IR 05000424/1989005
| ML20235U778 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 02/21/1989 |
| From: | Kahle J, Stoddart P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20235U768 | List: |
| References | |
| 50-424-89-05, 50-424-89-5, 50-425-89-06, 50-425-89-6, NUDOCS 8903090369 | |
| Download: ML20235U778 (16) | |
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REGION 11 o,
101 MARIETTA ST., N.W.
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ATLANTA, GEORGIA 30323 FEB 211999 Report Nos.: 50-424/89-05 and 50-425/89-06 Licensee: Georgia Power Company P. O. Box 1295 Birmingham, AL 35201 Docket Nos.: 50-424 and 50-425 License Nos.: NPF-68 and CPPR-109 Facility Name: Vogtle 1 and 2 Inspection Conduc
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- 0, 1989 and January 23-27, 1939 Inspector:
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edM f7 P. G.'Stoddart ' 3 Date Signed Accompanying Personnel:
T. Volk Approved by:
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J. B./K hie, Chief
'Date' Signed Radtfl ical Effluents and Chemistry Section Emerg cy Preparedness and Radiological Protection Branch Division of Radiation Safety and Safeguards SUMMARY Scope: This routine, announced inspection was conducted in the areas of confirmatory radiological measurements for Units 1 and 2 and preoperational system tests for Unit 2, encompassing liquid and gaseous radwaste systems, process and effluent monitoring, and post-accident sampling and monitoring systems.
Results:
All preoperational testing of Unit 2 systems within the inspector's scope of review had been satisfactorily completed.
Systems included the waste gas system (Paragraph 5); process and effluent radiological monitoring and sampling system (Paragraph 4); Containment and Auxiliary Building drains (Paragraph 6); liquid waste process system (Paragraph 7); heating, ventilation and air conditioning system HEPA filters and charcoal adsorbers (Paragraph 10);
nuclear sampling system (Paragraph 8); balance-of-plant sampling system (Paragraph 9); and backflush liquid filters (Paragraph 3).
Confirmatory radiological measurements were p)erformed by licensee personnel on all licensee multi-channel analyzers (MCA's using gamma-emitting spiked samples supplied by NRC and reactor coolant samples provided by the licensee.
Utilizing the RII mobile laboratory MCA, all samples were analyzed by NRC and the results were compared to licensee results obtained using the licensee's six MCA's.
Results were within agreement criteria in 120 out of 120 possible e903090369 s90221
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comparisons.
The inspector considered the demonstrated performance of the licensee's MCA's and of the licensee's Health Physics and Chemistry count room staffs to be licensee strengths (Paragraph 2).
Eight inspector follow-up items (IFIs) were closed (Paragraph 11).
No violations or deviations were identified.
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l l-REPORT DETAILS l
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1.-
Persons Contacted
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Licensee Employees M. Biron, Supervisor, Process and Effluent Radiological Monitoring and -
Sampling System
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- C.-Eckert, Manager, Health Physics anr. 'hemistry
- G. Frederick, Quality Assurance Site Waager, Operations.
- W._Gabbard, Senior. Regulatory Special m
- T. Greene,-Plant Support Manager
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- D. Hallman, Chemistry Superintendent I. Kochery, Health Physics Superintend.nt R. LeGrande, Operations Superintendent
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- C. Miller, Engineering Support Superintendent
- W. Nicklin, Compliance Supervisor Other licensee employees contacted.during this inspection included engineers, operators, technicians, and administrative personnel.
.0ther Organizations i
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M. Bagale, Bechtel A. Balderson, Bechtel R. Cis10, Bartlett Corporation i
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- S. Hall Westinghouse
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I. Jamieson, Bechtel N. Leftwich, Westinghouse Nuclear Regulatory Commission-
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- R. Aiello, Resident Inspector
- C. Burger, Senior Resident Inspector I
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- J. Rogge, Senior Resident Inspector
- Attended exit interview
-2.
Confirmatory Measurements (84750 - Unit 1; 84525 - Unit 2)
During the inspection, reactor coolant samples from Plant Vogtle, Unit 1, taken by the licensee and " spiked" samples provided by the inspector were analy;'ed for radioactivity concentrations using the licensee's MCA gamma
spectrometry systems and the MCA gamma spectrometry system of the NRC
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Region 11 mobile laboratory.
Results of all measurements were compared i
for accuracy and consistency.
The purpose of these comparative q
measurements was to verify the licensee's capability to accurately detect, j
identify, and measure gamma emitting radionuclides concentrations in
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various plant systems and effluent streams. Comparisons were made between
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the MCA detector in the NRC Region 11 mobile laboratory, four. MCA detectors located in the licensee's Chemistry Count Room, and two MCA detectors located in the licensee's Health Physics Count Room.
