IR 05000313/1975003
| ML19317H094 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/13/1975 |
| From: | Brown G, Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19317H090 | List: |
| References | |
| 50-313-75-03, 50-313-75-3, NUDOCS 8004140577 | |
| Download: ML19317H094 (14) | |
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s U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
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REGION IV
IE Inspection Report No. 50-313/75-03 Docket No.
50-313 Licensee: Arkansas Power and Light Company (AP&L)
License No. DPR No. 51 Sixth and Pine Streets Pine Bluff, Arkansas 71601 Category B2 Facility: Arkansas Nuclear One, Unit (ANO-1)
Location: Russellville, Arkansas Type of License: PWR Power Reactor 2568 Mwe Type of Inspection: Routine, Unannounced, Radioactive Waste Systems Dates of Inspection: April 23-25, 1975 Dates of Previous Radiological Inspection: January 8-9, 1975.
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75 Inspector:
BYMurray',RadiationSpep'alist
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Accompanying Personnel: None lh
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J Reviewed By:
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SOLL 1/ lh j\\'7 D Clen D. Brown, Chief, Radiological and
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Environmental Protection Branch
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mU-2-SUMMARY OF FINDINGS i
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I.
Enforcement Action None II.
Licensee Action on Previously Identified Enforcement Matters Control of Portable Radiation Survey Instruments 1/
Approval of the procedure which lists calibration frequencies has not been completed. This item remains open.
(See DETAlLS, para-graph 3)
III.
New Unresolved Items 75/03-1 High Cross Liquid Activities The gross liquid activities reported in the fourth quarter 1974 Semi-Annual Report exceeded Technical Specification limits.
This item is considered unresolved.
(See DETAILS, naragraph 7)
V)
75/03-1 Gaseous Sample, Line Losses Tests have not been conducted to establish the per cent of sample loss occurring in the gaseous sample delivery lines. This item
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is considered unresolved.
(See DETAILS, paragraph 13)
IV.
Status of Previously Identified Unresolved Items 2_/
75/01-1 Effluent Monitoring System Test The test of the liquid and gaseous radioactive waste effluent monitoring system failed to meet the test acceptance criteria for the correlation between monitor results and laboratory analysis results. The item remains unresolved.
(See DETAILS, Paragraph 4)
74/14-3 Radiation Levels Inside Reactor Containment Corrective action for the radiation level in the reactor contain-ment which exceed the design bases has not been determined. Tlis item remains open.
(See DETAILS, paragraph 5)
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RO Inspection Report 50-313/74-14, I.A.1 2/
RO Inspection Report. 50-313/75-1 v)
(continued)
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V.
Unusual Occur ~ences No unusual occurrences involving radiological matters were noted.
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VI.
Other Significant Findings None VII.
Management Interview At the conclusion of the inspection on April 25, 1975, a manage-ment interview was conducted to discuss the inspection findings.
The following licensee personnel were in attendance:
Arkansas Power and Light Company (AP&L)
Mr. J. W. Anderson, Jr., Plant Superintendent Mr. G. H. Miller, Assistant Plant Superintendent Mr. T. C. Baker, Chemistry and Environmental Supervisor Mr. R. G. Carrol, Hea!.th Physics Supervisor Mr. J. L. Orlicek, QC Engineer The items discussed and the licensee's position with respect to O
these items, as applicable, follow:
Scope of Inspection The inspector outlined the areas covered during the inspection.
Control of Portable Radiation Survey Instruments A licensee representative stated that a procedure would be ready for submission for approval by May 15, 1975.
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Effluent Monitoring System Test A licensee representative stated that further tests are planned in order to reach agreement between laboratory results and process monitor readings. No dates for conductitig these tests have been established.
Radiation Levels Inside Reactor Containment A licensee representative stated that a method of correcting the high radiation problem is still under review. No completion date has been established.
(continued)
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' Gaseous Sample Line Losses l
A licensee representative stated that tests would be performed l
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f DETAILS
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1.
AP&L Personnel Contacted Mr. J. W. Anderson, Jr., Plant Superintendent Mr. G. H. Miller, Assistant Plant Superintendent Mr. C. A. Halbert, Technical Support Engineer Mr. T. C. Baker, Chemistry and Environmental Supervisor Mr. R. G. Carrol, Health Physics Supervisor Mr. J. L. Orlick, QC Engineer 2.
