IR 05000286/1983008
| ML20023E038 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 05/20/1983 |
| From: | Clemons P, Mcbride M, Shanbaky M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20023E034 | List: |
| References | |
| 50-286-83-08, 50-286-83-8, IEB-79-19, NUDOCS 8306060267 | |
| Download: ML20023E038 (5) | |
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U. S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No. 50-286/83-08 Docket No. 50-286 License No. DPR-64 Priority
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Category C
Licensee: Power Authority of the State of New York P. O. Box 215 Buchanan, New York 10511 Facility Name: Indian Point 3 Nuclear Power Plant Inspection At: Buchanan, N. Y.
Inspection Conducted:
April 12-15, 1983
_ /a/9$r Inspectors:
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'P. Clemons, Radiation Specialist
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$ 2/' S M. McBride, Radiafion Specialist
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dite Approved by:
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5'/2d f/'s M. Shanbaky, Chief, TacilKies Radiation da'te'
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Protection Section, Radiation Protection Branch Inspection Summary:
Inspection on April 12-15, 1983 (Report No. 50-286/83-08)
Areas Inspected:
Routine, unannounced safety inspection of transportation activities including: previously identified items, package selection, proce-dures, training, audits, transuranic determinations and the Girth Weld ALARA considerations. The inspection involved approximately 70 hours8.101852e-4 days <br />0.0194 hours <br />1.157407e-4 weeks <br />2.6635e-5 months <br /> onsite by two regionally based inspectors.
Results: No violations were identified.
@306060267 830523 DRADOCK05000g
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DETAILS 1.
Persons Contacted Licensee Personnel J. Brons, Resident Manager W. Josiger, Superintendent of Power J. Russell, Superintendent of Power J. Perrotta, Radiation and Environmental Services Superintendent D. Halama, Quality Assurance Superintendent D. Quinn, Senior Radiological Engineer J. Cirilli, Quality Assurance Supervisor R. Deschamps, General Health Physics Supervisor W. Greenman, Radwaste Supervisor J. Gillen, General Chemistry Coordinator J. Schivera, Licensing Coordinator NRC Personnel T. Kenny, Senior Resident Inspector M. McBride, Radiation Specialist L. Rossback, Resident Inspector Other licensee employees were also interviewed during this inspection.
2.
Purpose The purpose of this routine inspection was to review the licensee's transportation program with respect to the following elements:
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Transportation of radioactive material;
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Training in transportation activities;
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Status of previously identified items;
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Review of package selection;
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Review of procedures associated with transportation activities; Review of audits;
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Review of transuranic determinations; and s
Review of Girth Weld ALARA considerations.
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Status of Previously Identified Items
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(Closed ) Inspector Followup Item (82-06-01) Review Dosimetry discrepancy
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evaluations from October 1, 1981 on for possible overe190su'res. Dosi-
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metry discrepancy evaluations were reviewed for the period October 1, 1981 - April 5,1982. There were no overexposures for the period review-ed.
(Closed) Violation (83-01-01) Radiation Exposure Authorization (REA) was not posted at the Contractor Control Point Sign-In Area. Two revised procedures were reviewed to assure that the corrective action stated in the licensee's letter dated March 22, 1983 had been implemented. The procedures had been revised as stated, and they appeared to be adequate.
4.
Training Training records of ten licensee employee's were reviewed to determine compliance with the licensee's commitment to IE Bulletin No. 79-19,
" Packaging Of Low-Level Radioactive Waste For Transport and Burial." The records indicated that the selected employees had received training, and also had successfully completed an examination.
Within the scope of this review, no violations were identified.
5.
Procedure Review and Implementation The adequacy and effectiveness of the licensee's procedures were reviewed against the criteria contained in Technical Specification 6.8, "Proce-dures."
The licensee's performance relative to the criteria was determined from discussion with the Radwaste Supervisor.
Procedures reviewed included:
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"Demineralizer Liquid Waste Processing System", Procedure No.
HPI-12.3, Revision 6;
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" Radioactive Waste Handling and Packaging", Procedure No. HPI-9.20, Revision 1;
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" Transportation of Radioactive Material", Procedure No. HPP-9.2;
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" Handling Procedures for Cask AL-33-170", Procedure No. HPI-910; and
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"HN-100S Shielded Transport Cask Handling", Procedure No. HPI-9.14.
Within the scope of this review, no violations were identified.
6.
Transportation of Radioactive Material The licensee's program for the shipment of radioactive material for burial was examined against the requirements of 10 CFR 71 and 49 CFR 173.
Records of those shipments made on July 9, 1982, August 22, 1982, and
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November 24, 1982, were examined to determine if the reguletions were
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complied with. The shipments chosen for review contained greater than Type A quantities of radioactive material.
Within the scope of the review, no violations were identified.
7.
Package Selection The licensee's program for selection of packages was reviewed against the requirements of 10 CFR 71.12. The licensee's records for procurement of a package were reviewed inasmuch as the licensee had purchased a NRC certified package.
The licensee did not have drawings of the package at the time of the inspection, but a Quality Assurance Engineer stated that at one time he had the drawings in his possession because he was the person responsible for following the package as it was being fabricated. The licensee called the company that fabricated the package and requested co;,ies of the drawings.
Within the scope of this inspection, no violations were identified.
8.
Review of Transuranic Determinations Thelicbnseeseffortsindeterminingthetransuraniccontentinshipments was reviewed against the criteria contained in 10 CFR 30.41, " Transfer of by?roduct material." The licensee's performance relative to the criteria was determined by discussions with the Senior Radiological Engineer.
Within the scope of this review no violations were identified, but it was noted that no transuranic determinations had been made for the three shipments referenced in The licensee indicated that the transuranic content of waste shipments had been evaluated in the past, but the evaluations were not documented.
The licensee evaluated three 1982 waste shipments during the inspection and confirmed that those shipments did not contain transuranic levels above the burial site limits of 10 nC1/g. The licensee stated that the transuranic evaluations would be formalized and documented.
This item will remain as an unresolved item, and will be inspected during a subse-quent shipment (83-08-01).
9.
Audits of Transportation Packages The licensee's efforts in auditing the transportation activity were reviewed against the criteria contained in Appendix B, 10 CFR 50. The licensee's performance relative to the criteria was determined by discus-sion with the Quality Assurance Superintendent and the Quality Assurance Supervisor, and by reviewing a report of an audit conducted during August-September 1981.
The audit report was issued on January 6, 1982 and it contained items requiring corrective action.
Within the scope of this inspection, no violations were identified, but it was noted that the licensee's followup action on the identified items
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was not timely. The Quality Assurance Supervisor stated that the followup action will be improved. This item will remain as an unresolved item, and will be inspected during a subsequent inspec-tion (83-08-02).
10.
Girth Weld ALARA Review The licensee's efforts in the Girth Weld repair operation were reviewed against the criteria contained in 10 CFR 20.101, " Radiation dose standards for individuals in restricted areas", and the licensee's
" Preliminary Girth Weld Repair ALARA Report". The licensee's performance relative to the criteria was determined by discussion with the Senior Radiological Engineer.and the Radiological Engineer.
The discussion revealed that the Girth Weld repair operation was about eighty percent complete, and as of March 31, 1983, the total man-rem exposure for the operation was eighty-three percent of the estimated total man-rem exposure.
Within the scope of this inspection, no violations were identified.
11.
Exit Interview The inspector met with licensee representatives (denoted in paragraph 1)
at the conclusion of the inspection on April 15, 1983.
The inspector summarized the scope of the inspection and the findings.
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