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types compared included:
(1) reactor coolant, taken from the Residual Heat Removal-(RHR) system sampling point; (2) simulated liquid radwaste
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(spiked sample provided to the licensee by the inspector) (3) simulated
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charcoal cartridge (spiked sample provided to the licensee by the inspector) and (4) simulated particulate filter (spiked sample provided to the licensee by the inspector).
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A detailed tabular summary and description of the sample types and-geometries, together with a ccmparison of the NRC and licensee results, is presented in Attachment 1.
The methodology for determining agreement or disagreement is discussed in Attachment 2.
The results showed good agreement for all compared nuclides; however, since the licensee's two Health Physics Count Room MCA detectors were not calibrated for the 15 ml vial geometry used for analysis of the reactor coolant sample, no comparison of the 15 ml vial geometry was made for those detectors.
No violations or deviations were identified.
3.
Backflushable Filters - Liquid Radwaste Systems (84523)
The licensee utilized backflushable filters on a variety of plant liquid systems, including certain radioactive liquid process streams and liquid radwaste process streams.
The specific type of backflush filter used at Plant Vogtle was a stacked etched-disk assembly, in which a large number of thin metallic disks were stacked to form a filtration assembly.
An etched pattern on each disk face formed an extremely thin void space, through which water / liquid was forced at pressure but which precluded the passage of suspended micron-sized particulate.
Accumulation of a sufficient volume of particulate on the outside surface and in void spaces would reduce the volumetric flow through the filter; the accumulated material would be removed by valving-off the filter from the process stream and backflushing by forcing gas, usually nitrogen, through the filter in the reverse-flow direction.
The particulate material dislodged from the filter would then be sluiced to a holdup tank and the cleaned filter would be valved back into the system.
The inspector reviewed Preoperational Test Procedure 2-3HC-01,
"Backflushable Filters System."
Systems employing backflush filters at Plant Vogtle, Unit 2, were:
reactor coolant, steam generator blowdown, resin sluice, seal injection, waste evaporator feed, waste monitor tank, spent fuel pit, floor drain tank, and seal water return.
The preoperational tests appeared to have been adequately completed. The inspector noted, however, that the preoperational tests were concerned with the electrical and mechanical functional aspects of the systems and that no actual filtration of liquids or check-out of the backflush function had been made.
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No violations.or deviations were identified.
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Process and Effluent Radiation Monitoring and Sampling System (PERMSS)
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i (84523,84524)
l The inspector reviewed the completed preoperational test procedures for nine PERMSS radiation monitors or samplers which had not been previously tested (Inspection Report No. 50-425/88-71, December 12, 1988, through January 6, 1989, paragraph 6).
All-preoperational test procedures appeared to be adequate and the radiation monitors and samplers had been turned over to the operating group for calibration.
The inspector reviewed the completed radiological calibration procedures for all 22 PERMSS monitors and samplers in the inspector's review area.
All calibrations appeared to have been performed adequately and all components were calibrated to specified accuracies.
PERMSS problems which had been identified during Plant Vogtle, Unit 1, initial fuel cycle operation, had been taken into consideration and, where practicable, problem resolutions identified for the Unit 1 PERMSS were adopted for the Unit 2 PERMSS.
This included such matters as using i
matched sets of detectors and the use of uniform beta window thickness for system beta radiation detectors.
During inspection of the PERMSS monitoring locations, the inspector noted that the insulation and weather-tight jacketing of the heat tracing for the main stack effluent monitor sample transport tubing had been removed.
A licensee representative stated that the original heat tracing cables had not worked properly during testing and calibration and that it had been necessary to remove the insulation and jacketing in order to replace the original heat tracing cable.
It was also necessary to install a special heat-condur. ting covering over and around the heat-tracing cable in order to provide adequate heat transfer from the cable to the sample tubing. As of the end date of this inspection, the insulation and jacketing replacement work was in progress for the three sampling lines for the Unit 2 main stack.
The inspector and a licensee representative inspected the locations of liquid effluent release monitors which had functions to initiate the closure of valves to terminate liquid discharges in the event of inadvertent release of radioactive materials at concentrations exceeding established control values.
The licensee's monitors and their locations relative to their isolation valves were acceptable.
With the exception noted immediately above, the inspector determined that the PERMSS met the conditions outlined in Inspection Procedure 84523, conformed to the guidance of Regulatory Guides 1.97, Revision 3 (February 1983) and was consistent with the description contained in the licensee's FSAR.
