IR 05000348/1982004
| ML20054D806 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 03/03/1982 |
| From: | Evans C, Montgomery D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20054D789 | List: |
| References | |
| 50-348-82-04, 50-348-82-4, 50-364-82-03, 50-364-82-3, NUDOCS 8204230400 | |
| Download: ML20054D806 (9) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION o.
E REGION 11
o 101 MARtETTA ST., N.W., SUITE 3100
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o ATLANTA, GEORGIA 30303
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Report Nos. 50-348/82-04 and 50-364/82-03 Licensee: Alabama Power Company P. O. Box 2641 Birmingham, AL - 35291
Facility Name:.Farley Docket Nos.~ 50-348 and 50-364 License Nos. NPF-2 and NPF-8 Inspection at Farle ; site ne,ar Ashford, Alabama Insp tor:
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/8II WJ C. D. Evans V
'Dat/ Signed Accompanying Personnsl:
R. McPhail
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Approved by:.
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0. M.'1%ntgoinery, Ch '
, IM&EP Section Fate 6igned EPOS Division SUMMARY Inspection on February 8-12, 1982 Areas Inspected This routine, unannounced inspection involved 36 inspector-hours on site in the areas of quality control and confirmatory measuremer.ts including: review of-the laboratory quality control program; review of chemical and radiochemical proce-
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dures; review of quality control audits and effluent accountability; and -
comparison of.the results of split samples analyzed by the licensee and the NRC Region II Mobile Laboratory.
Results e
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Of the four areas inspected, no violations or deviations were identified in three areas; one violation was found in one area (failure to implement procedure FNP-1-RCP-706, in that silver zeolite cartridges were used as the collection
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medium for radioiodine during the period of January 18, 1982 to February 10, j
1982; see paragraph 6g.).
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- W. G. Hairston, Plant Manager
- J. D. Woodard, Assistant Plant Manager
- W. G. Ware Quality Assurance Supervisor
- W. C. Carr, Chemistry and Health Physics Supervisor
- W. G. Grippentog, Environmental and Emergency Planning Supervisor J. Gieger, Acting Count Room Foreman Other licensee employees contacted included four technicians.
NRC Resident Inspector
- W. H. Bradford
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on February 15,1982, with those persons indicated in paragraph 1 above. The violation disclosed was discussed. The plant manager acknowledged the violation and stated that an appropriate response would be made to the Notice of Violation. The inspec-tor requested that an area with appropriate electrical power outlets be provided for the RII Mobile Laboratory. The plant manager agreed to provide these facilities.
3.
Licensee Action on Previous Inspection Findings (Closed) Infraction (348/80-24-03): Failure to review changes in Procedure FNP-0-CCP-4, " Potentiometric Determination of Fluoride in Aqueous Solutions" prior to implementation.
The inspector noted that personnel in the chemistry section had been instructed in the proper method of making procedural changes.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Laboratory Quality Control Program The inspector reviewed the licensee's Quality Control Program for radio-chemistry, radiological effluent monitoring and secondary plant chemistry in the following area _ _ -
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a.
Assignment of responsibility and authority to manage and conduct the QC program.
The Environmental and Emergency Planning Supervisor is responsible for general supervision of the radiochemistry and radiological effluent monitoring programs. The day-to-day responsibility for management of the radiochemistry countroom has been delegated to the countroom foreman. The Chemistry Supervisor is responsible for supervision of the secondary plant chemistry program.
b.
Provisions of Audits Quality Assurance Administrative Procedure No. 5 provides for periodic audits in the areas of radiochemistry, radiological effluent monitoring, and secondary plant chemistry.
c.
Methods for Assuring Deficiencies and Deviation in the Program are Recognized, Identified and Corrected Procedure 0QA-AP-09 describes the methods for ensuring that appropriate corrective action is promptly initiated, completed, and reported for all noncompliances which are identified in audits.
6.
Audits a.
Contracted Services Analyses of composite liquid effluent samples and particulate filters for radiostrontium are contracted to the Center for Applied Isotope Study of the University of Georgia. The quality assurance program of the Center for Applied Isotope Study was audited by the Safety and Engineering Review Audit Section on December 3, 1981.
No items of noncompliances were reported. A licensee representative indicated that the licensee is developing the capability to perform radiostrontium analyses within the plant radiochemistry section and that termination of the contract with the center for Applied Isotope Study is expected sometime during the year.
b.
Annual Audit The radiological ef fluent monitoring program was audited by the Safety and Engineering Review Audit Section during the period of October 19, 1981 to December 15, 1981.
One noncompliance was reported, in that allowance for sufficient recirculation time of the monitoring tank was not done before sampling.
The intent of the audit was to show compliance with Technical Specification 3/4.11,
" Radioactive Effluents".
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7.
Review of Radiochemistry and Chemistry Procedures, Logs, and Records a.
