IR 05000099/1982003
| ML20054M890 | |
| Person / Time | |
|---|---|
| Site: | Lynchburg Research Center |
| Issue date: | 06/18/1982 |
| From: | Barr K, Peery W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20054M887 | List: |
| References | |
| 50-099-82-03, 50-99-82-3, NUDOCS 8207150097 | |
| Download: ML20054M890 (3) | |
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UNITED STATES t
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JUN 181982 Report No. 50-99/82-03 Licensee:
Babcock and Wilcox Company Lynchburg Research Center Lynchburg, VA 24505 Facility Name:
Lynchburg Research Center Docket No. 50-99 License No. R-47 Inspection at Lynchburg site near Lynchburg, Virginia Inspector:_ _ _ he
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Date Signed Approved by-
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Technical Inspection Branch Division of Engineering and Technical Programs SUMMARY Inspection on May 25-26, 1982 Areas Inspected This special announced inspection involved eight inspector-hours on site in the areas of radiation protection associated with the dismantling of the LPR facility and a confirmatory survey to determine that the radioactivity levels specified in the dismantling plan had been achieved.
Results No violations or deviations were identified.
8207150097 820618 PDR ADOCK 05000099 G
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- T. Engelder, Laboratory Director
- A. Olsen, License Administrator J. Cure, III, Health and Safety Supervisor C. Burnham, Senior Operator S. Pennington, Health Physics Engineer
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on May 26, 1982, 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.
Disposition of Materials a.
A previous preliminary inspection (Report No. 50-99/82-02) revealed that remaining radioactivities in the LPR consisted primarily of activation products in the pool walls and the interior end of beam parts.
Report No. 50-99/82-02 described the disposition of materials as of that inspection on March 16-18, 1982 and the report and sup-porting documentation are included as Attachment A.
b.
This inspection of the LPR facilities revealed that the licensee has apparently removed radioactivity adequately to comply with his dis-mantling plan dated July,1981.
6.
Conf irmatory Survey a.
Review of licensee records of surveys and decontamination efforts have revealed a continuing reasonable ef fort to eliminate residual contam-ination. Attachment B shows the results of analysis by NRC, Region II and the licensee of various sample media that indicate low quantities of radioactivity.
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b.
Inspection of the premises, buildings and equipment and comparison with the licensee's final survey report revealed that all potentially contaminated items and equipment were included in the survey. The LPR facility was observed to be essentially empty except for the remainder of the decontaminated pool walls and the water clean-up system in the demineralizer room. These two areas were included in the licensee's survey. Attachment C shows the results of the licensee's final survey.
c.
A comparison of NRC and licensee final radiation survey measurements for fixed and removable contamination is shown in Attachment D.
The direct reading surveys were performed simultaneously on May 26, 1982, by the NRC inspector and a licensee representative. The NRC inspector used an Eberline. Model PRM-7, micro-R meter, and the licensee repre-sentative used a Reuter-Stokes, Model RSS-111, micro-R meter.
No discrepancies were observed between any of these measurements or between removable contamination measurements.
These measurements met all of the 'ixed and removable contamination limits specified in the dismantling pla ;L I /or
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APR 2 81982 Babcock and Wilcox Company ATTN:
Dr. T. C. Engelder. Director Lynchburg Research Center P. O. Box 1260 Lynchburg, VA 24505 Gentlemen:
Subject:
Report No. 50-99/82-02 This refers to the special inspection conducted by Mr. W. W. Peery of this office on March 16-18, 1982, of activities authorized by NRC License No. R-47 for the Lynchburg Pool Reactor facility and to the discussion of our findings held with you and members of your staff at the conclusion of the inspection.
Areas examined during the inspection and our findings are discussed in the enclosed inspection report.
Within these areas, the inspection consisted of selective examinations of procedures and representative records, interviews with personnel, and observations by the inspector.
Within the scope of this inspection, no violations or deviations were disclosed.
In accordance with 10 CFR 2.790(a), a copy of this letter and the enclosure will be placed in the NRC's Public Document Room unless you notify this office, by telephone, within ten days of the date of this letter and submit written appli-cation to withhold information contained therein within thirty days of the date of this letter.
Such application must be consistent with the requirements of 10 CFR 2.790(b)(1).
Should you have any questions concerning this letter, we will be glad to discuss them with you.
