ML20058M084
| ML20058M084 | |
| Person / Time | |
|---|---|
| Site: | Washington State University |
| Issue date: | 12/12/1993 |
| From: | Miles M, Tripard G WASHINGTON STATE UNIV., PULLMAN, WA |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20058M090 | List: |
| References | |
| NUDOCS 9312200145 | |
| Download: ML20058M084 (4) | |
Text
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] Washington StateUniversity M Nuclear Radiation Center Pullman, WA 99164-1300 509-335-8641 FAX 509-335-4433 December 12,1993 1 l
Document Control Desk i U.S. Nuclear Regulatory Commission j Washington, D.C. 20555 Ref: Docket 50-27 1
Dear Sir:
In accortlance with the provisions of the Code of Federal Regulations section 10 CFR 50.4 and
! 50.36, Washington State University TRIGA reactor facility (License No. R-76) requests to amend its Technical Specifications. The proposed changes are necessary to make our document comply:
with the new 10 CFR 20 regulations and to correct some minor errors. The document including the proposed changes has been reviewed and approved by the Facility Reactor Safeguards-Committee. .
Proposed Changes:
l Page Change ;
! i 2 In Reportable Occurrence:(2) change .
" limiting condition for operation" '
to " limiting condition of operation listed in Section 3.0" .
l 13 In section 3.8, Specification: change "4 x 10-8 ci/ml" to-- j "I x 10-8 pCi/ml" 13 In section 3.8, Basis: change "4 x 10-8 pCi/ml" to "I x 10-8 pCi/ml" 14 In section 3.9, Basis: change 1 l " maximum permissible concentration (MPC) values."
to " derived air concentration (DAC)." '
14 In section 3.9, Basis: change l "the appropriate MPC value."
l to "the appropriate DAC value."
14 . In section 3.10, Soecification:(5) change .
, "In calculations pursuant to item 4 above,"
to "In calculations pursuant to item 5 above,"
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18 In section 3.14, Specification: (3) change .
"10 CFR 20 Appendix B, Table II, Column 2 value" to "10 CFR 20 Appendix B, Table 3 value" 19 In section 3.14, Buis: (3) change .
" Table II, Column 2 limit for 60Co is 3 x 10-3 pc/t."
to " Table 3 limit for 60Co is 3 x 10-5 Ci/mt."
also change
" worst case would be atleast 1 x 104 c/f, or 100 Pc/f, or about one-thirtieth of the 10 CFR 20 limit stated above. : Setting a limit'of ten times -
' the detection limit and one-thint the discharge limits pmvide the facility" ~
to " worst case would be at least 1 x 10-7 pCi/mt, er 100 pCi/f, or -
about one-thme-hundredth of the 10 CFR 20 limit stated above. Setting a limit of 100 times the detection limit and one-thint the discharge limits pmvides the facility" 22 In section 4.3.3,Saccifications: change
" a calibration of the A-41' system" -
to " a calibration of the Ar-41 system"~
32 In section 6.5.2, change'
" The University's Radiation Safety' Supervisor"'
to " The University's Radiation Safety Director" ~
32 In section 6.5.4, Reviews: add to the list of RSC responsibilities
"(9) annual review of the radiation protection program" ' ;
i j 34 In section 6.8, item (7) change - . i
" power equipment" ,
to "powercalibration"-- J
.1
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.)
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. - . . - - ~ - - -. . . __ _
i 1 !
-l 37 change l
"Lianid Waste (summarized on a monthly hacic) !
i t) radioactivity discharged dudng the reponing period
. total estimated quantity of radioactivity released (in curies),
{
- an estimation of the s gific activity for each detectable radier aclide present if the specific activity of the released i material after dilution is greater than 10 CFR20 Appendix t B limits,
. summary of the total release (in curies) of each'nuclide i determined just above for the reportmg penod based on . i representativeisotopic analysis, ;
- estimated average concenuation of the released radioactive - .
material at the point of release for the reporting period ;
in terms of pCi/cc and fraction of the applicable MPC. i i
(ii) total volume (in gallons) of effluent water (including dilutant) released during each period of release" ,
to }
"Liauid Waste (summarized on a monthly basis) !
(i) monthly radioactivity discharged 0 total estimated quantity of radioactivity released (in curies),
an estimation of the specific quantity for each detectable radionuclide in the monthly release,- ,
fraction of 10 CFR 20 table 3, appendix B limit for each 3 detectable radionuclide taking into account the dilution !
factor from the total volume of sewage released by the ,
l licenseeinto the sewage system, ;
i l
- sum of the fractions for each radionuclide reported above. .!
(ii) total quantity of radioactive material released by the facility into ,
the sewage system during the year period of the report" - -
.l l
l i
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_ - ~ _ _ . ._ _- ~_ . - _ . . ._ _
1 37 In section 6.10, Gaseous Waste, (i) change
" in terms of pCi/cc and fraction of the applicable MPC value,"
l
- to "in terms of pCi/ml and fraction of the apolicable DAC value," ~l
- i' 37 . greater than 8 days released in pCi/cc durinfj the"
. o ,
to " greater than 8 days aleased in pCi/ml during the" 1 38 In section 6.10, Gaseous Waste, (i) change .
" terms of pCi/cc and fraction of the applicable MPC value for the mporting period if the estimated release is greater than 20% of the applicable MPC," -
to " terms of pCi/ml and fraction of the applicable DAC value for the reponing 4 !
period if the estimated release is greater than 20% of the applicable DAC,"
l I
Y If you have any questions, please contact Dr. Gerald Tripard, Facility Director.(509)'335-0172
.l .
l Sincerely, - - - -
.?
'. s*G f }%$ V Gerald E.Tripard M. Howard Miles .
. i Director Chair, Reactor Safeguards Committee !
.l cc: Region V NRC office !
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