The inspector reviewed the following procedures:
(1) FNP-STP-518, " Principle Gamma Emitter Analysis of Waste Gas Decay Ta n k", 8-6-81.
(2) FNP-0-RCP-713,
" Preparation of Standards for Radiochemical Counting Geometries", 7-29-81.
(3) FNP-1-RCP-705, " Liquid Waste Release Program", 8-6-81.
(4)
FNP-0-RCP-728, Operation and Calibration of Multichannel Analyzer Systems", 8-19-81.
(5)
FNP-1-RCP-721, " Establishing Sensitivity Limits for Selected Liquid Radionuclides by Ratio Method", 9-23-81.
(6) FNP-1-STP-717, " Tritium Analysis of Waste Decay Tank Releases",
8-6-81.
(7)
FNP-0-RCP-700, "The Chemical Separation and Radiochemical Analysis of Phosphorus-32",12-23-81.
(8)
FNP-0-RCP-716, "Tri tium Analysi s", 12-30-81.
(9)
FNP-0-RCP-701, "The Chemical Separation and Radiochemical Analysis of Iron-55", 8-7-81.
(10) FPN-0-RCP-730, " Operation and Calibration of Gas Flow Preportional Counting Systems", 8-6-81.
(11) FNP-1-RCP-704, " Schedule for Effluent Monitoring and Counting Room Acitivites", 6-17-81.
(12) FNP-1-STP-121 " Iodine Determination in Charcoal Samples at Plant Vent Stack Releases", 8-19-81 (13) FNP-0-CCP-88, " Determination of Fluoride Ion Using Fisher Model
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525 pH Meter", 7-12-81.
(14)
FNP-0-CCP-9, "The Determination of Boron in Aqueous Solutions",
5-4-80.
(15)
FNP-0-CCP-7, "The Determination of Dissolved Hydrogen, Nitrogen, and Oxygen", 5-30-80.
(16) FNP-0-CCP-34, " Calibration and Control of Chemical Analysis Instruments", 5-1-8 *
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b.
The inspector reviewed the following Logs and Records:
(1) Fluoride Electrode Calibration Curve, 9-3-81.
(2) Calibration Standard Certificates for Ge(L1) Detector Counting Gecmeteries, 1-1-81.
(3)
172.00.00, Beckman Quench Standard Certificate.
(4) Ge(L1) Efficiency Calibration Records for 1981 and 1982.
(5) Liquid Scintillation Counter Daily Backgrounds,1-1-81 to 2-9-82.
(6) H-3 Efficiency vs. External Standards Ratio Curve,1-29-82.
(7) Daily Performance Check for Ge(Li) Detectors, 9-1-81 to 2-9-82.
The inspector discussed the results of the procedure and record review with licensee representatives as noted in paragraphs 6c through 6h.
c.
The inspector reviewed the procedure for determination of fluoride in reactor coolant samples, FNP-0-CCP-88 and noted that the quality control program for the ion selective electrode specifies a daily response check.
This closes a
previously identified item (348/80-24-01; 364/80-31-01).
d.
The inspector noted that efficiency determinations for tritium analysis by liquid scintillation counting are being conducted with a tritium standard that is in a different chemical state and in a different scintillation cocktail than actual samples. The inspector noted that NBS tritiated water standards should be utilized for calibration purposes since tritium is present as tritiated water in actual samples, and that the same scintillation cocktail mixture should be used for standards and samples. A licensee representative agreed to investigate the efficiency calibration method.
This was a previously identified item and will be reviewed in a subsequent inspection (348/80-29-02, 364/80-31-02).
The inspector reviewed the daily resolution checks of Ge(Li) Detector 1 e.
and noted that the resolution of the 1333 kev photopeak had gradually e increased from 2.26 to 2.81 kev during the period of October 1,1981 to February 2, 1982.
The detector subsequently failed to function on February 3, 1982. At no time prior to the failure of the detector did the daily resolution check exceed the control limit, established by calculating a one sigma value from recent resolution data.
The inspector noted that the method for defining a control limit may not be sensitive to gradual degradation of the Ge(Li) detector.
The licensee representative agreed to review the resolution test and revise the method as necessary.
This area will be reviewed during a subsequent inspection (50-348/82-04-01, 50-364/82-03-01).
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f.
The inspector noted that the licensee was using outdated calibration standards for the Ge(Li) gamma spectroscopy system and that many of the photopeaks were no longer present, because of decay. The use of outdated calibration standards can increase the uncertainity of the Ge(Li) detector efficiency calibrations.
A licensee representatives stated that new calibration standards were on order and that the procedure controlling the acceptance of calibration standards would be revised. This area will be reviewed during a subsequent inspection (SC-348/82-04-02,50-364/82-03-02).
g.
