ML20040C123
| ML20040C123 | |
| Person / Time | |
|---|---|
| Site: | 07001201 |
| Issue date: | 12/30/1981 |
| From: | Hosey C, Kahle J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20040C119 | List: |
| References | |
| 70-1201-81-13, IEIN-81-26, NUDOCS 8201270291 | |
| Download: ML20040C123 (8) | |
Text
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f UNITED STATES NUCLEAR REGULATORY COMMISSION g
o REGION 11 U
101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 Report No. 70-1201/81-13 Licensee:
Eabcock & Wilcox P. O. Box 800 Lynchburg, VA 24505 Facility Name:
Commercial Nuclear Fuel Plant Docket No. 70-1201 License No. SNM-1168 Inspection at Lypchburg, Vi gi ia
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Inspector:
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. Kab1b Datd Sigried Approved by:
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C. M. Hose 9, Acting Sef tion Chief Dat'e Signed '
Technical Inspection Branch Engineering and Technical Inspection Division
SUMMARY
Inspection en December 7-11, 1981 Areas Inspected This routine, unannounced inspection involved 29 inspector-hours on site in the areas of followup on previous inspector identified items, IE Information Notice, internal exposure control, external exposure control, health physics procedures, t
health physics training, respiratory protection, instrument calibrations, contam-ination surveys, radiation work permits, records and reports, radioactive efflu-ents, waste treatment and disposal, packaging and transportation of radioactive material and. postings.
Results I
j Of the 15 areas inspected, no violations or deviations were identified.
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8201270291 811231
{DRADOCK 07001201 POR
REPORT DETAILS 1.
Persons Contacted Licensee Employees
- R. Alto, Virginia Operation Manager
- D. Zeff, Health-Safety and Licensing Manager
'W. Engelke, Manufacturing Engineering Manager
- J. Ficor, Quality Assurance Manager
- T. killingsworth, Materials Manager
- L. Lee, Manufacturing Operations Manager
- T. Ford, Licensee Administrator
- J. Powers, Nuclear Materials Control Manager
- K. Shy, Health-Safety Supervisor
- R. Vinton, Health Physicist A. Cure, Health Physicist G. Johnson, Operations Foreman J. Foster, Custodian J. Anderson, Custodian Other licensee employees contacted included three technicians, two opera-tors, and one office person.
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on December 11, 1981 with those persons indicated in paragraph 1 above.
3.
Licensee Action on Inspector Identified Items a.
(Closed) Open Item, 78-15-01, Penetrating and Burial Losses in Air Sampling Filters.
The licensee uses Gelman Type AE filter media for static and lapel sampling. An examination of the vendor's literature showed that penetration is not a problem. An examination of several sets of test data showed that there was no increase in the activity detected radiometrically after chemically processing the filter media compared to the gross alpha activity detected prior to the processing.
This would indicate that there is no apparent loss of activity due to alpha particle absorption by the filter media or self-absorption due to dust or other material collected.
b.
(Closed) Open Item, 79-02-07, Revise Solid Waste Procedure to Include License Condition 8.3.1(e). The inspector reviewed procedurc AS-1110, Rev. 6, Waste Control, Paragraph 5.1.4 contains provisions which require that items leaving the controlled areas which cannot be ef fectively monitored are treated as contaminated items.
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(Closed) IFI, 80-06-01, Increasing Lung Burden In One Individual. An examination of the lung counting data showed that a subsequent lung count of the individual was 0 52 micrograms of uranium - 235. Licensee representatives stated that they had discussed with the individual the I
importance of prevsating and/or removal of skin contamination prior to i
being counted in the body counter.
Subsequent body countr. showed background counting levels.
l d.
(Closed) IFI, 80-06-02, Internal Consistency Check on Vendor Urinalysis Service. The licensee has prepared a uranium (standard) solution which has been analyzed by the -vendor.
Each quarter a spike from. the standard solution is submitted for analyses. An examination of the vendor results shows a good correlation.with the submitted spike valves. The vendor's internal consistency for assay of spiked uranium samples is satisfactory and acceptable.
e.
(Closed) IFI, 80-06-03, Air Sampling Study to Check the Location of Two Static Air Samplers.
Special air sampling studies were conducted at the two locations. The results showed that there was no significant i'
difference in the results obtained, consequent y no changes were made in the location of the air samplers at the walk ng beam furnace loading and unloading hoods.
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(Closed) IFI, 80-06-04, Licensee Use of " Practical Examination" of Radiation Monitor. A licensee ~ representative showed the inspector a copy of the' form used by the Health-Safety Supervisor to document the' practical examinations given to the Health-Safety Monitors to demon-strate-their ability to complete identified assignments in a satis-factory manner.
