IR 05000313/1975005
| ML19317H087 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/25/1975 |
| From: | Brown G, Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19317H084 | List: |
| References | |
| 50-313-75-05, 50-313-75-5, NUDOCS 8004140570 | |
| Download: ML19317H087 (15) | |
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U. S. NUCLEAR REGULATORY COMMISSION G
OFFICE OF INSPECTION AND ENFORCEMENT
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REGION IV
IE Inspection Report No. 50-313/75-05 Docket No. 50-313 Licensee: Arkansas Power and Light Co.
(AP&L)
License No. DPR No. 51 Sixth and Pine Streets Pine Bluff, Arkansas 71601 Category B2 Facility: Arkansas Nuclear One, Unit 1 (ANO-1)
Location: Russellville, Arkansas Type of Licensee: PWR Power Reactor, 2568 Mt Type of Inspection: Routine, Radiochemistry Analytical Measurements and Radiation Protection (partial completion)
Date of Inspection: June 11-13, 1975 Date of Previous Radiological and O
Environmental Protection Inspection: April 23-25, 1975 Inspector:
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d Blaine Murray, Radiatiod ppecialist
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Accompanying Personnel: None
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Reviewed By:
'Gleh D'. Brown', Chief
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/ Dark Radiological and Environmental Protection Branch
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-g-2-I SQTdARY OF FINDINGS I.
Enforcement Action
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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
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not been completed. This item recafas open. The details surrounding this item appeared in IE Inspection Report No. 50-313/75-03, DETAILS, paragraph 3.
III.
New Unresolved Items 75/05-1 Radiation Levels at Restricted Area Fence i
Present radiation survey procedures do not include measurements made at the restricted area fence.
(See DETAILS, paragraph 7.a)
N 75/05-2 Air Sampler Flow Rates l
Flow rates for ANO air samplers have not been determined.
(See l
DETAILS, paragraph 10.b.2)
i 75/05-3 Whole Body Counter Calibration Procedures Calibration procedures for the whole body counting system have not been written.
(See DETAILS, paragraph 6.b)
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75/05-4 TLD Calibration and Ouality Control Procedures Calibration and Quality Control procedures for the TLD read-out
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system have not been written.
(See DETAILS, paragraph 5.b)
75/05-5 Laboratory Counting Equipment Calibration Procedures l
Calibration procedures have not been written for the laboratory I
counting equipment.
(See DETAILS, paragraph 10.b.1)
75/05-6 Training Radiological and respirator trainin'g has not been completed.
(See DETAILS, paragraph 8)
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IE Inspection Report 50-313/75-03
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J-3-IV.
Status of Previously Identified Unresolved Items 2/
75/03-1 High Cross Liquid Activities Corrections have been made for the gross liquid activities reported in the fourth quarter 1974 Semi-Annual Report. This iten is considered closed.
(See DETAILS, paragraph 14)
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75/03-1 Caseous Sample Losses in Delivery Lines Tests have not been conducted to establish the percent of sample loss occurring in the gaseous sample delivery lines.
The status of this item is unchanged from the previous inspection report.
(See IE Inspection Report No. 50-313/75-03, DETAILS, paragraph 7)
75/01-1 Effluent Monitoring System Tests The test of the liquid and gaseous radioactive vaste effluent monitoring system failed to meet the test acceptance criteria for the correlation between monitor results and laboratory analysis results. The status of this item is unchanged from the previous inspection report.
(See IE Inspection Report No.
50-313/75-03, DETAILS, paragraph 4)
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74/14-3 Radiat' ion Levels Inside Reactor Containment Corrective action for the radiation levels in the reactor contain-ment which exceed the design bases has not been completed. The status of this item is unchanged from the previous inspection report.
(See IE Inspection Report No. 50-313/75-03, DETAILS, l
paragraph 5)
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V.
Unusual Occurrences None t
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Other Significant Findings None l
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Management Interview i
At the conclusion of the inspection on June 13, 1975 a management
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interview was held to discuss the inspection findings. The following AP&L personnel were in attendance.
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IE Inspection Report No. 50-313/75-03
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J. W. Anderson, Plant Superintendent C. H. Halbert, Technical Support Engineer R. G. Carrol, Health Physics Supervisor D. C. Trimble, Training Coordinator T. L. Green, Assistant Iraining Coordinator J. L. Orlicek, QC Engineer The items discussed and the licensee's position with respect to
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these items, as applicable, follow.
1.
