ML20094J981
| ML20094J981 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 03/10/1992 |
| From: | Warembourg D PUBLIC SERVICE CO. OF COLORADO |
| To: | Weiss S NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| P-92107, NUDOCS 9203170238 | |
| Download: ML20094J981 (3) | |
Text
.
l
(
Public Service Public Service" g
16805 WCR 19 1/2, Platteville, Colorado 80551 March 10, 1992 Fort St. Vrain Unit No. 1 P-92107 U.
S.
Nuclear Regulatory Commission ATTN:
Documcnt Control Desk Washington, D.C.
20555 ATTN:
Dr. Seymour H. Weiss, Director Non-Power ReLetor, Decommissicting and Environniental Project Directorate Docket No. 50-267
SUBJECT:
CORRECTION OF ERROR IN REFEMENCED LETTER
REFERENCE:
PSC Lettel, Warembourg to Weiss, dated 2/18/92 (P-92064)
Dear Dr. Weiss.
As discussed in the veekly decommissioning status phone conversation between Pub)ic Service Company of Colorado (PSC) and the Nuclear Regulatory Commission (NRC) on March 5,
1992, PSC identified an error on Table 9.5-2 of the Referenced letter The headings ft:' two columns of numbers in Table 9.5-2 " Inventory of Rad'opuclides on One Steam Generator Module" are " Initial Curies" anu " Final Curies (3 year decay)".
However, the values listed in these columns are actually expressed in ':its of microcuries.
Attached is a corrected Table 9.5-2 of the Referenced letter, with the activity columns properly labelled as nicrocuries. The correct activity inventories of the varicus nuclides were used in the calculations to project doses at the Emergency Planning Zone in the postulated primary steam generator module drop accident, so the doses projected in the Referenced letter are unaffected.
/
9203170238 920310 00!
PDR ADOCK 05000267 P
PDR i -
l
\\ \\
j
} ty u t '
1
_____.___...m._._
s P-92107 Page 2 March 10, 1992 If you have any questions on this subject, please contact Mr. M. H.
Holmes at-(303)'620-17(1.
Sincerely yours, 5
RA.ls&ima,.
./
i
.W.
Warembourg D.
Manager, Nuclear Oper ions DWW/JRJ/Img l-Attachment cc:
Regional Administrator, Region IV Mr.
J.
B.
Baird-Senior. Resident Inspector Fort St. Vrain Mr. Robert Ms Quillin, Director Radiation Control Division l
Colorado Department of Health L
4210. East lith Avenue Denver, CO 80220 i
' Attachment to P 92107 March 10,1992 TAllLE 9.5 2 INVENTORY OF RADIONUCLIDES ON ONE STEAM GENERATOR MODULE 0)
' NITI AL ll ALF-LIFE 3 YEAR DECAY ISOTOPE ACTIVITY (nCi)
.(years)
Acr1VITY htCi)
Mn-54 1.74 E + 05 8.55 E-01 1.53 E + 04 Fe 55 5.20 E+ 06 2.70 E + 00 2.41 E+ 06 Co 60 5.71 E + 05 5.26 E+00 8.48 E+ 05 Ni-63 9.31 E+ 04 9.20 E + 01 9.10 E+ (M Sr-90 3.94 E+ 04 2.81 E + 01 3.66 E + 04 Y-90' 1.68 E+ 05 64 Ilours 1.41 E + 05 Ru-106 1.47 E+ 04 1.01 E + 00 -
1.88 E+ 03 Ag-110m 1.83 E+ 05 6.90 E-01 9.00 E4 03 Cs-134 2.34 E+ 05 2.06 E + 00 8.53 E + 04 Cs-137 5.71 E+ 05 3.01 U + 01 5.33 E+ 05 Cc 144 2.18 E+ 05 7.78 E-01 1.50 E + (M Pm-147 1.83 E + 05 2.62 E+ 00 8.42 E + 04 Y-90 continues to be produced from the radioactive decay of Sr-90 0)
Nuclides that contribute at least 0.1% to the offsite radiological consequences (Whole body or maximum organ) 1-9.5-9