IR 05000324/1982022
| ML20058C547 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/29/1982 |
| From: | Albright R, Barr K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20058C504 | List: |
| References | |
| 50-324-82-22, 50-325-82-22, NUDOCS 8207260378 | |
| Download: ML20058C547 (5) | |
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UNITED STATES
NUCLEAR REGULATORY COMMISSION g
a REGION 11 g[
101 MARIETTA ST., N.W., SUITE 3100 o,
ATLANTA, GEORGIA 30303 Report Nos. 50-324/82-22 and 50-325/82-22 Licensee:
Carolina Power and Light Company 411 Fayetteville Street Raleigh, NC 27602 Facility Name:
Brunswick Docket Nos. 50-324 and 50-325
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License Nos. OPR-71 and DPR-62 Inspection at Brunswick site near Southport, N.C.
Inspector:
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i R. H.
Tbright Date Signed d-A?41 Approved by: _KP. Barr, SectionJd11ef Date Signed
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w chnical Inspection Branch
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Division of Engineering and Technical Programs SUMMARY Inspection on June 7-11, 1982 Areas Inspected This routine, unannounced inspection involved 32 inspector-hours on site in the areas of personnel qualifications, training, licensee surveillance of the health physics program, and personnel contamination control.
Results
Of the four areas inspected, no violations or deviations were identified.
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8207260378 820702
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PDR ADOCK 05000324 G
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REPDRT DETAILS 1.
Persons Contacted Licensee Employees
- C. R. Dietz, General Plant Manager
- W. M. Tucker, Manager, Operations
- G. J. Oliver, Manager, E and RC
- F. R. Coburn, Director, QA/QC
- E. A. Bishop, Manager, Technical Support
- J. Boone, Project Engineer
- D. C. Warren, Jr. Engineer
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- R. M. Poulk, Jr. Regulatory Specialist
- E.
D. Levinson, Consultant
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C. Prevatte, Consultant L. F. Tripp, Radiation Control Supervisor J. B. Cook, RC and T Foreman B. Failor, RC and T Forman T. Priest, RC and T Foreman J. Henderson, RC andT Foreman R. White, QA/QC NRC Resident Inspectors
- D. Myers, Senior Resident Inspector
- L. Garner, Resident Inspector
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on June 11, 1982, with those persons indicated in paragraph 1 above.
3.
Licensee Action on Previous Inspection Findings (Closed) (82-03-02) This item addressed two examples of health physics procedure violations. One example concerned operations personnel violating the plant procedure for drywell entry with the reactor critical.
These personnel entered the drywell under a standing RWP rather than using a specific RWP for the entry as required. The licensee informed operations personnel of this requirement. The drywell entry procedure was revised to clarify this requirement and copies were sent to the operations section.
The other example described a violation when an individual was issued a respirator without his practical mask fit training,being documented in his file. The individual was given the practical respirator fit training again.
Personnel giving the training have been instructed to fully complete each individual's training file and respirator qualification card. The corrective action for the above procedure violations appear adequate.
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4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Licensee Action on Previous Inspector Follow-up Items (Closed) (80-45-10) - This item concerned the method that the licensee used to adjust pocket dosimeter readings for comparsion to an individual's TLD dose.
The inspector reviewed the dosimetry evaluation form and had no further questions.
(Closed) (80-45-18) - This item concerned the need for the licensee to revise and expand the respiratory protection classroom training. Material covered in the classroom training has been expanded and appears adequate.
The inspector had no further questions.
(Closed) (80-45-21) - This item questioned the hydrocarbon sensitivity for the method used to periodically test service air to the specification of Grade "0" a i r.
The licensee now uses a vendor service to analyze the service air for hydrocarbons. The inspector had no further questions.
(Closed) (80-45-34) - This item concerned the identification and documenta-tion of Group I and II isotopes on resin shipping papers. The licensee has had resin samples analyzed for Group I and II isotopes.
The analysis indicated that no Group I and II isotopes were present. The licensee has an approved procedure to determine the presence of the Group I and II isotopes in further resin shipments. The inspector had no further questions.
(Closed) (80-45-37) This item concerned the need for extremity dosimetry to be worn by instrument calibration technicians during instrument calibration with radioactive sources. The licensee now requires instrument calibration technicians to wear head and left and right hand dosimetry. The inspector had no further questions.
(Closed) (82-03-01) This item concerned the method used to assign dose to an individual when pocket dosimeter and TLD readings were dif ferent by more than 25 percent of the TLD reading. The inspector reviewed the revised procedure which is used to investigate TLD and pocket dosimeter differences greater than 25%. The procedure appears to be adequate.
