IR 05000313/1976008
| ML19326B614 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/05/1976 |
| From: | Brown G, Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19326B613 | List: |
| References | |
| 50-313-76-08, 50-313-76-8, NUDOCS 8004160391 | |
| Download: ML19326B614 (14) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
IE Inspection Report No. 50-313/76-08 Docket No. 50-313 Licensee: Arkansas Power and Light Ccspany License No. DUR 51 Sixth and Pine Streets Pine Bluff, Arkansas 71601 Categcry C Facility: Arkansas Nuclear One (ANO-1)
Location: Russellville, Arkansas Type of Licensee: FaR, Power Reactor, 2568 Mw(c)
Type of Inspection: Routine, Unannounced, Radioactive Waste Systems, and Analytical Measurements Dates of Inspection: July 21-23, 1976
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Dates of Previous Radiological Inspection and Environmental Protection Inspection: March 3 and 5, 1976 I
Inspector
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Blaine Murray, iChdiation $peci t
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Accompanying Personnel: None Reviewed by:
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Glen D. Brown, Chief, Fuel Facil f Date'
and Material Safety Branch
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-24-SUMMARY OF FINDINGS
_I. Enforcement Action A.
Items of Noncompliance Identified by the Inspector
B.
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-f Noncompliance Identified by the Licensee Nene.
II. Licensee Action on Previously Identified Enforcement Matters No outstanding items.
III. New Unresolved Items 76-08/1, Radiochesistry QC Program The radiochemistry QC program has not been completed. This item
is considered open.
(See DETAILS, paragraph F.2.)
IV. Status of Previously Identified Unresolved Items A.
-76/04-1, Stack Monitor The status of this item was not reviewed during this inspection. This item remains open.
(See DETAILS, paragraph C.l.a.)
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B.
74/14-03, Radiation Levels in Reactor Containment
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Corrective action related to radiation levels inside contain-ment which exceeds design basis has not been completed. This item remains open.
(See DETAILS,-paragraph Col.f.)
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C.
75/01-1, Effluent Correlation Tests i
Tests have been completed that compared laboratory and effluent monitor results. This item is considered closed.
(See DETAILS, Item C.l.a.)
D.
75/05-2, Air Samp?'- Flow Rates
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Air sampler flow rates have not been verified. This item
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(See DETAILS, Item C.l.b.)
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E.
75/09-3, Whole Body Counter Calibration Procedures Calibration procedures have not been completed for the whole body counting system. This item remains open.
(See DETAILS, paragraph C.1.c.)
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F.
75/05-5, Laboratorv Counting Equipment Calibration Procedures Calibration procedures have not been complaced for laboratory counting equipment used to analyze Health Physics air and cont==4 nation surveys. This item remains open.
(See DETAILS, paragraph C.1.d.)
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V. Unusual Occurrences Approximately 9,500 gallons of borated water containing 262 milli-curies was inadvertently released.
(See DETAILS, paragraph G.1.)
VI. Other Significant Findings
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None.
VII. Management Interview At the conclusion of the inspectian, the inspection findings were discussed with the following AP&L personnel:
Mr. H. Miller, Assistant Plant. Superintendent
Mr. C. H. Halbert, Technical Support Engineer i
Mr. J. L. Bates, Radiochemistry Supervisor
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Mr. L. Alexander, QC Engineer The items discussed and the licensee's position with respect
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to these items, as applicable, follow:
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Scope of Inspection
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The inspector outlined the areas covered during the inspection.
B.
Items of Noncompliance The inspector stated that no items of noncompliance were identified.
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C.
Status of Previously Reported Unresolved Items
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f The licensee provided a status report on outstanding unresolved
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items.
(See DETAILS, paragraph C.)
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RadLochemistzv Quality control Program A licenses representative stated that the present radiochemistry QC program will be improved. This will include obtaining cali-bration sources traceable to NBS and reviewing current cali-
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bration procedures.
(See DETAILS, paragraph F.2.)
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V-5-DETAILS
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A.
