IR 05000259/1993042
| ML18037A624 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/21/1993 |
| From: | Decker T, Mcneill N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18037A623 | List: |
| References | |
| 50-259-93-42, 50-260-93-42, 50-296-93-42, NUDOCS 9401040059 | |
| Download: ML18037A624 (12) | |
Text
UNITED STATES'UCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W., SUITE 2900 ATLANTA,GEORGIA 30m4I199
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Licensee:
Tennessee Valley Authority 6N 38A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801, QKC 23 1993 Report Nos.:
50-259/93-42, 50-260/93-42, and 50-296/93-42 Docket Nos.:
50-259,'0-260, and 50-296 License Nos.:
DPR-33, DPR-52, and DPR-68 Facility Name:
Browns Ferry 1, 2, and
Inspection Co ducted:
Novemb 29 - December 3,
1993 Inspector:
iz-~t -~
N.
G.
Mc i
Date Signe Approved by: Zv'J>w~~lr ICCi 4'z ~
/8 ~/
T.
R. Decker, Chief Date Signe Radiological Effluents and Chemistry Section Radiological Protection and Emergency Preparedness Branch Division of Radiation Safety and Safeguards SUMMARY Scope:
This routine, announced inspection was conducted in the areas of organizational changes, radiological effluent monitor calibration and operability, Technical Specification chemistry parameters, the Semiannual Radiological Effluent Report, plant decommissioning records, audits, and the Nicrobiologically Influenced Corrosion program.
Results:
The licensee's audits and activities in the areas of radioactive waste-treatment, effluent, and environmental monitoring were detailed and well documented.
The licensee effectively controlled, quantified, and monitored releases of radioactive materials in liquid, gaseous, and particulate forms to the environment; and maintained and operated radioactive waste treatment systems to keep offsite doses as low as reasonably achievable (ALARA)
(Paragraph 2).
Changes to the licensee's organizational structure were found to have no t
apparent negative effects on the ability of the affected units to perform required tasks (Paragraph 3).
, 9401040059 931223 PDR ADOCK 05000259 PDR
Radiological effluent monitors calibration and operability records were found to meet regulatory requirements (Paragraph 4).
The licensee's chemistry parameters were maintained within'echnical Specification requirements (Paragraph 5).
The Semiannual Radiological Effluent Report was examined and total effluents and cumulative resultant doses were found to be well within requirements (Paragraph 6).
The requirements for the licensee to maintain and update records required for decommissioning were discussed with plant representatives (Paragraph 7).
The licensee's program to monitor and prevent Microbiologically Induced Corrosion (HIC) was in place and operable (Paragraph 8).
0, Persons Contacted REPORT DETAILS
2.
Licensee Employees
- S. Armstrong, Chemistry Technical Support Supervisor
- H. Bajestani, Technical Support S.
Bugg, Radwaste Manager
- D. Cathey, Environmental Waste Manager
- R. Crumpler, Mechanical Engineer
- R. Hires, Site Engineering
- D. Horn, Site Engineering
- R. Howard, Site Engineering
'J.
Johnson, Site equality Hanager
- J.- HcDaniel, NA Assessor
- J. Sabados, Chemistry and Environmental Manager
- P. Salas, Compliance Manager K. Schaus, Monitoring Manager, equality Assurance
- A. Sorrell, Program Manager
- R. Wells, Compliance Licensing Manager Nuclear Regulatory. Commission personnel
- C. Patterson, Senior Resident Inspector
- W. Cline, Chief, Region II, Radiological Protection and Emergency Preparedness Other licensee employees contacted included engineers, technicians, and office personnel.
- Attended exit meeting on December 3,
1993 Audits (84750)
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) in the following areas:
(1) the radiological environmental monitoring program and the.results thereof at least once per 12 months; (2) the OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months; (3) the PROCESS CONTROL PROGRAM and implementing procedures for SOLIDIFICATION of wet radioactive wastes at least once per 24 months; (4) the performance of activities required by the equality Assurance Program to meet the criteria of Regulatory Guide 4. 15, December 1977 or Regulatory Guide 1.21, Rev.
1, 1974, at least once per 12 months; and (5) the Radiological Effluent Manual and implementing procedures at least once per 12 months.