The inspector determined from discussions with licensee representatives and from examination of sampling points for gaseous releases, that charcoal cartridges had been replaced with silver zeolite cartridges for sampling radiciodine during the perid of January 18, 1982 to February 10, 1982. The inspector noted that the use of an alternate sampling media had not been approved or evaluated.
Prior to substitution, the need to recalibrate the Ge(L1) counters for silver zeolite cartridges and the collection efficiency of various radioiodine species as a function of flow rate was not evaluated. The inspector noted that procedure FNP-1-RCP-706 requires the use of charcoal cartridges at all gaseous efflumt sampling points. The inspector informed licensee representati. :s that failure to follow procedure FNP-1-RCP-706 constituted a violation of Technical Specification 6.8.1 (348/82-04-03, 364/82-03-03).
h.
The inspector examined the plant stack sampling system and questioned if the single sampling probe design was adequate for the large diameter of the stack. A licensee representative stated that the flow of the stack was turbulent and that a multiprobe sampler was not necessary.
The inspector noted that transverse velocity data indicated a varience in velocity of 1000 FPM across the stack diameter at the point of sampling, which would support the possibility for nonunifom particle composition at the sampling point and the need for a multiprobe sampler. The inspector also noted that additional sample lines for post accident monitoring had been attached to the routine sampling system without an evaluation of the necessary flow rate changes to maintain isokinetic sampling. This area will be reviewed during a subsequent inspection (50-348/82-04-04, 50-346/82-03-04).
8.
Confinnatory Measurements a.
Liquid and gaseous samples were collected during this inspection and counted by the licensee and the NRC RII fiobile Laboratory to verify the licensee's capability to measure radionuclides in effluent and primary coolant samples.
Samples were anlayzed by gamma ray spectroscopy and included a waste gas holdup tank sample, a residual heat removal (RHR)
sample from the primary side and a liquid waste holdup tank sample. A spiked particulate filter and charcoal cartridge were counted by the licensee since suitable samples were not availabe for counting during the inspection. An aliquot of the liquid waste holdup tank was sent to the NRC contract laboratory for H-3, Sr-89, and Sr-90 analyses. The
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results will be compared to licensee results in a subsequent inspection report (50-348/82-04-05, 50-364/82-03-05).
The comparisons of the licensee and the NRC results are presented in Table I with acceptance criteria in Attachment 1.
The results show agreement for all radionuclides except for Co-58 and Co-60 in the RHR primary side sample.
The Co-58 and Co-60 results were in "possible agreement" This may be attributed to the use of outdated calibrations standards for the Ge(Li) detector efficiency calibration as discussed in paragraph 6f.
b.
The inspector reviewed licensee results for Sr-89 and Sr-90 analyses of a liquid waste hold-up tank sample collected during a previous inspec-tion.
The comparison of licensee and NRC analyses are given in Table 2, with the acceptance criteria in Attachment 1.
The activity levels reported from the analyses were to low for a meaningful comparison. The licensee did not report results for tritium.
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TABLE 1 RESULTS OF CONFIRMATORY MEASUREMENTS AT FARLEY NUCLEAR PLANT FEBRUARY 8-12, 1982 (Concentration,Microcuries/cc)
Sample Isotope Farley NRC Ratio /NRC Resolution Comparison Waste Gas Xe-133 8.948 E-4 8.25E-4 2.85E-05 1.08
Agreement Decay Tank RHR Primay Cr-51 1.56 E-1 1.61.03E-1
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Side Mn-54 7.70 E-3 8.04.21E-3-
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Agreement Co-58 4.55 E-1 6.09.01E-1
.75 609 Possible Agreement Fe-59 7.94 E-3 7.74.34E-3 1.03
Agreement Co-60 1.89 E-2 2.57.04E-2
.74 64-Possible Agreement Zr-95 1.11 E-2 1.23.04E-2
.90
Agreement Co-57 7.56 E-4 8. 37 1.1 E-4
.90
Agreement Liquid Waste Mn-54 2.46 E-4 1.99.37E-4 1.24
Agreement Tank Co-60 2.22 E-3 2.19.07E-3 1.01
Agreement Co-58 4.70 E-2 4.39.02E-2 1.07 220 Agreement
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Spiked Cr-51 3.86 E-4 3.931.71E-4
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Agreement Particulate Co-58 2.41 E-3 1.88.04E-3 1.28
Agreement Filter Co-60 1.50 E-4 1.18.14E-4 1.27
Agreement Spiked Ba-133 5.93 E-2 5.5.1E-2 1.07
Agreement Charcoal
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TABLE 2 RESULTS OF CONFIRMATORY MEASUREMENTS AT FARLEY NUCLEAR PLANT (concentration,microcuries/cc.)
NRC Sample Isotope Laboratory Farley Ratio Resolution Comparison Liquid Waste Sr-90 6 4 E-9
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NC Holdup Sr-89 0 1 E-8
'2 E-9
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NC NC - No Comparison
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