IR 05000327/1981041
| ML20041C728 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/29/1981 |
| From: | Collins T, Hosey C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20041C692 | List: |
| References | |
| 50-327-81-41, 50-328-81-50, NUDOCS 8203020515 | |
| Download: ML20041C728 (5) | |
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UNITED STATES
1, NUCLEAR REGULATORY COMMISSION g
n REGION 11 g[
101 MARIETTA ST., N.W., SUITE 3100 o,
ATLANTA, GEORGIA 30303
Report h 2. 50-327/81-41, 50-328/81-50 Licensee:
Tennessee Valley Authority 500A Chestnut Street Tower II Chattanooga, TN 37401 Facility Name:
Sequoyah Docket Nos. 50-327, 50-328 License Nos. DPR-77, DPR-79 Inspection at
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Inspector: C
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T. R. Collins Date Signed
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Approved by:
i t-w C.'M. Hofg9, Ag/ ting Section Chief D4te Signdd Technical Inspection Branch Engineering and Technical Inspection Division SUMMARY Inspection on December 7,1981 to December 11, 1981 Areas Inspected This routine, unannounced inspection involved 36 inspector-hours on site in the l
areas of radiation protection and radwaste management.
Results Of the two areas inspected, no violations or deviations were identified in one
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area.
One violation was identified in one area (Failure to make suitable
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i measurements of radioactivity in air).
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- J. M. McGriff, Assistant Plant Superintendent
- R. J. Kitts, Health Physics Supervisor
- H. R. Rogers, Compliance Engineer E. Paris, Health Physics Shift Foreman D. E. Crawley, Health Physics Shif t Foreman J. Reagen, Health Physics Shift Foreman R. J. Prince, Assistant Health Physics Supervisor D. Crisp, Health Physics Support Functions G. B. Kirk, Acting Compliance Supervisor T. L. Howard, Quality Engineering Supervisor A. M. Carver, Nuclear Engineer L. W. Smith, Training Officer J. C. Smith, Health Physics Training Instructor
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NRC Resident Inspector
- E. J. Fo rd S. D. Butler
- Attended exit interview
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2.
Exit Interview The inspection scope and findings were summarized on December 11, 1981 with those persons indicated in paragraph 1 above. The inspector discussed the apparent violation of NRC requirements with those present (paragraph 13 of the details). Licensee management acknowledged the inspector's findings.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Inspector Follow-Up Items (Closed) 79-F1-05 Inspection for Service Air Contamination.
The inspector discussed this matter with a licensee representative and determined that their present program for checking service air for radioactivity appeared to
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be adequate.
The licensee is sampling the service air compressors for radioactivity by taking an air sample and analyzing this sample for cross contamination on a monthly frequency.
The inspector had no further questions.
6.
Startup Tests and Surveys FSAR Table 14.1-2, List of Startup Tests.
List those tests to be performed following fuel loading and during power ascension; prerequisites for each test and test objectives and acceptance criteria.
Included in these tests are the chemical and radio chemical baseline analyses, radiation survey and shielding effectiveness tests and effluent monitor tests.
The inspector reviewed test procedure SU-1.D, Unit 2 radiation baseline survey after initial core loading and radiation baseline survey at hot-zero power to determine that the design shielding is adequate for safe plant operation and to keep personnel radiation exposures ALARA.
The inspector concluded after his review that the shielding appeared to be adequate and had no further questions.
7.
Respiratory Protection Program The inspector reviewed the respiratory protection program which included proper storage of full face respirators, monthly inspections of self contained breathing apparatuses (SCBA), hydro static tests of breathing air cylinders, respirator training of personnel, annual respiratory physicals for personnel, and breathing air quality analysis as required by NUREG-0041.
The inspector concluded that the respiratory protection program appeared to be adequate and had no further questions.
8.
Posting, Labeling and Control The inspector toured both Units 1 and 2 auxiliary buildings to ensure proper posting and labeling of contaminated areas, radioactive materials areas, radiation areas, and high radiation areas.