The form contains the. monitor's name and ' social securi ty - number, thirteen identified assignments, the date 'and the initials of the person who observes and certifies that the monitor has demonstrated satisfactorily performance of the various assignments.
The inspector concluded that the form provided satisfactory documenta-tion-that monitors exhibited the specified degree of ~ proficiency as determined by practical-examinations, g.
(Closed) IFI, 80-06-05, Determination of Proper Calibration Frequency i
for Lapel Samplers. A licensee representative stated that the. lapel samplers were calibrated on a ' semi-annual basis as required by the license and that tests had baen conducted at various time intervals to-show that the instruments remained in a calibrated condition at the six-month interval.
4.
Unresolved Items Unresolved items were not identified during this inspection.
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3 5.
Procedure Review An examination of health-safety procedures showed that almost all procedures had minor revisions within the past year. Documentation was examined that showed that the health-safety procedures had been reviewed annually as required by license conditions. No violations were identified and inspector had no further questions.
6.
External Exposure Control The inspector examined the vendor personnel dosimetry reports for 1980 and the first three quarter of 1981.
It was apparent that personnel were not receiving an occupational radiation dose in excess of the limits specified in 10 CFR 20.101.
Verification was made that Form NRC-4 information was maintained for each individual even though radiation exposure levels did not exceed 10 CFR 20.101(a) limits.
No violations were identified and the inspector bad no further questions.
7.
Internal Exposure Control a.
Air Sampling An examination of the air sampling records revealed that the average concentration of airborne radioactive c.~terials in the work areas were less than 10 percent of the MPC valved in most situations.
A few results exceeded the 25 percent valve.
Discussions with licensee representatives revealed that investigations were conducted in accordance with the license requirements and corrective actions taken which showed a reduction in airborne concentrations of radioactive material.
Tnis was verified by an examination of graphed results furnished by the licensee. An examination of the MPC-hr records fur individuals who work in the controlled area showed that the quarterly exposure to individuals were less than 10 percent of the 520 MPC-br quarterly limit. No violations were identified.
b.
In-vivo Counting An examination of whole body counting reports for 19SO and 1981 showed no results greater than 100 micrograms U-235.
The inspector had no further questions, c.
Urinalysis An examination of the 1980 and 1981 urinalysis records showed no results greater than the licensee's action level of 15 micrograms per liter and/or 50 dpm per liter. The inspector discussed at length the licensee's program for spiking samples for verification of the vendor's ability to arsay spiked uranium samples and produce results with consistency. The inspector had no further questions.
4 d.
Respiratory Protection The inspector examined the licensee's procedure AS-1109, Rev.
8, Respiratory Protection Program and discussed the appilcation and implementation of the procedure with licensee representatives. It was apparent that the respiratory protection program met the guidance and requirements provided in Reg. Guide 8.15, Acceptable Programs for Respiratory Protection.
Licensee representatives related the various types of work or jobs where respiratory protection was used and the technique for testing that individuals had a good fit. The inspector had no further questions.
8.
Radioactive Effluents a.
Gaseous An examination of the stack air sampling records for 1980 and 1981 revealed that the concentrations of uranium in the gaseous effluent discharged from the plant was 1-2 percent of the maximum permissible concentration (MPC).
The inspector verified that the HEPA filter systems were DOP tested in accordance with the license requirements and that the checks of the pressure differential across the filters were made and recorded weekly.
No violations were identified.
b.
Liquid An examination of the liquid effluents released from the retention tanks showed that all releases were below the MPC valves.
Licensee representatives discussed their flocculent technique for treating liquid wastes prior to release from the decon area to the retention tanks. No violations were identified.
9.
Solid Wastes i
Licensee representatives stated that practically all contaminated wastes are sent to the Pennsylvania Operations (NUMEC) for incineration as recoverable scrap.
Occasionally, noncombustible contaminated items are sent to a licensed burial ground. No shipments of contaminated waste were made to the burial ground in 1981. The inspector had no further questions.
10.
Contamination Surveys An examination of the contamination survey records showi<i that surveys were conducted in accordance with the frequer.cies stated in R. license condi-l l
S tions. The results indicated that contamination was not being spread to uncontrol',ed areas and that corrective measures were taken when action levels were exceeded. Surveys, taken by the licensee at the request of the inspector, showed that the contamination levels in the clean side of the change room were background for both removable and fixed contamination. No violations were identified.
11, Sealed Source Leak Tests An examination of the licensee's documentation showed that the sealed sources were leak tested in accordance with the license requirement of every six months. The records also reflected that sources were leak tested upon receipt and prior to packaging for shipment. The results showed that there was no evidence of any leakage. No violations were identified.
12.
Instrument Calibration From an examination of the instrument calibration records verification was made that the health-safety instruments were calibrated according to the licensee's procedures m1 license requirements. During tours of the plant the inspector obse; ad that instrument s contained calibration s_ tic kers depicting the due date for the next schsduled calibration. No violations were identified.
