ML20210V407

Forwards Revised Detailed Description of Criticality Safety Basis for Change in Chapter 6.0 of License SNM-1097

ML20210V407
Person / Time
Site:	07001113
Issue date:	09/19/1997
From:	Reda R GENERAL ELECTRIC CO.
To:	Weber M NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
NUDOCS 9709230310
Download: ML20210V407 (10)

Text

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i C B 7 5 5 *.17 D PAGc 2/10 GENuc;earEnergy GetesT&c Com;ey P G Box 10117. Sc.wt 1 c28 41 9'O 4572297 u 914:

September 19,1997 Mr. M. F. Weber, Licensing Branch, NMSS U.S. Nuclear Regulatory Commission Mail Stop T 8-D-14 Washington, DC 20555 0001

Subject:

License Submittal Revising Chapter 6.0 of the Referenced License

Reference:

NRC License SNM-1097, Docket 70-1113

Dear Mr. Weber:

GE'r Nuclear Energy Production (NEP) facility in Wilmington, N.C., hereby transmits a revision to Chapter 6.0 as discussed during the conference call between GE-NE and the NRC Staff, on September 19,1997. is a detailed description of the Criticality Safety Basis for the change in Chapter 6.0. is a Description of Revisions made to the license submittal by page and section. contains the page changes to our license submittal for pages contained in Revisions By Chaper and Chapter 6.0, All pages of this submittal have been dated 9/19/97. A vertical ( l ) line appears in the right

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column by the line where changes have been made, p;

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Ten copies of this submittal are being provided for your use.

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-COP-10-C7 10 12 FCOMsCUILDING J 1D:01E07E5070' PACE 3/1G

.hir.*h(, F. Weber September 19,1997 Page 2 Please contact Charlie Vaughan on (910) 675 5656 or me on (910) 675 5889, if you have any questions or would like to discuss this matter further.

Sincerely, GE NUCLEAR ENEROY 4

Ralph J. Reda, Manager Facility Licensing

/zb Enclosure cc:

RJR-97-114 C. Hrabal, NRC-HQ -

A.Gooden,NRC Atlanta M. Fry, State ofNC

l ccP-to-o? is.ta raon.CUILDING J IDeOlC370337Q Pact 4/10 Mr. M. F. Weber Septemler 19,1997 Page1of1 ATTACHMENT 1 Detailed Description of the Criticality Safety Basis for the Change in Chapter 6.0

CEP-tC-C7 15 12 l'ROMiculLDING J 1 D 8 01 C 37 55?,70 PAGE 5/10

'Mr: M. F. Weber Septernber 19,1997 Page 1 of I CRITICALITY SAFETY BASIS FOR NF RECOVERY AND STORAGE The following parameter controls are provided for the DCP HF recovery and storage facility. The parameter control scheme is dependent upon the source of uranium, and is independent on the mode of operation. Dual parameter control is used for particulate forms of uranium carryover; ship.le parameter control is used for gaseous unreacted UF6 (See revind Table 6.0, page 6.16).

L PAR'11CULATE CARRYOVER Mass Procen flow controls on steam and UF6, and physical ba: Tiers (sintered monel flhers) prevent carry over of particulate uranium mass. During normal conversion operations, with full UF6. N2, and steam flows, active engineered interlocks prevent UF6 flow if either hydrolysis or

_ pyrohydrolysis superheated steam flow drops below the minimum set polnt. This will be accomplished by independently signaling both hydrolysis and pyrohydrolysis flow switches (through independent l'O cards) to close two separate block valves (e.g. XV12902 and XV121905).

Geometry Process flows that may be expected to contain uranium during accident conditions are restricted to equipment and components that are favorable geometry. The HF off gas pipe, HF condenser, piping upstream of the Vi separator inlet, V/L seperstor, and piping between the V/L separator outlet and pipe detectors, polluted HF storage tank, and HF building floor sump are favorable geometry. Shape and dimension of these systems and components form the basis of geometty control.

Pipe detectors are continuous uranium monhor instruments that are installed the condensed HF piping below the vapor liquid separators. Pipe detectors include a hardwired interlock that automatically blocks condensed HF flow to the unfavorable geometry storage tanks and diverts flow to the favorable geometry (annular) polluted tank when U235 is detected above a preset threshold. A primary detector is dedicated to each com ersion line and condensed HF flow passes through this primary detector as well as a second pipe detector com:non to all conversion lines for control reliability.

II. UNREACTED UF6 GAS CARRYOVER Mass During cold shutdown or startup conditions (temperature profile not achieved on reactor kiln) the UF6 source term from the 30B cylinder is effectively blocked. Since no steam is flowing, interlocks exist to prevent UF6 valves from oper.ing (as described in 1. above). At least four independent block valve isolate the 30B cylinder from the reactor chamber during this mode of operation. nis rules out a mass of UF6 in excess of residual quantities remaining in the lines his residual quantity is estimated to be less than ~$00 gU which is well below a safe batch of 15.9 kgU at 5% U235.

