RA-11-044, Cycle 23 Startup Test Report Supplement

Cycle 23 Startup Test Report Supplement

ML11174A038
Person / Time
Site:	Oyster Creek
Issue date:	06/17/2011
From:	Massaro M Exelon Nuclear, Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RA-11-044
Download: ML11174A038 (2)

Text

Exelon.

Oyster Creek Generating Station Route 9 South www.exeloncorp.com ExeNuI ear PO Box 388 Forked River, NJ o8731 TS 6.9.1 RA-1 1-044 June 17, 2011 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Oyster Creek Nuclear Generating Station Renewed Facility Operating License No. DPR-16 Docket No. 50-219

Subject:

Oyster Creek Nuclear Generating Station Unit 1 (OCNGS) Cycle 23 Startup Test Report Supplement Enclosed for your information is the OCNGS Cycle 23 Startup Test Report first sequence exchange. This supplemental report is submitted in accordance with Technical Specifications (TSs) Section 6.9.1 due to the introduction of a new fuel design GNF-2 at OCNGS.

OCNGS achieved initial cycle criticality on November 30, 2010, and reached steady state full power for the first time in Cycle 23 on December 30, 2010. Startup testing was completed on January 14, 2011, with the exception of the first sequence exchange. A report, RA-11-017, was issued on March 30, 2011. This supplementary report is being submitted following the completion of the first sequence exchange on May 28, 2011.

Should you have any questions concerning this letter, please contact Declan Doran at 609-971 -

4367.

Sincerely, Michael J. Massaro Site Vice President Oyster Creek Nuclear Generating Station

Enclosure:

Cycle 23 Startup Report Rod Pattern Exchange cc: USNRC, Regional Administrator, Region I USNRC, Senior Project Manager, NRR USNRC, Senior Resident Inspector -

(jLC

U. S. NRC Attachment to FAA-1 1-044 Page 1 of 1 Rod Pattern Exchange Purpose The purpose of this test is to determine the representative change in basic rod pattern at a high reactor power level Criteria Compare actual core conditions to predicted core conditions to determine correlation between predicted and actual core conditions. Any deviations are to be analyzed.

Results and Discussion The first Control Rod Sequence Exchange was performed on 5/28/11 at -2800 MWD/ST. The control rod pattern was changed from an A-2 (BPWS Gr 9) to an A-1 (BPWS Gr 8) pattern.

Below is a comparison between the predicted rod pattern verse actual core conditions.

Core 3DMONICORE Projected 3DMONICORE Actual Value Condition Value Rod Pattern BPWS Gr 8-1 at position 08 BPWS Gr 8-1 at position 08 Core Flow 98.9% 99.1%

MFLCPR 0.728 0.726 MFLPD 0.854 0.851 MAPRAT 0.832 0.832 K effective 1.0057 1.0057 Actual core conditions match within 1% of predicted core conditions at the target rod pattern.

No discrepancies were identified during this sequence exchange.