IR 05000409/1979024
| ML19320B240 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 06/03/1980 |
| From: | Fisher W, Greger L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19320B237 | List: |
| References | |
| 50-409-79-24, IEB-79-19, NUDOCS 8007100089 | |
| Download: ML19320B240 (4) | |
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U.S. NUCLEAR RECULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-409/79-24 Docket No. 05000409 License No. DPR-4-Licensee: Dairyland Power Cooperative 2615 East Avenue - South Lacrosse, WI 54601 Facility Name:
Lacrosse Boiling Water Reactor Inspection At:
Lacrosse Boiling Water Reactor Site, Genoa, WI Inspection Conducted: December 27-28, 1979
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Inspector:
L. R. Grege
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.D Approved By:
W. L. Fisher, Chief 6 / 7/[6'd Fuel Facility Projects and Radiation Support Section Inspection Summary Inspection on December 27-28, 1979 (Report No. 50-409/79-24)
Areas Inspected: Nonroutine, announced inspection of licensee actions taken in response to IE Bulletin 79-19, " Packaging of Low-Level Radio-active Waste for Transport and Burial." The inspection involved twelve inspector-hours onsite by one NRC inspector.
Results: No items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted L. Kelley, Assistant to Operations Engineer
- L.
Krajewski, Health and Safety Supervisor
- J.
Parkyn, Assistant Plant Superintendent S. Raffety, Reactor Engineer
- R. Shimshak, Plant Superintendent H. Towsley, Quality Assurance Supervisor The inspector also contacted several other licenset employees, includ-ing members of the technical and engineering staffs.
- Denotes those attending the exit interview.
2.
General This inspection, which began at 2:00 p.m. on December 27, 1979, was conducted to examine the licensee's processing, packaging, transfer, and transport of low-level radioactive waste materials in response to IE Bulletin 79-19.
3.
Regulations and Licenses The inspector verified that the licensee possessed copies of current requirements of the commercial burial sites and copies of the current Department of Transpor*.ation and Nuclear Regulatory Commission (NRC)
regulations for the transfer, packaging, and transport of radioactive material. Methods for maintaining these documents current had been established by the licensee.
4.
Designation of Responsibilities LACBWR Administrative Control Procedure 14.0 delineates responsi-bilities fer the transfer, packaging, and transport of radioactive waste material. Certain responsibility definitions regarding these activities are also found in LACBWR Health and Safety Department Procedures 4.1 and 4.3.
According to the Health and Safety Super-viscr, a memo would be prepared requiring the Health and Safety Super-visor to personally authorize the final release of all radioactive waste shipments. No problems were noted regarding impleme;tation of assigned responsibilities.
5.
Procedures and Check Lists The inspector selectively reviewed the following procedures related to the transfer, packaging, and transport of radioactive waste material.
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ACP 14.0 (3/79)
Handling, Storage, and Shipping WCT 5.4.29 (4/76)
Procedure for Changing and Shipping Spent Resin Liners HSP 4.1 (8/79)
Radioactive Material Shipments HSP 4.3 (9/78)
Solid Waste Disposal HSP 4.4 (8/79)
Sampling of Spent Resin Liner No discrepancies from the procedure review and approval format speci-fied in Section 3.8 of the Technical Specifications were noted.
Several comments on the procedures, in particular HSP 4.1 and HSP 4.3, were provided by the inspector for licensee consideration during future procedural revisions. The revised procedures will be reviewed during a future inspection.
i 6.
Training
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The inspector reviewed the training of personnel involved in the pro-cessing, packaging, transfer, and transport of radioactive waste materials. Although training programs are not finalized in these areas, limited training has been provided radiation protection, operat-ing, and guardforce personnel. A recently revised training program will be implemented in the near future. This matter will be reviewed further during a future inspection.
7.
Audits The inspector reviewed the licensee's audit activities regarding low-level radioactive waste transfer, packaging, and transport activities.
These areas were audited in October 1979 and are scheduled for future biennial audits. The October 1979 audit included examination of Items 1-6 of IE Bulletin 79-19.
Three items remained open from the October audit.
The open items pertained to training and retraining activities and criteria for defining resia depletion. The resolution of these items will be reviewed during a future inspection. No significant discrepancies were identified with the audit program.
I 8.
Waste Packaging Systems and Procedures The licensee does not have installed equipment for solidification of radwaste. Spent resins are shipped dewatered. The only other poten-tially liquid radwaste routinely shipped offsite is residue from the liquid radwaste tanks and various plant sumps.
Periodic cleaning of the tanks and sumps produces the residue, which is removed as a wet sludge and allowed to dry by evaporation before shipment offsite. On occasion, 55-gallon drums are hand mixed with concrete for shipment of radwaste items which require additional shielding. A conventional compactor is used for compactible DAW.
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I 9.
Radwaste Package Examination
, A 55-gallon drum containing noncompactible radwaste awaiting shipment was selected by the inspector. The drum top was removed and the con-tents examined. No liquid was observed; the drum contents were as described in the licensee's records.
10.
Radioactive Waste Shipments The licensee shipped two radwaste shipments during 1979. One ship-ment contained approximately 40 curies of dewatered resin. The other shipment contained approximately 80 curies of dewatered resin and dried sludge. Neither shipment was observed by the inspector.
Both shipments were made in casks approved by NRC certificates of compliance. The licensee was cautioned to ensure that future de-watered shipments could be demonstrated to meet the allowable free water restrictions of the applicable burial site.
11.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection on December 28, 1979. The inspector summarized the scope and findings of the inspection.
In response to certain items discussed by the inspector, the licensee:
Stated that the Health and Safety Supervisor's responsibility a.
for authorizing release of radwaste shipments from the site would be clarified and documented. (Paragraph 4)
b.
Stated that procedures HSP 4.1 and HSP 4.3 would be reviewed and revised as necessary. (Paragraph 5)
c.
Acknowledged the inspector's comments regarding confirmation of the free water content of future dewatered radwaste shipments.
(Paragraph 10)
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