CEP-tO-07 15e12 FNOHeCUILDINC J 10:01G2755070 PACE 3/10 W. M. F. Weber September 19,1997 Page1of1 i

ATTACHMENT 2 Description of Revisions to the License Submittal by Page and Section

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CEP-lO-07 15 12 FROM*DUILDING J 1D:018375537Q PAGE' -7/18

. Mr.'M F. Weber September 19,1997 l

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i Descrietion of Revisions i

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Eagg Section Descriotion 1

Revisions by Changed the date on Chapter 6.0 to 09/19/97.

Chapter 4

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6.2.3 -

Updated the control parameters for HF recovery and storage vessels.

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License Submittal Page Changes d

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CEP-lO-C7 15e13 FROHeCUILDING J IDeC1h37EbC70 PAGE C 'tC RF. VISIONS BY CHAPil!R Application Application Page Date Fage Date l

TABLE OF CONTENTS

]

l CHAPTER 6.0 l

1 through 3 06/05/97 1 through 36 09/19/97 l

LREVIS ONS BY CHAPTER l l

CHAPTER 7.0 l

1 09/19/97 l

1 through 3 06/05/97 l

CHAPTER 1.0 l

l CHAPTER 8.0 l

1 through 22 06/27/97 1 through 5 06/05/97 CHAPTER 2.0 CHAPTER 9.0

]

I through 11 06/05/97 1

06/05/97 l

CHAPTER 3.0 -.

l l

CHAPTER 10.0 l

1 through 12 06/05/97 1 through 16 06/05/97 s

CHAPTER 4.0 l

l CHAPTER 11.0 1 through 8 06/05/97 1

06/05/97 l

CHAPTER 5.0 l

APPENDIX 1 through 13 06/05/97 1

06/05/97 LICENSE SNM-1097 DND3 09/19/97 Page DOCKET 70-1113 REVISION 3

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GEP-19-97 15 t3 FROHiBUILDING J 1Di9168755879 PACE 10/10 1

ARE PROCESS SUBAREA BASIS FOR i

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OR OR FQUIPMENT CRITICALITY BOUNDING ASSUMPTIONS SYSTEM SAFETY

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Blending, Moderation Heterogeneous UO 2

o Precompaction, Maximum Credible UO Density 2

Oranulation Maximum Credibic wt. % H O 2

Full Reflection Tumbling:

Moderation Heterogeneous Voi ~ __

in Powder Container Maximum Credible UO Density 2

Maximum Credible wt % H O '

I 2

Full Reflection Powder Pack hWeration Heterogercous UO2 Screener Maximum Credible UO Densit-2 Maximum Credible wt. % H/'

Full Reflection Powder Pack Geometry Homogeneous UO 2

3 Product Container Mass Optimal H 0 Moderation 3

E Pull Reflection h

Utilities: N, H H O Mass Backflow into large supply vessels not 2

3 2 y

Supply, Refri;erant credible due to backflow prevention measures, physical barriers, and'or process characteristics.

HF Effluent Recovery Particulate:

Homogeneous UO2 ar.d Storage Vessels Geometry OptimalH O Moderation 2

Mass Full Reflection

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Unreacted UF. Gas:

Mass Recycle Blender MMeration Hererogeneous UO2 Maximum Credible UO Density 2

Meximum Credible wt % H O 2

Full Reflection Recycle Unicone Moderation Heterogeneous UO2 Product Maximum Credible UO Density 2

Container! Storage Maximum Credible Internal wt. % H O 2

OptimalInterunit H,0 Recycle 3-Gallon Geometry 1

Heterogeneous UO2 E

Product Container /

Mass J*

OptimalH O Moderation 2

Storage Moderation Full Reflection Press Warehouse Conveyor Storage:

Geometry 1

Homogeneous UO2 Facility Process 3 and 5 gallon Cans Mass J*

OptimalIntenmit H O Moderation 2

Moderation FullReflection Pow' der Dump Transfer Geometry Homogeneous UO2 Hopper / Chute MMeration OptimalH O Moderation 2

Full Reflection Pellet Presses Geometry / Mass Heterogen:ous UO2 Moderation Optima! H O Moderation 2

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Full Reflection 2-

• ewo out of any three control parameters required for,;riticality safety.

LICENSE

% 31-1097 DATE 09/19/97 Page DOCKET 70-1113 REVISION 2

6.16

SEP-19-97 15:11 FROM BUILDING J ID.91CG755979 FAGE 1/10 O

GE NUCLEAR ENERGY GE Nuclear Energy Production WILMINGTON, NORTH CAROLINA To: Mike Weber Company:

US NRC Phone:

Fax:

301-415-5955 From:

Ralph Reda

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Phone:

910 475-5869 Fax:

-5879 Date:

September 19,1997 Pages including this cover page:

10 Mike:

Per our conference call today, attached is a copy of the submittal revising chapter 6 of our license which includes a description of the basis for criticality safesy. I have only faxed the one page in chapter 6 affected by this revision., am sending (via FedEx) the original submittal with chapter 6 in its entirety.

If you have any questions or concerns please call me at 910-675-5889 or prge me at (910) 371-8072.

Ralph Reda

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