ML20202G169

Forwards Correspondence Re Application for 10CFR70 License for Possession & Storage of Unirradiated Reactor Fuel & Associated Snm.W/Svc List.Related Correspondence

ML20202G169
Person / Time
Site:	Vogtle
Issue date:	07/10/1986
From:	Churchill B GEORGIA POWER CO., SHAW, PITTMAN, POTTS & TROWBRIDGE
To:	Linenberger G, Margulies M, Paris O Atomic Safety and Licensing Board Panel
References
CON-#386-962 OL, NUDOCS 8607150315
Download: ML20202G169 (18)

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July 10, 1986 i

w AITER S DimECT DIAL NuMSER Morton B. Margulies, Chairman Mr. Gustave A. Linenberger, Jr.

Atomic Safety and Licensing Atomic Safety and Licensing Board Board U.S. Nuclear Regulatory U.S. Nuclear Regulatory Commission Commission Washington, D.C. 20555 Washington, D.C. 20555 I

l Dr. Oscar H. Paris i

Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Washington, D.C. 20555

In the Matter of Georgia Power Company, et al.

(Vogtle Electric Generating Plant, Units 1 and 2)

Docket Nos. 50-424 and 50-425 A / .

l

Dear Administrative Judges:

Georgia Power Company has filed an application for a i Part 70 license authorizing the possession and storage of ,

unirradiated reactor fuel and associated special nuclear materials. Enclosed for the information of the Board is

! the cover correspondence related to the application.

Sincerely /

'3 8607150315 24 ' ce . Churchill PDR ADOCK PDR Counsel for Applicant G

Enclosures cc: Service List (attached) ,

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Before the Atomic Safety and Licensing Board In the Matter of )

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GEORGIA POWER COMPANY, et al. ) Docket No. 50-424

) 50-425 (Vogtle Electric Generating Plant, )

Units 1 and 2) )

SERVICE LIST Morton B. Margulies, Chairman Atomic Safety and Licensing Atomic Safety and Licensing Board Board Panel U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Washington, D.C. 20555 Commission Washington, D.C. 20555 Mr. Gustave A. Linenberger Atomic Safety and Licensing Board Atomic Safety and Licensing U.S. Nuclear Regulatory Commission Appeal Board Panel Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Dr. Oscar H. Paris Washington, D.C. 20555 Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Douglas C. Teper Washington, D.C. 20555 1253 Lenox Circle Atlanta, Georgia 30306 Bernard M. Bordenick, Esq.

Office of Executive Legal Director Docketing and Service Section U.S. Nuclear Regulatory Commission Office of the Secretary Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Bradley Jones, Esquire Washington, D.C. 20555 Regional Counsel U.S. Nuclear Regulatory Commission Suite 3100 101 Marietta Street Atlanta, GA 30303 9

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, ogen March 7. 1986 Director of Nuclear Material Safety and Safeguards File: X38C35 U.S. Nuclear Regu atory Comission Log: GN-824 Washington. D.C. 20555 NRC DOCKET NUM8ER 50-424 l CONSTRUCTION PERMIT. NUMBER CPPR-108

! V0GTLE ELECTRIC GENERATING PLANT - UNIT 1

! SPECIAL NUCLEAR MATERIAL LICENSE

Dear Str:

Georgia Power Company, acting on its own behalf and as agent for Oglethorpe Power Corporation. Municipal Electric Authority of Georg'a, and the City of Dalton Georgia, hereby submits, in accordance with 10 CFR Part 70, the Vogtle Electric Generating Plant (VEGP) Unit 1 application for a Specia Nuclear Material License. This application is for the receipt, possession, and storage of unitradiated reactor fuel and associated radioactive materials. The term of the requested Special Nuclear Material License is for the period beginning August 1.1986 until receipt of the pennanent operating license.

Eight (8) copies of the application, as required by the Regulatory Guide 3.15. are enclused for your review and approval. Your prompt consideration of this application will be appreciated.

Respectfully submitted.

N% V R. E. Conway l

REC:js Enclosure cc: R. A. Thomas G. Bockhold. Jr.

