ML20077P917
| ML20077P917 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 08/15/1991 |
| From: | Crawford A PUBLIC SERVICE CO. OF COLORADO |
| To: | Weiss S NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20077P923 | List: |
| References | |
| P-91265, NUDOCS 9108200132 | |
| Download: ML20077P917 (2) | |
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P.O. Bon 840 Denver CO 80201 o840 A. Clegg Crawfoid Vice P#esident Nuclear Optotons August 15, 1991 Fort St. Vrain Unit No. 1 P-91265 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:
VERIFICATION OF FSV ACTIVATION ANALYSIS
REFERENCE:
PSC Letter, Crawford to Weiss, dated April 15, 1991 (P-91137)
Dear Dr. Weiss:
Attached is the final report of Public Service Company of Colorado's (PSC's) actions to verify the Fort St.
Vrain (FSV) Prestressed Concrete Reactor Vessel (PCRV) activation analysis.
The activation analysis provided the basis for decommissioning cost estimates-for concrete removal and disposal during PCRV dismantlement.
In the referenced letter, PSC provided _an interim report on the activation analysis verification efforts. At that time, activities were in progress to obtain independent confirmatory laboratory analyses of the activity levels in various material samples, and to analyze concrete impurity samples from various PCRV surface locations.
These analyses were performed to confirm the validity of the assumed neutron-flux levels and material compositions.
As stated in the attached report, all analyses have now been completed.
The results confirm that the original analytical methods and assumptions are_quite reasonable, and that the previous estimates of the. amount of concrete that must be removed were conservative.
Even allowing for the worst case variations in activity levels described in the attached report, PSC's plans to remove between 27 inches and 32 inches of PCRV concrete, as identified in Section 2.3.3.12 of the Proposed Decommissioning
- Plan, will ensure satisfsetion of the 5 microR/hr at 1 meter release criterion.
9108200132 910915
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P-91265 Page 2 August 15, 1991 If you have any questions regarding PSC's verification of the FSV activation analysis, please contact Mr.
M.
H.
Holmes at (303) 480-6960.
Very truly yours, hjp j
a A. Clegg Crawford Vice President
- Nuclear Operations ACC/SWC/1mg Attachment cc:
Regional Administrator, Region IV Mr. J. B. Baird Senior Resident inspector Fort St. Vrain Mr. Robert M.-Qu1111n, Director Radiological Control Division Colorado Department of Health t
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