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The inspector concluded that the PERMSS met all preoperational test requirements, had been adequately calibrated, and was operational.
No violations or deviations were-identified.
5.
Waste Gas System (84524) (Unit 2)
The inspector, accompanied by licensee representatives, inspected portions of the waste gas system and reviewed the completed Preoperational Test Procedure No. 2-3HA-02, " Waste Processing System-Gas." The test procedure had been completed January 12, 1989, after a delay caused by the need to'
replace a recombiner pre-heater, which had overheated during an earlier test.
The inspector's review of the test procedure concluded that the test results appeared to be adequate.
It was noted that in Section 6.10 of the preoperational test procedure ~
(2-3HA-02), it had been necessary to replace a 2-pen recorder with a -
temporary recorder.
The test log reported that an exact replacement recorder was no longer available from the manufacturer due to a model change.
A design change request to replace the original recorder with a current model had been initiated in accordance with plant procedures.
The failure of the recombiner heater was previously )noted in Paragraph 5 of Inspection Report No. 50-425/88-71 (Vogtle Unit 2, December 12, 1988, to January 6, 1989.
A licensee representative stated that the root cause of the preheater failure had been traced to a stuck contact on an electrical relay.
The heater and the relay were both replaced and the replacement components were tested satisfactorily.
On the basis of the preoperational test procedure results, the inspector concluded that the Waste Gas Processing System was ready to be placed in operation.
No violations or deviations were identified.
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Containment and Auxiliary Building Sumps and Drains (84523)
The inspector, accompanied by licensee representatives, inspected selected portions of the Containment and Auxiliary Building radioactive sumps and drains associated with the liquid radwaste system.
The inspector also reviewed Preoperational Test Procedure No. 2-4HG-01, " Containment and Auxiliary Building Drains - Radioactive." The requisite tests appeared to have been successfully completed.
On the basis of the preoperational tests and in-place inspection of j
portions of the sumps and drains in Containment and in the Auxiliary Building, the inspector concluded that the system was adequate and operational.
No violations or deviations were identifie.
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" Waste Processing System - Liquid" (84523)
The inspector, accompanied by licensee representatives, inspected subsystems of the liquid radwaste system in Containment and in the Auxiliary Building.
The ' inspector.. also reviewed Preoperational: Test Procedure 2-3HB-01, " Waste Gas Processing System - Liquid." -Subsystems included. the reactor coolant drain tank (RCDT) and system control features, spent resin storage tank and system control features, and the
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boron recycle holdup tank.
Three sections of the Test Procedure had not been completed pending a management decision on whether or not the systems were to be used; there were the spent resin-storage tank control circuitry checkout and performance test (Sections 6.4 and 6.7) and the recyclable and disposable waste systems performance' test (Section 6.6).
The inspector, based on discussions with licensee representatives, concluded that operation of the subsystems for which Preoperational Test Procedure 2-3HB-01 had not been completed would not be required for. fuel load.
It was also noted that the liquid radwaste system (Unit 2) had not yet been tied-in to the Plant Vogtle Alternate Radwaste Building (ARB) and that liquid radwaste from Unit 2 could not be processed until such time as the tie-in was completed.
With the exception noted above, the inspector concluded that the preoperational test program for the Unit 2 liquid radwaste system had been completed and was sufficiently operational to meet fuel load requirements.
No violations or deviations were identified.
8.
Nuclear Sampling System (84523, 84524)
The Nuclear Sampling System at Plant Vogtle, Unit 2, sampled primary coolant fluids from nine subsystems and primary coolant system gases from four subsystems.
Liquid sample points were:
reactor coolant system hot leg (Loop 1 or 3); pressurizer vapor space; pressurizer liquid space; chemical and volume control system downstream of the letdown heat exchanger; residual heat removal system downstream of heat exchanger A or B; chemical and volume control system downstream of the thermal.
regeneration; chemical and volume control system downstream of the mixed-bed demineralized, the boron recovery system downstream of the recycle evaporator feed demineralized; and the recycle holdup tank at the outlet of the recycle evaporator feed pumps.
Gaseous sample points were:
recycle holdup tanks gas spaces; waste gas decay tanks; reactor coolant.
drain tank gas space; and volume control tank gas space.
The inspector reviewed Preoperational Test Procedure 3-SF-01, " Nuclear Sampling System." The tests run under the procedure appeared to have been conducted in an adequate manner.
The tests had been completed on January 20, 1989, and were reviewed by the inspector on January 24, 198 _
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No violations or deviations were identified.