(Closed) (82-03-03) This item described a concern that the standing RWP could be used to enter an area that required additional health physics evaluation prior to entry.
A licensee representative stated that posting practices used by health physics have prevented the type problems described by this item. The inspector had no further questions.
(Closed) (82-03-04) This item concerned the neutron exposure received by two individuals during a drywell entry but not documented in their exposure files.
The licensee revised the drywell entry procedure to ensure that neutron exposures will be documented in the individual's exposure file. The procedure revision appeared adequat,,
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(Closed) (82-03-06) This item concerned the need for a program to periodically audit dress out areas for proper frisking techniques.
The licensee is auditing these areas one day each month. The inspector reviewed the surveillance reports and had no f urther questions.
(Closed) (82-03-07) This item raised the concern that individuals found to be contaminated were not reporting to the decontamination station.
The licensee now keeps logs of contaminated personnel at the frisking stations and the decontamination station. Names on the two lists are compared daily to ensure that all contaminated individuals report to the decontamination station. The inspector had no further questions.
6.
Personnel Qualification The inspector reviewed the resumes of 11 plant health physics technicians and 60 contract health physics technicians who a licensee representative stated were considered qualified in accordance with ANSI N18.1-1971.
A licensee representative stated that heaith physics experience listed on the resumes of the contract technicians is spot checked for verification purposes. The qualifications of the personnel whose resumes were reviewed appeared adequate to meet the requirements of ANSI N18.1-1971.
7.
Training for Contract Health Physics Technicians Contract health physics technicians receive the general employee training for plant workers. These technicians also go through approximately 3 hrs.
of training designed to f amiliarize the contract technician with specific plant procedures, instruments, forms f requently used, plant radiological limits, surveys, and posting.
The inspector reviewed the orientation procedure for contract technicians. A test with a passing score of 70 is required at the end of the training.
The training provided to contract health physics technicians appears adequate to familiarize the technician with plant procedures and work practices.
8.
Training for Personnel Stationed at Frisker Stations As part of the plant contamination control program, personnel have been hired to watch frisker stations, such as the turbine building breezeway and the exit to the protected area. These personnel are given general employee training for plant workers and 3-4 hrs. of job specific training.
These personnel ensure that individual workers frisk properly at the frisker stations.
The training received by the frisker watchers includes proper frisking techniques, survey of material coming through the check point and actions to take in the event workers are found contaminated.
Successful completion of this training requires passing a test and demonstrating proper use of instruments at the frisker station.
The frisker watchers are not allowed to do the final survey for unrestricted release of materials from the plant. Observation of the control points indicated that these personnel appear to have been adequately trained to ensure proper frisking techniques and the action to take if personnel were found to be contaminated.
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9.
Licensee Surveillance of the Health Physics Program The inspector reviewed the corporate assessment of the plant ALARA program.
The assessment appeared adequate and made several recommendations to plant management for program improvement. The plant response to the recommenda-tions indicates that plant management supports the ALARA program.
The inspector noted that several jobs are being tracked by the ALARA staf f.
Graphs of the predicted man-rem vs. time and actual man-rem used vs. time show good agreement for the jobs being tracked.
The graph in general indicate exposure savings. These graphs are located at the entrance to the protected area so that they are accessible to plant personnel.
The inspector also reviewed eight surveillance type inspections conducted by the plant QA/QC group.
These inspections covered posting of radiation control areas, transport of radioactive material, air samplers, RWP's,
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radiation surveys and frisking.
These inspections covered the obvious aspects of these areas.
It appears that more indepth inspections into the dosimetry and respiratory protection programs are planned.
This program appears adequate.
10.
Personnel Contamination Control The inspector reviewed the personnel decontamination logs for 10 days during the present unit 2 outage. On these days there appeared to be an average of 50 personnel contaminated each day. On the average approximately 30 percent of the contamination cases involved shoe contamination. The balance of the cases were split between facial, hair, hand, and cicthing contamination. A review of the personnel contamination reports did not give sufficient detail to draw a conclusion as to the major cause.
This area appears to need additional attention by management and will be examined during a future inspection (82-22-01)
11.
Tour of the Facility The inspector toured unit I and 2 and the surrounding outside areas. The posting of radiation areas, high radiation areas, contaminated areas, and radioactive materials areas appeared adequate.
The inspector verified radiation readings in radiation areas and at radiation /high radiation area boundaries.
These independent measurements indicated that all areas and boundaries were properly posted insofar as radiation levels.
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