ML19270H529

Application for SNM License for Storage Only of Fuel Elements & Byproduct Matl

ML19270H529
Person / Time
Site:	Three Mile Island
Issue date:	06/08/1972
From:	John Miller METROPOLITAN EDISON CO.
To:
Shared Package
ML19270H523	List: ML19270H527 ML19270H528 ML19270H529 ML19270H530 ML19270H531 ML19270H532 ML19270H533 ML19270H539 ML19270H540 ML19270H541 ML19270H543
References
NUDOCS 7911040158
Download: ML19270H529 (8)

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APPLICATION FOR SPECIAL NUCLEAR !!ATERIAL LICENSE FOR STORAGE ONLY OF FUEL ELEMENTS MiD BY-PRODUCI MATERI AL .

R)R Tile TilREE lHLE ISLAND NUCLEAR STATION

UNIT 1 METROPOLITE! ED1 SON COMPANY 7779 ??l es, cm e

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. TilREE MILE ISLAND LC!IT 1 FUEL AND

BY-PRODUCT STORACE LICENSE APPLICATION

' 'This application is filed pursuant to titic 10 code of Federal Regulations, Part 70 for authori=ation to receive , possess , store ,

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inspect, and package for transport nuclear fuel assemblics. Authori-zation is also requested for the storage of other radioactive by-product materials to be used in subsequent operations of the reactor. It is requested that the Special Nucicar Materials License remain in effect until receipt of the Operating License.

The following information is submitted in support of the application:

1.0 APPLICANT '

r i Metropolitan Edison Company 2800 Pottsville Pike, Muhlenberg Township Berks County, Pa.

Mailing Address: P. O. Box 542, Reading, Pa. 19603 2.0 ADDRESS OF STORAGE SITE .

The Three Mile Island Nuclear Station is located on Threa Mile Island near the East shore of the Susquchanna River in Londonderry Township of Dauphin County, Pennsylvania.

3.0 CORPOPATE INF0PJtATION The informatien set forth in the application for Construction Parmit and Operating License, Docket 50-289 dated May 3,1967, for the Threc Mile Island Nuclear Station Unit 1, I hereby incorporated b. re f e ren:0 o  ???~

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Findings concerning control and ownership of the applicant are set forth in the Order of the Atomic Safety and Licensing Board dc.ted May 16, 1972.

4.0 RADT0 ACTIVE MATERIAL .

4.1 Fuel Elements

'Ihc 177 fuel assemblics of the initial core that will be roccived and stored are described in the following tabic:

Square cross-section 8.536 inches square of fuel asse:bly Effective fuel length 144 inches -

Over-all fuel asscebly length 165.625 inches Rod array type 15 7. 1C = 225 (208 fuel rods 16 control rod channels 1 instrucent channel)

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kod clad thickncss .0265 inches Rod clad material Zr-4 Rod outside diarcter .430 inches No. of fuel asserblics 177 U-235 enrichments (%) 2.06% 2.72% 3.05%

No. of Assemblics 56 61 60 UO2 Weight Per assembly (pounds) 1,159 .5 lb s . UO2 UO2 Weight per rod 5.5 7 lb s . CO 2 U weight per asserbly 1,022. 2 lbs . U The maximum arount of special nuclear caterial JC JJhl.as_kilograts k.n of U-235, which may be possessed at any one time is 10,300 kilograms. This t c ; re i.cn ts th e i ni t ia l c o t e an d as.s um.'s th a t all additional s torage si 'ce han eeen utu i. d. '

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,c s 4.2 Other Radicactive !mterials Up to 50.1 curies of. Cesium 137 will be received for subsequent use as gagma sources for calibrations in connection with reactor operation.

Up to 800 curies of An.ericium will b'c received for subsequent use as neutron sources.for reactor initial startup, operation, and portabic instrument calibration.

5.0 TP).NSPORTATION All fuel assemblics are to be de_ivered to the site in accordance with shipping procedures and arrangements of the Babcock & Wilcox Company.

The fuel assemblics will be shipped in steel shipping containers (BSU Model B Fresh Fuel Shipping Container) supplied by the fuel

• manufacturers, Babcock &

Wilcox Company as licensed under S:01-1168. The Model B shipping container has been assigned DOT Special Perait No. 6206. ,

Fuel will be shipped to the site by truck, six containers per truck

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and one or two fuel assemblies per container Upon arrival at the site, the .

contain~cre and truck trailers will be inspected for damage and renitored for external radioactive contamination.

6 . 0' STORACE CONDITIONS The fuel asse:blies will be stored in the Fuel Handling Building shown on Figures 1-3, 1-4, 1-5, 1-7 & 1-8 of the Final Safety Analysis Repart.

