L-98-196, Forwards Rev 1 to Calculation 456, Combined BV1-BV2 Control Room Doses Due to Waste Gas Sys Line Rupture Accident at BV1, Per RAI During 980924 Conference.Calculation Sent as Addl Info Re LAR 250: Difference between revisions

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{{Adams
#REDIRECT [[L-98-196, NPDES Noncompliance Notification:On 980717,discovered That 15 Juvenile Least Terns Died in Roof Drainage Sys at Plant Screens Placed Around Drains Earlier in Nesting Season to Protect Hatchlings from Entering Drain Gutters]]
| number = ML20195C631
| issue date = 11/09/1998
| title = Forwards Rev 1 to Calculation 456, Combined BV1-BV2 Control Room Doses Due to Waste Gas Sys Line Rupture Accident at BV1, Per RAI During 980924 Conference.Calculation Sent as Addl Info Re LAR 250
| author name = Jain S
| author affiliation = DUQUESNE LIGHT CO.
| addressee name =
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000334
| license number =
| contact person =
| document report number = L-98-196, NUDOCS 9811170185
| package number = ML20195C634
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 1
| project =
| stage = Other
}}
 
=Text=
{{#Wiki_filter:Beam Va: ley Power Station Shippingport, PA 15077-0004 4
en or Va e President Fax 6 360 Nc r P wer DMsion November 9, 1998 L-98-196 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
 
==Subject:==
Beaver Valley Power Station, Unit No.1 Docket No. 50 334, License No. DPR-66 Response to Request for AdditionalInformation UFSAR Unreviewed Safety Question - Waste Gas Line Break This letter provides additional information as requested during a conference call with the NRC staff on September 24,1998. The staff requested this information to support its review of License Amendment Request No. 250, which was submitted by {{letter dated|date=January 17, 1998|text=letter dated January 17,1998}}, concerning an unreviewed safety question resulting from an increase in the waste gas system line break accident dose consequences. The Waste Gas Tank j
Rupture dose analysis is provided in the attached.
The attached calculation may be changed to reflect facility or procedure changes or other ongoing improvement processes. Any further questions regarding this submittal may be directed to Mr. M. S. Ackerman at (412) 393-5203.
Sincerely, Sushil C. Jain kgh c:
Mr. D. S. Brinkman, Sr. Project Manager Mr. D. M. Kern, Sr. Resident Inspector Mr. H. J. Miller, NRC Region I Administrator DELIVERING 98111701E5'9Nk109 O b lIIY PDR ADOCK 05000334 ENERGV P
PDR
,}}

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