The inspector reviewed the following audit reports:
Browns Ferry Nuclear Plant (BFN) - Nuclear Assurance-Radiological Effluent and Environmental Monitoring Audit BFA92303
Browns Ferry Nuclear Plant (BFN) - Plant Chemistry/Plant Layup and Equipment Preservation Audit SSA93301 The inspector also reviewed the following quarterly assessments:
Browns Ferry Nuclear Plant (BFN) - Fiscal Year 1993 Third quarter assessment of Radiological Control (RADCON) and Chemistry, and Environmental/Waste Control - NA-BF-93-091 Browns Ferry Nuclear Plant (BFN) - Nuclear Assurance and Licensing Fiscal Year 1993 Fourth quarter Assessment of Radiological Control, Chemistry, and. Environmental/Waste Control - NA-BF-93-159 The inspector reviewed the following monthly reports:
Browns Ferry Nuclear Plant (BFN) - Nuclear Assurance and Licensing
- October 1993 - Monthly Assessment of Environmental/Waste Control
- NA-BF-93-182 Browns Ferry Nuclear Plant (BFN) - Nuclear Assurance and Licensing
- October 1993 - Monthly Assessment of Chemistry - NA-BF-93-180 Browns Ferry Nuclear Plant (BFN) - Nuclear Assurance and Licensing
- September 1993 - Monthly Assessment of Chemistry - NA-BF-93-156 Browns Ferry Nuclear Plant (BFN) - Nuclear Assurance and Licensing
- September 1993 - Monthly Assessment of Environmental/Waste Control
- NA-BF-93-158 Browns Ferry Nuclear Plant (BFN) - Nuclear Assurance and Licensing
- August 1993 - Monthly Assessment of Chemistry - NA-BF-93-139 Browns Ferry Nuclear Plant (BFN) - Nuclear Assurance and Licensing
- August 1993 - Monthly Assessment of Environmental/
Waste Control
- NA-BF-93-142 Browns Ferry Nuclear Plant (BFN) - Nuclear Assurance and Licensing
- July 1993 - Monthly Assessment of Chemistry - NA-BF-93-120
Browns Ferry Nuclear Plant (BFN) - Nuclear Assurance and Licensing-July 1993 - Monthly Assessment of Environmental/Waste Control-NA-BF-93-123 I
The above audits assessed the adequacy and effectiveness of the radiological effluent monitoring program, radiological environmental program, and the waste management program.
The audits covered the areas specified in TS 6.5.2.8.
In general, the audits were detailed and well documented.
The audits identified some program weaknesses and licensee management made adequate commitments to correct the few deficiencies identified.
Items which were identified as
"Areas For Improvement" were
tracked for management attention and action.
Items which were unresolved or trending negatively were progressively escalated to ensure proper management level involvement.
No violations or. deviations were identified.
Organizational Changes (84750 and 86750)
The inspector and the licensee discussed any changes in the radwaste and radiological environmental monitoring organizations.
These discussions focused on management and personnel changes which could have an impact on the affected "departments ability to perform their required tasks.
The primary change which had occurred in the abovementioned areas concerned the combining of the RADCON Manager, Chemistry Manager, and the Environmental/Waste Control under a
RAD-CHEM Manager.
This reorganization had been implemented in Hay 1993.
The change, beside the removal of Chemistry from Operations, is primarily a combination of similar areas under a single RAD-CHEN Manager.
The impact of this reorganization has been evaluated since the implementation.
There have been no negative effects on the operation of the affected units.
Licensee representative mentioned that this reorganization is to be implemented at the Sequoyah and Watts Bar nuclear plants also.
There were no other significant organizational changes in the areas noted above since the last inspection.
No violations or deviations were identified.
Radiological Effluent Monitor Calibration and Operability (84750)
Browns Ferry Nuclear Plant Offsite Dose Calculation Manual Revision 10, Sections 1/2. 1. 1 and 1/2. 1.2 describes the controls and surveillance requirements for radioactive liquid effluent and gaseous effluent
. monitoring instrumentation, respectively.
Technical Specification 3/4.2.D states the operability and surveillance requirements for radioactive liquid effluent monitoring instrumentation, and Technical Specification 3/4.2.K states the operability and surveillance requirements for radioactive gaseous effluent monitoring instrumentation.
