IR 05000327/1981021
| ML20009D870 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 06/12/1981 |
| From: | Cunningham A, Montgomery D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20009D867 | List: |
| References | |
| 50-327-81-21, 50-328-81-25, NUDOCS 8107240450 | |
| Download: ML20009D870 (8) | |
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S NUCLEAR REGULATORY COMMISSION J/..$
REGION II
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o 101 MARIETTA ST.. N.W.. SUITE 3100 ATLANT A. GEORGIA 30303 g '.V
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Report Nos. 50-327/81-21 and 50-328/81-25
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-Licensee:
Tennessee Valley Authority 500A Chestnut Street Tower II Chattanooga, TN 37401 Facility Name:
Sequoyah Nuclear Plant Dockco Nos. 50-327 and 50-328 License Nos. DPR-77 and CPPR-73 Inspection at Chatt o'o
, TN, Dai sy, TN, i onore, TN Inspector:
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'y, Acting Section Chief D' ate figned EDPS Branc SUMMA'lY Inspection on May 13-20, 1981 Areas Inspected This routine, unannounced inspection involved 40 inspector-hours onsite in the area of radiological environmental monitoring and surveillance including manage-ment controls; status review of radiological environmental surveillance program; inspection of environmental sampling stations; review of analytical quality control program; and implementation of radiological environmental monitoring and surveillance program.
Results Of the five areas inspected, no violations or deviations were identified in five areas.
8107240450 810616 PDR ADOCK 05000327-G
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REPORT DETAILS 1.
Persons Contacted Licensee Employees J. Ballentine, Plant Superintendent
- M. R. Harding, Compliance Supervisor
- D. O. McCloud, Quality Assurance Supers._
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- M. L. Hellums, Environmental Engineer C. Mills, Environmental Engineer R.' Carter, Supervisor, Eastern Radiochemical Laboratory R. H. Shell, Supervisor, Environmental Planning Section (Regulatory Staff)
J. W. Dillard, Analytical Chemist J. T. Harvey, Analytical Chemist R. H. Inman, Radiological Chemical. Analyst J. L. Lob, Supervisor, Quality Assurance (RH3)
NRC Resident Inspector
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- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on May 20, 1981 with those persons indicated in paragraph 1 above.
3.
Licensee Action on Previous Inspection Findings No previous inspection findings were outstanding.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Management Controls a.
Management and administrative controls defined in Section 6.0 of the Technical Specifications were reviewed by the inspector with respect to the following items: (1) organizational and management responsibility for the radiological environmental monitoring program; (2) environ-mental monitoring procedures; (3) quality assurance including periodic audits and analytical quality control.
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b.
The inspector conducted a detailed review including discussions with cognizant licensee representatives of recent organizational changes to determine the adequacy of specific management responsibility for the radiological environmental monitoring and surveillance program.
Inspection disclosed that organizational structure and specific manage-ment assignments should assure continued implementation of the program in accordance with license requirements.
There were no questions regarding this item.
c.
Technical Specification 6.8.4 requires the Radiological Hygiene Branch to establish, implement, and maintain detailed written procedures for the following program commitments:
(1) radiological environmental monitoring and surveillance; (2) quality assurance program for radio-
.logial effluent and environmental monitoring in accordance with
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guidance defined in NRC Regulatory Guide 4.15 (Quality Assurance For Radiological Monitoring Programs).
Inspection included a detailed review of procedures and discussions of same with cognizant licensee representatives. The procedures listed below were reviewed.
(1) Radiological Hygiene Branch Environmental Radiological Monitoring Manual.
The subject manual included:
quality assurance proce-dures addressing routine environmental radioactive monitoring reports, source calibration of environmental radiation monitors, sampling of environmental media, and analysis of environmental samples collected during radiological emergencies.
(2) Radioanalytical Laboratory Manual.