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Non-Radioactive Sampling System (84523, 84524)
The non-radioactive sampling system was included in the Preoperational Test Procedure 2-4RC-01, " Balance of Plant Sampling System."
The inspector, accompanied by a licensee representative, viewed the turbine-
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plant sampling panel, several secondary coolant sampling points, and the water (potable and plant) treatment plant sampling panel.
The turbine plant sampling system had 47 instrumented sampling points and 115 additional-process grab sample points.
A separate sampling system was provided for the Waste Water Retention Basin Effluent Sampling. System (WWRBESS), which included flow data and composite sampling.- Parameters continuously monitored by the turbine plant sampling system included:
pH, conductivity, dissolved oxygen, residual hydrazine, sodiun, turbidity and silica.
The inspector's review of Preoperational Test Procedure 2-4RC-01 indicated that the procedure had been completed and that the various systems were ready to be turned over to the licensee's operations group. The procedure was completed on December 19, 1988, and reviewed by the inspector on January 25-26, 1989.
No violations or deviations were identified.
10.
Heating, Ventilation and Air Conditioning System High Efficiency Particulate Air (HEPA) Filters and Charcoal Adsorbers (84524)
The inspector reviewed the completion of Preoperational Test Procedure 2-4GL-06, " Auxiliary Building Continuous Exhaust Filtration Units."
This procedure covered the preoperational testing of the HEPA filter and charcoal adsorber units in the three Auxiliary Building ventilation exhaust systems which were the last three outstanding items in the inspector's review area for HVAC systems for Plant Vogtle, Unit 2.
Testing had been delayed due to the need for repairing charcoal retantion screens in all three trains.
The trains contained charcoal beds he/ing a depth of four inches of charcoal for the purpose of retention af radiciodine aerosols.
Tests included air flow capacity, air flow distribution, air and aerosol mixing uniformity, di-octyi phthalate aerosol penetration of HEPA filters, and halogenated hydrocarbon penetration of charcoal adsorbers (leak testing).
Testing was conducted in conformance with ANSI /ANS N510.
All systems were satisfactorily tested and the inspector concluded that the systems were ready for operation.
No violations or deviations were identified.
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11.
Inspector Follow-up Items (92701)
(Closed) INC 50-425/86-18-32:
Complete equipment installation and ensure operational and procedural adequacy for post accident gas and particulate
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effluent sampling.
This item was incorrectly listed for Unit 2 in 1986, some two years prior to an appropriate date.
Post accident gas and particulate effluent sampling was provided at Plant Vogtle, Unit 2, by the PERMSS.
The specific functions were provided by sampling devices which were part of monitor / sampler No. 2RE-12444A,B,C.
Preoperational testing of 2RE-12444A,B,C was discussed in paragraph 6 of Inspection Report No. 50-425/88-71 but was not specifically identified in that report. This matter is considered closed.
(Closed) INC 50-425/86-18-88:
Assure volume of vent air sampled representative of actual effluent activity or that correction factors
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developed compensate for sample scavenging mechanisms.
This item was l
incorrectly listed for Unit 2 in 1986, some two years prior to an appropriate date. Vent sample efficiency representativeness and correction factors for sample scavenging mechanisms were discussed in Inspection Report No.86-137 and the question concerning correction factors for sample scavenging mechanisms was separately tracked under IFI 86-137-06 and, as of the end date of this inspection, was being actively reviewed by the licensee.
The question of representativeness of vent sampling was addressed in Inspection Report No.86-137 and was also addressed during preoperational testing of the PERMSS in Inspection Report No. 50-425/88-71 and in this inspection report. This matter is considered closed.
(Closed) IFI 50-425/88-42-02:
Completion of installation and testing of Unit 2 Post Accident Sampling System (PASS).
Completion of installation and preoperational testing of the Plant Vogtle Unit 2 PASS was discussed
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in Inspection Report No. 50-425/88-70, paragraph 6.
Operational testing
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of the Unit 2 PASS will be conducted at a later date to be established.
IFI 50-425/88-70-01 was established to track the full-power operational testing of the Unit 2 PASS. This matter is considered closed.
(Closed)IFI 50-425/88-42-03: Completion of installation and operation of instruments, systems and equipment required to conduct sampling and analysis of liquid, gas, and particulate effluents.
Preoperational testing of the PERMSS was discussed in Paragraph 4 of this inspection report. This matter is considered closed.
(Closed) IFI 50-425/88-42-04:
Completion of installation, calibration and testing of Unit 2 area and process radiation monitors.
The subject of installation, calibration and testing of Unit 2 process radiation monitors was discussed in Paragraph 4 of this inspection report.