The inspector reviewed the calibration procedures and records for the liquid radwaste monitors, wide range gaseous effluent monitors, and Continuous Air Monitor (CAM) records for the Reactor Building, the Turbine Building, and Radwaste Building.
The following procedures were included in this review:
O-SI-4.2.D. 1, "Liquid Radwaste Monitor Calibration and Functional Test", Revision 7, 1991
O-SI-4.2.F-25(A),
"Wide Range Gaseous Effluent Radiation Monitoring System (WRGERNS) Mid and High Range Noble Gas Calibration", Revision 2, 1991 1-SI-4.2.K.2.a, Reactor Building CAM Detector Calibration 1-SI-4.2.K.2.d, Reactor Building CAN Flow Calibration 1-SI-4.2.K.3.a-l, Turbine Building CAN Detector Calibration 1-SI-4.2.K.3.d-l, Turbine Building CAN Flow Calibration O-SI-4.2.K.4.a, Radwaste Building CAM Detector Calibration The inspector reviewed the calibration records of the monitoring systems noted above and determined that the monitoring systems had been calibrated in 'accordance with the applicable procedures and within the frequencies prescribed by the ODCM.
The inspector also discussed with the licensee representative replacement of all ten of the building gaseous effluent monitors.
These included three Reactor Building Effluent monitors, one Radwaste Building Effluent monitor (common to all three reactor buildings),
and six Turbine Building Effluent monitors (two per unit). The licensee also discussed the addition of a wide range gaseous effluent monitor to the stack as well as the recalibration of the normal range effluent monitor.
The licensee stated that the performance of all the new monitors had been excellent and that their performance would be monitored closely in the future.
No violations or. deviations were identified.
Technical Specification Chemistry Parameters (84750)
Technical Specification 3.6.B.3.a through c outlines the limiting condition level requirements for conductivity, chloride concentration, and pH.
Technical Specification 4.6.B.3.a through c outlines the surveillance requirements for conductivity, chloride concentration, and pH.
The inspector reviewed chemistry performance data for the calendar year 1993 to date.
In all areas specified in the Technical Specifications, the licensee was below the maximum values permitted.
On average, the values for chloride concentration were averaging 0. 100 parts per billion (ppb), the conductivity was averaging 0. 10 to 0. 14 uS/cm, and the pH was averaging 6.75 to 6.85.
The licensee was also monitoring several parameters which, while not required by Technical Specification, are important for fuel integrity and radwaste system surveillance.
These parameters include sulfate analysis which was averaging 1.4 ppb and the dissolved oxygen levels which were averaging 32 t0 34 ppb.
In all parameters analyzed the licensee was performing well below regulatory
requirements as well as industry guidelines.
No violations, or deviations were identified.
Semiannual Radiological Effluent Release Report (84750)
The Browns Ferry Nuclear Plant (BFNP) Radiological Effluent Technical Specification (RETS) Manual,Section II, REM, Revision 13, Section F.2.,
states the requirements for the Semiannual Radiological Effluent Report including timel,iness, content, and format.
The inspector reviewed the report to examine liquid and gaseous effluents specified in this and previous reports to evaluate trends.
Total effluent summaries were available for the first half of 1993 and these were compared to previous yearly totals.
The following Table compares the effluents for the past three years:
Table
Effluent Release Summary for Browns Ferry Units 1, 2 and
Activity Released (Curies)
1991 First Half 1992 1993 Gaseous Effluents:
Fission and Activation Products Iodines and Particulates Tritium 2. 10E+03 1.62E+04 3.54E+03 8.62E-02 1.64E-01 2. 18E-02 2.79E+00 1.86E-01 2.39E+00 Liquid Effluents:
Fission and Activation Products Tritium 9.90E-Ol 2.41E+00 4.06E+00 5.96E+00 2.85E+Ol 6.84E+00 Volume of Liquid Waste Released (liters)
3.31E+07 3.33E+07 1.94E+07 Inoperable Effluent Monitoring Instrumentation for Greater than 30 Days
Unplanned Releases
As can be ascertained from the Table, based upon the half year totals some 'increasing trends are predicted.
This is expected due to the continued operation of Unit 2 after extended outages.
The levels of effluents are in line with projected operating levels for similar reactor s for this time frame of operation.
Trends will be monitored for yearly totals to determine the effect of operations in the future.