Scope of Inspection The inspector outlined the areas covered during the inspection.
2.
Verification Tests The inspector reviewed the purpose and reporting procedures associated with liquid, gaseous, and filter verification tests.
(See DETAILS, paragraph 4)
3.
Unresolved Items Licensee representatives reported that the status of unresolved items 75/03-1, 75/01-1, and 74/14-3 were unchanged from the previous inspection. Unresolved item 75/02 is considered
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closed.
4.
Radiation Levels at the Restricted Area Fence A licensee representative stated that routine survey procedures would be changed to include radiation level measurements made at various points along the restricted area fence.
(See DETAILS, paragraph 7.a)
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Air Sampler Flow Rates A licensee representative stated that tests would be conducted to establish flow rates for ANO air samplers.
(See DETAILS,
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paragraph 10.b.(2))
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6.
Whole Body Counter Calibration Procedures A licensee representative stated that a procedure would be written to cover calibration of the whole body counting system.
(See DETAILS, paragraph 6.b)
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TLD Calibration and Quality Control Procedures A licensee representative stated that a procedure would be written to cover calibraitor. and quality control of the TLD read-out system.
(See DETAILS, paragraph 5.b)
8.
Laboratory Counting E0uipment Calibration Procedures
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A licensee representative stated that a procedure would be written to cover calibration of Health Physics laboratory counting equipment.
(See DETAILS, paragraph 10.b. (1))
9.
Training A licensee representative stated that radiological and respirator training should be completed by the end of July, i
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1975.
(See DETAILS, paragraph 8)
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-6-g(oJ DETAILS 1.
Persons Contacted a.
Arkansas Power and Light Company (AP&L)
Mr. J. W. Anderson, Jr., Plant Superintendent Mr. C. H. Halbert, Technical Support Engineer Mr. R. G. Carrol, Health Physics Supervisor Mr. T. C. Baker, Chemistry and Environmental Supervisor Mr. M. M. Nichols, Health Physicist Mr. G. J. Birdwhistell, Health Physicist Mr. J. L. Bates, Radioche=isc Mr. D. C. Trimble, Training Coordinator Mr. T. L. Green, Assistant Training Coordinator b.
Arkansas Health Department Mr. G. W. Rowlett, Chemist 2.
Chemistry and Health Physics Organization No changes have occurred in the Chenistry and Health Physics staff since the previous inspection.
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3.
Scope of Insoection The purpose of this inspection was to collect effluent samples for initial verification test co=parisons and to examine the Radiation Protection Program.
4.
Sample Collection - Verification Tests
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The following radioactive waste samples were collected.
l Liquid - from liquid waste hold-up tank Gaseous - from gas decay tank
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, Stack particulate filter j
Stack charcoal cartridge
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IE Inspection Report No. 50-313/75-03
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The types of analyses to be performed and reporting procedures were discussed with the licensee.
5.
Personnel Dosimetry - External Radiation a.
Records The licensee maintains their own in-house beta-gamma TLD
system. Neutron film badges are obtained from an independent vendor. Both TLD beta-gacca and neutron film badges are exchanged at a monthly frequency. A TLD badge is issued to each individual entering a control area. Neutron films are only issued to individuals entering certain areas (e.g.
containment) where neutron radiation fields have been identified through radiation surveys. Personnel monitoring procedures appear in the following two documents:
Procedure 1602.20, Radiation Excosure Control Procedure 1602.21, Personnel Dosi=eter Control l
Dose records for the period January 1, 1974 through April 30, 1975 were examined. The maximum dose noted for any individual in 1974 was less chan 700 = Rem.
The maximum
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1, 1975 through April 30, 1975 was 450 mrem.
Selective personnel records were examined for compliance with NRC Form 4 and 5 requirements. No discrepancies were noted.
b.
Calibration - TLD System
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i The calibration and quality control programs associated with
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the licensee's in-house TLD system were reviewed. The licensee l
maintains a contract with an independent reference laboratory
that provides TLD cross check programs.
The cross check program i
consists of the licensee submitting several blank TLD chips
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on a monthly basis to the reference laboratory who doses the l
TLDs with a known amount of radiation.
The TLDs are then returned to the licensee for analysis. The, licensee also.
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i has conducted their own in-house. comparisons where TLDs have
been exposed to a known gamma field. The read-out results
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are then compared against the exposure established with a condenser R-meter.
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d weekly frequency.
Survey results are recorded on the form
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titled HP 2.1.
