IR 05000259/1982002
| ML20041F998 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 02/17/1982 |
| From: | Barr K, Collins T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20041F995 | List: |
| References | |
| 50-259-82-02, 50-259-82-2, 50-260-82-02, 50-260-82-2, 50-296-82-02, 50-296-82-2, NUDOCS 8203170638 | |
| Download: ML20041F998 (4) | |
Text
-
[
'o,,
UNITED STATES
NUCLEAR REGULATORY COMMISSION
/
REGION il o
p t
101 MARIETTA ST., N.W., SUITE 3100
'
o ATLANTA, GEORGIA 30303
,
.....
FE B 191982 Report Nos. 50-259/82-02, 50-296/82-02, and 50-260/82-02 Licensee: Tennessee Valley Authority 500A Chestnut Street Tower II Chattanooga, TN 37401 Facility Name:
Browns Ferry Nuclear Plant Docket Nos. 50-259, 50-296, and 50-260 License Nos. DPR-33, DPR-52, and DPR-68 Inspection at Browns Ferry Nuclear Plant site near Athens, Alabama Inspector:
J
h T.'R. Collins ja t) ate Signed Approved by:
k.
__y/f7!BL L,
K. Barr, S6ction Chief'
'
[ fate / Signed Technical Inspection Branch Engineering and Technical Inspection Division SUMMARY Inspection on January 25-29, 1982 Areas Inspected This routine, unannounced inspection involved 33 inspector-hours on site in the areas of radiation protection, refueling operations, radwaste management and shipments of radioactive material.
Results Of the four areas inspected, no violations or deviations were identified.
l 82'3170638 820219 PDR ADOCK 05000259 O
!
-
-
- -
.
,
REPORT DETAILS 1.
Persons Contacted Licensee Employees
- G. T. Jones, Plant Manager J. Bynum, Assistant Plant Manager
- T. L. Chinn, Compliance Staff Supervisor
- C. J. Rozear, Compliance Engineer
- R. T. Smith, Quality Assurance Engineer
- J. E. Swindell, Field Services Engineer
- J. H. Miller, Field Services Engineer
'
- A. W. Sorrell, Health Physics supervisor
,
- E. M. Cargill, Assistant Health Physics Supervisor H. M. Crowson, Assistant Health Physics Supervisor D. G. Bohlender, Health Physics Shift Supervisor R. N. Armstrong, Assistant Shift Engineer Other licensee employees contacted included six health physics technicians and three office personnel.
NRC Resident Inspector
- J. W. Chase
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on January 30, 1952 with those persons indicated in paragraph 1 above.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Health Physics Appraisal Inspector Follow-up Items Closed (IFI) 50-259, 260, 296/80-36-19 Proper Use of Portal Monitors. A licensee representative stated that two additional more sensitive portal monitors have been ordered and approved for purchase.
These additional portal monitors will be used at the turbine building exit for personnel
'
contamination control. The inspector concluded this was adequate and had no further question i
.
6.
Issuance of Special Work Permits On January 26, 1982 the inspector observed a Special Work Permit (SWP)
written for work te be performed in the Unit 3, Reactor Water Clean-Up Pump Rooms A and B.
The SWP (No. 01-3-31450) indicated 30 mr/hr smear-able contamination and no airborne survey results recorded.
The inspector questioned the Health Physics technician issuing the SWP on the airborne survey results and was told that air samples would be taken upon entry into these areas. The inspector reviewed radiation survey results taken from this area on January 21, 1982, which were used on SWP No. 01-3-31450.
Radiological Control Instruction RCl-10 Section VI, Radiation and Contamina-tion Survey Requirements Prior to Issuance of Special Work Permits, states that if significant changes to dose rates and airborne activity levels are likely to occur, surveys must be made immediately preceeding the work. The inspector stated that a SWP should not be issued until air sample results are known and that this practice will be reviewed during future inspections (50-259, 260, 296/82-02-01).
7.
Plant Tour The inspector observed the use of tobacco products and chewing gum in potentially contaminated areas. The inspector stated to plant management that this is a poor health physics practice and there was a good potential for personnel to ingest radioactive contamination.
The inspector stated that consideration should be given to restricting smoking, eating, and chewing in the restricted area.
8.
Housekeeping The inspector observed on all elevations of the unit three reactor building the buildup of trash and debris. The inspector stated to plant management that this practice was not satisfactory, and it could potentially lead to a contamination control problem. The inspector stated consideration should be given to eliminating the poor housekeeping practice.
9.
Radioactive Waste Shipments
~
The inspector had the licensee open six 55 gallon drums of compacted trash to verify the requirement of 0.5% free standing liquid in shipping con-tainers.
The inspector concluded after his inspection of drum numbers D82-371, D82-372, D82-373, D82-375, and DR2-376 that no free standing liquid was evident.
In addition, the inspector reviewed a radwaste shipment, TVA shipping number 1731, for Department of Transportation (DOT) shipping requirements. The inspector concluded after his review of the Radioactive Shipment Record (RSR) and the external dose rates of the shipping vehicle,
,
the radwaste shipment, met all requirements of DO.
- 10.
Respiratory Protection Program The inspector reviewed the respiratory protection program which included proper storage of full face respirators, monthly inspections of self con-tained breathing apparatuses (SCBA), hydrostatic 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.
11.
Posting, Labeling and Control The inspector toured both Units 1, 2, and 3, reactor, radwaste and turbine 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.
12.
Instruments and Equipment 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 checked selected portable instruments for proper operation. The inspector discussed the radiation survey instrument calibration program with licensee representatives. The inspector had no further questions.
13.
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.
14.
Refueling Operations of Unit Three The inspector observed the major control points at the drywell, torus, turbine deck, and refueling floor for the use of special work permits, current radiation survey data, respiratory issuance control and staffing of Health Physics Technicians.
The inspector concluded that these control points appeared to be acceptable and had no further questions.
(
15.
Health Physics Staff and Organization The inspector reviewed the licensee's current Health Physics Organization and staff for adequacy to perform required duties of units one and two normal operation and unit three refueling outage.
The licensee has at present approximately 86 Health Physics Technicians to perform required duties of all three units.
The inspector concluded this appeared to be adequate and had no further questions.
!
l l