IR 05000313/1977015
| ML19320A113 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/13/1977 |
| From: | Brown G, Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19320A106 | List: |
| References | |
| 50-313-77-15, NUDOCS 8004140716 | |
| Download: ML19320A113 (10) | |
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U. S. NUCLEAR REGULATORY COMMISSION
,d 0FFICE OF INSPECTION AND ENFORCEMENT
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REGION IV
Report No.
50-313/77-15 License No.
DPR-51 Licensee:
Arkansas Power & Light Co. (AP&L)
Docket No.
50-313 Sixth and Pine Streets Pine Bluff, Arkansas Category C
Facility:
Arkansas Nuclear One, Unit One (ANO-1)
Inspection conducted: September 20-23, 1977 i
Inspector:
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Blaine Murray, Radiat n Specialist
'Date Approved by:
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Glen D, Brown, Chief, Fuel Facility and Material Date Safety Branch Inspection Summary:
Inspection on September 20-23, 1977 (Report No. 50-313/77-15)
Areas Inspected Routine unannounced inspection of the licensee's Radio-active Waste Systems including liquid and gaseous effluent releases, records and reports of radioactive effluents, effluent control instrumenta-tion, procedures for controlling the release of effluents, testing of air cleaning systems, reactor coolant water quality, solid radioactive waste,
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audits perfomed by the licensee, training and qualifications of Radio-chemistry personnel, radiochemistry procedures and laboratory QC program.
The inspection involved 30 on-site hours by one NRC inspector.
Results:
No items of noncompliance or deviations were noted.
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DETAILS 1.
Persons Contacted (AP&L)
J. W. Anderson, Plant Superintendent
- H. Miller, Assistant Plant Superintendent
- C. H. Halbert, Technical Support Engineer
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- J. L. Bates, Radiochemistry Supervisor
R. T. Elder, Assistant I&C Supervisor
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- R. G. Carrol, Health Physics Supervisor j
- L. Alexander, QC Engineer
- denotes persons present during exit interview.
2.
Action on Previous Inspection Findings (0 pen) Items of noncompliance (50-313/77-08): Two items of noncom-
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pliance and one deviation were noted in IE Inspection Report
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50-313/77-08. Action has been completed for one item of noncompliance-(Training of Off-Site Support Agencies) and the deviation. The
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other item (First Aid Room) remains open pending a follow-up response
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Scope of Inspection
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The purpose of this inspection was to review the licensee's radio-i
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active waste systems and analytical measurements programs for the l
period July 23, 1976, through September 22, 1977.
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4.
Radiochemistry Staff
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The inspector reviewed the training and qualification records of all newly assigned personnel.
Three persons have been added to the radiochemistry staff since the previous inspection 1 It was noted
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that a training and review program has been established for all radio-
chemistry personnel.
5.
Radioactive Effluent Releases - Liquid and Gaseous The ~ inspector examined records of liquid and gaseous effluent releases to determine compliance with Sections 2.4.1, 2.4.2, and Table 2-2 of
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+he Environmental Technical Specifications (ETS).
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No items of noncompliance or deviations were noted.
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Records and Reports of Radioactive Effluents The inspector reviewed the records and reports required by ETS 5.6.1 for content and format.
No items of noncompliance or deviations were noted.
7.
Effluent Control Instrumentation The calibration, response tests, and alann set-point records for the various liquid and gaseous monitors were reviewed to determine com-pliance with ETS 2.4.2.1, 2.4.2.2, and Table 4.1-1 of Appendix A.
It was noted that the background readings for the gaseous waste monitor (RE-4830) were approximately SE+05 counts per minute (cpm).
The read-out range for RE-4830 is 0 to E+08 cpm.
A licensee representative stated that the high background is a i
result of the detector being located at a low spot in the discharge lime. As a result of the monitor location, condensate has a tendency to collect in the counting chamber. According to a licensee repre-sentative, a design change request will be initiated to require that the monitor be relocated to an elevated position in the discharge sys tem.
(See paragraph 14.f.)
In reviewing procedure 1304.27, " Process Radiation Monitoring System Annual Calibration" results, it was noted that the licensee experienced difficulties in completing Section 9.0 for the Penetration Room Ventilation monitors (RI-2120 and RI 2130) and Hydrogen Purge Monitors (RI 7441 and RI 7442).
Section 9.0 involves a sensitivity check with i
a liquid and/or gaseous standard.
The apparent problem with completing i
the calibration procedure seem to be with difficulties in purging the counting chamber between injection of various calibration concentra-
tions.
(Seeparagraph14.d.)
8.
Procedures for Controlling the Releases of Effluents The inspector reviewed waste discharge sampling, and analyses proce-dures to determine compliance with ETS 5.5.1.
The following procedures were reviewed:
1607.07, " Sampling the Laundry Drain Tank" 1607.08, " Sampling the Filtered Waste Monitor Tank" 1607.09, " Sampling the Treated Waste Monitor Tank" 1607.10 " Sampling the ANO-1 unit vent" 1608.18, " Sampling the Gas Decay Tanks" p)
1607.25, " Sampling the ANO-1 Condenser Vacuum Pump Discharge"
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Liquid Waste Release Permit Gaseous Waste Release Permit.
