IR 05000259/1992016
| ML18036A759 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/08/1992 |
| From: | Decker T, Gloersen W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18036A757 | List: |
| References | |
| 50-259-92-16, 50-260-92-16, 50-296-92-16, NUDOCS 9207020182 | |
| Download: ML18036A759 (22) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30323 IillN I E IIII; Report Nos.:
50-259/92-16, 50-260/92-16, and 50-296/92-16 Licensee:
Tennessee Valley Authority 6N 38A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Docket Nos.:
50-259, 50-260, and 50-296 License Nos.:
DPR-33, DPR-52, and DPR-68 Facility.Name:
Browns Ferry 1, 2, and
Inspection Condu ted:
May 1-1
,
1992 Inspector:
W. B. Gloersen c s/p~
Date Signed Accompanying Personnel:
A. Massey Approved by:
Date Signed T. R. Decker, Chief Radiological Effluents and Chemistry Section Radiological Protection and Emergency Preparedness Branch Division of Radiation Safety and Safeguards SUMMARY Scope:
This routine, unannounced inspection was conducted in the areas of audits, semi-annual radiological effluent, reports, annual environmental monitoring reports, solid radioactive waste, shipping, and transportation.
Results:
During the Semiannual Radiological Effluent Report period for July 1 through December 31, 1991 there was no airborne or liquid radiological effluent instrumentation inoperable for periods greater than 30 days.
The area-of effluent monitor operability improved in that during the last half of 1990, the Semiannual Radiological Effluent Report documented a large number of effluent instrumentation inoperable for greater than 30 days due to plant modifications.
The majority of the plant modifications had been completed, and during the first half of 1991, only three 9207020182 920bl5 PDR ADOCK 05000259 Q
had been completed, and during the first half of 1991, only three RHR service water monitors were inoperable for greater than 30 days..
The licensee's program to control and quantify radioactive effluents was effective.
There were no unplanned radioactive releases that required reporting to the NRC.
Although the quantities of radioactive material released in both liquid and gaseous effluents increased significantly over the previous two years, the lower levels of activity released dur'ing the previous years reflected that the units had been shut down since 1985.
The licensee's audits and activities in the area of radioactive materials control were technically sound, thorough, detailed and well documented.
The licensee's program for processing, packaging, storing and shipping radioactive solid wastes was effective.
There have been no shipping violations during the last year.
The technicians who performed radioactive waste shipments were adequately trained and performed their duties competently.
Daily solid waste generation has been reduced through aggressive management attention and the bulk material permit program which basically limits the material entering the radiation controlled area (RCA).
e
REPORT DETAILS Persons Contacted Licensee Employees S. Armstrong, Chemistry Technical Support Supervisor
- M. Bajestani, Technical Support Manager
+S. Bugg, Radwaste Manager
- J. Cory, Radiation Protection Manager
- C. Crane, Maintenance Manager
- M. Herrell, Operations Manager G. Knight, Radwaste Controller D. McDaniel, Nuclear Chemist D. Nix, Nuclear Chemist
+J.
Sabados, Chemistry and Environmental Manager
- P. Salas, Compliance Manager
- J. Scalice, Plant Manager
- K. Schaus, Monitoring Manager, Quality Assurance H. Schwan, Radwaste Controller
- J. Wallace, Compliance Engineer, Licensing Nuclear Regulatory Commission
- W. Bearden, Resident Inspector
- E. Christnot, Resident Inspector
- T. Decker, Chief, Radiological Effluents and-Chemistry, RII
- J. Munday, Resident Inspector
- C. Patterson, Senior Resident Inspector
+Attended exit meeting on May 15, 1992 Audits (86740, 86750)
Technical Specification (TS) 6.5.2.8 requires that audits of unit activities be performed under the cognizance of the Nuclear Safety Review Board (NSRB).
CFR 71.137 requires that the licensee carry out a comprehensive system of planned and periodic audits to verify compliance with all aspects of the quality assurance program and to determine the effectiveness of the program for packaging and transportation of radioactive material.
The inspector reviewed the following audit report:
Browns Perry Nuclear Plant
- Nuclear Quality Assurance
- Radioactive Materials Management Audit Report No. BFA92208 The above audit assessed the adequacy and effectiveness of the radioactive materials management program.
The scope of the audit included the review and observation of the receipt, use, and storage of by-product and source material; processing of waste; and the packaging and offsite shipment
of radioactive solid waste.
