steam generator material integrity is closely aligned with the control and minimization of several different secor dary water chemistry parameters, including sodium.
The nspector reviewed both primary and secondary system parameters.
The :,econdary system parameters examined were feedwater oxygen and sodium as well as Hotwell oxygen and sodium. The primary system parameters examined were Reactor Coolant System (RCS) lithium, hydrogen, and DEI-131.
Daily chemistry reports as well as monthly summaries were reviewed and trends for the last six months noted. All of the parameters were well within iS guidelines. The DEI-131 values in particular were very low, averaging less than.0025 uCi/g. No iodine spikes were noted for the time frame reviewed and were indicative of good fuel performance to date. The daily chemistry reports were well organized and had the added feature of trending for the last 28 day time frame.
Based on this review, the inspector determined that the licensee was effectively monitoring TS chemistry parameters within guidelines.
No violations or deviations were identified.
8.
Offsite Dose Calculation Manual (84750)
The Offsite Dose Calculation Manual (0DCM) establishes the requirements for the Radioactive Effluent and Radiological Environmental Monitoring Program (REMP). This manual includes the methods and parameters for the calculation of offsite doses resulting from radioactive gaseous and liquid effluents. These calculations are performed to verify that the concentrations of effluents to the unrestricted area, and the resultant doses at the site boundary or to the maximum exposed member of the public, will not exceed the applicable regulatory limits.
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The incorporation of the Radiological Effluent Technical Specifications (RETS) into the ODCM, as per Generic Letter 89-01 issued by the NRC in January 1989, was reviewed to assess the impact of the change on the calculational methodologies. As stated above, there appears to La little if any change in the methods employed at this time. The TSs and ODCM will be reviewed in the future for any changes made by the licensee. The calculations were also reviewed for comparison with the Semiannual Radioactive Effluent Release report for 1992 and effluent monitor alarm / trip setpoint methodologies, which are examined later in this report.
Based upon this selective review it appears that the ODCM was adequate for the requirements of the TSs and that no substantial changes had occurred in the Manual with the incorporation of the RETS into the ODCM.
No violations or deviations were identified.
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Calibration and Operability of Effluent Monitors (84750)
TS 3.3.3.8 requires that radioactive liquid effluent monitoring instrumentation channels shall be operable with their alarm / trip setpoints set to ensure that the concentrations of radioac'ive material released to unrestricted areas shall be less than or equal to the concentrations specified in 10 CFR part 20, Appendix B, Table II, Columa 2 for radionuclides other than dissolved or entrained noble gases. The setpoints shall be determined in accordance with the ODCM.
TS 3.3.3.9 requires that radioactive gaseous effluent monitoring instrumentation channels shall be operable and that the effluent release isolation alarm / trip setpoints be set to ensure that the dose rate at or beyond the site boundary, due to radioactive materials released in gaseous effluents shall be limited as follows:
Noble gases: less than or equal to 500 millirem (mrem) per year
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totai body and less than or equal to 3000 mrem per year to the skin.
Iodine-131, tritium, and radioactive particulates with half-lives
of greater than eight days: less than or equal to 1500 mrem per year to any organ.
The setpoints shall be determined in accordance with the ODCM.
The radioactive liquid and gaseous instrumentation is provided to monitor and control the releases of radioactive materials in effluents during actual or potential releases. The setpoints should be set to ensure that the alarm / trip will occur prior to exceeding the limits of 10 FR 2 _
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Pursuant to these requirements, the inspector reviewed the methodology in the ODCM, and selected related documentation, relative to the determination of the setpoints for the liquid and gaseous effluent monitors.
The inspector also reviewed monitor displays in the Control Room, to verify that there was a visible response of the meters to a source check of the detectors associated with the instrumentation.
The inspector also discussed system operation and monitor operability with the licensee.
The licensee indicated that effluent monitors were operable a high percent of the time.
For the last six months of 1992,
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the licensee reported that there were no monitors inoperable for thirty days or more.
For the current year, to the date of the inspection, there were no monitors ineperable for greater than thirty days with one
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exception. The monitor, RML 7, which is a liquid monitor on the secondary side, had been inoperable for 37 days at the time of the inspection. The monitor is used on the sample lines to monitor condensate releases during startup and the Secondary Drain Tanks (SDT).
