ML20148J317
| ML20148J317 | |
| Person / Time | |
|---|---|
| Site: | 07001308 |
| Issue date: | 09/22/1978 |
| From: | Dawson D GENERAL ELECTRIC CO. |
| To: | Myers S NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 7811150251 | |
| Download: ML20148J317 (10) | |
Text
1 GENER AL h ELECTRIC
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,,, -gy RECEIVED PROGRAMS ppny'Ei'F T DIVISION GENERAL ELECTRIC COMPANY,175 CURTNER AVJa SAN JOSE,QLI(OR){lA 95125 408*925-6330 MC 86T 93 ;5 m3.
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DMD-222
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Docket No. 70-1308 ff/
SNM-1265 j~?,
September 22, 1978
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n l!,A y/f Office of Nuclear Material' Safety and Safeguards Attention: Mr. Sheldon Meyers, Director Division of Fuel Cycle & Materials Safety U.S. Nuclear Regulatory Commission Washington, D.C.
20555 i
SUBJECT:
DOCKET N0. 70-1308, SNM-1265 APPLICATION FOR AMENDMENT
Reference:
- 1) Dairyland Power Cooperative letter, Madgett to Boyden, dated March 6,1978 (LAC-5195) 2)
Department of Energy letter, Thorne to Madgett, dated July 12, 1978
- 3) Dairyland Power Cooperative letter, Madgett to Miles, dated July 19,1978 (LAC-5404)
Gentlemen:
General Electric Company hereby requests amendment of Material License No. SNM-1265 to authorize the storage of 10x10 La Crosse BWR fuel bundles, a configuration not presently authorized for storage at the Morris facility.
This request results from a serious situation involving the potential forced shutdown of the reactor.
The situation is described more fully, together with other alternatives that were considered in references (1), (2),
and (3) (Attachment 1).
To further define BWR bundles of the type used at La Crosse, they are 10x10 rod arrays with nominal dimensions of 5.61 x 102.34 inches IOf20 115
.61115d2FI C
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GENER AL h ELECTRIC
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and a maximum enrichment of 3.93% U-235.
Fuel rod lattice dimensional characteristics are as follows:
rod pitch
.565 inches rod outside diameter
.396 inches pellet diameter
.350 inches cladding
.020 inches Type 348SS An analysis was made of the keff for La Crosse 10x10 GWR fuel bundles in the BWR stainless steel storage baskets currently in use at the Morris facility. The calculated value of keff is 0.86 j
(Attachment 2), which is within the storage pool keff limits of SNM-1265.
The maximum rod lattice k. was calculated to be 1.35 (Attachment 3).
These analyses show that the specified La Crosse BWR fuel bundles may be safely stored at the Morris facility in the BWR stainless steel storage baskets.
Since SNM-1265 is written to accept specific BWR fuel bundle con-figurations which do not currently include 10x10 fuel bundles with the lattice characteristics of this fuel, it is requested that the Materials License SNM-1265 be amended as follows:
Amend license section 6-A and conditions 14 and 16 by adding the italicized wording as shown.
6-A.-Fuel assemblies fromreactors using natural water for cooling ?nd enriched not greater than 5 percent U-235 with t. maximum reactivity not to exceed k.
(cold) of 1.40 for 7x7 or 8x8 BWR fuel bundles,1.36 for 10x10 BWR fuel bundles (<5.65 inches square), 1.37 for 15x15 PWR fuel bundles (<8.55 inches square),
and 1.41 for 14x14 PWR fuel bundles (<7.80 inches square).
These fuels will possibly contain:
1.
Uranium 235 2.
Plutonium 3.
Fission Products
- 14. - Fuel to be stored shall meet k. limits of 1.40 for 7x7 or 8x8 BWR fuel, 1.36 for 10x10 BUR fuel
(<5.65 inches square) 1.37 for 15x15 PWR fuel
(<8,55 inches square),and 1.41 for 14x14 PWR fuel l
(<7.80 inches souare) without allowance for burnup.
t
GENERAL h ELECTRIC i
16.- Fuel stored shall be limited to that not exceeding the maximum enrichments, and range of other parameters shown in Figures A.11-1 and A.11.2 of NED0-21326, eith the following exception: the licensee is authorized to atore stainlese steel clad La Crosse 10x10 BWR fuel vith pellet diameter of 0.35 inches, a pitch of 0.565 and enriched to a maximwn of 3.93 percent U-235.
The. requested amendment to SNM-1265 does not raise any unresolved safety issues; therefore this application is considered an "adminis-trative" amendment for licensing fee purposes and a check.in the amount of $150 is enclosed.
Respectfully submitted, GENERAL ELECTRIC COMPANY l
bl OW 0.M. Dawson, Manager Licensing & Transportation
/bn Enclosure t
4 n.tutnAND POWEIt C00PEft.tTIVE Sa Grone, Obomirr 54601 March 6, 1978 In reply, please refer to LAC-5195 Mr.
