ML061930417

Request for Additional Information (RAI) Related to Revising the Fort Calhoun Station Updated Safety Analysis Report

ML061930417
Person / Time
Site:	Fort Calhoun
Issue date:	07/19/2006
From:	Wang A NRC/NRR/ADRO/DORL/LPLIV
To:	Ridenoure R Omaha Public Power District
Wang A, NRR/DLPM, 415-1445
References
TAC MC8857
Download: ML061930417 (4)

Text

July 19, 2006Mr. R. T. Ridenoure Vice President - Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.

Post Office Box 550 Fort Calhoun, NE 68023-0550

SUBJECT:

FORT CALHOUN STATION, UNIT 1 - REQUEST FOR ADDITIONALINFORMATION (RAI) RELATED TO REVISING THE FORT CALHOUN STATION UPDATED SAFETY ANALYSIS REPORT (TAC NO. MC8857)Dear Mr. Ridenoure

By letter dated October 31, 2005, Omaha Public Power District (OPPD) submitted anamendment request to revise the Fort Calhoun Station, Unit 1, Updated Safety Analysis Reportfor the radiological consequences of events affected by the planned 2006 replacement of the steam generators and pressurizer.The U.S. Nuclear Regulatory Commission staff has reviewed OPPD's submittal and hasdetermined that additional information is needed to complete our review. A request for additional information is enclosed. This request was discussed with Thomas Matthews of your staff on July 5, 2006, and it was agreed that a response would be provided within 30 days of receipt of this letter.If you have any questions, please contact me at (301) 415-1445. Sincerely,

/RA/ Alan B. Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No.

50-285

Enclosure:

RAIcc w/encl: See next page July 19, 2006Mr. R. T. Ridenoure Vice President - Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.

Post Office Box 550 Fort Calhoun, NE 68023-0550

SUBJECT:

FORT CALHOUN STATION, UNIT 1 - REQUEST FOR ADDITIONALINFORMATION (RAI) RELATED TO REVISING THE FORT CALHOUN STATION UPDATED SAFETY ANALYSIS REPORT (TAC NO. MC8857)Dear Mr. Ridenoure

By letter dated October 31, 2005, Omaha Public Power District (OPPD) submitted anamendment request to revise the Fort Calhoun Station, Unit 1, Updated Safety Analysis Reportfor the radiological consequences of events affected by the planned 2006 replacement of the steam generators and pressurizer.The U.S. Nuclear Regulatory Commission staff has reviewed OPPD's submittal and hasdetermined that additional information is needed to complete our review. A request for additional information is enclosed. This request was discussed with Thomas Matthews of your staff on July 5, 2006, and it was agreed that a response would be provided within 30 days of receipt of this letter.If you have any questions, please contact me at (301) 415-1445. Sincerely,/RA/

Alan B. Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No.

50-285

Enclosure:

RAIcc w/encl: See next pageDISTRIBUTION

PUBLICLPLIV R/FRidsOgcRpRidsRgn4MailCenter(DGraves) RidsNrrLALFeizollahiRidsNrrPMAWangRidsAcrsAcnwMailCenterRidsNrrDorlLpl4 RidsNrrDorlDprADAMS ACCESSION NO.: ML061930417OFFICELPL4/PMLPL4/LALPL4/BCNAMEAWangLFeizollahiDTeraoDATE07/17/0607/17/0607/19/06OFFICIAL RECORD COPY

REQUEST FOR ADDITIONAL INFORMATIONREGARDING UPDATED SAFETY ANALYSIS REPORTRADIOLOGICAL CONSEQUENCE ANALYSISOMAHA PUBLIC POWER DISTRICTFORT CALHOUN STATION, UNIT 1DOCKET NUMBER 50-285By letter dated October 31, 2005, Omaha Public Power District (OPPD) submitted anamendment request to revise the Fort Calhoun Station, Unit 1 (FCS), Updated Safety Analysis Report (USAR) for the radiological consequences of events affected by the planned 2006 replacement of the steam generator and pressurizer. The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed OPPD's submittal and has determined that the followingadditional information is needed to complete our review: 1.The NRC staff notes that the atmospheric dispersion factors (/Q values) provided in theOctober 31, 2005, license amendment request (LAR) are the same as those approved in the safety evaluation associated with FCS Amendment No. 201. Amendment No. 201 implements use of the alternative source term in the FCS design-basis accident dose assessments. Therefore, for each design-basis accident or event addressed in the October 31, 2005, LAR, please discuss any differences between the two sets of release scenarios. If there are differences, please justify how the differences do not impact the applicability of the /Q values associated with Amendment No. 201 to the doseassessment associated with the October 31, 2005, LAR.2.Which water mass inventories (both primary and secondary) were used in calculatingcoolant activities? Please indicate if the used values are the minimum, nominal or maximum.3.The submitted S-RELAP5 analysis indicates 0 percent/0 percent fraction of failed/meltedfuel. Is this a change from the analysis of record? 4.Attachment 4 (AREVA document 86-5064251-00) describes the thermal-hydraulic inputin support of the consequence analysis. Please confirm that the main steam safety valves and atmospheric dump valves actuation setpoints used are those specified in thetechnical specifications.5.Presumably, the cumulative steam releases used in the Attachment 6 (Stone & Websterreport) came from the Attachment 4 (AREVA document). However, it is not immediately obvious which tables in Attachment 4 were used to generate Tables 7.6 - 7.9 in . Please clarify.

April 2006Ft. Calhoun Station, Unit 1 cc:Winston & Strawn ATTN: James R. Curtiss, Esq.

1700 K Street, N.W.

Washington, DC 20006-3817ChairmanWashington County Board of Supervisors

P.O. Box 466 Blair, NE 68008Mr. John Hanna, Resident InspectorU.S. Nuclear Regulatory Commission

P.O. Box 310 Fort Calhoun, NE 68023Regional Administrator, Region IVU.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005Ms. Julia Schmitt, Manager Radiation Control Program Nebraska Health & Human Services R & L Public Health Assurance 301 Centennial Mall, South P.O. Box 95007 Lincoln, NE 68509-5007Mr. David J. Bannister, ManagerFort Calhoun Station Omaha Public Power District Fort Calhoun Station FC-1-1 Plant

P.O. Box 550 Fort Calhoun, NE 68023-0550Mr. Joe L. McManisManager - Nuclear Licensing Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.

P.O. Box 550 Fort Calhoun, NE 68023-0550Mr. Daniel K. McGheeBureau of Radiological Health Iowa Department of Public Health Lucas State Office Building, 5th Floor 321 East 12th Street Des Moines, IA 50319