Persons Contacted
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AP&L Mr. H. Miller, Assistant Plant Superintendent Mr. C. H. Halbert, Technical Support Engineer Mr. L. Alexander, QC Engineer Mr. J. L. Bates, Radiochemistry Supervisor Mr. R. T. Elder, Assistant I&C Supervisor Mr. R. G. Carrol, Health Physics Supervisor B.
Scope of Inspection The purpose of this inspection was to review the licensee's radioactive waste systems and analytical measurements.
C.
Licensee Action on Previously Reported Items 1.
Items of Noncompliarg No outstanding items.
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2.
Unresolved Items a.
76/04-1. Stack Monitor This item was reported in IE Inspection Report
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No. 50-313/76-04 and involved designating which stack monitor system is to be used during emergency situations.
The status of this item was not examined during this inspection. This item remains open.
i b.
75/05-2, Air Samplers Flow Rates This item was reported in IE Inspection Report Nos. 50-313/75-05 and 50-313/76-04 and involved the measuring of flow rates of various air samplers.
A licensee representative stated flow rate measurements have not been completed. This item remains open.
c.
75/05-3, Calibration Procedure For Whole Body Counter This item was reported in IE Inspection Report g
Nos. 50-313/75-05 and 50-313/76-04 and involved the
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-6-development of a written procedure'for calibration of the whole body counting system. A licensee repre entative stated that the procedure.has not been completed. This item remains open.
d.
75/05-5, Calibration Procedure For Laboratory Counting Equipment This item was* reported in IE Inspection Report Nos.
50-313/75-05 and 50-313/76-04 and involved the development of a written procedure for calibration of laboratory
counting equipment used to analyze health physics air and contamination surveys. A licensee representative stated that the procedure has not been completed. This item remains open.
e.
75/01-1, Effluent Monitoring System Tests This item was reported in IE Inspection Report Nos.
50-313/74-14 and 50-313/76-04 and involved the correlation of laboratory analyses versus corresponding liquid and
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gaseous monitors indications.
This study has been completed.
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Data indicated a close r.reement between liquid values.
However, the study revealed that gaseous measurements did not fall within established acceptance limits. A licensee representative stated that additional work is planned in order to attain better agreement for gaseous
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releases.
The correlation portion of this item is considered closed.
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_74/14-3, Radiati:m Levels Inside Reactor Containment This item was reported in RO Inspection Report No.
50-313/74-14 and involved radiation levels in containment that exceeded design basis. The status of this item is unchanged from that previously reported. This item remains open.
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D.
Crganization The following-chart shows the radiochemistry organization.
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-7 Plant Superintendent
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Assistant Plant Superirtendent Plant Technical Support Engineer
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C. H. Halbert i
Radiochemiscry Cold Chemistry J. L. Bates, Supervisor Health Physics
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Radiochemists D. H. Nickols G. L. Fiser
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M. E. Frala A. L. Smith
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E.
Radioactive Waste Systems
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Radioactive Effluent Release The licensee's rec.ords were examined to determine compliance with the following:
- Limits on ralease rates, concentrations, and total quantities
- Monitoring of specific release points
- Analysis for specific radionuclides
- Limits on activity contained in hold-up tanks
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Liquids Section 2.4.1 of the Environmental Technical Specifications
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(ETS) contains release and storage limits.
Selected release records for the period January 1, 1975, through July 20, 1976, were avamined. No discrepancies were noted.
b.
Gaseous C.weous release limits appear in ETS 2.4.2.
Selected records
were examined. No discrepancies were noted.
2.
Radioactive Effluent Reports The 1975 semiannual reports and a draft copy of the first 1976 semiannual reports were reviewed to determine compliance with ETS 5.6.1.
No discrepancies were noted.
3.
Radioactive Effluent Sampling and Analyses a. ' Liquid The sampling and analyses requirements of ETS 2.4.1. and Table 2-2 were reviewed on the following forms:
- HP 9830 Computer print-out, ' Preliminary Report"
- Form Chem. 024-00
- Form chem. 032-01 No discrepancies were noted.
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b.
Gaseous
The sampling and analyses requirements of ETS 2.4.2 and i
Table 2-2 were eynmined. Gaaeous laboratory results are recorded on the following forms:
- HP 9830 Computer print-out " Preliminary Report"
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- Form chem. 019-01
- Form chem. 021-01
- Form chem. 020-01
- Form chem. 018-01
- Form chem. 017-02 No discrepancies were noted.
