ML20114D685

Forwards Tritium Leach Test on H-327 Graphite. Rept Concludes That Less than 0.1% of Tritium Content Released from Each Reflector Block in 30-day Interval

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: ML20114D685 ML20114D687
References
P-92273, NUDOCS 9209090259
Download: ML20114D685 (2)

Text

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g-9 45 Public Service, Public Service i c - ,...c-i 4-

/ 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 u -residedwin the reactorfcore-for;its; entire. operating life of1890 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 i rradiatedL graphite ' from a British Magnox reactor, as reported in the referenced letter.

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- 9209090259 920901 5 R

PDR1 ADOCK 05000267, P- -PDR JfO

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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

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