The subject manual included
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the procedures listed below:
G-01 Gross Alpha and Gross Beta Activity Determination (10/15/80-R1)
G-02 Determination of Gross Fission Products in Urine (5/1/78-RO)
G-03 Gamma Analysis of Environmental Samples (10/15/80-R1)
I-01 Radiochemical Determination of Iodine-131 in Milk (10/15/80-R3)
and Water I-02 Radiochemical Determination of Iodine-131 in (10/15/80-R1)
Charcoal Filters OP-01 Operating of Low Background Beta (Alpha) Co.;nting (10/15/80-R1)
Instruments
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OP-02SodiumIodideSingle.Channelknaly:erOperating (10/15/80-R1)
Procedure OP-03 Alpha Spectrometer Operating Procedure (10/15/80-R1)
OP-04 Sodium Iodide Spectroscopy System Operating (10/15/80-R1)
Procedure OP-05 Germanium Spectroscopy System Operating (6/1/79-RO)
Procedures OP-06 Operation of Liquid Scintillation Counting (10/15/80-R1)
Instruments OP-08 Beta / Gamma Coincidence Operating Procedure (10/15/80-R1)
P-01 Radiochemical Determinaton of Phosphorus-32 in (7/1/77-R0)
Urine Pb-01 Determination of Lead-210 in Environmental (6/1/79-RO)
. Samples PO-01 Oetermination of Polonium-210 in Environmental (6/6/79-RO)
Samples QC-01 Germanium Spectroscopy System Energy Calibration (10/15/80-R2)
and Count Reproducibility Check QC-02 Germanium Detector System Background Check (10/15/80-R3)
QC-03 Germanium Detector Photopeak Resolution Check and (10/15/80-R2)
Peak-to-Compton Ratio Check QC-04. Efficiency Calibration (10/15/80-R3)
QC-05 Systems Linearity. Check (10/15/80-R2)
QC-06 MC. Elapsed Time Clock Check (6/1/79-RI)
QC-07 Multichannel Analyzer Live-Time Clock Check (6/1/79-R1)
QC-08 Pole /Zero Cancellation and DC Level Adjt stment (10/15/80-R3)
QC-09 System Noise Check (6/1/79-R1)
QC-10 Alpha and Beta Background and Counts Reproduci-(10/15/80-R2)
bility Checks
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QC-11 Iodine 131 Single-Channel Analyzer Counting (10/15/80-R2)
System Energy-Calibration, Counts-Reproducibility, and Background-Level Checks QC-12 Beta-Gamma Coincidence Counting System Energy (6/1/79-R1)
Calibration, Count-Reproducibility, and Background Checks QC-13 Alpha / Beta Crossover Check ( 10/15/80-R2)
'C-14 Determination of Beta Counting Plateau (10/15/80-R2)
Q QC-15 Sodium Iodide Background Check (10/15/80-R1)
QC-16 Sodium Iodide Photopeak Resolution Check (10/15/80-R1)
-QC-17 Sodium Iodide Energy Calibration and Count (10/15/80-R1)
Reproducibility Check QC-18 Liquid Scintillation Background and Count (10/15/80-R1)
Reproducibility Check QC-20 Alpha Spectrometer Energy Calibration and Count (6/1/79-RO)
Reproducibility Check-QC-21 Alpha Spectrometer Background Check (10/15/80-R1)
QC-100 Calculation of Lower Levels of Detection for (6/1/79-R0)
Environmental Analysis Ra-01 Radiochemical Determination of Radium-226 in (6/1/79-R2)
Environmental Samples Ra-02 Radiochemical Determination of Radium-228 in (6/1/79-RO)
Environmental Samples S-01 Total Sulfide (Sulfur? in Urine Sample (7/1/77-RO)
Preparation SP-01 Sample Preparation (10/15.'80-R1)
Sr-01 Radiochemical Determinatior, of Strontium-89 & 90 (10/15/80-R1)
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in Environmental Samples Sr-02 Determination of Strontium-90 in Urine by Anion (6/1/79-R1)
Exchange STD-01 Standardization of Carriers (10/15/80-R1)
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STD-02 Beta-Gamma Coincidence Standardization for (10/15/Ea-R1)
Iodine-131 STD-03 Iodine-131 Single Channel Analyzer Counting (6/1/79-R0)
i Systam Standardization
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l T-01 Radiochemical Determination of Aqueous Tritium (10/15/80-R2)
TH-01 Radiocnemical Determination of Thorium in (10/15/80-R2)
Environmental Samples U-01 Fluorimetric Determination of Uranium in (6/1/79-R1)
Envi.mnmental Samples QC.31 Quali cy Assurance Program for Radioanalytical (2/1/80-RO)
Laboratory QC-102T Radicanalytical Laboratory Procedure (Control (1/16/81-RO)
Thereof)
QC-103T Quality Assurance Records Procedure (1/16/81-R0)
Review and inspection of procedures, including discussions with cogni-zant licensee representatives, disclosed that all procedures appeared to be consistent with license requirements and accepted industry practice.
The inspector informed licensee representatives that the radioanalytical laboratory manual table of contents required updating to include Procedure QC-101, QC-101T, QC-103T, and STD-04.
There were no further questions regarding this item.
d.
Technical Specification 6.5.2.8k provides for a it of the radiological environmental monitoring program and the results thereof at least once per 12 months.
Technical Specification 6.5.2.8.1 provides for audit of the Offsite Dose Calculation Manual and respective implementing proce-dures at least once per 24 months.
The inspector reviewed and discussed with cognizant licensee representatives audits and respective check lists implementi,g t'ie above requirements.
These audits are
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discussed below.
(1) Audit Report No. OPQAA-SQ-80TS-03 (February 20, 1981) included, in part, the activities and documentation associated witn radiolo-gical environmental monitoring defined in the facility Technical f
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Specifications.
