IR 05000250/1991009
| ML17345A788 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 03/25/1991 |
| From: | Decker T, Marston R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17345A787 | List: |
| References | |
| 50-250-91-09, 50-251-91-09, NUDOCS 9104120163 | |
| Download: ML17345A788 (13) | |
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30323 Report Nos.:
50-250/91-09 and. 50-251/91-09 Licensee:
Florida Power and Light Company 9250 West Flagler Street Miami, FL 33102 Docket Nos.:
50-250 and 50-251 License Nos.:
DPR-31 and DPR-41 Facility Name: Turkey Point 3 and
Inspection Conducted:
March 4-8, 1991 Inspector:
RRR. Narston Approved by; 5~~ i 'c A'>>
.
Radiological Effluents and Chemistry Section Radiological Protection and Emergency Preparedness Branch Division of Radiation Safety and Safeguards
~ ~~/g)'
bate Soigne
~i Date Signed SUMMARY Scope:
This routine, unannounced inspection was in the areas of radiological effluent processing and release, solid radwaste processing and transportation, process and effluent monitors, radiological environmental and meteorological monitoring, and engineered-safety-feature filtration systems.
Results:
In the areas inspected, no violations or deviations were identified.
The guality Assurance audit and surveillance program provided management with a tool to ensure effective monitoring and implementation of the programs within the scope of this inspection.
Programs within the scope of this inspection were determined to be effective.
Radiochemistry maintained effective quality control programs which should ensure accurate and precise measurement REPORT DETAILS Persons Contacted Licensee Employees
- M. Adside, Compliance Engineer J.
Berg, Chemistry Primary Operations Supervisor
"M. Blew, In Service Inspection Coordinator
"V. Kaminskas, Operations Superintendent J. Kovarik, Instrumentation and Control Supervisor D.
Lee, Chemistry Radwaste Coordinator C. Murray, On-Line Monitor Coordinator-
- J. O'rien, guality Control Superintendent
"T. Plunkett, Vice President M. Poppell, Land Utilization Facility Site Superintendent
- D. Powell, Licensing Superintendent S. guinn, Radiochemist
'K.
Remington, System Performance Supervisor C. Rossi, guality Assurance Regulatory Performance Supervisor R.
Rowe, Radwaste Supervisor R.
Sanchez, Systems Performance Group Test Engineer R. Schuber, Radwaste Shift Supervisor
- R. Steinke, Chemistry Supervisor Other licensee employees contacted during this inspection included engineers, operators, security force members, technicians, and administra-'ive personnel NRC Resident Inspectors R. Butcher, SRI
- G. Schnebli
~Attended exit interview 2.
Audits (84750, 86750)
Technical Specification (TS) 6.5.2.8 requires that audits of facility activities shall be performed under cognizance of the Company Nuclear Review Board (CNRB).
The TS further specifies the subject areas to be audited and the frequency of audit."
The inspector reviewed Regulatory Performance audits, performed on subjects within the scope of this inspection which were published since the last inspection (50-250, 251/90-34)
in this area in order to verify compliance.
The following audits were reviewed:
gAO-PTN-90-049, TS 6. 13, Post Accident Sampling, conducted August
to October 29, 1990.
This audit consisted of reviews of various plant implementing procedures, surveillance and testing records, and
interviews.
Review areas included training of personnel, and review of lesson plans and job performance measures.
The audit also verified that the Post Accident Sampling System (PASS) flowpaths were verified every
days as required by TS 4. 18.
No findings were identified in this audit.
gAO-PTN-90-051, Meteorological Program, conducted August 28 to October 24, 1990.
This audit consisted of an evaluation of the implementation of on-site Meteorological Programs as delineated in Regulatory Guide 1.23, reviews of plant implementing procedures, surveillance and testing records, and interviews.
Specific areas reviewed were meteorological parameters, data indication, instrumen-tation accuracy,'nstrumentation maintenance and servicing, schedules, data reduction and compilation, program documentation, and interfaces between departments and recipients.
No findings were identified in this audit.
The inspector determined that the audit program was conducted in accordance with TS requirements, and that audits were conducted in such depth as to identify programmatic weaknesses if such existed.
NG violations or deviations were identified.
3.
.
Changes to Chemistry and Radwaste programs.
(84750, 86750)
The inspector reviewed changes to the Chemistry program with the Chemistry
.
Supervisor and the Chemistry Primary Operations Supervisor to evaluate capability and assess quality.
The Chemistry Supervisor stated that the Chemistry Department had had three losses, and had recruited one replacement.
The Department had 30 slots, with 28 of them occupied at the time of 'the inspection.
The Procedure Upgrade Program was ongoing, and the Supervisor stated that the procedures were up to date with the new TS.