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Effluent Control Instrumentation
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The various monitors used to monitor and control liquid and gaseous releases were reviewed. The monitor systems were av==ined to, determine compliance with technical speci-
fications for:
- Calibration and functional tests
- Alarm and trip setting
- Correlation between monitor reading and radiochemistry labocatory results ETS 2.4.2.1 and ETS 2.4.2.2 (Monitoring Requirements) and Table 4.1-1 of Appendix A requires that the liquid and gaseous monitors be calibrated quarterly, tested monthly, and checked daily.
i Monitors RE-4642 and RE-4830 have control functions associated with liquid and gaseous releases. In addition to the above mentioned monitors, the calibration and test records for all I
of the following monitors were ar==ined:
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Monitor Location RE-1237 Fail Fuel RE-2120 North Penetration Room Ventilation RE-2130 South Penetration Room Ventilation RE-2236 Intermediate Cooling Water Loop No. 2 RE-2237 Intermediate Cooling Water Loop No. 1 RE-2400 Reactor Coolant Leak
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RE-3618 Discharge Flumes RE-3632 Main Condenser RE-3809 Decay Heat Loop No. 1 RE-3810 Decay Heat Loop No. 2 RE-3814 Service Water Loop No. 1
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RE-3815 Service Water Loop No. 2 RE-4642 Liquid Rad. Wasta RE-4830 Gaseous Rad. Waste
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RE-7400 Gross Stack Monitor RE-7400(S)
131I Stack Monitor RE-7441 H2 Purge Calibration and test results were included as part of the following procedures:
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1304.26 " Process Radiation Monitoring System Procedure Quarterly Calibration" l
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-10-Precedure 1304.27 " Process Radiation Monitoring System Annual Calibration"
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Procedure lo02.30 " Daily Checks" A few minor discrepancias were noted with some cf the calibration data. These items were reviewed with the licensee.
No major probleme were identified.
The inspector visited the control rc::m to observe the various monitor read-outs and chart recorders. All systems appeared to be operating properly.
5.
Procedures For Controlling the Release of Effluents The procedures used for controlling planned releases of liquid and gaseous effluents were anmined, a.
Liquid
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The following liquid release procedures were reviewed:
Procedure 1604.17 " Analysis of Liquid Waste" g
Form Chem. 026-03 " Liquid Radwaste Release Permit" Procedure 1607.07 " Sampling the Laundry Drain Tank" Procedure 1607.08 " Sampling the Filter Waste Monitor Tank" Procedure 1607.09 " Sampling the Treated Waste Monitor Tank" The licensee's procedures require that prior to each liquid releases, the form titled: Liquid Radioactive Waste Release Permit be processed. The form contains information regarding:
- Tank Identification
- Radiochemistry Analysis Results
- Technical Specification Limits
- Valve line-up
- Monitor tested
- Authorized release rate
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- Total volume discharged
- Total activity discharged
- Approval signature
- Alarm set point Selected release permits were reviewed. In 197~., a total of 637 liquid releases were made. As of July 21, 1976, 564 release permics have been processed. No discrepancies were noted.
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Gaseous
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(1) Decay Tanks Gas decay release data are recorded on the form titled: Gaseous Release Pcrmit. The form provides the following information:
Tank identification Tank pressure Decay time Radiochemistry analysis Technical specificatica analysis Monitor tests Authorized release rate Approval signatura Alarm set point Gaseous release records indicated the following releasa data:
Date Type of Release Total
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1975 Decay Tank
1976 Decay Tank
No discrepancies were noted.
(2) Purge ETS 2.4.2.7 lists requirements for purging the reactor iI building. The licensee's records indicated that four j
purges occurred in 1975 and five so far in 1976 for the period ending July 20.