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Procedures 1607.03 and 1607.09 did not specify recirculation times prior to sampling the filtered and treated liquid waste monitor tanks. A licensee representative stated that current procedures will be amended to include recirculation times.
(See paragraph 14.d.)
It was noted that the above procedures had been properly reviewed and approved by the licensee.
9.
Testing of Air-Cleaning Systems The inspector examined test results for the HEPA filters and charcoal absorbers banks to detemine compliance with Technical Specification 3.9, 3.13, 3.14, 3.15, 4.10, 4.11, and 4.12.
The air-cleaning systems include:
-Fuel Handling Area Ventilation System-Control Room Emergency Ventilation Systems-Penetration Room Ventilation Systems-Hydrogen Purge System.
No items of noncompliance or deviations were identified.
10.
Reactor Coolant Water Quality The inspector examined analyses results of reactor coolant water quality to detemine compliance with Technical Specifications 3.1.4, 3.1.5, 3.10, and Table 4.1-3.
No items of noncompliance or deviations were noted.
11.
Radioactive Waste The inspector examined records of analyses of quantities and radio-nuclide composition, handling, storage, and shipments of radioactive wastes. The licensee's radioactive waste program is outlined in the following procedures:
1602.10, " Receipt Inspection and Inventory of Solid Waste Liners" 1602.12, " Radioactive Waste Disposal" 1602.13 " Shipment of Radioactive Material."
No items of noncompliance or deviations were noted.
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'Q-5-12.
Analytical Measurements a.
Analysis Procedures The inspector reviewed radiochemistry laboratory analysis proce-dures. This review involved the following procedures:
1604.01, " Gross Alpha Measurement" 1604.02, " Degassing Liquid Samples" 1604.03, " Tritium Sample Preparation" 1604.04, " Liquid Scintillation Counting for Gross Beta and Tritium" 1604.05, " Gross Gamma Activity Measurement" 1604.09, " Radiostrontium Determination" 1604.12. "E-Bar Determination" 1604.14, " Reactor Building Purge Analysis" 1604.15, " Unit Vent Analysis" 1604.16, " Analysis of Waste Gas Decay Tanks" 1604.17. " Analysis of Liquid Waste" 1604.22, "Use of the NO-6620 for Radiochemistry."
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The above procedures were properly reviewed and approved by s
designated AP&L personnel, b.
Quality Control Program The inspector examined the radiochemistry QC program.
The licensee's QC program is outlined in procedure 1604.19. " Daily Count Room Instrumentation Setup." This procedure contains, or references, test and calibration techniques, frequencies and records of test results.
The licensee uses calibration sources obtained directly from NBS or traceable to NBS.
In reviewing procedure 1604.19 it was noted that the procedure did not include criteria for accepting calibration results. A licensee representative stated that calibration procedures will be revised to include acceptance limits.
(See paragraph 14.e.)
c.
Confirmatory Measurements Confirmatory measurements were performed on the following samples:
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Liquid Waste
(2) Gaseous Waste (3) Stack Charcoal cartridge h
(4) Stack particulate filte ^
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O-6-The confirmatory measurements tests consist of comparing measure-ment made by the licensee and NRC's reference laboratory, Idaho Health Services Laboratory (IHSL).
IHSL's measurements are referenced to the National Bureau of Standards by laboratory intercomparisons.
Confirmatory measurements are only made for those nuclides identified by IHSL as being present in concentra-tions greater than 10% of the respective MPC's for liquid and gas samples and above the Lower Limit of Detection (LLD) for stack samples. Stack charcoal cartridge and particulate filter com-parisons are based on established Lower Limits of Detection (LLD)
for total activity per sample.
Attachment No. I contains the criteria used to compare results.
Attachment No. 2 lists LLD's for stack samples.