The Supervisor stated that after the units were operating again, it was planned to use morpholine control on the secondary loop to cut down transport of iron to the steam generators.
It was also planned to use the condensate polishers full time while running after startup.
The polishers would be run without the resin, since the matrix had been found to have good filter properties.
The Chemistry Primary Operations Supervisor stated that some changes in shutdown chemistry were being used during the dual unit outage.
Boron concentrations had been increased rapidly to refueling levels.
Hydrogen peroxide injection had been used prior to unit shutdown.
The Supervisor stated that in Unit 3, the initial"hydrogen peroxide injection was into the pressurizer.
The inspector examined chemistry trend charts which showed levels of cobalt-58, cobalt-60, the ratios of the two, and the ratio of cobalt-58 to nickel.
On Unit 3, the cobalt
showed a quick burst, then 5 days later, another peak.
The Unit 4 plots showed slower increases, then a leveling off.
The cobalt-58 /cobalt-60 ratio showed an initial peak, then a larger one after three days.
The cobalt-58/
nickel ratio remained fairly level after an initial peak.
The Supervisor
~ stated that flame emission was used to analyze for nickel, and that low levels were difficult to measure due to the high "noise" levels below 250 parts per billion.
The plant was considering modified boron-lith'ium control in the primary system.
The purpose would be to achieve lower dose, rates"in the system and less crud on the pipe walls, which would reduce the necessity to run the cation vessel every day.
The proposed modification would result in a pH of 6.9 at startup, gradually increasing
.to 7.4 as the core aged and the boron concentration decreased.
The Supervisor described a potential problem of concern to the industry.
A material used in the fuel racks in spent fuel pools (SFPs)
was discovered to be susceptible to some breakdown in high radiation fields.
The breakdown resulted in silicon leaching out of the material into the SFP water, forming silica.
At some plants, a loop between the SFP and Refuel Cavity could result in silica gettino into the reactor and affecting the fuel clad.
The Supervisor stated that there was very little
~
mixing between the SFP and refueling canal at Turkey Point.
There was no recirc.
loop between the SFP and the canal, only a transfer tube.
Fuel movement didn't cause much mixing.
The Refueling h'ater Storage Tank had very low levels of silica, and the SFP had only parts per million (ppm)
levels."
The Department planned to check for any transfer to the reactor after startup.
The Supervisor stated that an improvement in gas analysis was being worked.
on.
Many plants had a dissolved hydrogen analyzer installed in the
.letdown lines.
The Chemistry Department was configuring an analyzer for use as a portable instrument, with quick disconnect couplings, to be used as a portable grab sampler arid anialyzer.
Cther improvements beirig made were:
C Switching to a gradient type run on an ion chromatograph in order to better analyze for sulfates in the presence of boron Implementing EPRI Guidelines for Primary Chemistry on startup Developed action levels and hold points on the secondary side for startup t
Revised dissolved hydrogen specifications for startup.
Previously, Node
was entered with dissolved hydrogen levels at 25 cubic centimeters (cc) per kilogram (kg) of water, with 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> allowed in Yiode 2 to get down to 15 cc per kg.
It was planned for the upcoming startup to enter Yiode 2 with dissolved hydrogen concentration less than or equal to 15 cc per kg.
The inspector determined that the proposed system changes would be expected to improve system operation and not have any detrimental operational or safety defects.
No violations or deviations were identifie Radiochemistry Count Room and Instrumentation (84750)
The inspector toured the count room to evaluate capability and quality of the counting systems.
The count room was equipped with a Packard Tri-Carb liquid scintillator system, a Tennelec alpha-beta scintillator count system and three High Purity Germanium detectors.
The Germanium detection systems were controlled and read out by a
ND 9900 computer system, and were interconnected with a VAX 3100 and a Micro VAX 3400 system.
These other systems provided backup to the ND 9900.
Nuclear Chemistry Procedures NC-7, Radiochemistry guality Control Program, NC-21C, Operation of ND9900, and NC-25B, Gamma Spectrometer Efficiency Calibration for Various Geometries Using Radioactive Standards, state requirements for quality control, operation, and calibration of the gamma
'spectrometry systems.
The inspector reviewed records for the systems to verify compliance and assess quality.
'The Radiochemist stated that the most recent calibration for the systems was conducted in March 1990, which had been reviewed by the inspector during a previous inspection.
The inspector reviewed the control charts, for each of the three detectors for the period from Febr'uary 25 to March 7, 1991.
The quality control checks consisted of the Centroid, the Resolution (Full Width Half Max), and the Activity for each of three nuclides (Cobalt-57, Cobalt-60, and Cesium-137).
Resultant values were generally within the plus or minus
sigma bands, few were outside the 2 sigma band, and none were outside the
sigma band.
