IR 05000010/1979020
| ML19262A654 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 10/23/1979 |
| From: | Fisher W, Hiatt J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19262A653 | List: |
| References | |
| 50-010-79-20, 50-10-79-20, NUDOCS 7912070270 | |
| Download: ML19262A654 (3) | |
Text
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPEr
" AND ENFORCEMENT
REGION III
Report No. 50-010/79-20
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Docket No.50-010 License No. DPR-2 Licensee:
Commonwealth Edison Company P. O. Box 767 Chicago, IL 60690 Facility Name:
Dresden Nuclear Power Station, Unit 1 Inspection At:
Dresden Site, Morris, Illinois Inspection Conducted: October 16, 1979 (M1 Inspector:b.W.Hiatt
/C 3/77
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T Approved By:
W. L.' Fisher, Chief
/6/23[77 Fuel Facility Projects and Radiation Support Section Inspection Summary Inspection on October 16, 1979 (Report No. 50-010/79-20)
Areas Inspected: Routine, announced inspection of radwaste management and radiation protection program for the Unit I decontamination.
The inspection involved four inspector-hours onsite by one NRC inspector.
Results: No items of noncompliance were identified.
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DZTAILS
_hf 1.
Persons Contacted T. Gillman, Health Physicist
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J. Harrison, Engineer F. Jones, Health Physicist
- J. Parry, Radiation Che'nistry Supervisor
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eDenotes those present at the exit interview.
2.
General This inspection, which began at 8:30 a.m. on October 16, 1979, was conducted to examine the licensee's radiation protection and radwaste management program for the chemical decontamination of Unit 1.
The inspector, accompanied by licenset personnel, toured the chemical cleaning building (CCB).
Except for an item regarding potential radiation problemyj)in the truck loading bay (discussed in a previous inspection report--
no problems were noted.
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3.
Radiation Protection Program The licensee does not plan any staffing increases or organizational changes to cover the chemical cleaning of Unit 1.
Contract techni-cians will be used if additional manpower is needed.
Dow Chemical will provide their own health physicists, who will perform indepen-dent sampling ano surveys. However, overall health physics control will be maintained by the licensee.
Most health physics coverage is detailed in the licensee's existing radiation protection procedures.
During the actual running of the solvent through the primary system, the entire sphere will be considered a high radiation area.
Any individual entering the sphere (for sample collection, routine observation, etc.) will be accompanied by a rad-chem technician.
The licensee continues to develop procedures for calculating the curie content of Dow solidifi-cation drums, collecting samples from the chemical cleaning building (CCB) stack, and surveying the CCB.
Before the chemical cleaning, the licensee plans to adjust the alarm setpoints of area radiation monitors in the sphere (setpoints will be increased in anticipation of high radiation levels during the solvent flushing), to check status high of radiation doors in the CCB, and to calibrate the ventilation, area radiation, and service water monitors in the CCB.
These items will be reviewed during future inspections.
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IE Inspections Reports No. 50-010/79-15, 50-237/79-19, and 50-249/79-17.
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Solvent leaks into the sphere will be detected by either dew point recorders (small leaks), conductivity probes in twenty selected
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floor drains, or level indicators in the steam drum and reactor enclosure drain tank.
The licensee plans to " bag" motor operated valves and direct any leakage into floor drains.
A heat exchanger located on the north cnd of the sphere at the 517'
level (ground level) will be used to heat the solvent.
Because high radiation levels are anticipated, the licensee plans to build
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a shield wall (probably using Unit 1 shield blocks) about six to
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seven feet high and 100 feet long around the northern periphery of the sphere.
As of October 1979 about 100 man-rems (about 20% of the licensee's dose commitment) have been received during preparatory work for the decontamination.
Pipefitters, who were making connections between the primary svstem and CCB, received about 85% of this dose.
4.
Radiation Mo titors
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None of the area, continuous air, or process radiation monitors planned for the CCB had been installed at the time of the inspection.
Four area radiation monitors (ARM's) will be installed on the first floor, three on the second floor, two on the third floor, and three in the waste solidification area.
The monitors will have readouts and audible alarms locally and at the CCB control panel.
There will be nine continuous air monitors (CAM's) at selected areas of greatest airborne potential in the CCB.
Each monitor will record and alarm in the control room.
The CCB's exhaust stack will be isokinetically sampled and monitored for noble gas, iodine, and particulate activity.
Service water (used for cooling evaporators, air compressors, etc.) will be sampled by an offline monitor.
Status and calibration of the above monitors will be reviewed during future inspections.
5.
Exit Interview The inspector met with Mr. Parry Ot the conclusion of the inspection and discussed the scope and findinga of the inspection.
The inspector stated that the status of process, continuous air, and area radiation monitors would be reviewed during future inspections.
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