J. E. Joiner. Esquire T. Johnson B. W. Chuidill . Esquire D. C. Teper (w/o enclosure)

M. A. Miller (2) L. I'owler (w/o enclosure)

8. Jones (w/o en:losure) W. C. Ramsey (w/o enclosure)

L. T. Gucwa Vogtle Project File

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l 70 3040 W 321900 Georgia Power Company '

ATTN: Mr. R. E. Conway J*E*J*

Senior Vice President 3 Post Office Sox 4545 Atlanta, Georgia 30302 )

I Gentlemen:

We have initiated our review of your application transmitted on March 7,1986, for the special nuclear material license for the Vogtle Electric Generating Plant-Unit I and find that supplemental infomation is recuired for completion of the licensing process. The enclosure identifies the atditional infomation ,

I needed for our review. This information should be provided within 30 days so we can meet your requested licensing date.

If you have any questions, please call me at 301-427-4510.

Sincerely, j'a . .e,.,/ </1. 7 ,

George'H. Bidinder Uranium Process Licensing Section Uranium Fuel Licensing Branch Division of Fuel Cycle and Material Safety, HMSS

Enclosure:

As stated

9 M'R 1 31986 I

Supplemental Infomation Request '

Georgia Power Company Application Dated February 1986 Vogtle Electric Generating Plant-Unit 1 l

1. We do not believe that sufficient experimental data is available for low.

density hydrogeneous moderation, of low-enrichment uranium arrays to permit It will validation of k-effective calculations with a 0.98 limit.

be necessary to show that validated k-effective values do not exceed 0.95 for the stnrage arrays or extensive controls must be established to exclude the low-density moderator from the array.

2. The storage cells' characteristics, e.g., materials of construction, inside dimensions, and tes11 thickness, should be provided so that we can independently calculate the k-effective of the storage arrays for fresh and spent fuel racks. A cross-sectional view of the poisoned spent fuel cell showing dimensions and material locations would be very helpful.

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Georg a Pcwer Comcary Route 2, Box 299A Wayresecro. Georg a 30830 ('

Te!ecnore 404 554-9961 )

404 724-8114 Soutnem Comcany Services. Inc.

Post Office Box 2625 m B rmingham. Alaoama 35202 Tetecnore 205 870 6011 Vogtle Proj.ect May 14, 1986 Director of Nuclear Material File: X3BC35 Safety and Safeguarcs Log: GN-912 U. S. Nuclear Regulatory Commission Washington, D.C. 20555 REF: LETTER FROM GEORGE H. BIDINGER TO R. E. CONWAY DATED APRIL 10, 1986 NRC DOCKET NUMBER 50-424 CONSTRUCTION PERMIT NUMBER CPPR-108 V0GTLE ELECTRIC GENERATING PLANI - UNIT 1 SPECIAL NUCLEAR MATERIAL LICENSE

Dear Str:

Enclosed are eight copies of the supplemental information requested in the above referenced letter. We trust this information will be sufficient for you to co=plete the review and approval of this application.

Should you have any additional questions, please inquire.

Sincerely, f

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'J. A. Bailey Project Licensing Manager JAB /sm xc: R. E. Conway G. Bockhold, Jr.

R. A. Thomas D. C. Teper ,

W. C. Ramsey J. E. Joiner, Esquire B. W. Churchill, Esquire NRC Resident Inspector M. ~A. Miller (2) L. T. Gucwa B. Jones, Esquire B. E. Hunt Vogtle Project File 0483V i 1

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Supplemental Information Georgia Power Company Application Dated February 1986 Vogtle Electric Generating Plant-Unit 1

1. We do not believe that sufficient experimental data is available for low-density hydrogenous moderation, of low-enrichment uranium arrays to permit validation of k-effective calculations with a 0.98 limit. It will be necessary to show that validated k-effective values do not exceed 0.95 for the storage arrays or extensive controls must be established to exclude the low-density moderator from the array.