Anomalies were labeled and the cause identified.
The quality control programs for the count room were conducted in accordance with requirements.
No violations or deviations were identified.
Radwaste (84750, 86750)
The inspector discussed the solid radwaste and transportation program and toured the processing and storage facilities to assess capability.
The Health Physics Radwaste Supervisor stated that the Radioactive Material Storage Building was being cleaned out as much as possible, and a
computerized inventory system was to be implemented.
Trash segregation was done in a separate building which was equipped with a sorting air hood which had a
HEPA filter installed in its exhaust duct and had an air sampler installed in the region of the breathing zone.
Incoming trash was stored in large metal containers awaiting sorting.
The Radwaste Building included several storage areas, from those used for low level waste, up to locked high rad areas used for resins arid dewatering and for storage of RTD bypass piping.
A Duratek skid was located in the building.
The Radwaste Supervisor stated that the output from the Duratek was piped to the Waste Monitor Tanks, which were located in the building.
Monitor Tanks were located in the Auxiliary Building and were used primarily for the Laundry and Hot Shower drains.
Laundry was performed onsite with some contractor assistance during outage In addition to the Supervisor, the Radwaste organization wa's manned by one Assistant Supervisor and eight, full time technicians.
Assistance was provided by a Mechanical Maintenance Foreman and 10 Mechanical Maintenance
.
helpers.
The inspector observed that the Radwaste Building and outside areas had a
considerable amount of sorted and unsorted waste, however, this did not appear to be excessive with a dual unit outage in process.
No violations or deviations were identified.
6.
Liquid Effluent Processing and Monitoring (84750)
7.
TSs 3.9. l.a and b state requirements for liquid effluent concentrations and doses.
The inspector reviewed 34 Liquid Release Permits and Release Logs for the month of February 1991 to verify compliance.
The releases were made from Waste Monitor Tanks (WMTs) A, B, and C,
and from Monitor Tanks A and B.
Doses were calculated for each release and for the current month.
The inspector discuss'ed liquid releases with the Chemistry Radwaste Coordinator and reviewed Temporary Chemistry Procedures, TP-691, Determination of Ratio of Isotopic Concentration to Yiaximum Permissible Concentrations in Liquid Release, January 29, 1991, and TP-692, Prepara-tion of a Liquid Release Permit, January 29, 1991.
These procedures were developed and implemented because the circulating water pumps were shut down.
These pumps usually provided the dilution water for liquid releases.
The intake cooling water pump was being used for dilution while the circulating water pumps were shut down.
The intake cooling water pump flow was considered to be 7500 gallons per minute, so the new procedures were required to account for the lower than normal dilution flow.
I The inspector reviewed the Preliminary Radioactive Release Report for January 1991.
These monthly reports served as the input to the Semiannual Radioactive Effluent Reports.
The Report summarized volumes and activities for liquid and gaseous waste, then summarized doses and compared these dose's to quarterly and annual limits.
i All releases were well-controlled; no limits were approached.
i, No violations or deviations were identified.
Radioactivity Monitors (84750)
'I TS 3.9. 1.c and Table 4. 1-3 state requirements for calibration and functional test of~ liquid effluent monitoring instrumentation, and TS 3.9.2.d and Table 4. 1-4 state requirements for calibration and functional test of gaseous effluent monitoring instrumentation.
The inspector reviewed documentation showing the most recent calibration and most recent functional test for selected effluent monitors to verify compliance.
The records showed that the most recent calibration for the R-14 Plant Vent Gas Yionitor was conducted on January 19, 1990, and the most recent calibration for the R-18 Waste Disposal Liquid Effluent Monitor was
conducted on February 15, 1991.
The most recent Operability (functional)
tests on both monitors were conducted on February.
19, 1991.
The Chemistry On-Line Monitor Coordinator stated that the hydrogen analyzer on the Post Accident Sampling System (PASS)
had been repaired and showed good comparison with grab sample results during the last compara-tive tests.
Corporate Engineering was to make a decision whether to replace the unit or not.
The most recent problem was with liquid getting into the hydrogen space of the unit.
The fix was to replace the phase separator.
The process and effluent monitors had been calibrated and functionally tested at required intervals.
The PASS was operating acceptably, with continuing problems with the hydrogen analyzer.
The licensee had continued to evaluate and try to fix these problems.
The PASS computer was being moved from its previous location to the Computer Room.
No violations or deviations were identified.
Gaseous Effluent Filtration Systems (84750)
TS 3.4 states the operability requirements for the Emergency Containment Filtering System, the Post Accident Containment Vent System, and the Control Room Ventilation System.
TS 4.7 states the Operating Tests and Performance Tests for the specified systems.
The inspector reviewed completed test procedures for the inplace filter testing and charcoal analysis for the designated systems to determine compliance.
