ML20137Z326
| ML20137Z326 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 09/25/1985 |
| From: | Gahm J PUBLIC SERVICE CO. OF COLORADO |
| To: | Hunter D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| P-85339, NUDOCS 8510080219 | |
| Download: ML20137Z326 (2) | |
Text
.
4 Public Service-
.. s.,*. -
Company of Colorado 16805 WCR 19 1/2, Platteville, Colorado 80651 September 25, 1985 Fort St. Vrain Unit No. 1 P-85339 Regional Administrator Region IV SEP 3 01985 U. S. Nuclear Regulatory Cor ission l
611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011
=
Attn: Mr. Darwin Hunter Docket No. 50-267
SUBJECT:
Beta Radiation in FSV Radioactive Liquid Effluent
REFERENCE:
- 1) PSC Letter, Gahm to Johnson, dated 6/17/85 (P-85212)
- 2) NRC Letter, Johnson to Lee, dated 7/9/85 (G-85265)
Dear Mr. Hunter:
This letter is to inform you of our current status and future plans in regard to addressing the NRC concerns over beta radiation in Fort St. Vrain (rSV) radioactive liquid effluents.
In Reference 1, PSC described our experience with a beta liquid monitor currently being utilized in the biomedical industry.
PSC has completed an evaluation of this monitor and have concluded that, in principle, the monitor could be applied at FSV to evaluate discharges from the Reactor Building Sump. The major drawback to the use of this technology is the fact that the quality of the water monitored must be increased to prevent fouling of the flow cell portion of the monitor. This would mean that all of the Reactor Building Sump f
discharges would have to be filtered prior to being monitored and fi released.
g f) g
[ }p '-(j \\
es10000219 e50925 y
ADOM 05W2#
~
m egg )
p E
(0 i o F
o' In light of the uncertainties inherent in the application of this new technology to FSV, PSC proposes to install a filtration system and a beta monitor on the discharge from the Reactor Building Sump on a trial basis.
During this trial period, the monitor would be installed with a local alarm and rate meter to evaluate instrument performance and feasibility.
No automatic functions would be included.
PSC would be able to install a filtration system and a beta monitor within 60 days of receiving a favorable response from the NRC, and a six month trial period would be adequate to fully evaluate the feasibility of permanently installing a beta monitor with remote alarm and automatic isolation functions. During the trial period, PSC would continue the batch release and 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> sampling program currently in effect (Reference 2).
In parallel with the above proposed action plan, PSC is continuing to evaluate the effectiveness of our Reactor Building Sump drain mapping and id0ntification program in providing assurance that 10CFR20 limits will not be exceeded for beta emitting radionuclides discharged from the Reac'.or Building Sump.
PSC believes that the parallel approach as outlined above will allow us the opportunity to fully evaluate the feasibility of applying state of the art beta monitoring systems at the Fort St. Vrain Nuclear Generating Station while continuing to provide assurance that 10CFR20 limits will not be exceeded for liquid releases from the Reactor Building Sump. Upon receiving a favorable response from the NRC, PSC will implement our proposed action plan and provide you quarterly reports on our progress.
Place contact Mr. M. H. Holmes at (303) 571-8409 if you have any questions on this matter.
Sincerely,
/ d fs % 2 9 a.
/
c
' d. W. Gahm Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station JWG:FJB/dje
-