Chemistry and Health Physics Organization
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The following table, shows the present Chemistry and Health Physics organization.
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Plant Superintendent
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J. W. Anderson, Jr.
Assistant Plant Superinterdent G. H. Miller Plant Technical Support Engineer C. A. Halbert l
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Cold Chemistry Radiochemistry Health Physics
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T. C. Baker Supervisor R. G. Carroll l
Supervisor Position Vacant Supervisor T. E. Tubb Radiochemists Health Physicists Senior Chemist J. L. Bates M. M. Nichols D. H. Nickols G. J. Birdwhistell G. L. Fiser M. E. Frala Apprentice Chemists A. L. Smith
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R. D. Gillespie Apprentice Health K. W. Cook Physicists P. L. Young K. A. Bell R. E. Fishencord R. E. Green A. E. Murray R. L. Owings (continued)
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3.
Calibration of Portable Survey Instruments The background regarding this item is contained in RO Inspection Report Nos. 50-313/74-14 and 50-313/75-1. A licensee representa-tive stated that formal approval of the portable survey instrument procedure which will contain calibration frequencies is expected by May 15, 1975.
4.
Effluent Monitors Response Tests
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This item was discussed in RO Report No. 50-313/75-1 and involved the correlation of laboratory sample analysis versus stack effluent monitors results. Station Procedure No. TP 362.01 requires the verification of laboratory radiochemistry analyses against liquid and gaseous effluent monitors. The acceptance criterion for TP 362.01 was that the laboratory analysis and the monitor results should agree within + 20%. It was noted that of the 20 tests conducted, 19 were unsatisfactory in that laboratory analysis and effluent monitor results were not within + 20%.
A licensee representative stated that the reason for the poor agreement was due to low activity of the samples analyzed. According to a licensee representative, the sample activity was less than the minimum detectable activity (MDA) of the monitors. As a result, s
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it was not possible to achieve the + 20% agreement as required in k _,/
TP 362.01.
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s 5.
Radiation Levels Inside Reactor Containment This item was discussed in RO Report Nos. 50-313/74-14 and 50-313/75-1 and involved the radiation levels inside containment at 40% power exceeding the design basis values for 100% power.
A licensee representative stated that various methods of shielding the high radiation levels are under review by the architect-engineer
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and AP&L.
6.
Radioactive Effluent Release Rates and Limits Section 2.4 of the Environmental Technical Specifications (ETS),
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Appendix B, contains the liquid and gaseous limits.
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Liquid l
ETS 2.4.1.2 states that the release rate of radioactive liquid effluents, excluding tritium and dissolved gases, shall not exceed 10 curies during any calendar quarter.
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-8-v A review of the licensee's individual laboratory data sheets of specific radionuclide analyses indicated that the maximum activity released in any one quarter was less than 2.5 curies.
However, it was noted that the gross beta-gamma activity for the fourth quarter, 1974 exceeded Technical Specification limits.
(See paragraph 7 below).
b.
Gaseous The gaseous release limits appear in ETS 2.4.2.1, ETS 2.4.2.3.a, ETS 2.4.2.3.b, ETS 2.4.2.4.a. and ETS 2.4.2.4.b.
Selective records for the period August, 1974 through April 22, 1975 were examined. No discrepancies were noted.
7.
Radioactive Effluent Reports The licensee radioactive effluent releases contained in the third and fourth quarter, 1974 Semi-Annual Report were examined. It was noted that on page 202, the total gross liquid beta-gamma activity, excluding tritium and dissolved noble gases was reported as 12.05 curies for the period October through December, 1974.
These releases appear to exceed ETS 2.4.1.2 and ETS 2.4.1.3 which state:
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ETS 2.4.1.2
"If the release rate of radioactive materials in liquideffluents,whenaveragedovpracalendarquarter, exceeds 2.5 curies, the Licensee shall: 1 a.
Make an investigation to identify the causes for such release rates; b.
Define and initiate a program of action to reduce such release rates to the design levels; and,
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Notify the Director, Directorate of Licensing within 30 days, identifying the cause and describing the proposed program of action to reduce such release rates."
2.4.1.3
"The release rate of radioactive liquid effluents, excluding tritium and dissolved gases, shall not exceed 10 Curies during any calendar quarter."
