IR 05000261/1982025
| ML20062K023 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 07/20/1982 |
| From: | Albright R, Barr K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20062K011 | List: |
| References | |
| 50-261-82-25, NUDOCS 8208160526 | |
| Download: ML20062K023 (4) | |
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>Q G8Gug'o UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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101 MARfETTA STREET, N.W.
- ATLANTA, GEORGIA 30303
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Report No. 50-261/82-25 Licensee:
Carolina Power and Light Company 411 Fayettevile Street Raleigh, NC 27602 Facility Name:
H. B. Robinson Docket No. 50-261 License No. DPR-23 Inspection at H. B. Robinson site near Hartsville, South Carolina Irispector:
7M8'[/A R. H. Albright Date Signed
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Approved by:
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K. P. Bph,' 3ection-etit ef '
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Technical Inspection Branch Division of Engineering and Technical Programs SUMMARY
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j Inspection on July 6-9, 1982
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Areas Inspected This routine, unannounced inspection involved 24 inspector-hours on site in the
areas of radiation protection and transportation of radioactive materials.
I Results Of the two areas inspected, no violations or deviations were identified.
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L 8208160526 820726
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PDR ADOCK 05000261 i
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REPORT DETAILS l
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l 1.
Persons Contacted i
Licensee Employees
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R. B. Starkey, Jr., Plant General Manager l
- C, W. Crawford, Manager, Operations and Maintenance
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- J. Young, Director, QA/QC l
- W. L. MacCready, Radiation Control Supervisor
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- J. A. Eaddy, Supervisor, Chemistry and Environment F. Gilman, Senior Specialist, Regulatory Compliance f
- C. L. Wright, Specialist, Regulatory Compliance
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R. Denny, RC Foreman I
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W. T. Ritchie, RC Foreman
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i J. Petitigout, ALARA Specialist
t M. Layton, Project Specialist Environmental and Chemistry
i NRC Resident Inspector
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S. Weise
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- Attended exit interview
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2.
Exit Interview
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The inspection scope and findings were summarized on June 9,1982, with
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those persons indicated in paragraph 1 above.
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i 3.
Licensee Action on Previous Inspection Findings
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l Closed (82-14-02) (URI) This item concerned the potential overexposure of a contract worker.
The licensee became aware of a potential personnel
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i overexposure when an individual's TLD was read as a prerequisite to issuing
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multiple whole body dosimetry.
The TLD reading indicated an exposure of l
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6.63 rem.
The investigating committee concluded that while the TLD reading could not be discredited, there was also no evidence to indicate the individual had
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received the 6.63 rem exposure.
The committee recommended assigning the
individual 265 mrem from his pccket dosimeter totals since this exposure
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compared well with the exposure estimated from his work at the plant.
The inspector followed the investigation closely and reviewed the final
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report.
The inspector concluded that the investigation appeared to be thorough and the final committee recommendation agreed with available data.
l The inspector had no further questions.
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Unresolved Items Unresolved items were not identified during this inspecticn.
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l 5.
Licensee Action on Previous Inspector Followup Items l
(Closed) (81-07-13) (IFI) Whole body count trend analysis. The inspector reviewed a whole body count trend analysis report for the years 1977-1980.
The type of analysis performed appears adequate to evaluate the respiratory
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protection program effectiveness.
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Health Physics Procedures The inspector reviewed revision 15 to the Radiation Control Protection Manual.
This review did not identify any violations or items of
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non-compliance. The inspector noted that the criteria used by the licensee to release material for unrestricted use is less restrictive than the guidelines suggested in IE Circular 81-07.
The release criteria in question is that materials may be released after passing a smear test as
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long as direct radiation readings are less than 0.25 mr/hr. The IE Circular does not indicate a direct radiation dose rate limit but it does suggest a fixed contamination limit of 5000 dpm/100 cm.
The inspector stated that
the direct radiation limit used by the licensee appeared to be high and should be evaluated (82-25-01).
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Radioactive Waste Shipment
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The inspector observed radwaste shipment number D60-82.
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placards were visible on each side of the transport vehicle. The inspector performed an independent radiation survey of the exterior of the shipping vehicle and in the cab and found radiation levels to be within DOT requirements.
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Radioactive material shipping records for shipment numbers 059-82, 060-82,
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and C6-82 were reviewed and found to be in compliance with DOT requirements.
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The inspector had no further questions.
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Respiratory Protection I
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The inspector selectively reviewed RWPs that required personnel to wear respiratory protection.
The dosimetry records of selected individuals who were issued respirators to perform the work described on the RWPs were y
reviewed.
These records contained the required medical evaluations for
personnel who wear respirators. The inspector had ne further questions.
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l 9.
Housekeeping Inside Containment f
The inspector reviewed startup procedure GP-2 which contained inspection requirements for startup. This procedure requires the reactor vessel sump,
RHR sump and the reactor cavity to be inspected and free of debris.
In
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addition, the inspection ensures that loose insulation has been removed from
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containment and all unprotected insulation has been secured. A licensee representative stated that substantial effort has been put into cleaning up work areas as work is completed so that the final cleanup is less of a problem. The inspector had no further questions.
10.
Health Physics Instruments The inspector checked calibration stickers, performt.d response checks and battery checks on several instruments that were available for use.
Instruments which needed repair were marked as out of service to ensure that they would not be used. Several friskers located in the plant were checked for proper alarm set point and calibration stickers.
No violations or deviations were identified.
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11.
Tour of Radiation Control Zone
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The inspector toured the radiation control zone with a licensee representative to observe posting practices for radiological barriers.
During the tour, the inspector found a door to the cask decon area open. A step off pad for the contaminated area was located outside the door; however, the posting for the area was on the outside of the door and could not be seen at the entrance to the area.
The licensee representative on tour with the inspector closed the door.
The licensee later initiated a request to have a closure device installed on the door.
Also during the tour, the inspector found one side of a radiation area barrier that had fallen down.
The highest radiition reading inside the areas and at eighteen inches from the warehouse exterior wall was less than 5 mR/hr. When a licensee representative tried to repost the area to its previous configuration, he found that someone had apparently removed approximatel.v fifteen feet of barrier rope.
The inspector stated that licensee cont ol of barriers will be re-examined during future inspections (82-25-02).