The audits were thorough, detailed, and well documented.
The audits identified some program weaknesses and licensee management made adequate commitments to correct the few deficiencies identified.
No violations or deviations were identified.
3.
Changes to the Solid Radioactive Waste Program (86740, 86750)
~
The inspector and the licensee discussed any changes in the solid radioactive waste program since the last inspection.
Although there had been no significant organizational changes to the radwaste organization,. the decontamination group had been incorporated into the radwaste organization during the last year.
In March 1991, the licensee had purchased and incorporated into their program a vendor-supplied waste form and classification software program (RADMAN).
Two technicians were interviewed and had demonstrated that their training had provided the skills to operate RADMAN adequately.
No violations or deviations were identified.
Training and Qualifications of Personnel (86750)
, 10 CFR 19.12 requires the licensee to instruct all individuals working or frequenting any portions of the restricted areas in the health protection aspects associated.
with exposure to radioactive material or radiation, in precautions or procedures to minimize exposure, and in the purpose and function of protection devices employed, applicable provisions of the Commission Regulations, individuals responsibilities and the availability of radiation exposure data.
The 'inspector reviewed the qualifications, training, and experience of selected personnel responsible for the processing, storage and shipping of low level radwaste and radioactive materials.. It was noted that radwaste technicians, received periodic training in DOT/NRC regulations, waste license burial requirements, and operating procedures for the transfer, packaging, and transport of radioactive material.
The last training workshop was provided by a,waste processing contractor in September 1991.
Approximately 13 individuals attended this three day training course and passed with at least an 80%
grade on the examination.
In addition, radwaste personnel were knowledgeable in the specialized computer software program (RADMAN) in waste classification, characterization, and radioactive materials shipment The inspector also reviewed the licensee's training program for packaging and'loading radioactive waste, including procedure RWT-001, "Radioactive Waste Packaging and Loading Inspector Training," Revision 1, May 29, 1991.
This four hour training program was provided to radwaste technicians annually, and covered the following areas:
(1) waste processing;,
(2) verification/certification of radwaste package contents';
(3) blocking and bracing; (4) acceptable materials for compaction; (5) disposal site criteria; and (6) package marking.
The last training date was June 26, 1991.
The inspector discussed with the licensee the need to consider expanding the course duration considering the amount of material covered.
No violations or deviations were identified.
Solid Radioactive Waste Management (86750)
CFR 20.311 requires a licensee who transfers radioactive waste to a land disposal facility to prepare all waste so that the waste is classified in accordance with 10 CFR 61.55 and meets the waste characteristic requirements of
CFR 61.56. It further establishes specific requirements for conducting a quality control program and for maintaining a manifest tracking system for all shipments.
The inspector reviewed the licensee's solid radioactive waste management program for wastes generated from Browns Ferry Nuclear Plant operations.
The review included the following: adequacy of implementing procedures to properly classify and characterize waste, to prepare the manifest, and mark packages; overall performance of the process control and quality assurance programs; and the adequacy of required records, reports, and notifications.
In addition, the inspector reviewed the methods used by the licensee to assure that the waste was properly classified, met the waste form and characteristic requirements of 10 CFR 61 and met the disposal site license conditions.
In general, the licensee's procedures provided sufficient detail and guidance to allow technicians to properly package and verify radioactive waste package contents, classify the waste, and prepare the waste manifest.
The inspector also discussed with licensee representatives the onsite storage of mixed wastes.
The licensee indicated that the following mixed waste 'forms were stored onsite:
(1) freon filters (freon has evaporated);
(2) contaminated acids (from electropolisher-approximately 600-700 gallons);
and (3) contaminated oils.
The inspector also reviewed the licensee's program for segregating DAW and clean trash.
Basically, all waste is
ultimately sorted and bagged.
All potentially radioactive trash was placed in y~~w bags, sorted for noncompactible and nondisposable items, and surveyed.
.All clean trash was placed in <gag bags and surveyed before leaving the RCA.
All clean trash was surveyed before compaction at the licensee's non-radwaste compactor.
Health Physics would be called to perform these surveys.
Compacted clean solid waste was disposed of at the licensee's Solid Waste Disposal Facility.
This facility was licensed by the State of Alabama Department of Environmental Management, Permit g 42-02R.. Waste approved for disposal included the following: non-hazardous, nonradioactive solid wastes consisting of scrap lumber, bricks, and spent filter treatment plant resins.
