ML20085N493
| ML20085N493 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 10/28/1983 |
| From: | Borst F PUBLIC SERVICE CO. OF COLORADO |
| To: | Madsen G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-TM P-83352, TAC-44443, NUDOCS 8311110061 | |
| Download: ML20085N493 (2) | |
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16805 WCR 19 1/2, Platteville, Colorado 80651 October 28, 1983 Fort St. Vrain q
Unit #1 P-83352 s
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I Mr. G. L. Madsen l
Chief, Re' actor Project Branch 1 E3lE l
i U.S. Nuclear Regulatory Commission 3
Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011
SUBJECT:
NUREG-0737, Item II. B. 3,
" Post-Accident Sampling System"
Reference:
P-82423, G-83349
Dear Mr. Madsen:
We offer the following comments with respect to the three unresolved criteria as contained in your letter dated September 22, 1983 (G-83349):
Criterion (1)
We stated in our letter P-82423 that we had two gas-driven generators available to provide emergency power for sampling. At the time that letter was written, we were utilizing the generators to obtain air samples in the field, thus the generators were dedicated for that purpose.
Currently we do not use the generators to obtain field air samples, and the generators are not dedicated.
In the event that generators would be required we would be able to obtain generators and collect and analyze air samples within the three-hour time frame.
Criterion (2)
You recommend that Public Service Company of Colorado "...should provide a procedure... to estimate the extent of core damage based on radionuclide concentrations and taking into consideration other physical parameters such as core temperature data.
Guidance
...is attached (Attachment 1)."
Unfortunately guidance was not attached, but was graciously provided by Mr. Phil Wagner on October 17, 1983.
We agree with this recommendation and will develop an appropriate i
procedure. Our estimated completion data is June 1, 1984.
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-g-Criterion (8)
Please note that 'our backup site for sample analyses is Colorado State University, not the University of Colorado as stated in your letter.
Criterion (9)'
You recommend that we
...should provide on site capability to measure these higher activities (in primary coolant samples) by means such as sample dilution of collimation of the sample beam." We agree with this recommendation, and feel that the best approach to this recommendation would be to reduce the volume of the samples sufficiently so that they may be counted in the radiochemistry laboratory. Thus far we have determined that primary coolant sample:
with radiation levels exceeding 1-mR/hr at~ the possibility of making the detector cannot be counted.
We are currently evaluating changes to our sample collection system to accomodate the small (approximately 0.04 scc) sample volume needed.
Our anticipated completion date for this item is June 1, 1984.
Criterion (10)
You recommend that we "... provide additional information on the measurement of coolant activities in the time period beyond the first few hours after the onset of a severe accident." As mentioned under criterion (9), we anticipate that we will be able to reduce the volume of primary coolant samples sufficiently such that even at 24' hours post-shutdown, when the primary coolant activity is maximized, we will be able to collect and analyze the samples on site. Thus samples can be collected at any desired times post-shutdown. We plan no further action on this-criterion.
l Please contact me if you have additional questions on this matter.
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Very truly yours, dLGcfL b&tSD Frederick J. 3orst Radiation Protection Manager I
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