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In reviewing the aforementioned releases, a licensee representative stated that the reported gross beta-gamma activity was a combined total of beta activity plus gamma activity and not based on analyses of specific radionuclides. As a result, the reported totals did not reflect the actual activities released.
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jf The letter dated 7/10/74 signed by D. R. Muller, L:EP, s_,
established that ETS 2.4.1.2 excludes tritium and dissolved gases.
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-9-According to a licensee representative, it is their intention to limit releases based on the summation of specific radionuclide analyses.
(Item I.7 of the Semi-Annual Report.)
The inspector reviewed the licensee liquid releases based on specific radionuclide analyses. These analyses indicated that releases were approximately 10% of the allowable limit.
A licensee representative stated that a review of their radio-chemistry and counting procedures will be performed in order to resolve the difference between gross and specific nuclide results.
8.
Effluent Release Procedures The licensee procedures relative to control of liquid and gaseous effluents were examined.
a.
Liquid
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The licensee'e procedures require that prior to each liquid release, the form titled: Liquid Radioactive Waste Release Permit be processed. The form contains information regarding:
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Tank identification Shift supervisor approval ss-Radiochemistry analysis Technical Specification Requirements Calibration of liquid waste monitors Valve line up Release rate Total activity discharged Total volume discharged.
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It was noted that during 1974, 398 liquid waste releases were made. For the period January 1 through April 22, 1975, 261 releases have occurred.
Several release permits for the period August 1, 1974 through April 22, 1975 were examined. No discrepancies were noted.
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b.' Caseous Decay Tanks Gaseous release data are recorded on the form titled: Caseous Release Permit. The form provides information regarding:
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Decay tank identification
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Pressure Decay time Shif t supervisor's approval Radiochemistry analysis Compliance with Tech. Specs.
Operation status of gas monitors Release rate During 1974, 56 gaseous releases were made. For the period January through April 22, 1975, 10 gaseous releases occurred. Selected release permits were examined. No discrepancies were noted.
It was noted that decay hold-up times were less than 45 days. However, the licensee's records indicated that the requirements of ETS 2.4.2.6 were satisfied.
c.
Reactor Building Purge ETS 2.4.2.7 lists requirement for purging the reactor building.
The licensee's records indicated that five purges occurred in 1974 and three in 1975 for the period ending April 22.
Purge release procedures require that form titled: Reactor Building
's Purge - Caseous Waste Release Permit be processed prior to each purge. This form indicated information regarding:
Flow rate Radiochemistry analyses Tech. Spec. requireme cs Filter system status Monitor system status Alarm settings Activity discharged
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Per cent of MPC e
Supervisor approval Purge release records for the period June 1974 through April 22, 1975 were examined. No discrepancies were noted.
9.
Effluent Control Instrumentation
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a.
Liquid
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Instrument control procedures to demonstrate compliance with ETS 2.4.1.4.b,ETS 2.4.1.4.c, ETS 2.4.2.4 (Monitoring Require-ments) and ETS 2.4.2.5 (Monitoring Requirements) were examined.
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'ETS 2.4.1.4.b - Waste Discharge Isolation Tests to verify operation of the liquid waste discharge valve j
associated with RE 4642 are performed prior to each liquid l
waste release. Results of tests are recorded on the Liquid l
Waste Release Fermit form.
ETS 2.4.1.4.c - Monitoring and Recording Releases
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Liquid releases are monitored by RE 4642 and RE 3618. Release data are recorded on a strip chart recorded located in the
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control room. The inspector visited the control room and it ap-peared that the system was operating properly.
ETS 2.4.1.4 - Calibration The check, test and calibration requirements were reviewed.
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Examination of selected records indicated that the requirements i
of ETS 2.4.1.4 (Monitoring Requirements) were satisfied. Cali-bration, check and test procedures appear in Procedure No.
1304.27 titled: Process Radiation Monitoring Systems.
b.
Gaseous Decay Tanks and Vent Systems The licensee's procedures to demonstrate compliance with ETS 2.4.2.5.a, ETS 2.4.2.5.b, ETS 2.4.2.7.a, ETS 2.4.2.8 and ETS 2.4.2.4 (Monitoring Requirements) were examined.
ETS 2.4.2.5.a and ETS 2.4.2.8 - Discharge Monitoring
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Gross teta-gamma activity is monitored, prior to discharge by RE 4830 and RE 7400. Results from RE 7400 are recorded on a strip chcrt recorder located in the control room.