The fuel storage pools arc constructed of reinforced concrete and lined with stainless steel. The fuel will be stored in the fuel storage racks in a wet condition with a boron concentration of 2270 PPM. Since the Fuel Handling Building is a reinforced concrete structure, and the fuel assemblies will be stored under borated water, it is conc ide red e:<t rer.;ely unlikely the.t c fire f

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• r will occur. However, the use of flamnabic materials in the Fuel Handling Building will be carefully controlled as an added margin of safety.

6.1 Inspection & Handling As soon as practicable af ter arrival at the Fuel Handling 'silding, the shipping containers will be unloaded from the truck trailers. The new fuel assemblies will be removed one at a time from the shipping containers and placed in a vertical position in the new fuel inspection stand, to check for integrity and numbering. Damaged rods, if any, will be detected by visual inspection and by the performance of radiation surveys by quali-fled personnel as the shipping containers are opened or as the ascenblics are unwrapped. All activities of unloading, inspecting, moving and storing of the asse blics will be performed in accordance with written procedures which will have been approved by the Three Mile Island Nuclear Station Super-intendent.

6.2 Safety Evaluation The storage racks in the Fuel Handling Building are designed to pro, vide a center-to-center spacing of twenty-one inches or more between the fuel assemblies. This arrangement provides for upright storage of the fuel assemblics in an array in which the effective multiplication factor is less than 1.0 in the flooded condition. This conclusion is based on the calculated Kegg of 0.87 in cold unborated water for 3.5 percent enriched fuel asser311es in a 21-inch square array (1) . Since the highest enrichment for which this application is being made is 3.05 percent, a factor of conservatism is p:e-sent in the calculations.

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se tJ It is concluded that since the fuel assemblies w'ill be stored in a 21-inch square array in water whose baron concentration is 2270 PPM, the storage nethods are adequate to prever t criticality and protect the health and safety of the public.

6.3 Radiation Monitoring

. The following RMS instrumentation will be operational and will be utilized to provide continuous radiation monitoring in the Fuel Handling Building:

6.3.1 MI-G9 Fuel Handling Brdige Detector, Victorcen Instrucent Corporation Area Monitor (Ion Chatber) Model 845 Range .1 to 107 cr/hr.

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6.3.2 RM-/.13 Fuel Handling Building Air Monitor (particulatc, s

gaseous, iodine). Victoreen Instruacnt Corporation Model 840.

The radiation monitors listed above will have an external clara of sufficient intensity to be heard throughout the storage and handling area. An assortment of portable and laboratory radiction instrumentation will also be available during receipt, inspection and storing of the feel assemb lics .

The above centioned radiation conitoring equipment will be in service prior to receipt of fuel and will be used for both routine and energency situations.

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6.3.3 Personnel Monitorine.

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All authorized personnel who enter the fuel inspection &

storage area shall carry personnel c.onitoring devices. In addition, routine

. radiation' surveys will'be conducted in the inspection and storage area.

6.3.4 Monitoring of Neu Fuel Asserblics Each new fuel assethly will be monitored for alpha and beta contamination. A beta-gn=na dose rate survey will alco be taken of each fuel assenbly. All readings will be recorded and identified by fuel assembly number.

6.3.5 Emergency Procedure An cecrgency procedure will be posted in the Fuci Handling Building. In the unlikely event of a radiological incident, this procedure

(' uill provide the following information: the evacuation route to be utilized by personnel when 1 caving the Fuel llandling Building, and lir. ting of reentry procedures to be followed af ter the accident. .

All personnel involved in fuel handling operations will bc trained in the energency procedures utilized in the event of a radiological incident.

Th'c Radiation Protection Supervisor or his designated Radiation Protection technician will be responcibic for execution of the emergency procedure.

s 6.3.6 Request fo r Exc eo t i c_n, Applicant requests exemption from the conitoring and er.2rgency procedures requirements of Section 70.24, 10 CFr. 70. This exemption ::

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requested because the nature of the special nuclear material, storage arrange-ments, and procedural controls shich Applicant proposes to employ preclude eny possibility of accidental criticality during receipt, unloading, inspec-tion and storage of the new fuel assc=blics.

7.0 INDE!NITY Application will be made by Met-Ed to Nucicar Energy Liability Insurance Associates for insurance in the amount of $1,000,000 for the period from first shipment of fuel asserblics frora Babcock & Wilco):'s manufacturing facilities in Lynchburg, Virginia, until the first fuel assembly is loaded into the reactor. Proof of financial protection will be furnished prior to fuel shipeent.

( i METROPOLITAN EDISON C0FT/u';Y By D1

/' Vice President Attest:

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r D Swotn and stiscribed to before ce this l ~k/' day o f!. u- s- 1972.

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