In reviewing survey results the following two items were noted:
(1) Routine surveys do not include obtaining ceasurements at the restricted area fence.
(2) Reactor power levels were not noted on Form HP 2.1.
The licensee's records indicated that surveys were conducted at 100 percent power levels in December 1974 as part of the startup and test procedures.
Survey results indicated that in December 1974, radiation levels at the fence were not above general background readings. However, a licensee representative stated that present survey procedures would be modified so as to include radiation measurements taken at various points along the restricted area fence. Particular attention will be given to increased radiation levels associated in waste accumulation or radioactive storage areas. In addition, the operating power level at the time inspections are performed will be recorded on Form HP 2.1.
Except for certain areas in containment that have been mentioned in IE Inspection Report 50-313/75-03, DETAILS, paragraph 5, no unusual high radiation levels were recorded.
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Contamination Routine contamination surveys are conducted in conjunction with radiation surveys. Contamination results are also recorded on Form HP 2.1.
Selected contamination survey results for che period January 1, 1974 through May 31, 1975 were examined.
It was noted that areas identified as being contaminationed and requiring decontamination were usually cleaned within an accept-
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able time period.
c.
Airborne Routine airborne surveys are performed within the plant at a weekly frequency. Depending on the area surveyed, samples are analyzed for one or a combination of particulate, Iodine, and noble gases concentrations.
Survey results indicated that airborne concentrations outside of containment were usually less that MPC's.
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Training a.
Radiological The licensee's radiological training consists of an initial 4 to 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Health Physics Indoctrination course followed by a more detailed 20 hour2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> Radiation Protection course. All plant personnel, plus selected visitors and construction personnel, are required to receive the Health Physics Indoctrination course.
Plant personnel whose normal job assignments (e.g. operation, instruments, maintenance) include working in control areas are required to take the 20 hour2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> Radiation Protection course.
Training records indicated that epproximately 15 persons have not received the required Radiation Protection course. A licensee representative stated that the training schedule is such that all designated individuals should receive the required Radiation Protection course by mid-July, 1975.
The plant's general initial and retraining policies are outlined in Memo No. JWA 1168, dated June 4, 1975.
The Health Physics Indoctrination and Radiation Prctection
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course outlines were reviewed. Both courses cover essentially the same material; the difference being that the Radiation i
e Protection course is more detailed. The courses cover such
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items as:
theory, exposure limits, biological effects, radia-l j
tion measurements, contamination control, and a general description
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of the ANO Radiation Protection Program.
Written examinations are given after completion of the Radiation
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i Protection course. A licensee representative stated that
individuals who do not receive a passing score (70%) are required
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to participate in additional training until such time they
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have demonstrated an understanding of the course material.
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Respirator
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Respirator training is provided to those individuals whose l
normal job duties require frequent access into control areas.
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The Training Coordinator is responsible for' identifying those persons that are to receive respirator training. A review i
of plant records indicated that approximately 15 persons are i
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scheduled for respirator training. A respiratory training
course is given about once each quarter. A licensee representh-tive stated that all designated personnel sould receive the required training by late July, 1975.
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-11-Procedure No. 1602.03 titled: ANO Respiratory Protection Program contains information related to respirator selection fitting, limitations, maintenance and cleaning. A licensee representative stated that the aforementioned procedure is used as the respiratory training course outline. The course consists of a four hour lecture followed by a two hour fitting and testing session.
c.
Retruining
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A licensee representative stated that the training records of each plant employee were reviewed in May, 1975 in order to identify areas of training deficiencies. A licensee represente-tive stated that the review uncovered incompleted training records for several employees. As a result, a number of the
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30 individuals scheduled for Radiation and Respirator Training were hired before July 1, 1974 and have received partial training. However, their records were not complete so they were included along with the new employees for training to be completed by late July, 1975.
A licensee representative stated that a radiological retraining program is being developed.
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Respirator Program The licensee's respirator program is outlined in Procedure No.
1602.03 titled: ANO Respiratory Protection Pro 2 ram.
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table lists the approxi= ate respirator inventory.
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]]gji Quantity SCBA W 13 i
Full Face-v 30
Airline
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I The respiratory program was examined to determine compliance with t
No discrepancies were noted.
10.
Instrumentation and Sampling Equipment
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Inventory (1) Portable Survey Meters The following table lists the approximate survey meter inventory.