The inspector determined that the posting, labeling and control appeared to be adequate and had no further questions.
9.
Instruments and Equipment
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The inspector observed a variety of radiological instruments (portable survey instruments, portal monitors, personnel friskers) in use and avail-able for use.
Checked calibration stickers, performed battery checks for selected portable instruments in the health physics office, and response r
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checked selected portable instruments for proper operation.
The inspector
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discussed the radiation survey instrument calibration program with licensee representatives. The inspector had no further questions.
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10.
Plant Tour The inspector observed the alarm set points on RM-14's were inconsistent throughout the auxiliary building or regulated area. These friskers are provided for plant personnel to survey themselves when leaving C-Zones or contaminated areas, 2 1000 dpm/100CM2 In addition, there were no signs posted for their intended use and the alarm set points for determining the levels of contamination on personnel was not adequate. The inspector stated to. licensee personnel this program was inadequate and further evaluation of the contamination control program within the regulated area in setting the alarm set points on RM-14's consistantly and posting adequate signs at each frisker for its intended purpose was needed.
The inspector stated to licensee management this would be left as an open item until further evaluation by the licensee has been completed (50-327/81-41-01; 50-328/81-50-01).
11.
Special Work Permit Program
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The inspector obse ved approximately 50 Special Work Permits (SWP's)
processed on December 11, 1981 for various work to be done on Unit-One and Unit Two. A licensee representative stated that the Health Physics Shift Foreman had to perform technician duties to enable the processing of these 50 SWP's. The current staffing of H.P. Technicians appeared to be inade-quate to give the surveillance necessary to assure full compliance with each SWP. The inspector discussed this with a licensee representative and was informed that a revision to their SWP program was under evaluation. The inspector stated to licensee management that this would be left as an open item until final evaluation was complete (50-327/81-41-02; 50-327/81-50-02).
12.
Decontamination of Protective Clothing The inspector selected several items of protective clothing for reuse from the laundry area to ensure acceptable levels of radioactivity for reuse.
The licensee's administrative limit for reuse of protective clothing is 0.75 mrad /hr.
The inspector concluded that the levels of radioactivity were within the licensee's administrative limit and had no further question.
i 13. Air Sampling of Unit One Containment On July 11, 1981 approximately nine personnel were working in Unit 1 containment in or near the accumulator number two room. When upon exiting the containment while frisking they determined they were contaminated around the face and hair.
Health Physics personnel were notified and performed
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further surveys of these personnel to determine levels of contamination and
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I the possible cause. All personnel received whole body counts to determine the levels of internal contamination. Two individuals received greater than 10% maximum permissible body burden (MPBB) of Iodine-131.
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Health Physics personnel were notified of the MPBB's of Iodine-131 of these personnel and immediately entered containment to take further air samples of the work area (Accumulator Number 2 Room).
Results of these air samples
taken indicated 1.58 Maximum Permissable Concentration (MPC) of Iodine-131.
Previous to this incident the licensee had taken general area air samples
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inside containment at the seal table area, race way, and upper containment
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and had not identified any significant concentration of Iodine-131. Once the levels of Iodine-131 was discovered in the work area, the licensee provided respiratory equipment for personnel during the remainder of their job.
10 CFR 20.103(a)(3) states that the licensee shall use suitable measurements of concentrations of radioactive materials in air for detecting and evaluating airborne radioactivity in restricted areas.
The licensee failed to make suitable measurements for detecting and evaluating airborne radioactivity inside the Unit 1 Containment in the accumulator number two room in that air samples were not taken immediately prior to or during the work in the accumulator room number 2.
Air samples taken after the workers exited the area and were found contaminated indicated the Iodine-131 concentration was 1.58 MPC.
The inspector stated that failure to perform adequate air samples of the work area was in violation of 10 CFR 20.103(a)(3) (327/81-41-01 and 328/81-50-01).