ML17262A415
| ML17262A415 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 03/08/1991 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9103180125 | |
| Download: ML17262A415 (10) | |
Text
ACCIELERATED DI TRIBUTION DEMONST TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR: 9103180125 DOC. DATE: 91/03/08 NOTARIZED:
NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas
& Electric Corp.
RECIP.NAME RECIPIENT AFFXLXATION JOHNSON,A.R.
Project Directorate I-3 DOCKET g
05000244
SUBJECT:
Forwards data reflecting current status of info in FES re I
plant operation, including transport of new fuel 6 transport of irradiated fuel.
DISTRIBUTXON CODE:
C001D COPXES RECEIVED:LTR ENCL SXZE:
TXTLE: Licensing Submittal: Environmental Rept Amdt 6 elated Corr spondence NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A INTERNAL: AEOD/DSP/TPAB OC B
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'eictj'II/rnZZZZ ROCHESTER GAS AND ELECTRIC CORPORATION cs 0
89 EAST AVENUE, ROCHESTER N. Y. 14649-0001 ROBERT C MECREDY Vice President Cinne Nucleer Production March 8, 1991 TELEPHONE AREA CODE 7t 6 646 2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Allen R. Johnson Project Directorate I-3 Washington, D.C.
20555
Subject:
Environmental Issues Related to CP-OL R.E.
Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Johnson:
Attached to this letter is data which reflects the current status of certain information contained in the Final Environmental Statement related to the o eration of R.
E.
Ginna Nuclear Power Plant Unit 1 (FES).
Recent conversations between members of the RG&E staff and the NRC have identified a need for this information.
The paragraph numbers associated.
with the data that is being provided correspond to specific paragraphs in the FES.
Bold lettering replaces information presently provided in the FES.
Very truly yours, Robert C.
Me ed JRJ/144 Attachment xc: Mr. Allen R. Johnson (Mail Stop 14D1)
Project Directorate I-3 Washington, D.C.
20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector 9103180128 510 0 =-m PDR ADOCK 05000244 D
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5.5.2 Trans ort of New Fuel The new fuel for the reactor at the Ginna plant is slightly enriched uranium in the form of sintered uranium dioxide pellets.
These pellets are stacked and sealed in Zircaloy-4 tubes to form 144-in.-long fuel rods.
The fuel rods are fabricated into individual fuel assemblies of 179 rods:
each assembly weighs (as UO~) about 770 lbs.
In each year of normal operation, about one fourth of these (32) will be replaced.
Fuel assemblies are currently shipped from the Westinghouse Corporation facility at
- Columbia, S.C.,
some 800 miles distant from the plant, and are shipped by truck in NRC-DOT-approved containers.
About three truckloads, each containing up to twelve assemblies, will be required annually for replacement fuel.
Table 5.4 lists the radiological doses expected to result from exposure due to transportation of new fuel to the plant site of a typical light water power reactor. 'ssumptions defined under "normal conditions of transport" in. Table. 5.4 are conservative.
The plant currently requires fewer truckloads to transport new fuel and. radiation doses are substantially lower than those reported in Table 5.4.
5.5.3 Trans ort of Irradiated Fuel The current U.S.
policy prohibits the reprocessing of commercial spent nuclear fuel and Congress
- has, in accordance with the Nuclear Waste Policy Act of 1982 as
- amended, designated that discharged spent fuel. be stored. at utility sites until delivery and. title transfer to DOE for permanent disposal in geologic repository.
Delays in the DOE program have resulted in a revised
- DOE, schedule which indicates that a: permanent repository'ill not be operational prior to 2010.
- However, the DOE is pursuing efforts. to have an interim storage facility in place which would allow them to begin accepting spent fuel prior to the availability of a permanent disposal. facility.
To continue operation of the plant independent of DOE schedules, RG&E has made its own arrangements.
The Ginna plant spent fuel storage pool has. been reracked to a maximum capacity of 1,016 positions. designed to store fuel assemblies and non-fuel-bearing components.
However, Spent Fuel Pool handling equipment. provides access to a magnumof 988 positions.
Following the Cycle 19/20 core reload. in Spring 1990, the spent fuel pool inventory consists of 59& fuel assembly and 37 non-fuel-bearing positions.
After allowing for a full core discharge capability, the plant has 232 positions
&V
remaining to store projected, spent fuel discharges.
Based on expected. discharges of about 32 fuel assemblies per year, spent fuel pool storage capability allows operation through the Spring of 1999.
The rod consolidation process is being explored and a-demonstration program has been conducted.
Rod consolidation would provide for operation beyond.
the.
year 2009 with full core discharge capability.
1f a Federal repository is not available by then, other methods of onsite
- storage, such as dry cask storage, could be employed.
Table 5.4 lists the radiological doses, expected to result from exposure due to transportation of irradiated. fuel to the plant site of a typical light water.
power reactor.
Because the plant. does. not expect to transport irradiated.
fuel, radiation doses are bounded.. by the results in. Table 5.4 which are considered. to he highly conservative.
Waste in the form-of resins. or filters. is shipped dewatered:
in 120 to 210 cubic foot High Integrity Containers.
Approximately 150 curies of waste. is shipped. in this fashion a year and based.
on DOT regulations the maximum. dose rate-at the exterior surface. of the shipping container is less than 200 mr/hr.
Approximately 5-high, integrity containers; are shipped, each year-.
The above volumes are predicated on the. assumption that all waste water is processed using-demineralizers.
On occasion, waste water is evaporated, with the, result= that activity remains in the evaporator bottoms rather than being deposited on resins.
Should. this method.. he used.,
only 120 curies of waste (primary resins and. filters) would. be shipped in the 2 High Integrity Containers.and: approximately 30 Curies. of waste would be shipped; (solidified. in cement) in approximately 450 fifty-fivegallon drums.
Again, based, on DOT regulations, the maximum surface. dose rate. of these.
containers is 200 mr/hr.
Most dry activated. waste. (mainly contaminated: person anti.-
contamination clothing and plastic used in contamination control) is shipped. in bulk form to a vendor for volume reduction and packaging.
Bulk containers of varying sizes can hold. up to 2600 cubic feet-of material.
Following.
processing by the
- vendor, approximately 50 curies.
(4000 cubic feet) of waste is delivered each year for disposal at
- Barnwell, South Carolina.
The vendor. is located., in Oak
- Ridge, Tennessee and. ships waste in containers. that hold.
from 44.5 to 54.5: cubic feet when shipping super compacted.
waste and.
ships 55 gallon drums for the shipment of incinerated waste.
In total, Ginna delivers an average: of 5000 cu. ft. with a content of 200 Curies of waste to disposal sites, each year.
t
Either directly or through a vendor, the applicant continues to ship solid radioactive waste by truck-to approved. burial locations.
Table S-4 of 10CPR51.52 shows the environmental impact expected to result from transportation of radioactive wastes to the burial site from. a typical light water power reactor.
The environmental. impact from the; operation of Ginna Station will remain within the restrictions of Table S-4 throughout plant life, including. the requested, license.
extension.
0 i1 4 II