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-12-Detector Tyge Model Range Quantity GM E-530 0-250,000 cpm
GH Teletector 0-1,000 R/hr
Ion Chamber PIC 6A 0-1,000 R/hr
Ion Chamber 440 0-300 =R/hr
Ion Chamber R0-1 0-500 R/hr
BF3 PNC-4 0-500,000 cpm
3 PNR-4 0-5 Rem /hr
BF Gas proportional PAC 4G 0-500,000 cpm
Gas proportional AC-21 0-500,000 cpm
(2) Friskers Detector llodel Quantity GM HP 190
GM HP 210
GM HP 200
GM HP 250
GM HP 177
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(3) Portal Monitors Detector Model Quantity GM Eberline
'4 (4) Hand and Foot Counter Detector Model Quantity
GM Eberline
(5) Constant Air Monitors (Portable)
Detector Model Quantity
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Beta Scintillation KMC 3-(6) Air Samplers Flow Model Quantity
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Ri volume Staplex
Lo volume ANO
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V (7) Laboratory Counting Eauipment - Health Physics Group Detector Model Quantity Gas flow proportional Nuclear Chicago Model 1152
NaI 3"X3" Crystal Nuclear Data Multichannel Analyzer
The above equipment is used to analyze contamination smears and air samples for ITC values.
b.
Calibration
(1) Laboratory Counting Eauipment Procedure No. 1602.32 Rev. I cicled: Operating Procedure for Nuclear Chicago Model 8703 Scaler and 1152 Samole Changer outlined general operating procedures associated with the Nuclear Chicago system. These procedures include recording daily background, efficiency, and high voltage setting on Form HP 8.1.
However, no for=al written cali-bration procedurec were available for Nuclear Chicago I
system. In addition, no operating or calibration procedures were available for the Nuclear Data NaI system.
According to a licensee representative, calibration and V
operating procedures will be developed. The Nuclear Chicago l
procedures will be expanded to include routine high voltage
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plateau and Chi square tests. The Nuclear Data procedures
will include such items as efficiency, resolution, channel
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shifts and background values.
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(2) Air Sampler
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the ANO air samplers.
Survey records indicated that most i
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performed with the ANO type sampler. A licensee repre-sentative stated that the ANO samplers were designed and
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constructed in-house. The samplers were designed for a 2-3 CFM flow rate; however, the actual flow rates were never established. According to a licensee representative arrangements will be made to determine the flow races.
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Calibration Sources A licensee representative stated that none of the sources presently used to calibrate the whole bcdy counters, CAMS, Nuclear Chicago and Nuclear Data laboratory counters are (continued)
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traceable to NBS.
It was noted that an order for NBS traceable standards had been placed in May, 1975 and delivery set for July, 1975. A licensee representative stated that once the new standards are received, the above mentioned instrumentation counting efficiencies will be based on the new standards.
11.
Work Authorization Records The Radiation Work Per. nit (RWP) and Special Work Permit (SWP)
program is outlined in Procedure No. 1602.04. A RWP is usually written to cover routine maintenance activity in areas having radiation levels less than one Rem /hr. A RWP can cover a period up to one year. Special Work Permits are issued for a specific job and must be renewed if the job lasts longer than two weeks.
Form HP 4.1 is used for both RWPs and SWPs.
Updating of radiological plant conditions (daily or weekly) is accomplished by means of Form HP 4.5.
Copies of HP 4.5 are posted near the change room area.
Selected RWPs and SWPs issued between January 1, 1974 and May 31, 1975 were examined. No discrepancies were noted.
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12.
Posting of Notice to Workers G
The requirements of 10 CFR 19.11 were posted on the bulletin board located in the Administrative Office area and in the control access change area.
13.
Confimatory Measurements Confirmatory measurements were made by the inspector of radiation i
levels recorded on the licensee's routine survey forms (HP 2.1)
and posting of specific radiation level within the plant. No
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discrepancies were noted.
14.
High Reported Gross Liquid Activ_1 ties
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This item was discussed in IE Inspection Report No. 50-313/75-03, DETAILS, paragraph 7 and involved high fourth quarter gross beta activity as reported in the third and fourth quarter, 1974 Semi-Annual Report. A licensee representative stated that a review
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of laboratory analyses revealed an error had been discovered in transferring numbers. As a result, the actual released activity for October 1974 should be 230 millicuries instead of 5.9 curies.
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-15-The details involving the error and subsequent correction of the Semi-Annual Report is contained in the May 2, 1975 Memo l
No. JWA 1054 to W. Cavanaugh signed by J. W. Anderson.
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