13.
Postings, Records and Reports The inspector observed that the licensee had posted notices to workers pursuant to 10 CFR 19.11.
The records maintained by the licensee met the requirements of 10 CFR 20.401.
The inspector verified that reports had been submitted to the Commission and to individuals pursuant to 10 CFR 19.13,10 CFR 20.407, 10 CFR 20.408, 10 CFR 70.59 and 10 CFR 71.61.
No violations were identified.
14.
Radiation Work Permits (RWP)
The inspector examined the RWP files and discussed the details of several permits with a licensee representative.
It appeared that the radiation protection requirements were adequate for the nature of the work and conformed to the licensee's procedure AS-1123, Rev. 4, Radiation Work Permit Program. The inspector had no further questions.
15.
IE Information Notice 81-26 A licensee representative stated that the licensee had received the notice and that the first four items of the notice were not applicable to their
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' operation.
He stated that they had evaluated their instrumentation in
- accordance with the guidar.ce furnished in part 5 of the notice and that no changes.or considerations were required. The inspector observed documenta-tion which confirmed'the representative's statement. The inspector had.no further questions.
16.
Packaging and Transportation of Radioactive Materials The inspector. verified that the licensee maintained procedures witch desig-j nated individuals and organizations assigned the responsibilities for-packaging and transport of radioactive materials. Verification was made that procedures were maintained for the preparation and' the inspection of containers for shipment of radioactive materials.
Procedures were main-tained for loading and closing containers with appropriate quality assurance checks.
The inspector verified that the licensee maintained copies of the applicable Certificates of Compliance for the appropriate containers. An examination of the records showed that the-necessary information was being maintained pursuant to 10 CFR 71.62. An examination of selected shipping -
documents indicated that the shipping papers contained the appropriate-information pursuant to 49 CFR 172 and that proper instructions were provided for labelling and placarding.
The inspector had no further questions.
- 17. Truck Accident On September 30, 1981, during a routine inspection at the B&W - LRC Labor-atory this inspector was informed that a truck carrying containers of radioactive material for the= Babcock & Wilcox Commercial Nuclear Fuel Plant had overturned at the junction of the Lynchburg Expressway and Candlers Mt.
Road in Lynchburg, Virginia. After -notifying the NRC Region II Office, the inspector responded to the site of the accident.
Arrival time at the accident site was 8:25 a.m., approximately one hour after the' truck had overturned.
The truck (Tri-State Motor Transit Company) had overturned as it exited the Expressway onto Candlers Mt. Road. The containers were thrown off the truck into the median strip between the Expressway and the exit ramp within approximately 50 feet of the truck bed. No other. vehicles were involved and there were no serious personnel injuries to the truck drivers.
3 The area in which the drums were scattered was isolated. B&W CFNP personnel with the assistance of B&W NNFO personnel established controls for entering and exiting the isolated area. Lynchburg police and firemen assisted with the isolation controls in addition to contolling traffic and sightseers.
Surveys were conducted of the containers, the truck and the involved area 1
for the presence of alpha emitting radioactive contamination. No ccatami-nation above background levels was detected.
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7 The truck was carrying 60 packages containing low-enriched uranium dioxide powder (Certificate of Compliance Number USA /5768/AF Model Number BB-250-2) and 24 empty 55 gallon drums which potentially contained low-level uranium contamination (100 dpm per 100 cm2).
Damage to the 88-250 containers consisted of dents with minor reduction of outer containment integrity. One BB-250 container was observed to have a tear in the outer container skin with a minor loss of vermiculite insula-tion. All BB-250 lids remained intact. Some of the empty 55 gallon drums were crushed significantly. One empty container was observed where the lid had been knocked of f, however, as stated above no contamination was detected.
At approximately 10:00 a.m.
instructions were issued to remove the con-tainers to the B&W-CNFP site. This operation was completed at approximately 4:00 p.m.
At which time a thorough survey was made of the truck and the involved area.
Again, no contamination was detected and the area was released.
The BB-250 containers were unloaded at the B&W-CNFP site with precautions taken to eliminate spread of contamination in the event any inner metal cans had lost their integrity.
All inner metal containers remained intact, however on seven of the BB-250's the aluminum metal spacer can on top was crushed from one-half to four inches.
In summary, the inspector concluded that the licensee and associated agencies responded to the emergency promptly and appropriately.
They immediately isolated the area and established the necessary controls to prevent or minimize the spread of contamination.
Communications were established between the site of the emergency and the licensee's plant site.
Public relation contacts were established with the local press and other news media.
Appropriate organizations (Commonwealth of Virginia, DOT and NRC) were promptly notified.
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