ML091070160

Draft Clarifications Concerning a Request for Additional Information Regarding Loss-of-Coolant/Mainstream Line Break Accident Dose Consequence Analyses License Amendment Request (Tac Nos. MD9141)

ML091070160
Person / Time
Site:	Prairie Island
Issue date:	04/27/2009
From:	Wengert T J Plant Licensing Branch III
To:	James L M Plant Licensing Branch III
Wengert, Thomas NRR/DORL 415-4037
References
TAC MD9140, TAC MD9141
Download: ML091070160 (4)

Text

UNITED NUCLEAR REGULATORY WASHINGTON , D.C. 20555-0001 April 27, 2009 MEMORANDUM TO: Lois M. James, Chief Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 ll-:> Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 DRAFT CLARIFICATIONS CONCERNING A REQUEST FOR ADDTIONAL INFORMATION (RAI) REGARDING COOLANT/MAIN STEAMLINE BREAK ACCIDENT DOSE CONSEQUENCE ANALYSES LICENSE AMENDMENT REQUEST (TAC NOS. MD9140 AND MD9141) The enclosed draft request for clarification of an RAI was transmitted on March 30, 2009, to Mr. Dale Vincent of Prairie Island Nuclear Generating Plant, Units 1 and 2 (PINGP), requesting clarification of PINGP's March 16,2009, response to the Nuclear Regulatory Commission (NRC) staff's RAI (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML090890180) concerning PINGP's loss-of-coolantlmain steamline break dose consequences analyses license amendment request dated June 26, 2008 (ADAMS Accession No. ML081790439). During a discussion between the NRC staff and the licensee's staff on April 2, 2009, the second to last sentence of Question (1) Bullet 7 in the enclosed was clarified to read: Do the planes of the exterior surfaces of the louvers face the control room and control room inleakage locations? Following the discussion, the licensee stated their intent to respond to this request for clarification. Docket Nos. 50-282 and 50-306

Enclosure:

As stated CONTACT: T. Wengert, NRR 301-415-4037 CLARIFICATIONS CONCERNING A REQUEST FOR ADDITIONAL INFORMATION LOSS-OF-COOLANT ACCIDENT/MAIN STEAM LINE BREAK ACCIDENT DOSE CONSEQUENCES ANALYSES AND AFFECTED TECHNICAL SPECIFICATIONS LICENSE AMENDMENT REQUEST NORTHERN STATES POWER COMPANY -MINNESOTA (NSPM) PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNI DOCKET NOS. 50-282 AND 50 uclear e NRC staff dment Bullet 3:

What are the height and width sp ct to determ ining that the initial sigma y input should be 6.1 met t should be 6

.3 meters? How much of the Shield Building i 43.6 meters determined to be the appropriat calculations?

Operated Relief Valve (PORV) and Main do not appear to match the graphical Bullet 7: eling Water Storage Tank releases through the louvers to be well mixed 0 f louvers per Regulatory Gu ide 1.194, "Atmospheric Relative Concentrations om Radiological Habitability Assessments at Nuclear Power Plants"? Do the p of exter ior surfaces of the louvers face the control room and control room air intakes? Does . in Table 5.2-1 in the June 26, 2008 license amendment request mean "make-up"? Enclosure Clarification of Reply to Question (2) of Enclosure 1: Pre-number text: For the list of source/receptor pairs evaluated, please provide either the calculations or all inputs and resultant atmospheric dispersion factors (XJQ values) for each source/receptor pair. With respect to the June 26, 2008, LAR:

Please provide a discussion that supplements Appendix H in the P r: Safety Analysis Report describing how the low population zone a historical perspective of their basis . The NRC staff notes th 4 -30 day time periods were calculated to include a non-co appears to be outside of the scope of the Regulatory Gu' . 1.

April 27, 2009 MEMORANDUM TO: Lois M. James, Chief Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Off ice of Nuclear Reactor Regulation Thomas J. Wengert, Senior Project Manager IRA! Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 DRAFT CLARIFICATIONS CONCERNING A REQUEST FOR ADDTIONAL INFORMATION (RAI) REGARDING COOLANT/MAIN STEAMLINE BREAK ACCIDENT DOSE CONSEQUENCE ANALYSES LICENSE AMENDMENT REQUEST (TAC NOS. MD9140 AND MD9141)

The enclosed draft request for clarification of an RAI was transmitted on March 30 , 2009, to Mr. Dale Vincent of Prairie Island Nuclear Generating Plant , Units 1 and 2 (PINGP), requesting clarification of PINGP's March 16,2009, response to the Nuclear Regulatory Commission (NRC) staff's RAI (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML090890180) concerning PINGP's loss-of-coolant/main steamline break dose consequences analyses license amendment request dated June 26 , 2008 (ADAMS Accession No. ML081790439). During a discussion between the NRC staff and the licensee's staff on April 2, 2009, the second to last sentence of Question (1) Bullet 7 in the enclosed was clarified to read: Do the planes of the exterior surfaces of the louvers face the control room and control room inleakage locations? Following the discussion , the licensee stated their intent to respond to this request for clarification. Docket Nos. 50-282 and 50-306

Enclosure:

As stated CONTACT: T. Wengert , NRR 301-415-4037 Distribution:

PUBLIC LPL3-1 RlF RidsNrrDorlLpl3-1 Resource RidsNrrPMPrairielsland Resource RidsNrrLABTully Resource RidsNrrDraAadb L. Brown, ABoatright, NRR Accession No' ML091070160 Office LPL3-1/PM LPL3-1/LA NRRlDRA/AADB/BC LPL3-'I/BC Name TWengert BTuily RTaylor LJames Date 04/22/09 04/22/09 04/23/09 04/27/09 OFFICIAL RECORD COpy