J. E.
Boyden, Manager Contract Management M/C 856 General Electric Company 175 Curtner Avenue San Jose, California 95125
SUBJECT:
STORAGE OF LACBWR IRRADIATED FUEL
Dear Mr. Boyden:
As a result of your telephone conversation on Tuesday, February 28, 1978 with Messrs, Lynn Papwor,th and Seymour Raffety of the LACBWR staff, we are submitting a formal request for the General Electric Company to consider our interest in obtaining short-term storage in the Morris storage pool for at least twelve (12) LACBWR irradiated fuel assemblies.
Start of LACBWR from the recent refueling outage is expected to commence this week and operations should continue for approximately ten (10) months.
At the present time the LACBWR fuel storage pool has a capacity for one-hundred thirty-four (134) irradiated fuel assemblies.
There are one-hundred fourteen (114) locations now occupied and with the forecasted discharge of at least thirty-two (32) additional irradiated fuel assem-blies at the end of the next cycle, there will be a shortage of at least twelve (12) storage locations.
It is also possible, in the case of unexpected failures, that a few more irradiated fuel assemblies would require core discharge and storage.
Although the need for extra storage would nct actually occur until the end of the next fuel cycle, it would be advantageous for us to be able to create the needed vacancies in the LACBWR storage pool at an earlier date, preferably during the summer months.
Therefore, we would antici-pate transferring at least twelve (12) irradiated fuel assemblies from LACBWR to Morris during July or August, 1978, for example.
The ATCOR Vandenburgh fuel shipping cask would be used for this transfer.
We understand that it can be readily handled at Morris.
We are actively pursuing an alternative for obtaining additional fuel storage capacity.
Design work is underway to increase the storage capacity of the LACBWR storage pool to 432 locations.
It is expected that the initial application to the NRC for an amendment to our oper-ating license dealing with the proposed storage pool modification will RECElvED MAR 1C 1978
- 1. E. BOYDEN
n j
LAC-5195 Mr.
J. E.
Boyden, Manager March 6, 1978 Contract Management General Electric Company
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be submitted in April 1978.
Delays due to regulatory review and l
public intervention are anticipated and it is not likely that approval for the modification together with its fabrication and installation can take place prior to the end of the next fuel cycle.
The ability to store a limited number of irradiated fuel assemblies for a temporary period (12-18) months) would enable us to continue plant operations and complete the necessary modifications to provide on-site storage thrcugh 1992.
Upon completion of the modifications, the LACBWR fuel stored at Morris would be returned to LACBWR.
Other storage alternatives such as the use of the NSS Savannah storage storage at Barnwell, Indian Point No. 1 and pool at Galveston, Texas, the decommissioned Pathfinder plant have been examined with negative-results.
We have also requested storage assistance from the U.
S.
Department of Energy and little encouragement has been received duerto our need for extra storage within a few months.
The Department of-Energy has stated that there is insufficient time for it to act in our behalf.
The seriousness of the fuel storage situation at LACBWR cannot be over-looked since failure to obtain additional temporary storage will result in a shutdown of a valuable energy source.
I am hopeful that a storage agreement and schedule can be arranged to permit LACBWR's continued operation.
We would welcome the opportunity to discuss the details of our storage requirements.
In this regard, Dr. Seymour Raffety and Mr. Lynn Papworth (608-689-2331) will be available to participate in the discussions.
Very truly yours, DAIRYLAND POWER COOPERATIVE h,
4
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g Jh P. Madgett, General Manager JPM:LGP:af l ('
DitIR1LtND POWER C00PERitT1YE l
Sa Grosse, QYisconsin 54601 July 19, 1978 In reply, please refer to LAC-5404 Mr. R. R. Miles, Specialist Market Development General Electric Company Nuclear Energy Marketing Dept.
175 Curtner Avenue San Jose, California 95125
SUBJECT:
STORAGE OF LACBWR IRRADIATED FUEL
Reference:
(1) DPC Letter, Madgett to Boyden, dated March 6, 1978 (LAC-5195).
Dear Mr. Miles:
With reference to our recent discussions regarding the tentative contractual agreement for interim storage of La Crosse Boiling Water Reactor (LACBWR) irradiated fuel assemblies at the General Electric Co. Morris facility, the enclosed copied letter, Thorne (DOE) to Madgett (DPC), dated July 12, 1978, is submitted for your review.
As indicated in our previous letter (Reference 1), the interim fuel storage is needed to allow continued La Crosse reactor oper-ation while additional on-site fuel storage is actively pursued.
Upon completion of the rerack modification, which is now expected to come about in 12 to 18 months from this date, the LACBWR fuel stored at Morris is to be returned to LACBWR.
The subject DOE letter is provided as an indication of willingness on the part of DOE to accept LACBWR fuel assemblies from the pro-posed interim storage at Morris should circumstances, beyond the control of DPC, prevent the intended fuel retrieval back to LACBWR, With the assurances provided in the DOE letter, it is our hope that formalized contractual negotiations can now proceed in an expedited manner between General Electric Co. and Dairyland Power Cooperative and we welcome the opportunity to discuss storage contractual de-tails at your earliest convenience.
In this regard, Messrs.