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particulate grab samples are also collected from gaseous effluent pathways. The inspector visited the sampling and recording area and determined that the systems appeared to be operating properly.
ETS 2.4.2.5.b - Waste Discharge Isolation The automatic isolation values associated with RE 4830 are tested l
prior to each decay tank release. Test results are recorded on
the Caseous Release Permit form.
l ETS 2.4.2.2 - Instrument Calibration
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l The test, check, and calibration requirements.were reviewed.
The licensee's records indicated ETS 2.4.2.2 (monitoring
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procedures are contained in Procedure No. 1304.27 titled:
Process Radiation Monitoring Systems.
10.
Effluent Sampling and Analysis Requirements Table 2-2 of the ETS lists the liquid and gaseous waste sampling and analysis requirements.
a.
Liquid Item 1 of Table 2-2 lists the <iampling frequencies and ana-lyses requirements for liquid effluents. Selected records for
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t the period June 1974 through April 22, 1974 were reviewed.
Composite and monthly analyses are recorded on form Chem. 032-01 titled: Liquid Release Proportional Composites and Monthly Analyses. No discrepancies with ETS requirements were noted.
b.
Waste Gas Decay Tank Item 2 of Table 2-2 contains the sampling requirements for waste gas decay tank releases. Decay tank analyses are recorded on each release permit.
Selected records for the period August 1974 through March 1975 were examined. No discrepancies were noted.
c.
Vent Sampling Item 3 and 4 of Table 2-2 list the vent sampling requirements.
Results were recorded on the following forms:
Attachment A - Chem 019-00 - Weekly Analysis Report of Unit One Vent Attachmert B - Chem 020-00 - Monthly Analysis Report of Unit
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One Vent Attachment C - Quarterly Analysis Report of Unit One Vent.
Selected sampling and analyses records for the period June 1974 through August 1975 were examined. No discrepancies were noted.
d.
Reactor Building Purge Item 5 of Table 2-2 lists sampling frequencies and analyses requirements for reactor building purges. Rasults are recorded on Attachment A of each purge release permit. Selective records for the period June 1974 through April 1975 were examined. No discrepancies were noted.
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12.
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The reactor coolant sampling and analysis requirements are listed in Appendix A Technical Specifications (TS). Reactor coolant require-ments appear in TS 3.1.4.1, TS 3.1.5.1, TS 3.10 and Table 4.1-3, Items 1 and 5.
The requirements of Table 4.1-3, Items 1.a,1.b,1.c, 1.d, 1.f and 1.g were recorded on licensee form titled: Daily Radiation Chemistry Laboratory Results. Table 4.1-3, Item 1.e and TS 3.1.5.1 requirements were recorded on_ licensee form titled:
Daily Hot Laboratory Water Report. The E determinations of TS 3.1.4.1 and Table 4.1-3, Item h requirements were maintained in a separate file.
Selected reactor coolant sampling and analyses results were examined.
No discrepancies were noted.
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13.
Gaseous Sample Line Losses A licensee representative stated that tests have not been performed to determine the amount of sample deposited or plated-out in sample lines between the sampling point and the detector or sampler collector. The sample delivery lines from the three different sampling points travel approximately 80 feet between the sampling point and the detector or collector.
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HEPA and Charcoal Filters i
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The requirement of Table 4.1-2, Item 7, TS 4.4.3, TS 4.11 and TS 4.12
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were reviewed. The quarterly tests of the control-roem system were recorded on form titled: OP 1104.34 - Control Room Emergency Venti-
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lation Quarterly Tests, Supplement I.
No discrepancies were noted.
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15.
QA-QC Audits e
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l The licensee activities relative to QC audits of Radioactive Waste-
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Systems were reviewed. The licensee's records indicated that
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audits of Health Physics and Chemistry functions were performed on
September 10-12, 1974 and January 29, 1975. These audits covered:
i Compliance with 10 CFR 20 Effluent Releases Analyses of Releases
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Calibrations of Monitors l
Releases Procedures
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A licensee representative stated that a similar audit is planned l
for the second quarter of 1975.
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AO's and Unusual Event Reports i
l AO's and unusual event reports for the period August 1974 through j
February 1975 were reviewed. No items related to radioactive j
waste management were noted.
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