ML20114D685
| ML20114D685 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 09/01/1992 |
| From: | Warembourg D PUBLIC SERVICE CO. OF COLORADO |
| To: | Weiss S NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20114D686 | List: |
| References | |
| P-92273, NUDOCS 9209090259 | |
| Download: ML20114D685 (2) | |
Text
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- g-9 45 Public Service Public Service, c -,...c-i 4-i
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P.O. Box 840 16805 WCR 19-1/2 Platteville, CO.
80651 September'1, 1992 Fort St. Vrain
- Unit No. 1
~P-92273 U.S.-Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C.-
-20555 ATTN:
Dr. Seymour H. Weiss, Director Non-Power Reactor, Decommissioning and Environmental Project Directorate DOCKET NO:-50-267-
SUBJECT:
- Tritium Leach Test on Irradiated Graphite Reflector
-Blocks from the Fort St. Vrain Reactor Core
REFERENCE:
PSC Letter, Brey to Weiss,- dated
.: October 10, 1991 (P-91299)
DearJDr.-% iss:
Nblic : Service Company _ of ; Colorado (PSC) contracted with Babcock and Wilcox: _(B&W): to-perform L a-leach test on - two replaceab'.e
, graphite hexagonal reflector blocks:from the Fort St. Vrain reactor core.
Both of these reflector ' blocks are ' composed. of H-327
= graphite, a relativelyyhigh purity grade'of nuclear graphite, and
-residedwin the reactorfcore-for;its; entire. operating life of1890 u
effective full-- power-days.
B&W analyzed graphite samples-from the blocks' to characterize them prior to immersion in deionized water.
B&W. then c analyzed water r samples taken at' = regular intervalc to
_ determine activity; concentration's'in'the water.
The-attached #eportidescribes the-leach test and summarizes the-results'of this test'for. tritium, the nuclide of primary concern,-
L over a:30-day intervali The. report concludes that less.than 0.1%
!of<the-tritium-' content was' released-from each reflector b1ock in a
the day finterval..
-This 1s.'significantly below the 0.44%
cmulativeitritiam leach -fraction at 30 -days observed in the test L
--involving f rradiatedL graphite ' from a British Magnox reactor, as i
reported in the referenced letter.
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Ceptember 1, 1992 Fort St. Vrain
. Unit No. 1 P-92273 Page 2 of 2 Should you have any questions on the attached report, please contact Mr. M. H. Holmes at (303) 620-1701.
Sincerely,
+wtt0 7Y /YNuw/,
Donald W. Warembourg Manager, Nuclear Operations DWW/JRJ:dh Attachment cc:
-Regional Administrator, Region IV Mr. J.
B.
Baird Senior Resident Inspector Fort St. Vrain Mr. Robert M. Quillin, Director Radiation Control Division Colorado Department of Health i
I L
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