IR 05000335/1983021
| ML20024F435 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 06/16/1983 |
| From: | Barr K, Wray J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20024F432 | List: |
| References | |
| 50-335-83-21, 50-389-83-45, NUDOCS 8309090381 | |
| Download: ML20024F435 (5) | |
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NUCLEAR REGULATORY COMMISSION
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101 MARIETTA ST N.W SUITE 3100 Y
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Report No: 50-335/83-21 and 50-389/83-45 Licensee:
Florida Power and Light Company 9250 West Flagler Street Miami, FL 33101 Docket Nos: 50-335 and 50-389 License Nos: DPR-67 and NPF-16 Facility Name: St. Lucie Units 1 and 2 Inspection at St. Lucie site near Ft. Pierce, Florida Inspector:
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K. P. Barr, Section Chief D' ate $igned Operational Programs Branch Division of Engineering and Operational Programs SUMMARY Inspection on May 16 - 18, 1983 Areas Inspected This routine, unannounced inspection involved 20 inspector-hours on site in the areas of transportation of radwaste, radiological controls for thermal shield cutting, and licensee action on inspector identified items for Unit 2.
Results Of the three creas inspected, one violation was identified in one area (consigning radioactive material to a person for land burial containing liquid
- who was not authorized to receive liquids.)
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I 8309090381 830825 PDR ADOCK 05000335
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- J. H. Barrow,.0perations Superintendent
- H. F. Buchanan, Health Physics Supervisor R. J. Frechette, Chemistry Supervisor
- H. M. Mercer, Health Physics - Unit 2 Coordinator
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R. M. McCullers, HP Operations Supervisor B. W. Kelsey, Chemistry D. H. Faulkner, Chemistry M. R. Olin, Health Physics A. Gould, Health Physics (Corporate)
NRC Resident Inspector S. Elrod, Senior Resident Inspector H. Bibb, Resident Inspector
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on May 18, 1983, with those persons indicated in paragraph 1 above. On June 9,1983, the licensee was informed by telephone that transfer of LSA radioactive material for burial containing liquid in violation of Chem-Nuclear's burial license is a violation of 10 CFR 20.301 as it relates to Part 30.
3.
Licensee Action on Previous Enforcement Matters Not inspected.
4.
Unresolved Items No unresolved items were identified during this inspection.
5.
Transporation of Radwaste On April 19, 1983, a shipment of Low Specific Activity (LSA) compacted trash was made by the -licensee to the Barnwell low level burial site.
The shipment consisted of twelve strong-tight metal boxes containing 1.9 curies total activity-(principal isotopes were Co-60, Co-58, Cs-137 and Cs-134).
-Licensee records-indicate that the vehicle was properly placarded and that radiation levels did not exceed regulatory limit _
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Upon arrival, the licensee was informed that approximately 20 milliliters of liquid was discovered in one of five boxes tested by puncturing holes in their bottom. The highest concentration was Co-60 at 1.14E-03 pci/ml. The State of South Carolina issued a notice of violation for noncompliance with Criteria 26 of the Barnswell site criteria which states that no liquid is permissible in this type of waste shipment.
The licensee was fined 51000 for this event.
During a meeting between the licensee and officials from the State of South Carolina, significance of the event and corrective measures were discussed.
It appears that condensation may be the cause of the liquid being present in the box upon receipt.
Corrective measures include use of additional absorbant material (i.e., speedy-dry, vermiculite) to control condensation.
Historically, the radwaste program at the site has been adequate. Based on this meeting, responsiveness of the licensee, and radiological significance of the event, the State of South Carolina reduced the fine to $500.
The inspector informed licensee representatives that transfer of material to a recipient not authorized to receive it appears to L^ a violation of 10 CFR 30.41(a) (335/83-21-01).
6.
Radiological Controls for Thermal Shield Cut The inspector reviewed the preparation for the thermal shield cut with regard to radiological controls. Advanced planning included trips to the NSSS vendor's site to observe practice cuts.
Based on these preplanning trips, the licensee's health physics organization identified the following potential problem areas associated with the job:
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Potential airborne via bubbles from the plasma torch 2)
Plate-out on cutting equipment of high activity partic'es after cuts 3)
High ri diation levels at pool surface due to irradi rted slag brought to surface
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Plate-at of highly irradiated material on pool side s faces 5)
Need i r effective vacuum systems and procedures for handi og spent filters 6)
Decont imination of equipment 7)
Waste disposal The inspector verified that these concerns have been addressed and observed during tours of the Unit 1 Containment Building that corrective actions have been initiated.
