IR 05000155/1976015
| ML20002D535 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 07/20/1976 |
| From: | Finn J, Fisher W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20002D533 | List: |
| References | |
| 50-155-76-15, NUDOCS 8101210313 | |
| Download: ML20002D535 (7) | |
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i U. S. !;UCLEAR Erf;ULATDI:Y CO?S!ISSIO::
OFFICE OF I!;SPECT10:; A!;D E!; FORCE!!J!?T
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REGIO!! III
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Report of Radiation Protection Inspection IE Inspection Report L. 050-155/76-15
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Licensee:
Consurers Pc.cer Cc pany 212 k'est Michigan Avenue Jackson, Michigan 49201 Eig Rcch Point Suelcar Plant License No. DPE-6 Charlevoix, Michigan Category: C Type of Licensee:
EL'R 240 K,lt Type cf Inspection:
Routine, Unannounced Dates of Inspection:
June 14 - 18, 1976 D }r i
J. A. Finn llJ.,., e t,m
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Principal Inspector:
(Date)
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v Accorpanying Inspectors: None Other Accenpanying Personnel: None
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L. Fisher, Chic./
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Fuel Facility Frojects and (Date)
Radiation Support Section
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SUtBIARY OF FINDINGS
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Inspection Summary _
Inspection on June 14-18, (76-15): Radiation protection inspection included review of personal monitoring procedures and records, air sampling, and in' vivo counts.
Enforcement Items No items of noncompliance with NRC requirements were identified during this inspection.
Licensee Action on Previously Identified Enforcement Matters Not applicable.
Other Sinnificant Findings A.
Systems and Components None.
B.
Facility Items (Plans and Procedures)
None.
C.
Managerial Items The licensee had not evaluated in vivo count data for compliance with 10 CFR 20.103.
D.
Noncompliance Identified and Corrected by Licensee
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None,
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E.
Deviations Nonc.
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F.
Status of Previously Report Unresolved Items Nonc reviewed during this inspection.
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Ibnagement Interview
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The following individuals were present during the management intervice at the conclusion of the inspection:
C. J. Hartman, Plant Superintendent C. E. Axtell, Plant !!calth Physicist The following matters were discussed:
A.
The scope of the inspection.
B.
The problem of recurrent freezing of the stack effluent sampling line was discussed. An engineer has been assigned the problem and corrective action is anticipated before the winter of 1976-1977.
Off-gas data has been logged for the periods stack sampling was out of service. These data will be used, as appropriate,- to -correct stack release data.
C.
The inspector noted that the lic..neee had estinated the internal dose to an individual based on t ie increase in cobalt-60 depositiens ceasured from the in vivo counts made on May 6 and May 13, 1976. However, no estinate.had been cade of air concen-trations to which the individual had been exposed. The licensee stated that air concentrations = culd be calculated and that the individual would be given aJditional in vivo counts.
The licensee further stated thrit future in vivo ccunt data would be evaluated for compliance with the airbore radio-active material exposure limits specified in 10 CFR 20.103.
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REPORT DETAILS 1.
Persons Contacted C. J. Hartman, Plant Superintendent C. E. Axtell, Plant Health Physicist T. M. Brun, Chemical and Radiation Protection (CRP) Supervisor P. J. Santek, Senior CRP Technician S. Vanderheide, Senior CRP Technician H. J. Russell, CRP Technician 2.
Organization A plant Health Physics Department was created effective March 1, 1976.
C. E. Axtell was appointed Plent Health Physicist, reporting to'the Plant Superintendent.
T. M. Brun was appointed Chemical and Radiation Protection Supervisor, reporting to the Plant Health Physicist. Six Chemical and Radiation Protection Technicians report to Mr. Brun.
3.
Personal Monitoring - External Beta-gamma film badges are provided by Radiation Detection Company on a monthly basis. Direct reading gamma dosimeters are worn alcrg with the film badges.
Ring badges are assigned for selected jobs where potential extremity exposures are significantly greater thmn whole body exposures.
Forms AEC-4 or their equivalent have been completed for all radiation workers.
The vendor's reports include lif etime doses, year-to-date doses, and current quarter doses. To control exposures, the licensee uses an accumulated exposure worksheet on which is recorded, for each individual, the dose accumulated during the current quarter
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and week.
The work sheet is updated weekly during operation and daily during outages. Pocket dosimeter readings are used to update doses since the last film badge report. Accumulated exposures
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are posted in the control room and other locations.