The following tables show the comparisons:
(a)
Liquid (Hold-up Tank T-16, Collected April 26,1977)
Nuclide NRC Measurement Licensee Measurement Decision b
bH 6.94 t 0.02E-03 uCi/ml 8.04 t 0.003E-03 uCi/ml Agreement Beta 7.4 t 0.2E-05 uCi/ml 1 t 0.02E-04 uCi/ml Agreement 57Co 1.3 t 0.2E-06 uCi/ml 5.06 i 1.2E-07 uCi/ml Agreement SICr 3.75 t 1.4E-05 uCi/ml 4.08 t 0.14E-05 uCi/ml Agreement 134 s 6.47 t 0.5E-05 uCi/ml 5.05 1 0.2E-06 uCi/ml Agreemerit C
137 s 1.17 t 0.07E-05 uCi/ml 8.79 ! 0.2E-06 uCi/ml Agreement C
58Co 1.45 t 0.04E-04 uCi/ml 1.08 t 0.004E-04 uCi/ml Agreement 54 n 2.06 t 0.08E-05 uCi/ml 1.38 t 0.02E-05 uCi/ml Agreement M
110 mag 1.78 i 0.09E-05 uCi/ml 1.05 t 0.02E-05 uCi/ml Agreement 59Fe 9.9 t 2.2E-06 uCi/ml 7.56 t 0.3E-06 uCi/ml Agreement 60Co 1.22 1 0.04E-04 uCi/ml 6.68 t 0.04E-05 uCi/ml Agreement (b)
Gaseous _ (Make-up Tank T-4, Collected April 26,1977)
Nuclide NRC Measurement Licensee Measurement Decision 133Xe 3.7 t 1.7E+01 uCi/ml 6.34 t 0.2E+01 uCi/ml Agreement 85Kr 9.9 1 0.4E-02 uCi/ml 1.09 t 0.02E-01 uti/ml Agreement (c) Stack Particulate Filter (Collected April 27,1977)
Results were below comparison levels.
(d) Stack Charcoal Adsorber (Collected April 27,1977)
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Nuclide NRC Measurement Licensee Measurement Decision 131 I 1.82 t 0.3E-03 uCi/ sample 1.43 i 0.06E-03 uCi/ sample Agreement 137 s C
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2.31 t 0.9E-04 uCi/ sample 4.35 t 0.4E-04 uCi/ sample Agreement
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13.
Licensee's Audits The inspector reviewed the reports of audits performed by the licensee.
The licensee's records indicated that the Safety kefiew Committee conducted audits of radiochemistry activities on July 29, 1976,
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January 19-20, 1977, and July 26-28, 1977.
The audits reports did not
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identify any significant problems.
14.
Exit Interview At the conclusion of the inspection on September 23, 1977, the inspec-tion findings were discussed with the AP&L personnel denoted in paragraph 1.
The items discussed and AP&L's position with respect to these items, as applicable, follow:
a.
Scope of Inspection The inspector outlined the areas covered during the inspection.
b.
Items of Noncompliance The inspector stated that no apparent items of noncompliance were noted.
c.
Recirculation Times for Liquid Waste Tanks A licensee representative stated that sampling procedures will be amendent to include recirculation times for the various liquid waste tanks.
(See paragraph 8.)
d.
Calibration of Effluent Monitors A licensee representative stated that present calibration proce-dures for the Hydrogen Purge and Penetration Room monitors will be reviewed to ensure that Section 9.0 of Procedure 1304.27 is
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completed.
(See paragraph 7.)
e.
Calibration Acceptance Limits A licensee representative stated the laboratory calibration procedures will be amended to include criteria for accepting calibration results.
(See paragraph 12.b.)
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High Background on Gaseous Waste Monitor
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A licensee representative stated that they would investigate the
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possibility of relocating RE 4830 in order to reduce the background count rate.
(See paragraph 7.)
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ATTACHMENT NO. 1 Criteria for Comparing Analytical Measurement-L The following is the criteria used in comparing the results of capability tests and verification measurements.
The criteria are based on an empirical relationship established through prior experience and this program's analyt-
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In these criteria, the judgement limits vary in relation to the comparison of the resolution.
Resolution = NRC'Value NRC Uncertainly Ratio = Licensee Value NRC Value Comparisons are made by first determining the resolution and then reading across the same line to the corresponding ratio.
The following table shows the acceptance values.
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RESOLUTION RATIO
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Possible Possible Agreement Agreement A Agreement B
0.4 - 2.5 0.3 - 3.0 No comparison 4-7 0.5 - 2.0 0.4 - 2.5 0.3 - 3.0 8 - 15 0.6 - 1.66 0.5 - 2.0 0.4 - 2.5
16 - 50 0.75 - 1.33 0.6 - 1.66 0.5 - 2.0 51 - 200 0.80 - 1.25 0.75 - 1.33 0.6 - 1.66 200 0.85 - 1.18 0.80 - 1.25 0.75 - 1.33
"A" criteria are applied to the following analyses:
Gamma Spectrometry where principal gamma energy used for identification is greater than 250 Key.
d Tritium analyses of liquid samples.
Iodine on adsorbers.
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"B" criteria are applied ~to'the following analyses:
Gamma Spectrometry where principal gamma energy used for identification is less than 250 Kev.
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89Sr and 90Sr Determinations.
Gross Beta where samples are counted on the same date using the same reference nuclide.-
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ATTACHMENT NO. 2 LLDs for Nuclides ~on Particulate'and Charcoal' Filters
'Nuclide
~LLD~(uCi/ sample)
51Cr 1E-04 54 n 1.5E-05 M
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58Co 1.5E-05
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59 e 3E-05
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65 n 3E-05 Z
89Sr 1E-05 90Sr 2E-07 2E-05 131 I 2E-05 134Cs
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2E-05 137Cs
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140 a 2E-05 B
140 a 4E-05 L
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141Ce 2E-05
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144Ce 1E-04 O
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