ML20086M530

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Responds to NRC 911028 Request for Addl Info on License Amend Request 199 Re Extension of Duration of OL to Forty Years from Date of Issuance of full-power License.Encl Addresses Conditions of 10CFR51.52
ML20086M530
Person / Time
Site: Oyster Creek
Issue date: 12/11/1991
From: J. J. Barton
GENERAL PUBLIC UTILITIES CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C321-91-2310, NUDOCS 9112170508
Download: ML20086M530 (3)


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GPU Nuclear Corporation Nuclear

= :r 88 Forked River New Jersey 08731-0388 609 971-4000 Wnter's Direct D,al Number.

December 11, 1991 C321-91-2310 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C.

20555 Gentlemen:

Subject:

Oyster Creek Nuclear Generating Station Operating License No. DPR-16 Docket No. 50-219 Request for Additional Information - License Amendment Request No. 199 In response to NRC request for additional information, dated October 28, 1991 of this letter adoresses the conditions of 10 CFR 51.52 for OrNGS as related to the request to oxtend the duration of the operating Itcense to forty years frc.n the date of issuance of the full-power license.

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.J a't i Vic re ident and Director, OCNGS JJB/DJD/amk Enclosure cc: Administrator, Region I NRC Resident Inspector Mr. Alex Dromerick, Jr.

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GPU Nuclear Corporation is a subsidwy of General Pubhc Utihties Corporation i

'e C321-91-2310 Page 1 of 2 ENCLOSURE I The following item by item position description addresses the conditions in paragraph (a) of 10 CFR 51.52:

(a)(1) The reactor has a core thermal power level not exceeding 3,800 megawatts; POSITIQN lhe OCNGS licensed maximum steady state power level is 1930 MWt.

(2)

The reactor fuel is in the form of sintered uranium dioxide pellets having a uranium-235 enrichment not exceeding 4% by weight, and the pellets are encapsulated in zircaloy rods; POSITION OCNGS currently -utilizes reactor fuel in the form of sintered uranium dioxide pellets having a maximum U-235 enrichment of 3.95 wt. percent, and the pellets are encapsulated in zircaloy rods.

(3)

The average level of irradiation of the irradiated fuel from the reactor

~does not exceed 33,000 megawatt-days per metric ton, and no irradiated fuel assembly is shipped unless at least 90 days after it is discharged from the reactor.

ROSITION The average level of' irradiation of the irradiated fuel from the reactor for the current operating cycle (E0C 13) is approximately 27,000 megawatt-days per metric ton.

OCNGS would not ship any spent fuel prior to 180 days discharge from the reactor.

(4)-

With the exception of irradiated fuel, all radioactive waste shipped from the reactor is packaged and in a solid form; POSITION-All radioactive waste shipped directly from the Oyster Creek Site to final burial is either solid by material composition, or solidified and/or dewatered. ' Dry Active Waste, such as wood, paper, plastic, metal and some wet waste (contaminated waste oil),

are sent to off-site Waste t

Reprocessors for volume reduction and final disposition.

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- r-C321 91-2310 Page 2lof:2-

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(5)

Unirradiated fuel-is snipped to the reactor by truck; irradiated fuel is shipped from the reactor by truck,_ rail or barge; and radioactive waste other than irradiated fuel is shipped from the reactor by truck or rail; and POSITION

- These shipment methods are consistent for OCNGS, with the clarification-L that irradiated fuel is no longer shipped from the site and there are no plans to do so' in. the near future (untti a suitable repository is available).

-(6)l The environmental impacts _ of transportation of fuel and waste to and_ from the reactor, with respect to normal conditions of transport and possible accidents in transport,' are as set forth in Summary Table S A in paragraph -

(c) of this section; and the values in 'the table represent the.

contribution of_ the transportation to the environmental costs of licensing the reactor.-

POSITION The environmental impacts attributable to the transportation of fuel and-

- waste to and from the OCNGS site, with respect to the normal conditions of

- transport and-possible accidents in transport, have been reviewed and it

-is'. concluded that the environmental impacts-are bounded by those identified in 10 CFR 51.52. The: basis-for thisLconclusion is that 10 CFR

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51.52 data is based on an annual refueling and shipment of 180 spent fuel assemblies: per. reactor year (NUREG-Oll6).

Presently,-OCNGS is on>a 24-

- month refueling _ cycle whichL would,c by itself, require fewer spent-fuel shipments per reactor year. Reducing the number of fuel: shipments-reduces-the overall impacts related to population exposure and - accidents.

In

- terms of transportation of solid. radioactive waste (other than fuel) from OCNGS, the number of shipments has closely approximated the assumptions of-the OCNGS Final Environmental Statement. (FES),- December,3 1974..TheffES,

- Section' 5.7.4, stated that 1500 drums per year-(ll,250 f t ) of solid waste would belshipped'per-yeaf from the OCNGS site.

In_1990,_OCNGS shipped approximately 12,200 feet of solid radioactive waste. The slight. increase =

Lin assumed i volume does not represent a--:-significant change _ in the<

conclusion of-the FES.

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