The r ecords showed that the most recent test of the Control Room Emergency Ventilation System was conducted in March 1990, and the charcoal lab test in January 1991.
All tests were successful.
The most recent testing of the Emergency Containment Filter System was conducted in January 1991 for Unit 3, and December 1990 for Unit 4.
Charcoal Lab tests were conducted in January 1991 for Unit 3 and in December-1990 for Unit 4.
All tests were successful.
The most recent tests of the Post Accident Containment Vent System was conducted in August 1989.
All tests were within limits.
No violations or deviations were identified.
Meteorological Monitoring (84750)
The inspector inspected the meteorological tower components and ground electronics equipment, discussed the meteorological program with the Land Utilization Site Superintendent and Meteorological Technician, and reviewed
. records to assess capability.
The South Dade tower, the designated backup tower, was equipped with wind direction and speed sensors at
and 60 meter levels, temperature sensors at both levels, dewpoint sensor at 10 meters, two rain gauges and a solarimeter at the surface.
The t'owei was equipped with a lightning protector, and had no obstruction to the free flow of wind.
Recorders inside the instrument shack recorded values for wind direction and speed at each level, and a
multipoint recorder recorded two temperature channels at 10 meters, the dewpoint, the delta T values, and rainfall and solar values.
The Site Superintendent stated that after an upgrade of the instrumentation, temperatures at the '60 meter level would be recorded.
- The primary tower was 10 meters high and was referred to as the
"Land Utilization Site."
Wind speed and wind speed average were recorded on one chart in the instrument shack, and wind speed and sigma (theta)
were recorded on the other.
The most recent calibrations were conducted in December 1990.
Calibrations and rechecks had been conducted as necessary during the year.
During the last summer and autumn, lightning strikes necessitated several component replacements and recalibrations.
In October, 10 meter wind direction sensors at both towers had to be replaced due to blown potentiometers.
The inspector reviewed the routine checklists for both towers, which was performed three times per week.
All calibrations and checks appeared to be performed at the required frequencies.
No violations or deviations were identified.
Training (84750, 86750)
TS 6.4. 1 states the requirements for the retraining and replacement program for the facility staff.
The inspector discussed the training program with the Chemistry Supervisor and the Health Physics Radwaste Shift Supervisor to verify compliance.
The Radwaste Shift Supervisor stated that, beyond the Radwaste training provided to Health Physics Technicians, those Health Physics personnel assigned to the Radwaste organization attended a three to five day Radwaste course offered by a vendor.
The next available course was to be in July 1991, and requalifi-cation was required every two years.
The Chemistry Supervisor stated that one new individual had been assigned since the last inspection in this area, and was to start formal classroom training sometime after April 1991.
Three other experienced personnel had come to the site approximately one year ago, and were approximately half way through their training program.
The inspector sat through approximately two hours of a radiochemistry course offered by the Training Department.
The course was comprehensive and professionally presented.
The handouts were informative and complemented the oral and visual presentation.
No violations or deviations were identified.
Semiannual Radioactive Effluent Release Report (84750)
TS 6.9.4.a requires that routine Radioactive Effluent Release Reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year.
The TS further includes requirements for the content and format of the report.
The inspector reviewed the Semiannual Radioactive Effluent Release Report to verify compliance with TS requirements and to determine trends in liquid and gaseous releases.
The inspector determined that the report was prepared in accordance with the TSs.
The following Table shows liquid and gaseous effluents for the past three years:
~
'
TABLE Gaseous 1988
~Ci)
1989
~Ci 1990
~Ci Fission and Activation Gases 2.56E+03 3.41E+03 1.28E+03 Iodine-131 and Particulates 9.60E-03 6.18E-04 6.52E-03
~Li uid Fission and Activation Products 6. 79E-Ol 3. 16E" 01 2. 52E-01 Tritium 5.98E+02 4.58E+02
'.44E+02 Unit 3 was shut down for most of the period from February through May, and from. December 12 through the end of the year.
Unit 4 was shut down from November 25 through the end of the year.
This could account for less gas production.
The Radiochemist stated that there was a considerable increase in containment purging during the year.
This could account for the increase in iodines and particulates released.
There were no unplanned releases during the year.
No limits were exceeded.
No violations or deviations were identified.
12.
Exit Interview (84750, 86750)
The inspection scope and results were summarized on March 8, 1991, with those persons indicated in Paragraph 1.
The inspector described the areas inspected and discussed in detail the inspection results.
No violations or deviations were identified.
The guality Assurance audit and surveil-
'ance program continued to maintain a comprehensive evaluation program which gave management a good tool for monitoring and control of effluents and chemistry parameters.
Radiochemistry maintained a
good quality control program which should ensure accurate and precise measurements.