ML19312C142
| ML19312C142 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/30/1976 |
| From: | Parker W DUKE POWER CO. |
| To: | Rusche B Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7912060707 | |
| Download: ML19312C142 (5) | |
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DUKE POWER COMPANY Powen Buttatso 422 SouTa Cuencu Srazzi, Cuantortz, N. C. 2824a wl LLI AM O. PA R M E R. J R.
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Mr. Benard C. Rusche iU' a
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Director of Nuclear Reactor Regulation
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U. S. Nuclear Regulatory Commission nC/ \\
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Washington, D. C.
20555 Attention:
Mr. A. Schwencer, Chief Operating Reactors Branch #1 Re: Oconee Nuclear Station Docket Nos. 50-269, -270, -287
Dear Mr. Rusche:
In response to a May 18, 1976 meeting with the NRC staff at Oconee Nuclear Station concerning the Permanent Waste Management Facility, the attached supplemental information is provided.
Ver truly yours, l
Q M. N l.b.
William O. Parker, Jr Q MST:vr Attachment i
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7912060707
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REQUEST FOR ADDITIONAL INFORMATION CONCERNING THE OCONEE NUCLEAR STATION 1.
Question Provide a summary of the liquid discharged from the Oconee Nuclear Station during 1975 and 1976.
This should specifically include the laundry, con-densate monitor and condensate test tanks.
RESPONSE
A tabulation of liquid waste released during 1975 is provided below:
6 Total processed waste 5.76 x 10 gal.
j 6
Powdex system waste water 1.83 x 10 gal.
Quench tank recirculation 1.43 x 10 gal.
i line leak, (see A0 270/75-19) 6 Spent fuel pool, Unit 3 1.86 x 10 gal.
From January 1, 1976 to April 30, 1976, the following information is provided concerning the releases from various station tanks:
Condensata Monitor Tanks 792,059 gal.
Condensate Test Tanks 432,302 gal.
Laundry and Hot Shower Tanks 265,284 gal.
2.
Question Discuss the necessity for the monitoring of the Permanent kaste Manage-ment Facility Building for I-131 and particulate affluents.
RESPONSE
l The radiation monitor currently installed in the PWMF building samples the building exhaust for gaseous activity primarily for the detection of activity leakage within the facility. All potential sources of activity are connected to the vent header and the PWMF building is not a release j
point for liquid or gaseous activity.
However, since the possibility exists for the release of a small amount of activity during certain main-tenance activities, radiation monitors will be installed which will be capable of detecting I-131 and particulate effluents.
3.
Question Provide a statement of the expected availability of the new 15 gpm waste evaporator.
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RESPONSE
Based upon experience which has been gained in the utilization of the 15 gpm evaporator, it is expected that availability in excess of 75 percent will be achieved.
4.
Question Discuss the methods to be used to replace the evaporator feed filters and maintain exposures as low as reasonably achievable (ALARA).
RESPONSE
The methods currently in use for replacement of the evaporator feed filters has consisted of manual removal techniques using remote tools. To date, the relatively low activity of the filters and the short exposure times have limited exposures to 40 mR during the last filter change.
In order to assess the exposure impact of high level filters, an analysis was performed which assumed a level of 50 R/hr at contact with the filter housing.
This analysis considered three alternatives; (1) use of the existing procedure, (2) elimination of certain tasks in the present procedure, and (3) the use of remote tools and a specially designed shielded disposable cask.
It has been determined (alternative (2) preceding) that a significant reduction can be affected through the use of a disposable filter hold-down spring which will minimize exposure time.
It is expected that six filter replacements per year, with this highly activated filter and using this procedure, will result in a total dose annual commitment of 2.8 rem.
Although further reductions in dose commitment could be achieved through the use of a specially-designed shielded, disposable cask, the existing facility design is not compatible with the use of this cask.
Modifications to the present facility to permit the use of this cask cannot now be cost justified for the reduction in exposure due to the extent of modifications-which would be required.
5.
Question Discuss the solid waste handling facility design in terms of achieving personnel exposures as low as reasonably achievable.
RESPONSE
A review of the solid waste handling system is currently in progress to determine what additional measures might be taken to improve the opera-bility of the prasent system and to obtain personnel exposures which are as low as reasonably achievable.
This review is expected to require several-months for completion. Further information concerning the solid waste system will be transmitted at that time.
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6.
Question Describe the hydrogen and oxygen monitoring instrumentation which will monitor the radwaste system for potentially explosive gas mixtures.
RESPONSE
A hydrogen, oxygen monitor is currently installed in the Oconee 3 radwaste system.
This monitor is of the sequential sampler type which takes a six-minute sample on various locations within the radwaste system. The monitor alarms on either high hydrogen or oxygen levels of 3 percent.
A redundant hydrogen and oxygen monitor will be installed which will be dedicated to monitoring of the waste gas header.
Since all liquid tanks in the PWMF are vented to the waste gas header and the PWMF waste gas decay tanks are filled from this header, it is considered that this new monitor in combination with the existing sequential monitor will detect any potentially explosive gas mixture.
7.
Question Provide a preliminary schedule for completion of the remaining modifications.
RESPONSE
It is preliminarily estimated that completion of those items necessary to convert the Interim Waste Management Facility to the Permanent Waste Management Facility would require approximately one year for engineering and an additional two years for equipment procurement and installation.
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