ML20079B242

Forwards Proposed Changes to Part a of ODCM for NRC Review & Approval.Changes to Part B of ODCM Will Be Submitted W/ Annual Radioactive Effluent Release Rept in Accordance W/Ts 6.13.2b

ML20079B242
Person / Time
Site:	Seabrook
Issue date:	12/27/1994
From:	Feigenbaum T NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20079B245	List: ML20079B242 ML20079B249
References
NYN-94140, TAC-M90917, NUDOCS 9501050351
Download: ML20079B242 (3)

Text

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North Atlantic Energy Service Corporation i

Nor(11 y.O.S ,300 I

Atlantic. Seabrook, NII 03874 (603)474-9521, Fax (603)474-2987 The Northeast Utilities System Ted C. Feigenbaum NYN. 94140 Senior Vice President &

Chief Nuclear Officer

. December 27,1994 i P

United States Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Document Control Desk

Reference:

Facility Operating License No. NPF-86, Docket No. 50-443

Subject:

Proposed Revision to Offsite Dose Calculation Manual (TAC No. M90917)

Gentlemen:

Seabrook Station Technical Specification 6.13.2a. requires that changes to Part A of the Offsite Dose Calculation Manual (ODCM) are to be submitted to and approved by the NRC prior to implementation. Accordingly, North Atlantic Energy Service Corporation (North Atlantic) has enclosed proposed changes to Part A of the ODCM for NRC review and approval. The North Atlantic Station Operation Review Committee has reviewed and approved the ODCM changer proposed herein. The proposed changes are discussed below. ODCM revisions are noted by revision bars in the margin.

Changes to Part B of the ODCM will be submitted with the Annual Radioactive Effluent Release Report in accordance with Seabrook Technical Specification 6.13.2b.

The ODCM Part A currently requires the submittal of certain radioactive effluent release information in the " Semiannual Radiological Efiluent Release Report." Seabrook Station Technical Specifications 6.8.1.4 and 6.13.2b. were revised by Amendment No. 22 to the Seabrook Station Operating License to require an annual report. References to the " Semiannual Radioactive Effluent Release Report" are changed to the " Annual Radioactive Efiluent Release Report". This change has no impact on the dose calculation methodologies in the ODCM.

Table A.3-1, " Radioactive Liquid Waste Sampling and Analysis Program" is proposed to be amended by stipulating that quarterly activity analyses for Sr-89, Sr-90, and Fe-55 in Turbine Building Sump and Steam Generator Blowdown discharges would only be made when one or more of the weekly analyses for principle gamma emitters indicates positive activity. These three nuclides represent a small fraction of any expected contamination event, which would be dominated by gamma emitting radionuclides. Without the detectable presence of such gamma emitters in waste samples, it is highly unlikely that any of these other radionuclides would be present and detectable above the required Lower Limit of Detection (LLD). This change does not impact the ability to project off-site doses since the reduction in the number of isotopic analyses only is concerned with those composite samples that have  !

no indication of any contamination. and therefore, no contribution to any offsite dose.

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9501050351 941227

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l PDR ADOCK 05000443 Jk P PDR Ii

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United States Nuclear Regulatory Commission December 27,1994

, Attention: Document Control Desk Page two Table A.4-1, " Radioactive Gaseous Waste Sampling and Analysis Program" is proposed to be amended by stipulating that quarterly activity analyses for Sr-89, and Sr-90, in the Gland Steam Packing Exhauster discharge would only be made when one or more of the weekly analyses for principle gamma emitters indicates positive activity. As noted above, these non gamma radionuclides represent a small fraction of any expected contamination event, which would be dominated by the principle gamma emitters.

Without the detectable presence of such gamma emitters in waste samples, it is highly unlikely that any of these other radionuclides would be present and detectable above the required LLD. This change does not impact the ability to project off-site doses since the reduction in the number of isotopic analyses only is concerned with those composite camples that have no indication of any contamination, and therefore, no contribution to any offsite dose.

Should you have any questions regarding this request, please con *act Mr. James M. Peschel, Regulatory Compliance Manager, at (603) 474-9521, extension 3772.

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Ve ' truly yours,

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w On v Ted C. Feige i TCF:EJC/act Enclosure cc: Mr. Thomas T. Martin Regional Administrator 11.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Mr. Albert W. De Agr.zio, Sr. Project Manager Project Directorate I-4 Division of Reactor Projects U.S. Nuclear Regulatory Commission Washington, DC 20555 Mr. Richard Laura  !

NRC Senior Resident inspector P.O. Box 1149 Seabrook, Nil 03874 4

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4 North Atlantic December 27,1994 ENCLOSURE TO NYN-94140 1