ML20135A586

From kanterella
Jump to navigation Jump to search
Submits Suppl Info Re Annual Environ Rept for 1995 Operation of Fsv ISFSI
ML20135A586
Person / Time
Site: 07200009, Fort Saint Vrain  Xcel Energy icon.png
Issue date: 11/25/1996
From: Borst F
PUBLIC SERVICE CO. OF COLORADO
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
P-96101, NUDOCS 9612030307
Download: ML20135A586 (3)


Text

.

i e rubiicservice'  := =

16805 Weld County Road 19-1/2 Platteville, Colorado 80651 November 25, 1996 Fort St. Vrain ISFSI P-96101 U.S. Nuclear Regulatory Commission Regional Administrator, Region IV 611 Ryan Plaza Drive, Suite 1000 '

Arlington, Texas 76011 Docket No.72-009

SUBJECT:

FORT ST. VRAIN INDEPENDENT SPENT FUEL STORAGE INSTALLATION, 1995 ANNUAL ENVIRONMENTAL REPORT, SUPPLEMENT

REFERENCE:

1. PSCo letter, Borst to Regional Administrator, Region IV, dated February 28, 1996 (P-96012)

Gentlemen:

This letter submits supplemental information for the Annual Environmental Report for 1995 operation of the Fort St. Vrain (FSV)

Independent Spent' Fuel Storage Installation (ISFSI). The attached supplemental information is submitted in accordance with the requirements of ISFSI Techn3 cal Specification Section 4.6.2.c, ISFSI Environmental Protection Technical Specification Section 1.4.1, and 10 CFR 72.44 (d) (3) .

The attached supplemental information does not change the conclusions of the report; that is, the concentration of gross beta air particulates and of tritiated water vapor in ambient air and the gamma-ray exposure rates were not significantly different than the general background rates of the area. Therefore, it can be concluded that there were no principal radionuclides released from the fuel storage containers or gaseous effluent and there was a negligible direct radiation dose commitment to the public resulting from ISFSI operations in 1995. There were no liquid effluents as a result of ISFSI operation in 1995.

9612030307 961125 PDR ADOCK 05000267 K PDR I)l.V'

\

_ _._ _ _ ___ _. _ . . _ . . . ~. _ _ _ - - _ _ _ . _ _ _ . - . . . _ , . . _ . . . . _ _ _ _ _ . . _ . . . _ _ _ _ . _ _ _ _ _ . _ . _

1 4 i

l l

November 25, 1996 P-96101 Page 2 If you have questions regarding the information contained in this

! submittal, please contact Mr. M. H. Holmes at (303) 571-7633.

Sincerely, hWCbt - St~~

Frederic J Borst Decommiss ning Project Director FJB/tb cc: w/ attachment Director l Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. Robert M. Quillin, Director Radiation Control Division Colorado Department of Public Health & Environment RCD-DO-B1 4300 Cherry Creek Drive South Denver, Colorado 80222-1530 Dr. James E. Johnson Department of Radiological Health Sciences MRB Building ,

Colorado State University Fort Collins, CO 80523

+w., c.---

.. - .. - . . - - .-~.- -..- - - - - - - n.- ~ - - - - -

1 l ,i RADIATION AND AIR MONITORING PROGRAM OF THE FORT ST. VRAIN INDEPI.NDENT SPENT FUEL STORAGE INSTALLATION (IRAMP) i

! SUPPLEMENTAL INFORMATION FOR j 1995

SUMMARY

REPORT NOVEMBER 25,'1996 This supplemental information provides an explanation for missing TLD data, . identified in the review of the 1995 Environmental Report for-'the Fort St. Vrain ISFSI.

Gamma exposure rates for November 1995 (Table II. A.1, Page 15), for TLD's that were posted from 9-8-95 to 12-5-95, were not obtained due to a technician error during analysis. The TLD set was improperly post-annealed, .and all data were lost prior to measurement.

The reported 1995 annual exposure rate for IRAMP sampling sites did not include any data from this time period. The exposure. rate at these sites during this time period can be inferred by examination of . surrounding TLD stations that were collected following the period in question. Exposure values at sites overlapping November.

j were found to be acceptable, as they were not statistically different from historical values at ISFSI sites. For the period of 10-3-95 to 1-4-96, the measured exposure rate was 0.40 (0.11) l mR/ day. For the period of 11-2-95 to 2-1-96, the measured exposure 1 rate was 0.39 (0.18) mR/ day. Values in parentheses represent the 95% confidence interval due to counting statistics. From the above available date, it can be clearly seen that'the exposure rate for November 1995 was not statistically different than for the other reporting periods of 1995.

All lab personnel. were notified of the problem, and a review training session on TLD preparation procedures and analysis was given. A written notice has since been placed near the annealing ,

ovens to serve as a reminder of correct procedures. There have l been no further problems of this sort since November 1995. '

I l

l l

1