A State inspection was performed once per quarter.
The disposal facility was located outside the protected area on the owner controlled property near the firing range across the road from the LLWSF.
The solid waste disposal facility was surveyed once per year as part of the environmental monitoring program.
This facility has been active since 1973.
The inspector and a licensee representative also discussed radioactive solid waste minimization.
The licensee had established several programs aimed at reducing the radwaste generated and personnel exposures to individuals handling the waste.
Daily waste generation has been reduced through aggressive management attention, such as the assignment of a senior reactor operator fulltime to radwaste.
Based on data provided by the licensee, from October 1991 through April 1992 the volume of radwaste generated was significantly below both the licensee's FY92 goal and the 1991 industry average.
The cumulative volume of radwaste generated from October 1991 through April 1992 was approximately 6E+03 cubic feet.
The licensee's cumulative goal and the 1991 industry average were 1.1E+04'cubic feet and 1.5E+04 cubic feet, respectively.
No violations or deviations were identified.
Shipping of Low-Level Wastes for Disposal, and Transportation (86750)
CFR 20.311 (b) requires each shipment of radioactive waste to a land disposal facility to be accompanied by a shipment manifest that indicates as completely as practicable; a physical description of the waste; the volume; the radionuclide identity and quantity; the total radioactivity; and the principal chemical form.
CFR 71.5 requires that licensees who transport licensed material outside the confines of its plant or other place of use, or who delivered licensed material to a carrier for
transport, shall comply with the applicable requirements of the regulations appropriate to the mode of transport of the Department of Transportation in 49 CFR Parts 170 through 189.
CFR 172.203 (d)(i) requires, in part, that.a shipping paper contain a 24-hour emergency number, as prescribed in subpart G of Part 172 of this subchapter.
The inspector reviewed selected records of radioactive waste and radioactive materials shipments performed from March 1991 to May 1992.
The shipping manifests examined were consistent with the 49 CFR requirements.
The radiation and contamination survey results were within the limits specified for the mode of transport and shipment classification and the shipping documents were being completed and maintained as required.
In addition, the inspector reviewed the shipping records for 1991 associated with radioactive material shipments made in DOT Spec 7A containers.
The inspector reviewed the records of the licensee's determinations for selected packages and determined that they had been fabricated in accordance with an approved design as specified in DOT specifications.
The inspector noted from past records that the licensee maintained on file for at least one year after each shipment the supporting documentation regarding the package specifications as required by 49 CFR 173.415(a).
In addition, the inspector verified that for NRC-certified packagings used by the licensee the Certificate of Compliance (COC) for package Model No.
CNS 3-55 was maintained-and up-to-date.
The inspector reviewed the procedures, license, and safety analysis report for the Chem-Nuclear Systems, Inc.
CNS. 3-55 Type B radwaste shipping cask and identified no apparent problems.
The inspector also reviewed the waste shipment manifests noted above to determine compliance with the 24-hour emergency telephone requirements specified in
CFR 172.203(d).
Based on a review of several waste shipment manifests, the inspector noted that the 24-hour emergency response telephone number was listed as 1-800-237-2322/1-800-258-2322 (in Tennessee).
The emergency contact was the operations duty specialist, located at the licensee's corporate emergency response center.
The inspector reviewed the procedure used by the Operations Duty Specialist, CECC/EPIP-22,
"Operations Duty Specialist/
.Transportation Accident Involving Shipment of Radioactive Materials."
The procedure specified that the Operations duty Specialist collect the necessary emergency response information from the incoming phone call; and then notify the State, plant Shift Supervisor, and the Corporate Rad
Assessment Group.
The Corporate Rad Assessment Group was tasked to notify the plant Radwaste Organization.
On May 14, 1992, the inspector called the emergency response telephone number during the normal shift, and noted that emergency response personnel answered the call while a practice emergency response drill 'was being conducted.
Although the inspector's call was eventually transferred to
.
the operations duty specialist, the inspector noted and
'iscussed with licensee management that'the emergency response telephone number should be a dedicated line only to be answered by the operations duty specialist as described in CECC/EPIP-22.
No violations or deviations were identified.
Low-Level Radioactive Waste Storage Facilities (65051, 86750)
The inspector and licensee representatives toured the licensee's low-level radioactive waste storage facility (LLWSF) which was located outside of the protected area, but in a remote location in-the owner controlled area.
