ML19257D391
| ML19257D391 | |
| Person / Time | |
|---|---|
| Site: | 07000033 |
| Issue date: | 12/13/1979 |
| From: | Sherman F TEXAS INSTRUMENTS, INC. |
| To: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 14987, NUDOCS 8002040283 | |
| Download: ML19257D391 (5) | |
Text
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70-33
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TEXAS INSTRUM ENTS I NC OIIPOR ATED ME T AL t.UltGIC AL M AT EF{l ALS OlVISION December 13, 1979 Mr. Leland C.
Rouse, Chief Fuel Processing & Fabrication Branch Div. of Fuel Cycle & Material Safety U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Ref:
SNM-23, Docket 70-33, Page Changes dated November 27, 1979 Gentlemen:
Please find enclosed ten (10) copies of further page changes to the most recent license amendment request dated October 10, 1979.
These page changes are made as a result of your staff's review of the referenced page changes and reflect changes discussed between Mr. Soong of your staff and Mr. Schwensfeir of our staff (telecon of December 12, 1979).
Attacnment I delineates page changes to made as a result of your staff's review.
Sincerely, LLt at h\\
F.
L.
Sherman Manager HFIR Project FLS:bls 1863 r305 Attachments c
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ATTACIIMENT I SUf@iARY OF PAGE CIIANGES Page 13, Rev. B to Rev. C Para. 5.5.1.5.1.1 - substitute "45 pCi/ liter or greater" for "in excess of the maximum acceptable levels by 30 pCi/ liter".
Para.
5.5.1.5.1.2 - substitute " excess of 15 pCi/ liter, but less than 45 pCi/ liter" for "the range of 15 to 30 pCi/ liter of maximum acceptable levels".
Page 20, Rev. B to Rev. C Para.
8.4.2.1
- add time candition on start of decon-tamination.
Page 20A, Rev. A to Rev. B Para 8. 4. 2. l (cont) - remove time restriction on period of decontamination and remove requirement to notify USNRC OI&E Region I.
1863 206
E.N.
79-70 Page 13 December 13, 1979 Rev.
C f
5.5.1.2 Anaiytical procedure for the determination of enriched uranium in urine shall consist of a radiometric technique whereby the uranium is extracted, quanti-tatively transferred to a planchet, and alpha counted.
5.5.1.2.1 Sample results are calculated and reported in tenns of pCi/li t er o f solution.
5.5.1.3 A11 orinalyses procedures shall be pertormed by a qualified laboratory whose results shall be reported to Health / Physics.
5.5.1.4 The maximum acceptable levels for uranium urinalyses for the specified sampling frequencies are 15 pCi/ liter.
5.5.1.5 Results of all urinalyses shall be reviewed by Health / Physics within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after receipt from the l abo ra t o ry.
5.5.1.5.1 Samples showing levels in excess of the maximum acceptable levels shall be reported immediately to Health / Physics by telephone from the laboratory.
5.5.1.5.1.1 When reported results are 45 pCi/ liter or greater, the individual shall be removed from the bare fuel processing area, a new sample shall be requested and analyred, and an investigation initiated by Health / Physics to de te rmine the source of the exposure.
5.5.1.5.1.2 When reported results are in e:< cess of 15 pCi/ liter, but less than 45 pCi/ liter, a new sample shall be requested and analyzed, and an investigation initiated by Health / Physics to dete r-mine the source of the exposure.
5.5.1.5.1.3 When a second sample shows results in excess of the maximum acceptable levels, the individual shall be removed from the bare fuel h
} }QJ processing area and the investi-gation continued to determine the source of exposure.
- Change
E.N. 79-70 Page 20 December 13, 1979 Rev. C Alpha Fixed Removable 8.2.4 Clothing (d/m/100 cm2)
(d/m/100 cm )
2 8.2.4.1 Protective clothing worn in Fuel Manufacturing Area 1000 8.2.4.2 Clean Protective Clothing 200 8.2.4.3 Personal Clothing 200 8.2.4.4 Personal Shoes 200 8.2.4.5 Skin Bkgd.
8.3.
FREQUENCY OF MEASUREMENTS (During Production Periods) 8.3.1 Measurements shall be made and recorded at least weekly for items 8.2.1.1, 8.2.1.2, 8.2.2.2, and 8.2.4.1.
Item 8.2.2.1 shall be measured and recorded at least monthly.
Items 8.2.2.3, 8.2.3.1, and 8.2.4.2 shall be measured and recorded as the need arises (i.e.,
release of material from the Fuel Manufacturing Area, release of protective clothing after laundering, etc.).
Items 8.2.4.3, 8.2.4.4, and 8.2.4.5 are measured by personnel before entering the Smidgen Clean Area (General Manufacturing Area) from the Fuel Manufacturing Area.
8.4.
PROCEDURE FOR MEASUREMENT 8.4.1 Fixed alpha activity shall be determined by direct measurement with survey meters.
Removable alpha activity shall be dete3 mined by) taking 8.4.2 smear samples of approximately 1000 cm (1 ft.
on Whatman #41 Filter Paper Discs (29 mm).
The discs are counted for a minimum of five minutes each in scintillation detection equipment.
8.4.2.1 When contamination levels are discovered in excess of those specified in 8.2, decontamination shall be started by the end of the following shift.
Decontamination shall not be considered complete until
- Chang 1863 208
E.N.
79-70 Page 20A December 13, 1979 Rev. B 8.4.2.1 measured contamination levels are (cont) acceptable according to the limits specified in 8.2.
- Change 1863 209 z.
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