The licensee has designed a gas collection system to collect bubbles from the plasma torch process at the pool surface. A hydrolazer will be positioned at the cavity edge for decontamination of equipment when lifting out of the pool is done. Provisions have been made to prevent slag from coming to the pool surface. Tents have been installed to prevent plate-out on pool side surfaces and on the Core Support Barrel, upper guide structure, and the thermal shield work platform.
Larger capacity under water vacuum systems have been purchased with filters that are easily manipulated underwater.
A large amount of strippable coating decontamination material is available for deconning equipment. The licensee
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is negotiating with a contractor (Chem-nuclear) for disposal of the thermal shield pieces at the Barnwell burial facility so that long term storage in spent fuel racks will not be required.
The inspector concluded based on discussion with licensee representatives and tours of the thermal shield cut area that adequate radiological controls are in effect and that adequate preplanning has taken place.
7.
Licensee Action on Previous Identified Items - Unit 2 (Closed)(389/82-72-01) Completion of Fe-55, Sr-89/90 Radiochemical Analysis Procedures. The inspector reviewed the contract which the licensee has made with Science Application, Inc. (SAI) to perform Fe-55, Sr-89/90 and other radiochemical analyses. A licensee representative stated that SAI is on the station's approved QA vendor list following an audit of the company by the licensee.
The inspector concluded that adequate analyses for Fe-55 and Sr-89/90 are afforded and had no further questions.
(Closed)(389/82-70-02) Review Shielding Adequacy of CVCS Letdown Monitor Sample Lines.
The inspector observed lead and steel shielding constructed around the letdown sample lines as they penetrate the floor in the 43 foot elevation of the Unit 2 Reactor Auxiliary Building.
In addition, a cognizant licensee representative stated that the monitor will not be routinely used and is valved out of service. The inspector concluded that the added shielding appeared to satisfy the requirements and stated that valving the monitor out of service appears to provide assurance that dose rates from the overheads on that elevation do not become excessive.
The inspector had no further questions.
(Closed)(389/82-72-03) Modification of particulate sampling collection on plant vent so isotopic analysis can be performed.
Plant vent monitors RS-26-13 and RS-26-14 have moving filter paper particulate detection. Plant vent monitor RS-26-90 uses a fixed particulate filter and charcoal cartridge sampling orientation. Effluent accountability is provided for particulates by RS-26-90. The inspector identified no concerns with this practice. To l
ensure that particulate effluent accountability can also be performed on particulate samples from monitors RS-26-13 and RS-26-14, the licensee has
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initiated a design change request to modify the monitors to have the equivalent sampling capability as RS-26-90.
A cognizant licensee representative stated that this change for both plant vent monitors (RS-26-13; RS-26-14) and the Fuel Building effluent monitor (RS-26-12) will be completed prior to first refueling.
In the interim, the licensee has provided procedure controls and corrections for RS-26-12, RS-26-13, and RS-26-14. The licensee has fixed the particulate filter media in place and procedurally modifies the analysis results to account for geometry varia-tions on the GeLi system.
The inspector reviewed CD-SPP-3, "Special Effluent Sampling and Effluent Accounting Technique" and identified no problems.
The inspector concluded based on discussions with licensee representatives, review of procedures, and equipment inspections, that adequate accountability of effluents from the plant vent is afforded by the capabilities of RS-26-90 and the procedural controls of CD-SPP-3 for monitors RS-26-12, RS-26-13, and RS-26-14.
The inspector had no further questions.
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(0pw)(389/82-75-07) Fume Hood Face Velocities. The inspector conducted an in.n endent test of chemistry laboratory exhaust hood face velocities using ar. NRC thermo anemometer.
The results on the two hoods in the hot leoratory and the hood in the sample room indicated that face velocities dveraged less than 100 linear feet per minute (the industry standard) when the hood door is full open.
If the doors are partially closed, the face velocities more nearly approach the standard.
The licensee stated that ventilation system damper modification may be possible which would result in accepted face velocities across the hood. The licensee will investigate the possibility of modifying' ventilation dampers or decide on permanently restricting hood door openings. This item will remain open pending licensee action.
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