IR 05000302/1990012
| ML20043A956 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 05/11/1990 |
| From: | Decker T, Seymour D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20043A955 | List: |
| References | |
| 50-302-90-12, NUDOCS 9005230340 | |
| Download: ML20043A956 (8) | |
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NUCLEAR REGULATORY COMMISslON
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ATL ANT A, OEORGI A 30323
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MAY 13 m Report No.:
50-302/90-12'
Licensee:
Florida Power Corporation I
3201 34th Street, South i,
St. Petersburg, F1 33733 Docket No.: 50-302 License No.:
DPR-72 Facility Name: Crystal River 3 Inspection Con ucted: April.16-20, 1990
'E /l" 70 Inspector:
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Date Signed
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Approved by:
d od 6-// ~ 90 T. R. Decker ~~ th'GT~~~~" ~~~~~~~"
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Date Signed Radiological Effluents and Chemistry Section Emergency Preparedness and Radiological Protection Branch Division of Radiation Safety and Safeguards SUMMARY Scope:
This routine, unannounced inspection was conducted in the areas of radiological effluents, the Post Accident Sampling System, meteorlogical procedures, and radwaste processing.
Results:
In the areas inspected, no violations or deviations were identified.
Liquid and gaseous radioactive effluents were within the concentrations-permitted by 10 CFR 20 Appendix B.
Radiation doses were well within the limits allowedby40CFR190and10CFR20.105(c)(Paragraph 2).
The Post Accident Sampling System has' experienced continuing operability problems. Thissystemhasreceivedsupportfromengineering(Paragraph 4).
Representative' sampling of gaseous effluents' was verified by the licensee (Paragraph 7).
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FDR ADOCK 05000302
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- A. Boettcher, Jr., Chief Chemistry Technician
- G. Boldt, Vice-President of Nuclear Production
- L. Cecilia, Nuclear Regulatory Specialist
- G. Clymer, Nuclear Waste Manager
- P. Ezzell, Radiochemistry & Environmental Specialist
- S. Johnson, Manager, Site Nuclear Services
- P. McKee, Director, Nuclear Power Operations
- R. Pinner, Nuclear Chemistry Supervisor
- S. Robinson, Chem / Rad Supervisor
- M. Williams, Nuclear Regulatory Specialist Other licensee employees contacted during this inspection included engineers, technicians, and administrative personnel.
NRC Inspectors
- W. H. Bradford, Resident Inrpector
- N. Economos, Region II Inspector
- P. Holmes-Ray, Senior Resident Inspector
- Attended exit interview Acronyms and Initialisms used throughout this report are listed in the last paragraph.
2.
Semiannual Radioactive Effluent Release Reports (84750)
Technical Specification (TS) 6.9.1.5.d requires the licensee to submit a Semi-Annual. Radiological Effluent Report within the time periods specified, covering the operation of the facility during the previous six. months of operation.
Additionally, reports that are submitted 60 days after i
January 1 of each year are required to include an assessment of radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar-year.
Pursuant to these requirements, the inspector reviewed the semiannual radioactive effluent release reports for 1989.
This review included an-
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2 examination of the liquid and gaseous effluents for 1989 as compared to those of 1988 and 1987, 1987 1988 1989 GaseousEffluents(Ci)
Fission and Activation 1.097E+03 3.42E+03 4.54E+03 Gases Iodines 2.00E-03 1.03E-03 1.66E-03 Particulates 5.60E-04 2.17E-04 2.86E-06.
Tritium 1.47E+01 9.93E+00 3.43E401 LiquidEffluents(C1)
Fission and Activation 9.60E-01 2.31E-01.
2.94E-01 Gases Tritium 3.56E+02 5.11E+02 3.44E+02 Dissolved and Entrained 2.53EiOI 2.60E401 4.30E+01 Gases Gross Alpha 49.00E-05 3.26E-06-6.90E-05 Volume of Released Wastes 2.39E+07 4.42E+07 3.03E+07 (liters)
Annual Doses To The Population From All Releases I
Whole Body Dose (mrem)
8.87E-01 2.97E-01 5.15E-01
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OrganDose(mrem)
2.02E+01 8.70E+00 7.93E+00
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Site Boundary Air Dose Beta (mrad)
9.50E-01 7.15E-01 1.37E+00 Gamma (mrad)
3.3E-01 2.44E-01 4.98E-01 A comparison of. the liquid and gaseous effluent results showed no significant trends for most effluent types.
For gaseous effluents, fission and activation gases and tritium increased for 1989, as did dissolved and entrained gases for the liquid effluents. The licensee attributed part of the increase of the fission and activation gases. to increased reactor coolant leakages.
Crystal River shut down in the first quarter of 1990 to repair these leaks.
During the last two quarters of 1989,- the plant
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underwent five shutdowns, which contributed to the increases in the fission i
and activation gases, and to the increases in tritium and dissolved and entrained gases.
