ML113470622: Difference between revisions

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| number = ML113470622
| number = ML113470622
| issue date = 12/19/2011
| issue date = 12/19/2011
| title = Quad Cities, Units 1 and 2 - Request for Additional Information Related to Technical Specification Change for Safety Limit Minimum Critical Power Ration
| title = Request for Additional Information Related to Technical Specification Change for Safety Limit Minimum Critical Power Ration
| author name = Wiebe J S
| author name = Wiebe J S
| author affiliation = NRC/NRR/DORL/LPLIII-2
| author affiliation = NRC/NRR/DORL/LPLIII-2

Revision as of 21:01, 8 February 2019

Request for Additional Information Related to Technical Specification Change for Safety Limit Minimum Critical Power Ration
ML113470622
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 12/19/2011
From: Joel Wiebe
Plant Licensing Branch III
To: Pacilio M J
Exelon Nuclear
Wiebe, Joel NRR/DORL/LPL3-2, 415-6606
References
TAC ME6383, TAC ME7613
Download: ML113470622 (4)


Text

UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 December 19, 2011 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION RELATED TO TECHNICAL SPECIFICATION CHANGE FOR SAFETY LIMIT MINIMUM CRITICAL POWER RATIO (TAC NOS. ME6383 AND ME7613)

Dear Mr. Pacilio:

By letters to the Nuclear Regulatory Commission (NRC) dated June 7,2011, and November 22, 2011, Exelon Generation Company, LLC (Exelon) submitted requests to revise the technical specification safety limit minimum critical power ratio, for the Quad Cities Nuclear Power Station, Units 1 and 2, respectively.

By letters dated September 21, 2011, and November 2, 2011, Exelon submitted additional information in response to our requests for additional information.

The NRC staff is reviewing your submittal and based on your submittals and audits of Westinghouse documents on October 19, 2011, and November 10, 2011, has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. This information was provided to your staff during a discussion on November 14, 2011. During a discussion with your staff on December 8, 2011, it was agreed that you would provide a response 30 days from the date of this letter. The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources.

M. Pacilio If circumstances result in the need to revise the requested response date, please contact me at (301) 415-6606.

Sincerely, Joel S. Wiebe, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-254 and 50-265 Request for Additional cc w/encl: Distribution via Listserv REQUEST FOR ADDITIONAL QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND DOCKET NOS. 50-254 AND In reviewing the Exelon Generation Company's (Exelon's) submittals dated June 7, September 21, November 2, and November 22, 2011 (Agencywide Documents Access Management System (ADAMS) Accession Nos. ML 111590206, ML 112650386, ML 113070426, and ML 113260348, respectively), and audits of Westinghouse documents on October 19, and November 10, 2011, related to the revision of the technical specification safety limit minimum critical power ratio (SLMCPR), for the Quad Cities Nuclear Power Station, Units 1 and 2, the NRC staff has determined that the following information is needed in order to complete its review: CENPD-300-P-A, Section 1.3 states, "Appendix A to this report provides a brief description of the computer codes used in ABB reload analysis methodology." The CENPD-300-P-A acceptance letter dated May 24, 1996, states that the staffs acceptance applies only to the matters described in the report. In Exelon's submittal dated June 7,2011, and supplement dated November 2,2011, you identified several computer codes that are not listed in Appendix A and therefore not considered in the staff's acceptance of CENPD-300-P-A.

Provide a complete listing of computer codes used in the implementation of 300-P-A for determining the SLMCPR. Justify your use of these codes for the NRC approved analytical method (i.e., CENPD-300-P-A) listed in the Technical Specifications. During the conference call on November 18, 2011, your staff stated that you were evaluating the MWd/MT threshold below which the Unit 1 SLMCPR was assured to be conservative.

Describe how you are establishing this threshold. The CENPD-300-P-A acceptance letter dated May 24, 1996, states that the staff finds the report and related documents to be acceptable to the extent specified and under the limitations delineated in the NRC evaluation.

Confirm that your implementation of CENPD-300-P-A for your June 6 and November 22, 2011, submittals continue to meet these conditions and limitations as described in your June 15, 2005 (ADAMS Accession No. ML060620352) submittal.

M. Pacilio -If circumstances result in the need to revise the requested response date, please contact me at (301) 415-6606.

Docket Nos. 50-254 and 50-265 Request for Additional cc w/encl: Distribution via LPL3-2 RidsNrrDorlLpl3-2 RidsNrrLASRohrer RidsAcrsAcnw_MailCTR RidsNrrPMQuadCities Sincerely, IRA by Araceli T.Billoch Colon forI Joel S. Wiebe, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsOgcRp Resource RidsRgn3MailCenter Resource RidsNrrDorlDpr Resource RidsNrrDssSrxb Resource ADAMS Accession No. ML 113470622 NRR-088 OFFICE LPL3-21PM LPL3-2/LA SRXB/BC LPL3-2/BC NAME JWiebe SRohrer TUlses JZimmerman DATE 12/15/11 12/14/11 12/19/11 12/19/11 OFFICIAL RECORD COpy