The subject audit was conducted on January 21-23, 1980, and disclosed that the monitoring program met all Technical Specification requirements and conditions.
(2) Audit Report No. OPQAA-MS-80TS-01 (September 12, 1980) was limited-to a review of activities associated with the Radiological Assess-ment Review Committee (RARC) and the offsite dose calculation program. The requirements assessed during the course of the audit conducted August 19-20, 1980, were Technical Specification 6.5.3, and the Offsite Dose Calculation Manual produced, maintained, and revised (when required) by the RARC.
The subject audit disclosed the following findings:
(1) audit reports were not being prepared and issued in accordance with Radiological _ Hygiene Branch proce-dural requirements; (2) unreviewed safety questions performed by the RARC were not adequately documented; (3) alternate members of the RARC were not designated in writing as required by Technical-Specification 6.5.3.3.
Inspection disclosed that the above findings were promptly resolved as required.
There were no questions regarding this item.
(3)- Audit Report No. RHB/QA-80-9 (December 3, 1980) was limited to radioanalytical services provided co the Radiological Hygiene Branch by the Laboratory Servic. a Branch.
The subject audit was conducted during the period October 20, 1980 through November 1, 1980. Although the subject audit was not directed toward any specific facility license, the audit scope and subject concernad radioanalytical requirements addressed in Sequoyah and Browns Ferry Nuclear Plants Technical Specifications.
The two major findings disclosed (viz., incomplete verification and documenta-tion of computer program summarizing annual environmental data for
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-NRC annual report, and failure tc evaluate laboratory cross-check analyses for first and second calendar quarters of 1980) were corr'ected, as required.
There were no questions regarding this item.
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e.
Technical Specification 6.8.4.b requires the Radiological Hygiene Branch to es' blish, implement, and maintain written procedures for an adequate Quality Assurance Program for effluent and environmental monitoring, using the guidance provided in NRC Regulatory Guide 4.15 (Quality Assurance for Radiological Monitoring Programs (Normal Opera-tions) - Effluent Streams and Environment).
Tecnnical Specification 3.12.3 provides for performance of analyses on radioactive materials supplied as part of an Interlaboratory Comparison Program (ICP) which has been approved by the NRC.
As part of the above program, Technical Specification 4.12.3 requires that a summary of results obtained as part of the ICP, and in accordance with the Offiste Dose Calculation Manual (or participants in the EPA cross-check program) shall be included in the Annual Radiological Environmental Operating Report.
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view cf the above license requirements, inspection included a detailed review of analytical quality assurance / quality control procedures and programs developed, implemented, and maintained by the Radiological Hygiene _ Branch.
Inspection disclosed that the quality assurance program in progress was consistent with the requirements defined in Procedure QC-101 (Quality Assurance Program-Radioanalytical Laboratory)
of the Radioanalytical Laboratory Procedures Manual, and guidance defined in the NRC Regulatory Guide 4.15.
The inspector reviewed quality assurance icgs, records and reports adcressing intralaboratory quality control (including replicate analyses, analyses of spikea and blank samples) and interlaceratory cross-checks with EPA and the State of Tennessee.
There were no questions.regarding this item.
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Implementation of Radiological Environmental Monitorirg and Surveillance Program a.
The inspector ccnducted a detailed review of the subject monitoring and surveillance program to determine if the status of the program was consistent with sampling parameters, sampling locations, and schedules defined in Technical Specifications 3.12.1, 4.12.1, 3.12.3, 4.12.3 and Tables-3.12-1, 3.12-2, and 4-12-2.
Inspection included the following:
(1) review Tnd discussion of monitoring,' surveillance and radiochemical procedures; (2) review of selected sampling and analytical logs; (3)
inspection of all air particulate and radiciodine monitoring stations, surface, ground, and drinking water sampling stations; (4) tour of all existing milk sampling stations; (5) selected area TLD stations (excluding those located at air particulate monitoring stations); (6)
selected leafy green vegetables sampling stations; (7) air tritium monitoring stations.
Inspection disclosed that the radiological environmental monitorin3 and surveillance program was implemented as required by the above cited Technical Specifications and license conditions.
Inspection disclosed that calibration status was not posted on 'en of the eleven air particulate /radiciodine monitoring systems.
It was noted however, that records of each six month system
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calibration was recorded in the compling log resident at each monitor-ing station.
There were no questions regarding this item.
b.
Inspection also includea review of the Environmental Radioactivity Levels Annual Report for the period ending December 31, 1980. The report indicated that there were no significant increases in environ-mental radioactivity attributable to operation of Unit 1 of the plant during calendar year 1980.
The contents of the report, including analysis of data appeared consistent with Technical Specification requirements and conditions.
There were no questions regarding this item.
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