Response

The use of a k-eff limit of 0.98 for the low density hydrogenous moderation accident has been accepted by the NRC for the past several years. It is recognized by the NRC and the industry, that experimental data on low density hydrogenous moderation of low enrichment uranium arrays is limited. However,

.he 0.98 k-eff limit was deemed acceptable due to the effectively zero probability that any kind of accident can produce the optimum low density moderation needed to cause a criticality concern. This limit has been reported in several Westinghouse 17x17, 4 loop plant technical specifications and FSAR's included those of Vogtle. Technical Specifications and FSAR's using the 0.98 valve have been reviewed and licensed by the NRC.

In order to confirm the current status of the k-eff valve, Westinghouse had a discussion with a member of the NRC staff and it was determined that 0.98 is the acceptable k-eff limit for the low density moderation accident. This limit is based on present internal NRC review guidelines.

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2. The storage cells' characteristics, e.g., materials of construction, inside dimensions, and wall thickness, should be provided so that we can

, independently calculate the k-ef fective of the storage arrays for f resh and spent fuel racks. A cross-sectional view of the poisoned spent fuel cell showing dimensions and material locations would be very helpful.

Response _

Cross sectional drawings of the new and spent fuel cells are attached.

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GAE (VOGTLE) SPENT FUEL STORAGE RACK GEOMETRY CELL & WRAPPER:

SA 240 TYPE 304 BORAFLEX:

THK .078 B IO .020 GM/CM 2

+ ~ .075 STK (CELL ENCL) n

7.50

.020 STK (BORAFLEX) (WRAPPER) y y y IO.60 NOMINAL (CELL CENTER o U TO CENTER) d' '

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CAVITY) 1.43 NOM  ;

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Georg a Paratr Cc cary

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Tesec cre 404 554 9961 424 724 8M4 Sstrem Compaay Serwces. Irc Post Otoce Box 2625 B rm:rgaam. Alacama 35202 b fe ecrcre 2CS 87040f t Vogtle Project June 20, 1986 Director of Nuclear Material Safety File: X3BC35 and Safeguards GN: GN-951 U. S. Nuclear Regulatory Commission Washington, D.C. 20555 REF: (1) LETTER FROM GEORGE H. BIDINGER TO R. E. CONWAY DATED 4/10/86 (2) LETTER LOG GN-912 DATED 5/14/86 FROM J. A. BAILEY TO DIRECTOR OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS NRC DOCKET NUMBER 50-424 CONSTRUCTION PERMIT NUMBER CPPR-108 V0GTLE ELECTRIC GENERATING PLANI - UNIT 1 SPECIAL NUCLEAR MATERIAL LICENSE Gentlemen:

Enclosed are eight copies of revised supplemental information originally submitted in Ref. 2 as requested in Ref.1. In addition, a copy of the American Nuclear Insurers (ANI) Liability Policy No. NF-302, effective June 1, 1986, in the amount of $1,000,000 for the VEGP is attached. Note that Figure 2.2-7 of the revised supplemental information shows a change in location of the rack modules from that currently stated in the VEGP-Unit 1 SNM license application. The rack modules will be installed in the north east corner of the VEGP-Unit 1 spent fuel pool as shown in the attached figure.

The revised supplemental and additional information attached is currently being included in Revision 1 to the VEGP-Unit 1 Special Nuclear Material License application which should be issued before the end of the month. We trust this information will be sufficient for you to complete the review and approval of this application.

Should you have any additional questions, please advise.

Sincerely,

.he/ .

J. A. Bailey Project Licensing Manager JAB /sm xc: List attached

i i,

Director of Nuclear Material Safety File: X3BC35 and Safeguards Log: GN-951 June 20, 1986 Page 2 xc: R. E. Conway R. A. Thomas J. E. Joiner, Esquire B. W. Churchill, Esquire M A. Miller (2)

B. Jones, Esquire G. Bockhold, Jr.

D. C. Teper W. C. Ramsey NRC Resident Inspector NRC Regional Administrator L. T. Gucwa B. E. Hunt C. W. Hayes Vogtle Project File 0544V y

t Supplemental Information Georgia Power Company Application Dated February 1986 Vogtle Electric Generating Plant-Unit 1

1. We do not believe that sufficient erperimental data is available for low-density hydrogenous moderation, of low-enriched uranium arrays to permit validation of k-effective calculations with e. 0.98 limit. It will be necessary to show that validated k-effective values do not exceed 0.95 for the storage arrays or extensive controls must be established to exclude the low-density moderator frcs the array.