As required in the TSs, the licensee had been performing dual analyses prior to release from those sample lines. This dual sampling had been documented and appeared to meet TS intent to assure that no 10 CFR 20 limits are exceeded and are used in calculating the Semiannual Radir, active Effluent Release Report values.
Based on this review, the inspector determined that radioactive effluent monitoring instrumentation channels were operable, and that the equipment was maintained and operated in a manner consistent with the TS requirements.
No violations or deviations were identified.
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Semiannual Radioactive Effluent Release Report (84750)
TS 6.9.1.5.d requires the submittal-of routine Radioactive Effluent Release Reports covering the operation of the unit during the previous six months of operation. These reports summarize the amounts of liquid and gaseous effluents released from the site and assess the dose to offsite populations from these effluents.
A summary of the effluent releases for 1990, 1991, and 1992, are presented. The doses to the public due to these effluents were less I
than two percent of the 25 mrem per year limit for total body or critical organ doses specified in 40 CFR 190. No adverse trends were noted.
'The licensee reported that there was one unplanned liquid release in February 1992.
Due to the unplanned release, 5700 gallons from the Nuclear Services Closed Cycle Cooling System (SW), which normally contains low levels of activity, were introduced into the Industrial Cooler Closed Cycle Cooling System (CI), which normally has no activity.
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The total activity released from all radionuclides was calculated to be 47 uCi. The majority of the activity was determined to be Tritium (H-3)
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at an activity of 25 uCi, Xenon-133 (Xe-133) at'an activity of 10 uti, and Cesium-137 (Cs-137) at an activity of 2 uCi, and the rest of the
activity made up of assorted radionuclides. There were no reported gaseous releases during the calendar year.
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There were no unplanned gaseous or liquid releases for 1993 to the date of the inspection.
Crystal River Unit 3 Radioactive Effluent Release Summary 1990 1991 1992 No. of Unplanned Releases i
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a. Liquid
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Activity Released (Curies)
a. Gaseous 1. Fission and Activation Gases 7.31E+03 1.407'03 7.86E+02
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2. Iodines 7.63E-04 2.55E-04 6.32E-04 3. Particulates 4.79E-06 2.80E-04 8.12E-06
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A. Tritium 2.64E+01 1.35E+01 1.50E+01 b. Liquid 1. Fission and
Activation Products 6.19E-01 4.64E-02 2.07E+00 2. Tritium 5.10E+02 4.49E+02 3.64E+02
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3. Gross Alpha 6.67E-05
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<LLD c. Volume of Liquid Wastes Released 4.23E+07 4.34E+07 3.35E+07 Prior to Dilution (liters)
A trend was noted for the increased activity of fission and activation products for 1992 liquids. This was discussed with the licensee. The cause of the increased activity was determined to be poor demineralizer i
performance, Control Rod Drive Mcchanism (CRDM) leakage, and the late
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9 stage of the fuel cycle. After Refueling Outage 8 (RF8), zeolite and improved resins were used in the demineralizers, a CRDM maintenance program was initiated, and levels of activity for subsequent quarters have shown a reduction in fission and activation to date.
Thu'e were no instances of effluent monitor inoperability of greater than 30 days in 1992, except for the one case discussed in Paragraph 7.
In conclusion, the effluent releases were within TS; 10 CFR 20, Appendix B; and 10 CFR 50, Appendix I limits.
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Exit Interview The inspection scope and results were summarized on May 21, 1993, with those persons indicated in Paragraph 1 above.
Licensee representatives acknowledged the inspector's comments and no dissenting comments were received.
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Acronyms and Initialisms ARE0R Annual Radiological Environmental Operating Report CFR Code of Federal Regulations CRDM Control Rod Drive Mechanism DEI Dose Equivalent Iodine LLD Lower Limit of Detection mrem millirem NRC Nuclear Regulatory Commission ODCM Offsite Dose Calculation Manual PCP Process Control Program PR Problem Report RCS Reactor Coolant System REMP Radiological Environmental. Monitoring Program RF8 Refueling Outage 8 RM Radiation Monitor SDT Secondary Drain Tank SP Surveillance Procedure TS Technical Specifications uti Microcurie