The subject of
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Unit 2 area monitors was discussed in Inspection Report No. 50-425/88-62
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and the installation, calibration and testing of Unit 2 area monitors was tracked as IFI 50-425/88-62-01.
Based on the above, this matter is considered closed for tracking purposes.
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(Closed) IEN 50-424, 425/88-IN-22:
Disposal of sludge from onsite sewage treatment facilities.
The inspector determined that the licensee had received Information Notice 88-IN-22 and that the licensee had taken appropriate action.
The licensee's facilities included a sludge drying facility for volume reduction.
Dried sludge was bagged and sampled and surveyed for radioactivity content prior to disposal.
In two cases, iodine-131 activity was detected and was traced to medical application to plant personnel by private physicians.
The I-131 contaminated sludge was held for several weeks until the 8.4 day half-life of iodine-131 had reduced the radioactivity content to below detectable levels and was then shipped to a landfill for disposal.
To forestall similar occurrences in the future, the licensee established procedures under which licensee employees would be required to report the medical administration of iodine-131 and those employees would be requested to use special facilities where urine would be collected and held for decay or processing as radioactive waste. All shipments of sludge were required to be sampled and surveyed prior to shipment offsite. This matter is considered closed.
(Closed) IEN 50-424, 425/88-IN-31:
Steam generator tube rupture analysis deficiency.
The inspector determined that the licensee had received the Information Notice and that the licensee had initiated appropriate action.
Licensee action had not been completed as of the end date of this inspection because the licensee was awaiting pending steam generator owners' group guidance. This matter is considered closed.
(Closed) IFI 50-425/88-62-02:
Review routine plant survey procedure.
The inspector reviewed health physics procedure 43008-C, Routine Plant Surveys, Revision 9, January 6,1989.
It was observed that the newly revised procedure incorporated the applicable areas of Unit 2 in the routine plant survey schedule.
The inspector also observed that hot particic surveys were included in addition to air samples, contamination l
surveys, and radiation surveys.
The frequencies and schedules for the various types of surveys were specified in the procedure.
All survey forms and data are submitted to health physics supervision upon completion for review. This item is considered closed.
12.
Exit Interview The inspection scope and results were summarized on January 27,1989, wi th those persons indicated in Paragraph 1.
The inspector described the areas inspected and discussed in detail the inspection results.
Proprietary information is not contained in this report.
Dissenting comments were not received from the licensee.
All preoperational testing of systems in the inspector's scope of review had been completed.
Systems inspected were waste gas, PERMSS, Containment and Auxiliary Building drains, liquid radwaste, HVAC HEPA filters and charcoal adsorbers, nuclear sampling system, balance-of-plant sampling system, and backflush filters.
All tests appeared to have been completed adequately.
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Confirmatory measurements of the accuracy of licensee multi-channel analyzers (MCA) were made using the Ril van and mobile laboratory. Of 120 possible points of comparison, the licensee's MCA's were in agreement on all 120.
Eight inspector follow-up items were closed.
No violations or deviations were identified.
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ATTACHMENT 2
.
('
CRITERIA FOR COMPARING ANALYTICAL MEASUREMENTS
'
This attachm nt provides criteria forlomparing results of capability tests and verification measurements. The criteria are based on an empirical relationship which combines prior experience and the accuracy needs of this program.
In this criteria, the judgement limits denoting agreement or disagreement between licensee and NRC results are variable. This variability is a function of the NRC's value relative to its associated uncertainty. As the ratio of the NRC value to its associated uncertainty referred to in this program as
" Resolution"1 increases, the range of acceptable differences between the NRC and licensee values should be more restrictive. Conversely, poorer agreement between NRC and licensee values must be considered acceptable as the resolution decreases.
For comparison purposes, a ratio 2 of the licensee value to the NRC value is computed. This ratio is then evaluated for agreement based on the calculated resolution.
The corresponding resolution and calculated ratios which denote agreement are listed in Table 1 below. Values outside of th2 agreement ratios are considered in disagreement.
NRC Reference Value
- Resolution =
Associated Uncertainty for the Value
'
Licensed Value 2 Comparison Ratio =
!
NRC Reference Value, TABLE 1 CONFIRMATORY MEASUREMENTS ACCEPTANCE CRITERIA RESOLUTION VS. COMPARISON RATIO
-
Comparison Ratio Re s_o_1_ uti on for Agreement
.
<4
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- 2.5 4-
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- 1.66 16 - 50
. 75 - T. 33 51 - 200
.80 - 1.25
>200
.85 - 1.18
!
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'
_ _ - _ _