Revised Response Fresh fuel storage calculations by Westinghouse and others(l) have shown that in storage configurations with poison plates present the highest reactivity condition is the full water density case and as such, the low density hydrogenous moderation condition in not limiting. Since the vogtle spent fuel racks are designed to meet the Keff limit of 0.95 for 4.3 w/o fuel and full density water, the maximum Ke gg of fuel with an enrichment of 4.3 w/o or less under hydrogenous moderation conditions will be less than 0.95.

Evaluation of the Vogtle new fuel racks, which do not have poison plates, have shown that an enrichment of 3.5 w/o U235 can be stored with a Keff less than 0.88 under low density hydrogenous moderation conditions.

2. The storage cells' characteristics, e.g. , materials of construction, inside dimensions, and wall thickness, should be provided so that we can independently calculate the k-effective of the storage arrays for fresh and spent fuel racks. A cross-sectional view of the poisoned spent fuel cell showing dimensions and material locations would be very helpful.

?avised Response Cross sectional drawings of the new and spent fuel cells are attached.

Note that outside cell walls of certain peripheral cell rows do not include Boraflex as shown in Figure 2.2-7.

(1) "Supercriticality Through Optimum Moderation in Nuclear Fuel Storage" from Nuclear Technology Volume 48, May 1980 - J. M. Cano, et al.

i l SNM T,ICENSE APPLICATIOM FIGURE 2. 2-6 CELL & WRAPPER:

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=

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I.43 NOM l.II MIN (WATER GAP)

U (H OUTSIDE CELL WALLS OF CERTAIN PERIPMER AL CELL ROWS DO NOT INCLUDE 80RAFLEX AS SHOWN IN FIGURE 2.2 7

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o t s cenway June 30, 1986 Director of Nuclear Material Safety File: X38C35 and Safeguards Log: GN-961 U. S. Nuclear Regulatory Commission Washington, D. C. 20555 NRC DOCKET NUMBER 70-3040 CONSTRUCTION PERMIT NUMBER CPPR-108 V0GTLE ELECTRIC GENERATING PLANT - UNIT 1 SPECIAL NUCLEAR MATERIAL LICENSE - REVISION 1

Dear Sir:

Georgia Power Company, acting on its own behalf and as agent for Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and the City of Dalton, Georgia, hereby submits in accordance with 10 CFR Part 70, Revision 1 to the Vogtle Electric Generating Plant (VEGP) Unit 1 application for a Special Nuclear liaterial License.

This revision includes:

1. additional information requested by your staff (Biddinger to Conway, dated April 10,1986)

2. proof of financial protection as required by 10CFR140.15

3. clarification of fuel storage areas involved during new fuel receipt

4. increase in total weight of U-235 requested due to increase in nominal fuel assembly uranium weight

5. description initial fuel receipt fire protection program Also included are instructions for inserting the Revision 1 material.

>4 s

t June 30, 1986 3

File: X3BC35 Log: GN-961 Page two The initial fuel receipt fire protection program included in Revision 1 is a temporary program implemented to meet our commitment to CMEB 9.5-1 paragraph C.1.e for fire protection for buildings storing new fuel from initial fuel receipt until the fire protection program for Unit 1 is fully operational. No changes are being made to the program as described in the FSAR. The program included in Revision 1 describes l

how we meet our FSAR commitment and no FSAR change is proposed.

Eight (8) copies of this revision, as required by Regulatory Guide 3.15, are enclosed for your review and approval. Your prompt consideration of this application will be appreciated, i Respectfully submitted, f

R. E. Conway REC /KWK/wkl Enclosure I

4 cc: R. A. Thomas .

J. E. Joiner, Esquire B. W. Churchwell, Esquire M. A. liiller (2)

B. Jones (w/o enclosure)

L. T. Gucwa C. W. Hayes G. Bockhold, Jr.

NRC Regional Administrator NRC Resident Inspector D. C. Teper W. C. Ramsey (w/o enclosure)

Vogtle Project Files i

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