A review of exposure records for the last half of 1975 and the first four months of 1976 showed no overexposures.
The highest annual whole body dose was 4930 millirem.
The highest quarterly whole body dose was 2600 millirem.
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Stack Effluent Samplinn/ltonitorinc
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During the 1975-1976 winter season, the stack effluent sacpling line was out of service for periods of 0.4 to 9.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> on 15 occasions.
Cause was attributed to frozen lines.
An engineer has been assigned the problen and correction of the causes is planned before the winter of 1976-1977. The off-gas strip chart was reviewed and readings were recorded for each period frcs four hours before removal of the stack sanpling systen from service to four hours after xcturning it to service. These data were sent to Corporate Health Ph/ sics for appropriate correction of iodine and particulate stack releases.
review of the data indicated a stable release rate during a
each of the out-of-cervice periods.
5.
Airborne Radioactivity Surveys During operation, continuous air conitors (CAMS) are located in the turbine area, the containment spherc~(entrance), and containment exhaust (for steam leah detection.)
During shutdown, the turbine area CAM is moved to the reactor deck and the containment exhaust CA" is used to conitor fuel sipping operations. The CAMS in the turbine area and in contain-cent are particulate conitors, liigh volure grab samples are taken routinely during operation.
and shutdown.
These include samples for iodine on the reactor deck.
Licensee procedures for counting and calculating air sa ples were reviewed and no problets were identified.
I A review of Internal Dose Estimate records identified no airborne
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overexposures as determined by air samples.
6.
Respiratory Protection The licensee's respiratory protection program, which consists of.
training, face piece fitting, testing, cleaning, inspection, repair, and storage, was reviewed. ilatf masks and full-face masks with filter cartridges are worn. The types used have been approved by Eureau of Mines or the National Institute f or Occupational Safety and I!calth.
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In Vivo Countinq
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The licensee has installed a rental whole body counter.
Data is processed and reported by lleir,eson. The unit utilizes shadow shiciding. The 8 x 4 sodium iodide detector travels the length of the body.
Counts for mixed fission, corrosion, and activation products are made twice a year for selected employees.
In the spring all individuals having potential for airborne exposure are counted. The fall count is limited to operators, maintenance personnel and technicians.
A review of in vivo count records for counts made in May 1976 showed that 105 counts were made on 90-individuals.
The most frequently observed radioisotopes were cesium-137, cobalt-60, and cesium-134.
Cobalt-58, manganese-54 and iodine-131 were also detected.
A series of counts were made on one individuni at-intervals of four to seven days. Measured depositions, in nanocuries, were reported as fo11cus:
Date Cobalt-60 Cobalt-58 Cesium-134 Cesium-137 5/6/76
72 115 N.D.
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5/13/76 255
261 157 5/17/76
96 120 N.D.
5/21/76
72 114 N.D.
N.D. - Not detected.
To determine the cause of the increase in the May 13 count, the licensee investigated the individual's work assignments and could find no definite cause of the high count. A review of CAM charts and grab air samples did not identify any high airborne activity. Analysis of whole body count profiles did not indicate presence of significant external
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contamination.
Calculations by the licensee indicated a small internal dose on the basis of the apparent increase in internal deposition.
No estimate was made by the licensee of the airbocne concentrations to which the individual was exposed based on the increase in internal deposition between the May 6 and May 13 counts. The licensee's calculation of airborne exposure for this individual will be reviewed during a subsequent inspection. Calculations made by IE:III indicate the individual was exposed to air concen-trations of less than 40 ffC-hours.
These calculations were based on in vivo count data and were made in accordance with International Commission on Radiological Protection (ICRP)
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Publication 2.
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The inspector noted that the licensee did not routinely evaluate the results of the in vivo counts for compliance with the airborne radioactive material exposure limits specified in 10 CFR 20.103.
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8.
Radiation Work Permits (RWP's)
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The radiation work permits in current use were reviewed and no prob-lems were noted.
RWP's were posted at Access Control. The current list of RWP-exempt personnel was also posted at Access Control.
9.
Tour During a tour of the plant the inspector observed posting of various areas in accordance with Part 20.
Area status boards were noted to be current. Posting required by Part 19 was noted at several locations.
10.
Records Reviewe_d_
Survey Meter Calibrations Scaled Source Leak Tests In Vivo Counts Film Badge Reports Selected Forms AEC-4 Selected Accumulated Radiation Exposure Worksheets Air Sample I.og g
IIcalth Physics Log
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