L. Papworth and S. Raffety will be available to participate in the discussions.
Very truly yours, DAIRYLAND POWER COOPERATIVE
-=mc;
%,:D' John D. Madge.tt,, b ral Manager m.-
JPM:LGP:af Enclosure
@@e Mr._ Fred Gates, GE-Minneapolis, MN
.7 RfCDJUL 1 8 1978
- f..,,%,.
p
%w' JUL 121978 Department of Energy _
R E C E I V E D' Washington, D.C. 20545 JUL 171978 GEN. MGR.
Mr. ' John P. Madgett, General Manager Dairyland Power Cooperative P. O. Box 817 Lacrosse, WI 546D1
Dear Mr. Madgett:
In response to your letter of April 25,197P., and our subsequent 16, 1978, the meeting with Dairyland representatives on May Department of Energy (DOE) has considered possible actions which could assist Dairyland.in providing adequate storage space for the We understand that you have applied next Lacrosse fuel discharge.
to the Nuclear Regulatory Commission for a license to expand the Lacrosse storage basin and that, if approvcJ, additional space would We also understand you have discussed be available within a year.
obtaining interim storage space at the General Electric Morris facility to provide sufficient storage space for your next discharge.
At the meeting you asked if DOE could give an indication of its
()
willingness to accept at a later date Dairyland's spent fuel that had been stored on an interim basis away from your reactor.
s.
We would accept Dairyland's spent fuel from the interim storage space if the authority envisioned in the Government's spent fuel policy announced last fall had been enacted and if the tenns and conditions underlying that authority were met.
Although we cannot state specifically what these terms and conditions will be, we presently expect that at least the following would be required:
- 1. DOE have space available to store or dispose of the fuel in accordance with the enabling legislation.
- 2. Dairyland have no other reasonably available storage place either at'or away from its reactor.
-3. Dairyland agreement to the tenns and conditions of a storage /
including the payment of appropriate charges disposal contract, established to implement spent fuel storage policy legislation.
4
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- Mr. John P. Madgett We understand that you wish to use this information in your contacts with General Electric and other companies that may have storage space We, therefore, specifically authorize you to give copies available.
of this letter to such companies. If they wish further information about DOE's present intentions relative to the storage or disposal of 301-353-4728.
spent fuel, they may call Michael Lawrence at Sincere,1y, I
f Ro ert D. Thorne g (Assistant Secretaryfor Energy Technoloty i
s
's.
ATTACHMENT 2 i
OBaHelle Pacific Northwest Laboratories P.O. Box 999 Richtand, Washington 99352 T.i.onen.(sos) 942-0855 Telen 324345 September 11, 1978 Mr. R. G. Barnes, M'anager Technical Development General Electric Uranium Management Corporation Mail Code 858 175 Curtner Avenue San Jose, CA 95125
Dear Bob:
Subject:
Evaluation of Fuel Baskets Containing Lacrosse BWR Fuel Bundles The calculation you requested in your letter to C. L. Brown dated August 31, 1978, has been completed.
The value calculated for the 8.625 inch center-to-center spacing between bundles (with 0.1295 inch stainless steel pipe thickness) for 3.925% 235U enriched Lacrosse fuel is keff =
0.855 t 0.006.
The model on page 9 of:
Criticality Safety Basis for the MFRP Project-1 Fuel Bundle Storage Baskets predicts keff = 0.755 with a maximum of keff = 0.784.
However, note that the bundle size is 5.65 inches square rather than the 5.166 inches of the 7 x 7 BWR bundles analyzed previously.
This 20% increase in bundle area accounts for the increase in keff.
A standard QA check-off sheet as used,before is attached.
If you have any questions, please give me a call.
i Sincerely, R. A. Libby Sr. Criticality Safety Specialist i
i RAL/ par s
Enclosure cc: CL Brown ED Clayton File /Lb Concurrence hru E. D. Clayton V-AssociateManagd Nuclear Analysis
i ATTACHMENT 3 NO OBattelle Pacific Northwest Laboratories P.O Box 999 Rechland, Washington 99352 T.i. phone (509) 942-0855 Telen 32 6345 July 11, 1978 i
Mr. R. G. Barnes, flanager Technical Development General Electric Uranium itanagement Corporation Mail Code 858 175 Curtner Avenue San Jose, CA 95125
Dear Bob:
Subject:
Evaluation of Lacrosse BWR Fuel Bundles l
The calculations yw requested in your letter to C. L Gra, n dated June 30, 1978 have been completed. The values for. - w h
{
j lattice k.'s were calculated to be:
)
235 Enrichment, wt%
U EGGNIT k.
KENO-II %
i 3.634 1.3316 1.330 0.003 3.925 1.3519 1.352 0.003 A standard QA check-off sheet as used before is attached.
If you have any questions, please give me a call.
Sincerely, h
R. A. Libby j
Senior Criticality l
Safety Specialist h,
h\\g Concurrence i
E. D: Clayton Associate Man ger Nuclear Anal sis i
RAL/ par O.
i V
Enclosure l
cc: CL Brown ED Clayton File /Lb l