Improvements were noted in the area of effluent monitor operability and in the continued absence of unplanned releases.
No violations or deviations were identified.
Decommissioning Records
CFR 50.75(g) requires, in part, that licensee's maintain "records of information important to the safe and effective decommissioning of the facil-ity in an identified location until the license is terminated by the Commission."
Furthermore, information considered important by the Commission for decommissioning is identified as "records of spills or other unusual occurrences involving the spread of contamination in and around the facility, equipment, or site",
and that the records
"must include any known information on identification of involved nuclides, quantities, forms, and concentrations."
The inspector discussed with licensee personnel the requirements for retention and availability of decommissioning records.
The licensee representative stated that no spills had occurred on site which had not been completely decontaminated and released as clean.
The representative further stated that records of such spills were not kept on site but were available as archived data and records offsite. The representative stated that the requirements for decommissioning records could be retrieved should the need arise.
The inspector found that availability of these records, by archival data if necessary, appeared to meet the minimum requirements of
CFR 50.75(g).
The representative was advised that retrieval of this data was a requirement and that the data should be in one location available for the Commission to review.
No violations or deviations were identified.
Hicrobiologically Induced Corrosion (84750)
Technical Specification 3/4.6.B, Reactor Coolant Chemistry, and Plant Hanager Instruction PHI-2., Conduct of Chemistry
, Revision 3, August 1989, describe the requirements and responsibilities of the Chemistry monitoring program.
Mater chemistry can have a major impact on component performance, availability, and expected durability.
Condenser water box material integrity is closely aligned with the control and minimization of several different secondary water chemistry parameters as well as biologically influenced corrosion factors.
The inspector discussed with cognizant licensee personnel the continuing
actions that the plant was taking to prevent microbiological attack and macrofouling of cooling water piping and heat exchangers within the plant service water system.
Protection against ingress of corrodants from the plant cooling system is discussed below.
The inspector. reviewed the following Project Engineering Specifications to become familiar with applicable system descriptions and programs:
~
Project Engineering Specification NIH-005, Corrosion Control, Hicrobiologically Induced Corrosion, dated January 1992 Project Engineering Specification NIH-006, Corrosion Control, General, Localized, and Galvanic Corrosion, dated April 1992 The inspector reviewed the following Site Standard Practice which outlines the overall program at BFNP:
Site Standard Practice, SSP-13.5, Raw Mater Fouling and Corrosion Control Program, Revision 1, dated October 1993 The inspector reviewed the following specific procedures which implement the particulars for, each affected organization:
Surveillance Instruction, 0-SI-4. 11.B.l.d, Biocide Addition to Raw Cooling Water System and High Pressure Fire Protection System, Revision 7, dated October 1993 Technical Instruction, O-TI-110, Emergency Equipment Cooling Water Chlorination, Revision 6, dated Harch 1992 Technical Instruction, O-TI-154, Coupons and Honitoring for Corrosion and Deposit Control, Revision 2, dat d August 1993 Chemical Instruction, CI-129, Hicrobiologically Induced Corrosion
'(HIC) Procedure, Revision 2, dated April 1991 The specific Instructions outline the duties of affected groups which both add biocides to the Emergency Equipment Cooling Water (EECM) system and the Raw Cooling Water (RCW) system as well as the monitoring of corrosion and biological attack in these systems.
At the present time the only biocide being added to these systems is sodium hypochlorite which is an active oxidizing agent.
No other chemical addition is now being implemented.
The addition of biocide is tied to water temperature in the Tennessee River and hence reflects clam reproductive cycles.
When conditions are optimum for growth of macro and micro-biological organisms, sodium hypochlorite addition is continuous within NPDES and State regulation The licensee stated that the plant has approved requisition plans to add a chemical addition and monitoring system.
This system will add both oxidizing and 'non-oxidizing biocides, sequestrants, dispersants, and other corrosion inhibitors.
The plant will maintain it's coupon corrosion and biofouling monitoring system when the new system is acquired.
The program is now in place and the existing equipment appear to meet minimum system and programmatic requirements.
The inspector stated that the new equipment and subsequent revised procedures will be reviewed during future inspections.
No violations or deviations were identified.
Exit Meeting The inspector met with licensee representatives indicated in Paragraph
at the conclusion of the inspection on December 3,
1993.
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 licensee.