The access to the facility was restricted by a locked fence.
The LLWSF consisted of four concrete modules.
There were five cells per module.
The facility's total storage capacity was approximately 29,000 cubic feet.
The thickness of the concrete walls of three modules was approximately
'8 inches.
The wall thickness of the fourth module was approximately 36 inches.
The licensee was planning to examine the modules for material condition in preparation for future use.
Although there was no formal schedule on facility activation, it was noted that following a 10,CFR 50;59 evaluation, the modules would be used for interim storage of radioactive waste with a storage, capacity of five to seven years.
Although the licensee was not using any of the four modules to store low-level radioactive waste, the fenced area within the LLWSF was being used to store contaminated equipment and as a staging area for dry active waste (DAW).
The DAW was either stored in a metal box or "sea-land" trailers.
The inspe'ctor noted a high radiation area where irradiated equipment from the fuel pool was stored in metal boxes and various containers.
The area was barricaded,
-conspicuously posted, and controlled in accordance with the applicable requirements of 10 CFR 20.203(c).
The containers were appropriately labeled with the necessary information on the potential hazard, including dose rate information and-container contents.
The fence surrounding the LLWSF was also conspicuously posted as a radiation area and was maintained locked except during periods when access to the area was required.
The Radwaste Organization controlled the
key.
No violations or deviations were identified.
Radiological Effluents (84750)
The Radiological Effluent Technical Specification (RETS)
Manual, Section F.2, states requirements for the -Semiannual Radiological Effluent Report including timeliness, content, and formats The inspector reviewed the reports issued for the first and second halves of calendar year 1991 to determine compliance and reviewed data from previous reports to evaluate trends in liquid and gaseous releases.
The effluent information presented in the following table was obtained from current and previous effluent reports:
EFFLUENT RELEASE SU1$9&Y FOR BROWNS FERRY UNITS 1 g 2 g AND 3 Activity Released (curies)
Gaseous Effluents:
1989 1990 1991 Fission and Activation.
Products 0.0 0.0 2.10E+3 Iodines and Particulates Tritium 1.86E-4 1.88E-4 8. 62E-2 2.00E-1 5.94E-1 2.79E+0 Liquid Effluents:
Fission and Activation Products 1.71E-1 3.02E-1 9.90E-1 Tritium 7.01E-1 2.07E-1 5.96E+0 Volume of= Liquid Waste Released (liters)
Inoperable Effluent Monitoring Instruments for greater than 30 days 3,.31E+7 Unplanned Releases The licensee's program to control and quantify radioactive effluents was effective.
There were no unplanned radioactive releases that required reporting to the NRC.
Although the quantities of radioactive material released in
0
both liquid and gaseous effluents increased significantly in 1991, the lower levels of activity released during the previous years reflected that the units had been shut down since 1985.
Due to the extended outage, radionuclides with short half-lives had decayed and only radionuclides with long half-lives were being released as a result of outage
'activities.
The licensee's effluent monitoring system was effectively maintained and system operability had improved since the previous reporting periods.
The report for the second half of 1990 documented a large number of effluent instrumentation inoperable for greater than 30 days. At the beginning of the January-June 1991 reporting period, there were three effluent monitoring instruments inoperable for greater than 30 days.
The liquid radiological effluent instrumentation that was inoperable for a period of greater than 30 days included three residual heat removal service water (RHRSW) monitors.
Monitor 1-RM-90-134 had been out of service due to seismic concerns and due to work on the associated RHRSW heat exchangers.
The seismic concerns were resolved under a design change.
The monitor was declared inoperable, on June 15, 1989.
A hold order was placed to isolate and remove from service the RHRSW piping associated with this monitor.
1-RM-90-134 was returned to service on March 31, 1991 after completion of the design change and heat exchanger work.
As a result of problems related to the sample pump automatic starting circuitry, 2-RM-90-,133 and 2-RM-90-134 were declared inoperable on September 24, 1989 and February 15, 1990, respectively.
A design change was written to correct the problem.
After the design change was completed 2-RM-90-133 and 2-RM-90-134 were declared operable on January 11, 1991 and February 18, 1991, respectively.
During the July-December 1991 reporting.period, there were
'o airborne or liquid radiological effluent instrumentation inoperable for periods greater than 30 days.
The effluent monitors which have been placed "out-of-service" status with their effluent streams isolated were not applicable to be reported to the NRC in the Semi-Annual Effluent Release Report.
