ML20198A965
| ML20198A965 | |
| Person / Time | |
|---|---|
| Site: | Framatome ANP Richland |
| Issue date: | 12/15/1998 |
| From: | Edgar J SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| JBE:98:105, TAC-L31135, NUDOCS 9812180017 | |
| Download: ML20198A965 (4) | |
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.JDecember 15,19981' i ?
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t i[1 SEbjecti ) Request to' Amend Limit for Transuranic-related Activity in Feedstock: SNM-1227J r
Docket 70-1257 (TAC L311350
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l Ref,:, Letter, JB Edgar to PW Lain, same subject, dated November 13,1998'
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! Per my. recent telephone. conversations with Pau'l Lain of the Licensing Branch, the following
' additional infor'mation is' provided relative to the subject request.
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JAs described in the referenced letter [Siemens Power Corporation,(SPCI expects to supply, pellets or rods to a fuel fabr cato'r who 'will use them to produce fuel assemblies. The uranium.
i cto produce such pellets has been down blended from DOE high enriched, reprocessed uranium:
fand contains higher activity than the 3.3 Bq/gU Pu/Np' allowed in' SPC's license, henco th%
Tamendment request. It is now expected that the pellets' delivered to the' fabricator will result in -
s up to 300 kgU of pellets being le'ft.over after fuel fabrication. Those ' ellets are expected to be' p
' l returned to SPC late in 1999. When they are returned, they will be dissolved and blended with
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other SPC uranium'to be used in a future reload fusi carnpaign at SPC. Such blending will
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f reduce the' Pu/Np activit'y to below 3.3'Bq/gU. The contribution to the annual dose j
> [invotved in'this' dissolution and. blending process'is expected to be well below'that described in g.7 dhe referenced letter., in additionsthe demonstration in the refarenced letter that the 1 pg
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l pij)g'sU ' limit 's not excee'ded continues to b'e valid.
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- m i i SPC bel' eves,the ' operations described herein and in the referenced letter fall under the criteria
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i Mi0 for categorical' exclusion described in 10 CFR 51.22(c)(11) in that: (1) there is no significant p ' ;g. change'in the qu'aritity or types of effluents; (2) there is no significant increase in individual or
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([ Mcumuistive occupational radiation exposure: (3) there'is no construction impact; and'(4) there is
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- w w&> jno 's.ignificar t increase in the potential for, or consequence's of, a radiological a'ccident.
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I,*(d$16 additionvenclosed are six copies of revised 1
[inanertent omission of'section 1.6.12 that occurred in conjunction with'the' referenced Vamendment submittal.
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Tif you need further information, pleese call me at 509-375-8663, 3
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nVery truly. pours,,
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=4 SiemenS Power Corporation - Nuclear Division euF-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 i
PART I-LICENSE CONDITIONS REv.
EMF-12(P),'" Nuclear Material Safeguards Procedures Description for the Fuels
. Fabrication' Plants."
This document shall be maintained in a current and approved status and shall be properly implemented.
1.6.6 Authorization at Reactor Sites i
SPC is authorized to possess fuel assemb!ies or fuel rods at reactor sites for the l
purpose of loading them into shipping containers and delivering them to a carrier for I
transport.
l 1.6.7 Authorized Release Guidelines SPC is authorized to release equipment, scrap or facilities for unrestricted use, or for termination of license according to the " Guidelines for Decontamination of Facilities i
! and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for' Byproduct, Source, or'Special Nuclear Material" as published by the U.S. Nuclear Regulatory Commission dated April 1993.
l 1.6.8 Authorized Criticality Alarm System Outaae i
SPC is granted an exemption from 10 CFR 70.24(a) for the purpose of performing maintenance on the criticality alarm system. Sections of the criticality alarm system may be taken out-of-service provided that all movement or. processing of fissile materialin affected areas is halted for the duration of the outage. Health and Safety Technicians shall~ conduct continuous surveys of the areas during the criticality alarm system outage.
- { - 1.6.9 Notification l Notifications to the NRC shall be made as required by regulations with the exception i of 10 CFR 20.2202(a)(2) and (b)(2) as they apply to restricted areas. Reports to the l NRC shall be made as required by regulations with the exception of those paragraphs j in 10 CFR 20.2203 which refer to 10 CFR 20.2202(a)(2) and (b)(2) as they apply to restricted areas.
[ '1.6.10 Authorized Workolace Air Samplina Adiustments l
SPC is authorized to adjust Derived Air Concentration (DAC) limits and Annual Limit of Intake (ALI) values in process areas to reflect actual physical characteristics of the airborne uranium.
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. i AMENDMFNT APPUCATION DATE:
PAGE NO :
December 15,1998 1-5 SPc-ND:3330.947 (R 1/07/92)
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Siemens Power Corporation - Nuclear Division.
eup.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 76-1257.
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PART l-LICENSE CONDITIONS REV.
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1.6.11 Authorized Release Guidelines for Hydrofluoric Acid L>
SPC is authorized to release hydrofluoric acid manufactured by the dry conversion i
process for unrestricted commercial use providing the following conditions are met:
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1.
A representative sample of each batch of hydrofluoric acid product I
shall be obtained and analyzed for uranium; i-f 2.
A batch shall be no larr,er than 46,000 liters; i
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The specific activity of any batch released for unrestricted use shall L
be s 3 pCi/ml.
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I 1.6.12 Authorized Release Guidelines for Ammonium Hydroxide l
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.l SPC is authorized to release ammonium hydroxide produced at the Ammonia j
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f, Recovery Facility for unrestricted commercial use provided the following conditions q
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. A representative sample of each batch of ammonium hydroxide -
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product shall be obtained an analyzed for uranium; L
2.
A batch shall be no larger than 40,000 liters; j
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3.
The uranium concentration in the ammonium hydroxide shall not j
. exceed 0.05 ppm.
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. AMEPeOUENT APPLICATONDATE:
PEE e December 15,1998 1-6 SPCWD3330.947 (R-1/07/97)