Purge release procedures i
require that the form titled: Reactor Building Purge -
l Gaseous Waste Release Permit be processed prior to each purge. The release form provides for recording:
l Discharge flow rates Radiochemistry analyses results Technical specification Filter system stat.us Alarm setting Total activity discharged Approval signature n\\
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Selected purge releases were examined. No discrepancies
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Air Cleanina Systems Technical Specifications 3.9, 3.13, 3.14, 3.5, 4.10, 4.11, 4.12 and 4.17 contain the test requirements e r the various HEPA filters and charcoal adsorber banks. These systems include:
- Control Room Emergency Ventilation Systems
- Penetration Room Ventilation Systems
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- Hydrogen Purge System The licensee's records indicated that the required in-place tests for the HEPA and charcoal systems and laboratory analyses of charcoal samples were performed in April and May, 1976.
These tests were performed by an off-site contractor.
The contractor's test results were reviawed. No discrepancies were noted.
In addition to the in-placing tests and laboratory analysis
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performed by the off-site contractor, certain other tests (e.g. automatic initiation, heater power verification, routine
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heater runs, etc.) are performed by the licensee. The results of these tests were recorded on the following forms:
I Procedure OP 1104.33 "H2 Purge System Test-Lead System"
Procedure OP 1104.34 " Control Room Ventilation Test" Procedure OP 1104.43 " Penetration Room Ventilation Test" Procedure OP 1304.8 " Safeguards System Test" No discrepancias were noted.
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7.
Reactor Coolant Technical Specifications 3.1, 4.1, 3.1, 5.1, 3.10 and Table 4.1-3 contain the sampling and analyses requirements for reactor coolant.
Analyses results are recorded on the form titled: Form Chem.
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002-02, " Hot Lab Technical Specification Surveillance Report."
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Selected results were reviewed. No discrepancies were noted.
8.
S_olid kadioactive Waste The licensee's solid waste program was reviewed to determine compliance with DOT regulations, 10 CFR 71, and Technical
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Specification 6.11.lg.
Shipping procedures and records are i
contained in procedure 1602.13 titled: " Shipment of Radioactive Materials." The licensee's records indicated ' hat 13 shipments b
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were made in 1975. As of July 21, twelve (12) shipments have been made in 1976. No discrepancies were noted.
F.
Analytical Measurements 1.
, Quality control Procedures The licensee's program related to radiochemistry quality control activities were aramined. The following procedures contain counting equipment operation and calibration instructions:
Chem. 1604.1 " Gross Alpha Measurements" Chem. 1604.04 " Liquid Scintillation Counting For Gross Beta and Tritium Measurements" Chem. 1604.19 " Daily Counting Room Instrumentation Setup" Chem. 1604.20 "ND-4420 Gamma Spectroscopy Procedure" In reviewing the licensee's inventory of calibration sources, it was noted that their alpha and tritium standards were not certified as traceable to NBS. A licensee representative stated that they have heth an 241 m and a tr1 tium NBS solution A
in stock. According to c. licensee representative, new cali-bration sources will be made from their NBS solutions. It was noted that in certain calibration procedures, the procedures did not include calibration frequencies, acceptance limits, or detailed techniques. A licensee representative stated that present procedures will be reviewed and updated as necessary.
2.
CA-QC Audits
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Audits of radiochemistry &ctivities were reviewed. The licensee's
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records indicated that radiochemistry audits were performed by the Safety Review Committee on July 31, 1975 and January 28 and 29, 1976. The audit reports did not reveal any serious problems.
3.
Confirmatory Measurements The results of tha latest confirmatory measurements were reported in IE Inspection Report No. 76-G4.
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G.
Licensee Event Reports 1.
Reportable Occurrence No. 50-313/76-11 On June 12, 1976, approximately 9,500 gallons of water from the Borated Water Storage Tank (BWST) was inadvertently released.
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The release contained 262 millicuries. The events and subsequent action surrounding the release are contained in the licensee's Reportable Occurrence No. 50-313/76-11,
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dated June 24, 1976. Sample results indicated that concen-trations at the restricted area boundar* did not exceed 10 CFR 20 limits. This item remains open pending completion of the proposed corrective action.
89-90 r Sample 2.
Lost S
The licensee reported on April 9, 1976, that the quarterly
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liquid waste composite sample was lost during a chemical
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analysis procedure. The events concerning this matter were documented in the Abnormal Plant Condicion, dated April 8, 1976.
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