Sincerely,
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.a n F. J. Long, Acting.ief Reactor Projects Branch 1 Division of Project and Resident Programs Enclosure:
Inspection Report No. 50-99/82-02 c: F
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E FIEGION 11
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APR 2 81982 Report No. 50-99/82 02 Licensee:
Babcock and Wilcox Company Lynchburg Research Center
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Lynchburg, VA 24505 Facility Name:
Lynchburg Research Center Docket No. 50-99 License No. R-47
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Inspection at Lynchburg site near Lynchburg, VA Inspector:
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'Date' Signed Approved by:
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fm K. P. Ba rd,' SeWCh'i e f j/Dap Signed Technical Inspection Branch Division of Engineering and Technical Programs SUMMARY Inspection on March 16-18, 1982 Areas Inspected This special, announced inspection involved 16 inspector-hours on site in the area of radiation protection associated with the dismantling of the LPR facility.
Results Of the area inspected, no violations or deviations were identified.
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- T. Engelder, Laboratory Director
- A. Olsen, License Administrator M. Baldwin, Supervisor Reactor Operations
- J. Cure, III, Health and Safety Supervisor C. Burnham, Senior Operator D. Harris, Senior Health Physics Engineer K. Long, Accountability Specialist
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on March 18, 1982, 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.
Disposition of Materials This preliminary inspection revealed that all LPR fuel has been shipped Three shipments were made in November 1981 for a total of 25 a.
to SR00.
fuel elements, utilizing a Battelle Columbus Laboratories cask, DOE /NRC USA /5957 8()F, under Certificate of Compliance Number 5957.
Forms 741, Nuclear Materials Transaction Reports were prepared by the licensee and these were reviewed to verify disposal of all LPR fuels.
Form 741s, Nuclear Material Transaction Reports and licensee internal records were reviewed to determine that all neutron sources possessed under the LPR license number R-47 had been transferred to authorized
-
All sources recipients of f-site or to the B&W License No. SNM-778.
had been transferred.
All major activated components have been removed from the LPR and are b.
being held in secured storage pending shipment to an authorized waste site.
The remaining radioactivity in the LPR consists of disposal activation products (Eu-152) in the concrete pool walls, metal activa-tion products (primarily Co-60) the majority of which is located in the S inch beam port on the interior end of the ports and contaminated
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f b '"" p0 fj'?9 c,rm ?4RC41a U.S. ANUCLEAR REGULATORY CoMMISSI N i2 31 CERTIFICATE OF COMPl. LANCE g
g For Radioactive Materials Packages 1.(a) Cer tificat e_ Number 1.(b) Revisme No.
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2. PRE AMBLE 7.6a)
This certificate is issued to satisfy Sectems 173.393a.173.394,173.335, and 173.396 of the Decartment of Transportaten Hazardous Materials Regulations (49 CFR 170189 and 14 CF R 103) and Sections 146-19-10a and 146-19-100 of the Department of Transportation Dangerous Cargoes Regusassons (46 CFR 146-149), as amended.
2.lb)
The packaging and contents described iss isem 5 below. meets the safety standards set forth in Subpart C of Title 10. Code of Federal Regulations. Part 71, ** Packaging of Radioactive Materials for Transport and Transportation of Radioactive Material Under Certain Conditions."
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This certificate does not relieve the consupnor from corripliance with any requirement of the regulations of the U.S. Department of Transportation or other applicable regulamery. agencies, including tne government of any country through or into which the package will oe transpor1ed.
3. This certificate is issued on the basis of a safety anasysis report of the package design or application-31a) Prepared by (Name and address):
3.(b)
Title and identification of report or application:
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Battelle Columbus Laboratories Battelle Columbus Laboratories application 505 King Avenue dated June 11, 1986, as supplemented.
Columbus, OH 43281 3.(c)
Docket No.
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coNDirloNS This certificate is conditional upon the fulfilling et the requirements of Subpart D of 10 CFR 71, as applicable, and the conditions specified in item 5 below.
5. Description of Packaging and Authorized Contents. SAodel Number, Fissile Class. Other Conditions, and References:
(a) Packaging (1) psy% amassu-l (2) Description A steel-encased lead shielded shipping cask. The basic cask body is a cylinder 33.37 inches in diameter by 73.37 inches high formed by two
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stainless'stbeTQE%ent having 7.75 inches of lead shielding.
The cask W_ )Id ~ [y lid is secured to the cask by twelve steel studs which are welded to the cask body.
Cask appurtenancies include a drain line with needle valve and
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T,he total-cask 1weighti
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The cask is constructed in accordance with the following Battelle Memorial Institute (BMI) Drawing Nos.:
0001, Rev. B; and 0003, Rev. B.
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