ML20236U228: Difference between revisions

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| number = ML20236U228
| number = ML20236U228
| issue date = 11/30/1987
| issue date = 11/30/1987
| title = Forwards Corrected Pages to 871103 Ltr.Five Units Mistakenly Sent as Ur/Hr Instead of Mr/Hr.Corrections Noted in Right Margin
| title = Forwards Corrected Pages to .Five Units Mistakenly Sent as Ur/Hr Instead of Mr/Hr.Corrections Noted in Right Margin
| author name = Sackschewsky R
| author name = Sackschewsky R
| author affiliation = WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
| author affiliation = WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
Line 11: Line 11:
| contact person =  
| contact person =  
| document report number = NUDOCS 8712020377
| document report number = NUDOCS 8712020377
| title reference date = 11-03-1987
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, VENDOR/MANUFACTURER TO NRC
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, VENDOR/MANUFACTURER TO NRC
| page count = 3
| page count = 3

Latest revision as of 21:06, 19 March 2021

Forwards Corrected Pages to .Five Units Mistakenly Sent as Ur/Hr Instead of Mr/Hr.Corrections Noted in Right Margin
ML20236U228
Person / Time
Site: 05000087
Issue date: 11/30/1987
From: Sackschewsky R
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To: Michaels T
NRC
References
NUDOCS 8712020377
Download: ML20236U228 (3)


Text

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e Westinghouse wantaining cemer i Electric Corporation so5 snaon Bouievara Zion Illinois 60099 4312.872 4585 November 30, 1987 1

Mr. Ted S. Michaels l Nuclear Regulatory Commission Mail Stop P234 7920 Norfolk Avenue Bethesda, Maryland 28014 Mr. Michaels, Enclosed are twe pages containing corrections to the information sent to you in a let.er dated November 3,1987. Five units on page 12 of the information were mistakenly sent as pR/hr (micro-R/hr) instead of mR/hr (milli-R/hr). This same error was made on page 17 of the transmittal concerning 49 CFR 173.441 limits for RAM shipments. The lines containing the correction are noted by vertical lines in the right margin.

If you have any questions, please give me a call.

Sincerely, f

ph@ >~

(-)

Roy P. Sackschewsky NTR Coordinator RPS/mtk Enclosure 1040a/18 0063 l

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h 8712O20377 871130 )\

PDR ADOCK 05000007 p PDR

p (2) Give a description of the Radioactive Materials which have been or are being shipped f rom the NTR Facility including the calibration'and check ,

sources.

The low power history of the NTR and the use of aluminum in'most-components have minimized the activity levels of materials within .the Facility. Contamination in the Facility and on reactor' components has I never. occurred, as shown in the results of'th'e water, air,and Facility smear surveys in Tables III, IV, y and VI in the' dismantling plan  !

submitted on 7/8/87.

Activated components consist mostly of stainless steel components .

utilized within the reactor. The major portion of the activated stainless steel was utilized to' support the fuel element followers in '

the five control rods. The fuel follower was attached to the control rod by a 3/8" stainless steel shaft. Maximum radiation level on a single shaft at its hot spot was 16 milli-R/hr. Stainless steel collar j 1

pieces were utilized to support the upper section of the fuel follower i to the stainless steel shaft. These collar pieces are-the most activated pieces of material from the reactor. A single collar measured 0.6 R/hr on contact and 20 milli-R/hr at one foot. . The collar pieces

.[

j were all placed in a single bag which measures 3.5 R/hr on contact and l 0.3 R/hr at one foot. This material has been packaged for shipment to a l

RAM burial site in a single 17H container. Other stainless steel- l components included in the shipment had low activated levels measuring l f rom a f raction of a milli-R/hr to 3 milli-R/hr. The total-measurable l activity of the stainless steel was calculated at 2.65 x 10~ ' curies.

l l Included in this shipment are the following 12 check sources:

l Source Description Number. A_ctivity Each Total Activity Cs-137 6 ~ 8 pCi 48 pci Th-230. 2 0.005 pCi .01 pCi.

Th-230 2 0.01 pCi .02 pCi

-3 -3 Sry-90 1 6.6 x 10 pCi' 6.6 x 10 pCi Co-60 1 .33 mci 330 uCi l TOTAL 378.04 pCi 1040a 1

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ = _ _ _ _ _

n (5) Contamination Limits for Shipment Offsite Contamination of the Facility or its components has not been.found due to the nature of our operations. Contamination limits at the Facility are 200 dpm beta-gamma activity and 10 dpm alpha activity for a'100 cm smear area, as per page 22 of the Dismantling Plan.

i For Radioactive Materials shipments, the containers cannot be greater than 200 milli-R/hr on the exterior of the container or greater.than 10 $

l milli-R/hr at one meter (49CFR 173.441). Three smears of at least 100 cm each are taken to assess non-fixed contamination levcis. The 2 2 limits are 22 dpm/cm beta-gamma and 2.2 dpm/cm al ha (49CFR 173.443).

All items remaining in the NTR Facility at the time of the final radiation survey will be within the contamination limits specified in Regulatory Guide 1.86 and within 5 pR/hr above background at one meter from the surface.

I 1040a

. _ _ .