Two abnormal releases were reported in 1989.
Both of these releases were gaseous releases occurring in January 1989.
The first release occurred during routine operation of the Post Accident Sampling System (PASS) and
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released an estimated 0.41 curies.
The second release also occurred from the PASS during system troubleshooting and released an estimated 0.9 curies.
For 1989, Crystal River's liquid and gaseous effluents were well' wi',hin
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TSs, 10 CFR 20, and 10 CFR 50 effluent limitations.
Doses for the liquid and gaseous pathways were within applicable TS limits.
No violations or desiations were identified.
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3.
Organization (84750)
i 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 e
adversely affect the ability to control radiation exposures or radioactive
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material.
The inspector determined that the licensee's organization +.'officient to meet the requirements of routine performance in these areat,.
No violations or deviations were identified.
4.
PostAccidentSamplingSystem(PASS)(84750)
NUREG-0737, Criterion 2a provides specifications for-the. establishment of
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onsite radiological analysis capabilities to provide quantification of noble gases, iodii.,, and non-violatile radionuclides in the reactor coolant and containment atmosphere.
Pursuant to these specifications, the inspector reviewed portions of l
selected procedures for the operation, maintenance, and testing of the l
licensee's PASS, and examined components of the _ PASS facility.
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inspector also discussed system operation, performance testing, and
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analytical capabilities of the PASS with the licensee.
Discussions with the licensee and the review of records indicated that operability of the PASS had been an on-going problem in the-last few years, since a pressurizer steam space sample had been taken without proper cooling,
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l causing leaks in valves and tubing (approximate 1987 time frame),
i The licensee indicated that an engineering study had been performed which evaluated the PASS, including requirements, modifications, and problem i
history.
Engineering support was received to test, troubleshoot, and-
repair the system in an attempt to br1ng it back into operability.
The system was then to be operated in its current configuration for one year, i.
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l and then, in late 1990, be re-evaluated by engineering to determine what
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l changes may be necessary to ensure relieble,, economic and efficient-l operation.
The inspector determi_ned that the engineering support for the.
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PASS was on-going, but that operability problems were still occurring. The
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inspector will review PASS maintenance and operability during subsequent inspections.
No violations or deviations were identified.
5.
Implementation of the Meteorological Monitoring Program (80521)
TSs 3.3.3.4 and 4.3.3.4 establish the operability and surveillance requirements for the meteorological monitoring instrumentation at Crystal River. Pursuant to these requirements, the inspector reviewed selected procedures, records, and discussed operating history of this instrumentation with licensee representatives.
This review included'the following surveillance procedures:
SP-153, Primary System Meteorological Monitoring Instrumentation Calibration, Revision (Rev.)3. June 3,1985 SP-157A, Meteorological System Surveillance (Daily), Rev. 6, April 5, 1990 SP-157B, Meteorological System Surveillance (Weekly), Rev. 8 March 29, 1990 SP-158, Meteorological-Monitoring Instrumentation Calibration.
Rev. 15, January 2, 1990 The records and discussion indicated that the' program was conducted in accordance with TSs and procedures.
No violations or deviations were identified.
6.
RadioactiveLiquidWastesandLiquidEffluentTreatmentSystem(84750)
TS 3.11.1.1 establishes limits for concentrations of radioactive materials in liquid effluents released to unrestricted areas.
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establishes limits for dose commitments to individuals' offsite as the consequence of the release of radioactive materials in liquid effluents to
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unrestricted areas.
TS 3.7.13.2 requires the. liquid radwaste treatment system to be 03erable and requires use of the system to reduce radioactive materials in l' quid wastes prior to their discharge.
Pursuant to these requirements, the inspector discussed operation of the liquid radwaste system with licensee representatives, reviewed operating records, and toured the plan't, examining components of the system.
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inspector determined that there were several liquid waste release pathways
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at Crystal River.
The Reactor Building and the. Auxiliary Building sumps both drain into the Miscellaneous Waste Storage Tank:(MWST)
located in the'
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These wastes were processed through the. Nuclear Waste-
Demineralizer System which consisted of a series of charcoal and sluiceable
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demineralizers, and stored in one of the two Evaporator Condensate Storege
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Tanks (ECSTs).
Prior to: a release from an ECST, the tank would be recirculated for two tank volumes and sampled.
The liquid would pass l
through liquid radwaste radiation monitor RM-L2 prior to release to the
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discharge canal and the Gulf of Mexico.
This pathway was the primary.
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l liquid release pathway at Crystal River.
Liquid wastes from the " seawater"
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room were drained into the turbine building sump and collected in System Drain Tank 7.
Depending upon the types and amount of activity present,
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these wastes were sent to the settling pond or released past the RM-L2 radiation monitor to the discharge canal.