No violations or deviations were identified..
Environmental Monitoring (84759)
The RETS Manual, Section F.1 states the requirements for timeliness, format, and content of the Annual Radiological Environmental Operating Report.
The inspector reviewed the Annual Radiological Environmental Operating Report for 1991, dated April 24, 1992.
In general, the environmental monitoring and sampling results
for direct radiation monitoring, atmospheric monitoring and sampling, terrestrial monitoring and sampl'ing, and aquatic monitoring and sampling were consistent.with previous reported levels.
The estimated doses to the maximum exposed individual due to radioactivity released from the licensee's facility in 1991 were presented in the 1991 Annual Radiological Environmental Operating Report.
The maximum calculated whole body dose equivalent was 0.08 mrem/year, or 2.7 percent of the Offsite Dose Calculation Manual (ODCM) limit.
The maximum organ dose equivalent from gaseous effluents was 0.2 mrem/year, or 1.3 percent of the ODCM limit.
The estimated increase in radiation dose equivalent to the general public resulting from plant operations since the last reporting period was trivial when compared to the dose from natural background radiation (typically 295 mrem/year per person, including
.
radon exposure).
The results from each environmental sample were compared with the concentrations from the corresponding control stations and appropriate preoperational and background data to determine influences from the plant. It was noted in the annual report that the average quarterly radiation levels from direct radiation monitoring were approximately 2mR/quarter higher than levels at offsite locations.
Similar differences were noted at the Watts Barr construction site.
The licensee postulated that the differences were probably attributable to combinations of influences such as natural variations in environmental radiation levels, earth-moving activities onsite, and the mass of concrete used in the construction of the site.
Air particulate samples indicated that gross beta activity in 1991 was consistent with levels reported in previous years.
Only natural radioactive materials were identified by monthly gamma spectral analysis of air particulate samples.
No fission or activation products were found at levels greater than the lower limit of detection (LLD).
The results from the analysis of milk samples indicated that no radioactivity which could be attributed to the Browns Perry site was identified.
Similar results were reported for vegetation samples.
The only fission or activation products identified in soil samples were Cs-137, Sr-90, and Sr-89.
The concentrations reported were consistent with levels previously reported from fallout.
The positive identification of Sr-89 at levels near the LLD was typically a result of artifacts in the calculational process.
In 1991, Co-60, Cs-134, Cs-137, and Sr-90 were observed in aquatic media.
The distribution of Cs-137 in sediment is consistent with fallout levels identified in samples both upstream and downstream from the plant during the preoperational phase of the monitoring program.
Cs-137 was
identified in two fish samples.
The downstream sampl'e had a concentration of 0.08 pCi/gram while the concentration in the upstream sample was 0.10 pCi/gram.
.Since the downstream and upstream concentrations were essentially equivalent, the Cs-137 activity was probably a result of fallout or other upstream effluent rather than activities at the licensee's facility. Co-60, Cs-134, and Sr-90 were identified in downstream sediment samples from the plant in concentrations that would produce no measurable increase in the dose to the general public.
No increases in radioactivity were observed in water samples.
Dose estimates were made from concentrations of radioactivity found in samples of environmental media.
Media evaluated included, but were not limited to, air, milk, food products, drinking water, and fish.
Inhalation and ingestion doses estimated for persons at the indicator locations were essentially identical to those determined for persons at control stations.
Greater than 95 percent of those doses were contributed to by the naturally occurring radionuclide K-40 and by Sr-90 and Cs-137, which are long-lived radionuclides found in fallout from nuclear weapons testing.
Concentrations, of Sr-90 and Cs-137 were consistent with levels measured in TVA's preoperational environmental radiological monitoring programs.
Prom a review of the environmental report, the inspector concluded that the plant had negligible impact upon the surrounding environment and any activity which may have been present as a result of plant operations did not represent a significant contribution to the exposure of members of the public.
In addition, the environmental report fulfilled the RETS requirements.
No violations or, deviations were identified.
Exit Meeting The inspector met with licensee representatives indicated in Paragraph 1 at the conclusion of the inspection on May 15, 1992.
The inspector summarized the scope and findings of the inspection.
The inspector also discussed the likely informational content of the inspection report with regard to documents or processes reviewed by the inspector during the inspection.
The licensee did not identify any proprietary documents or processes during this inspection.
Dissenting comments were not received from the license l
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