IR 05000245/1981017
| ML20041F102 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 02/22/1982 |
| From: | Baer R, Dan Collins, Knapp P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20041F096 | List: |
| References | |
| 50-245-81-17, 50-336-81-16, IEB-80-10, NUDOCS 8203160190 | |
| Download: ML20041F102 (5) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report Nos. 50-245/81-17 50-336/81-16 Docket Nos. 50-245
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50-336 License Nos. DPR-21 DPR-65 Priority
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Category E
Licensee: Northeast Nuclear Energy Company P. O. Box 270 Hartford, Connecticut 06101 Facility Name: Millstone Nuclear Power Station, Units 1 & 2 Inspection at: Waterford, Connecticut Inspection conducted:
December 1 - 4 and 14 - 18, 1981 c9pd7/cS2._.
Inspectors:
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ov R.' E. Baer, Radiation Specialist date signed A
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/f/fh D'l J. Collins, Radiation Specialist date signed e
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Approved
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P. & Kriapp, Chief, FaciV ty date signed Radiological Protection Section, Technical Inspection Branch.
Inspection Summary:
Inspection on December 1 - 4, and 14 - 18, 1981 (Report 50-245/81-17; 50-336/81-16)
Areas inspected:
Inspection of the licensee's response to IE Bulletin 80-10 conducted throughout the period of the inspection in conjunction with routine, unannounced inspection 50-336/81-14. Areas inspected included the review of the facility design and operation; sampling / analysis monitoring
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8203160190 820226 PDR ADDCK 05000245 O
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-program; current status of contaminated non-radioactive systems. The inspection involved 12 inspector hours onsite by two regional-based inspectors.
Results: Of the' three areas inspected, no items of noncompliance were identifled.
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Details 1.
Persons Contacted Mr. A. G. Cheatham, Radiological Services Supervisor I
Mr. E. C. Farrell, Station Services Superintendent
Mr. B. Granados, Health Physics Suparvisor
Mr. J. P. Kangley, Chemistry Supervisor
Mr. J. E. Lane, Health Physicist Mr. R. Robertson, Chemist, Unit 2 l
Mr. S. Scace, Operations Supervisor, Unit 2 Mr. R. Schleicher, Assistant Instrument and Control Supervisor, l
Unit 2 Mr. D. Wilkins, Assistant Chemistry Supervisor, Unit 1 Mr. J. T. Shedlosky, Senior Resident Reactor Inspector, USNRC Mr. D. R. Lipinski, Resident Reactor Inspector, USNRC The inspector also interviewed several other licensee employees, including chemistry technicians and instrumentation and control personnel.
2.
Review of Facility Design and Operation The inspector reviewed the licensee's response to IE Bulletin 80-10.
The response, dated July 3, 1980, transmitted the licensee's review, dated June 10, 1980 for Unit 1, and June 19, 1980 for Unit 2.
These reviews identified those systems that are considered nonradioactive, but could possibly become radioactive, in addition to two systems which had previously become contaminated.
Radioactivity had been detected in both the Unit 1 and Unit 2 auxiliary steam supply systems and the yard drain system. The systems reviewed were as follows:
Unit 1
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House Heating Boiler and (Auxiliary) Steam System
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Auxiliary Evaporator
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Demineralizer Water System Fire Water System
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Domestic Water System
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Station Air System
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Service Water System Reactor Building Closed Cooling Water System
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Emergency Service Water System
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Isolation Condenser Shell
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Yard Drains
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Unit 2 Main Steam System
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Condensate and Feed System Turbine Building Sumps
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Auxiliary Steam / Condensate System
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Reactor Building Closed Cooling Water System l
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Primary Water Makeup Tank
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Instrument / Station Air System l
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Sampling / Analysis or Monitoring Program l
The inspector reviewed the implementation of the routine sampling schedule the licensee had initiated in response to IE Bulletin 80-10.
Samples are taken of systems at varying frequencies, from weekly to semi-annual, depending on the potential for contamination.
Station chemistry procedures have been changed to incorporate the sampling
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frequency for all systems reviewed.
The licensee stated that the lower limit of detectability for liquid systems was less than 1E-5 microcuries per milliliter for tritium, and SE-7 microcuries per milliliter for gross beta gamma activity.
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Current Status of Contaminated Nonradioactive Systems The inspector reviewed the current status of the plant systems. All samples from plant nonradioactive systems indicated no activity above the lower limits of detectability listed above.
The Unit 2 auxiliary steam system reboiler indicated concentrations of contamination in the range of 3.35E-6 to 1.94E-4 on samples taken during November, 1981. Analyses indicate the contamination is comprised of nonvolatile corrosion products.
Unit 1 auxiliary steam system was not in operation and was not being sampled at the time of the inspection. The Unit 1 auxiliary steam system is operated only when the Unit 2 system is not in operation.
Both units are fed into a common steam header pipe and samples are taken from the unit in operation.
The licensee had performed a safety analysis on the two auxiliary steam systems and documented the results in a letter, NEE-80-RA-321, dated June 9, 1980. The licensee stated that, since all release paths from these systems are treated and/or monitored, operation of the auxiliary steam systems with the current contamination levels is not an unmonitored or uncontrolled release path to the environment.
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5.
Exit Interview The inspectors met with the licensee representatives (denoted in para-graph 1) at the conclusion of the inspection on December 17, 1981.
The inspectors summarized the scope of the inspection and the findings.
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