Liquid wastes from the laundry and shower sumps were collected in the Laundry and Shower Sump Tank, stored
in Waste Disposal Tanks 11A and/or 11B, and released past the' RM-L2 radiation monitor to the discharge canal. There were three Reactor Coolant Bleed Tanks (RCBTs); A, B, and C.
One tank stored RCS letdown prior to
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evaporation.
The raffinate-from the evaporation process was stored in the Concentrated Boric Acid Storage Tank and added as needed to the RCBT
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containing a high boron concentration.
The extract was stored in the third RCBT (negligible boron concentration).
Another release pathway was the reactor coolant drain tank, which could be discharged to the reactor building sump, to the MWST, or to a RCBT.
Section 2.4.1.K of Appendix B, Part I to facility Operation License No.
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DPR-72 specifies that prior to taking samples from a monitoring tank, or the laundry and hot sump, at least two tank volumes shall be recirculated, j
The inspector asked the licensee to provide information substantiating that recircing the tanks for a minimum'of two tank volumes would engender a homogeneous mixture allowing representative sampling to take place.
This information will be reviewed during a subsequent inspection.
The inspector reviewed selected liquid waste discharge permits and records for the release of radioactive liquid effluents for April 1990.
Based on the review of selected liquid effluent release permits, the inspector determined that the required sampling and analysis-frequencies were followed and the records required by TS 6.10 were maintained.
TSs 4.3.3.8 and 4.3.3.9 provide criteria for the testing and calibration of radioactive liquid and gaseous effluent monitors, respectively.. Pursuant i
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to these requirements, the. inspector reviewed selected testing and l
calibration records for 1989 and 1990 for RM-L2 (plant: liquid discharge L
monitorandRM-L7(turbinebuildingbasementdischargelinemonitor). This l
l review included selected portions of OP407-H Operation of the Laundry and
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Shower Monitoring Tanks, dated February 13, 1990; OP-407-A, Operation of the Evaporator Condensate Storage Tank, dated January 1,1990; and of
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OP-407-N, and Liquid Releases from the Secondary Plant, dated February 9,'
The inspector determined that the control operators were performing I
source checks prior to each liquid release and that the release lines were
flushed with demineralized water after each release.
In the event that a
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monitor failed a source check, the operators could direct a health physics technician to perform a. " wand" source check.at the monitor.
These wands l-were a 10 uCi, a 30 uC1, or 300 uti Cs-137 source on a shaft, which was l
inserted into a small diameter well built into the monitor.
The liquid I
radiation monitors RM-L2 and RM-L7 were full flow imine monitors which l
could not be disassembled and decontaminated to lower ackground' readings.
The inspector determined that these two monitors weis scheduled to be replaced prior to or during the next refueling outage (approximately 1992).
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The inspector considered the planned monitor replacenents to be an enhancement to the radiation monitoring program.
Violations or deviations were not identified.
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GaseousEffluents(84750)
TS 3/4.3.3. defines the operating requirements and surveillance requirements for the gaseous effluent monitoring instrumentation.
TS 3/4.11.2. defines the dose rate limits for tiese effluents.
Pursuant to these requirements, the inspector reviewed selected systems in place at Crystal River for monitoring and accounting for radioactive gaseous effluents, including iodine, noble gases, tritium, and radionuclides in particulate form.
The inspectors observed two members of the licensee staff collect routine samples from the auxiliary building exhaust duct system, which included a noble gas activity monitor, an iodine sampler, a particulate sampler, and a sample flow rate neasurement device.
The inspector reviewed procedure No. CH0349, titled Sampling at the Exhaust Duct Gas Monitor, Revision 9, dated December 12.1989.
This procedure was followed by the two staff members collecting the samples.
Proper sampling techniques and health physics practices were observed.
.I The inspector discussed the representativeness of the gaseous effluent samples with licensee personnel.
The licensee provided the inspector with thorough documentation covering this issue, including information from the manufacturer of the sampling nozzles in the stacks, information concerning
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the modifications due to the installation of high and mid range gas detectors, vendor information, and descriptions of total flow measurenent devices.
The inspector determined, based on the information provided, and based on discussions with the licensee, that representative sampling was occurring.
No violations or deviations were identified.
8.
Exit Interview The inspection scope and results were summarized on April 20, 1990, with those persons indicated in Paragraph 1.
The inspectors described the areas inspected and discussed in detail the inspection results as listed in-the summary.
Proprietary information is not contained in this report.
Dissenting comments were not received from the licensee.
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Acronyms and Initialisms i
CFR - Code of Federal Regulation j
ECST - Evaporator Condensate Storage Tank
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mrad - millired mrem - millirem
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MWST - Miscellaneous Waste Stora p Tank-i No,.- number i
NRC - Nuclear. Regulatory Commission
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. PASS:- Post Accident.-Sampling System
- RCBT - Reactor Coolant Bleed Tank i
RCS - Reactor Coolant System i
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Rev. - Revision:
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TS - Technical! Specification.
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