ML20059J041

From kanterella
Jump to navigation Jump to search
Submits Response to NRC Request Re Proposed TS Changes Reviewed & Approved by Facility Reactor Safeguards Committee
ML20059J041
Person / Time
Site: Washington State University
Issue date: 01/19/1994
From: Miles M, Tripard G
WASHINGTON STATE UNIV., PULLMAN, WA
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9401310318
Download: ML20059J041 (4)


Text

c

] Washington State University _

M NacMar nd tSon Center Pu:nnan. WA 9910L13i>0 509-335-CM1 F AX SO9-335-4433 -

Wednesday, January 19,1994 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Ref: Docket 50-27

Dear Sir:

In accordance with the previsions of the Code of Federal Regulations section 10 CFR 50.4 and 50.36, Washington State University TRIGA reactor facility (License No R-76) sent a letter en December 12,1993 to the US NRC requesting 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. After consultation with NRC project manager, Marvin Mendonca, a minor revision was made to the these changes in section 3.9, Basis The term MPC will be changed to air effluent concentration (AEC)instead of derived air concentration (DAC). This makes the terminology conform to the terminology of 10 CFR 20 appendix B. All requested changes are now as follows.

Proposed Changes:

Page Change 2 In Renortable Occurrence:(2) change ,

" limiting condition for operation" to " limiting condition of operation listed in Section 3.0" 13 in section 3.8, Specification: change "4 x 10-8 pei/ml" to "I x 10-8 pCi/ml" 13 In section 3.8, Basis. change "4 x 10-8 Ci/ml" to  ;

"I x 10-8 pCi/ml" -

14 In section 3.9, Basis change

" maximum permissible concentration (MPC) values."

to " maximum air effluent concentration (AEC) values."

l 14 In section 3.9, Basis: change  ;

"the appropriate MPC value."  ;

to "the appropriate AEC value." ]

0 I 9401310318 940119 J a  !

PDR ADOCK 05000027 U p PDR .L :I 1

i i

~ -

.14 In section 3.10, Soccification: (5) change "In calculations pursuant to item 4 above,"

to "In calculations pursuant to item 5 above,"

18 in section 3.14, Socci6 cation:(3) change .

+

"10 CFR 20 Appendix B. Tabic II, Column 2 value" to "10 CFR 20 Appendix B, Table 3 value" 19 In section 3.14,Hasis:(3) change

" Table II, Column 2 limit foru)Co is 3 x 10-3 pc/f."

to " Table 3 limit foru)Co is 3 x 10-5 Ci/mt." '

also change

" worst case would be at least 1 x 10dpc/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 third the discharge limits provide the facility"  ;

to " worst case would be at least 1 x 10-7 pCi/mf, or 100 pCi/f, or about one-three-hundredth of the 10 CFR 20 limit stated above. Setting a limit of 100 times the detection limit and one-third the discharge limits 1 provides the facility" 22 In section 4.3.3, Soccincalinas: change

" a calibration of the A-41 system" to " a calibration of the Ar-41 system" ,

32 In section 6.5.2, change l

" 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" l

34 In section 6.8, item (7) change

" power eqttipment" to " power calibration" I

I I

-u 1

)'

1

,_ .. -1

+

37 change

  • "Li inid Waste (summarized on a monthly basis) l (i) radioactivity discharged during the reporting period -

+

total estimated quantity of radioactivity released (in curies),

+ an estimation of the specific activity for each detectable radionuclide present if the specific activity of the released i material after dilution is greater than 10 CFR20 Appendix B limits,

. summary of the total release (in curies) of each nuclide determined just above for the reporting period based on  !

representative isotopic analysis, estimated average concentration of the released radioactive l material at the point of release for the reporting period in terms of pCi/cc and fraction of the applicable MPC. ,

(ii) total volume (in gallons) of effluent water (including dilutant) released during each period of release"

- to "Liouid Waste (summari7ed on a monthly basis)

(i) monthly radioactivity discharged ,

a total estimated quantity of radioactivity released (in curies),  !

an estimation of the specific quantity for each detectable .l radionuclide in the monthly release, e fraction of 10 CFR 20 table 3, appendix E limit for each detectable radionuclide taking into account the dilution ,

factor from the total volume of sewage released by the ,

licensee into the sewage system, i

sum of the fractions for each radionuclide reported above, ,

3 (ii) total quantity of radioactive material released by the facility into the sewage system during the year period of the report" P

E

+

, . + - .,,_r . , , , - ,-w- ,, . *

~ .. .

.g.

37 In section 6.10, Gaseous Waste, (i) change j

. " in terms of pCi/cc and fraction of the applicable MPC value," >

to "in terms of pCi/ml and fraction of the applicable DAC value."

37 " greater than 8 days released in pCi/cc during the" to " greater than 8 days released in pCi/ml during the" =t 38 in section 6.10, Gaseous Waste, (i) change "temis of pCi/cc and fraction of the applicable MPC value for the reporting 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 reporting ,

period if the estimated release is greater than 20% of the applicable DAC," l 3

If you have any questions, please contact Dr. Gerald Tripard, Facility Director (509) 335-0172 Sincerely, 5 it.1 cY / '

Gerald E. Tripard M. Iloward Miles .

Director Chair, Reactor Safeguards Committee cc: Region V NRC office 5

?

i

.i I

1

-L u a