IR 05000247/1986001
| ML20203D791 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 04/11/1986 |
| From: | Clemons P, Pasciak W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20203D781 | List: |
| References | |
| 50-247-86-01-MM, 50-247-86-1-MM, NUDOCS 8604220336 | |
| Download: ML20203D791 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-247/86-01 Docket No.
50-247 License No.
DPR-26 Priority
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Category C
Licensee: Consolidated Edison Company of New York, Inc.
Broadway and Bleakley Avenue Buchanan, New York, 10511 Facility Name:
Indian Point Nuclear Generating Station, Unit 2 Meeting at: NRC Region I, King of Prussia, Pennsylvania Meeting conducted: March 20, 1986 Prepared by:
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Radiation Specialist da{esfgned
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Approved by:
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WLPhstlak,Th'ief, EffluerYts Radiation
'd te/ signed Protection Section Meeting Summary: Management Meeting at NRC Region I, King of Prussia, Pennsylvania on March 20, 1986, to discuss the finding contained in Inspection Report 50-247/86-01. The topic discussed at this meeting was the licensee's assertion that a quality control program to assure compliance with 10 CFR 61.55 and 10 CFR 61.56 was in effect at the time of the inspection on January 6-10, 1986.
The meeting was attended by NRC and licensee management and lasted about 1-1/2 hours.
8604220336 860416 PDR ADOCK 05000247 G
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DETAILS 1.
Participants
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Consolidated Edison Company D. Domey, Director, Quality Assurance and Reliability a
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J. Mills, Manager, Program Development and
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Quality Assurance Engineering H. Sager, Manager, Quality Assurance Engineering M. Blatt, Manager, Regulatory Affairs
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T. Schmeiser, Radwaste Manager M. Spall, Nuclear Analyst-Nuclear Engineering
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Nuclear Regulatory Commission i
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S. Ebneter, Director, Division of Reactor Safety
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R. Bellamy, Chief, Emergency Preparedness and Radiological i
Protection Branch P. Eapen, Chief, Quality Assurance Section
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L. Norrholm, Chief, Reactor Projects, Section 2B
G. Napuda, Lead Reactor Engineer M. Miller, Radiation Specialist
i P. Clemons, Radiation Specialist
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2.
Purpose i
The Management Meeting was held at the request of the licensee to discuss the violation cited in Inspection Report 50-247/86-01.
The discussion at the meeting focused on the licensee's assertion that a quality control program was in ef fect at the time of the inspection on January 6-10, 1986.
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Discussion NRC management stated that this management meeting was requested by
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the licensee to discuss the finding contained in Inspection Report
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50-247/86-01.
The licensee representatives were asked to provide their perceptions of the finding presented in the report, and to provide any
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other supporting information.
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Licensee's Presentation Licensee management emphasized that.they did not agree with the violation
as stated in Appendix A of Inspection Report 50-247/86-01 which was as follows:
10 CFR 20.311(d)(3), " Transfer for disposal and manifests" requires a licensee who transfers radicactive waste to a land disposal J.
facility to conduct a quality control program to assure compliance
with 10 CFR 61.55 and 10 CFR 61.56.
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Contrary to the above, the licensee has transferred radioactive waste shipments composed of dewatered resins, solidified resins, solidified sludges, and filters, to a land disposal facility during 1985 and the
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licensee has not conducted a quality control program to assure that the packages did not contain free standing liquid greater than 1% of the waste volume, that the waste was properly classified, and that the waste was structurally stable for compliance with 10 CFR 61.55 and 10 CFR 61.56.
The licensee's; Director, Quality Assurance and Reliability stated that
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they have always had a quality control program in effect at the Indian Point 2 site.
He also stated that their prime purposa for requesting the meeting was to obtain a clear understanding of the i pection report findings, and to review their implemented quality control program with the NRC.
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Other licensee representatives presented various aspects of the quality
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control program for transport packages as follows:
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NRC original approval of the quality assurance program; 2.
~NRC approval of radwaste quality assurance program;
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Regulatory basis for the Con Edison radwaste quality assurance /
quality control program;
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Con Edison radwaste quality assurance / quality control program; 5.
Program implementation resources; and
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Annual audit program.
In addition, licensee representatives described their performance history for the shipments of radioactive material.
As stated earlier, the licensee did not agree with the violation as stated, but the licensee provided evidence of corrective actions that
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l were being addressed and implemented.
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Concluding Statements Licensee management concluded by stating their belief that the violation, as stated, was not correct.
It is their belief that an approved quality
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program was in effect at the time of the inspection, and the program addressed the specific requirements of 10 CFR 61.55 and 10 CFR 61.56.
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NRC Region I management acknowledged that the violation, as stated, did not accurately reflect our concern. The violation as stated in Appendix A of Inspection Report 50-247/86-01 will be witndrawn, and another violation would be issued that would reflect the existing condition more accurately, that is, the Environmental Health and Safety personnel were not aware that they were performing the quality control function.