PLA-6017, MCPR Safety Limits and Reference Changes Supplemental Information PLA-6017

MCPR Safety Limits and Reference Changes Supplemental Information PLA-6017

ML060530614
Person / Time
Site:	Susquehanna
Issue date:	02/17/2006
From:	Jones G Susquehanna
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
PLA-6017
Download: ML060530614 (4)

Text

George T. Jones PPL SusquehannaLLC  ;

Vice President- Two North Ninth Street \ Ad S a Special Projects-Nuclear Allentown, PA 18101-1179 * '

j Tel. 610.774.7602 Fax 610.774.7797 gtjones@pplweb.com " I l

• 0 u1 FEB 17 2006 4 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop OP1-17 Washington, DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION PROPOSED AMENDMENT NO. 283 TO UNIT 1 LICENSE NPF-14: MCPR SAFETY LIMITS AND REFERENCE CHANGES SUPPLEMENTAL INFORMATION PLA-6017 Docket No. 50-387

Reference:

1) PLA -5990, B. T. McKinney (PPL), "ProposedAmendment No. 283 to Unit I License NPF-14:MCPR Safety Limtits and Reference Changes,"

dated December 1, 2005.

The purpose of this letter is to supplement the referenced proposed amendment request, which proposed changes to the SSES Unit 1 Technical Specification 2.1.1.2 and 5.6.5b.

The supplemental information provided herein provides the information requested during the Febraary 13, 2006 teleconference held between Richard Guzman (NRC) and Michael Crowthers (PPL Susquehanna LLC).

Reference 1 provided in Attachment 4 a "Preliminary Unit 1 Cycle 15 Core Composition" and in Attachment 5 a "Preliminary Unit 1 Cycle 15 Core Loading Pattern." The final core loading pattern is provided in the Attachment to this letter. The Unit 1 Cycle 15 preliminary core loading provided in PLA-5990 was revised to mitigate the potential for excessive friction in peripheral control cells. No changes were made to the loading of interior control cells. The design maximizes the use of SQA-12 assemblies that were re-channeled during the November 2005 Unit 1 maintenance outage to improve clearances within the cell. The figure shows the locations of assemblies that received a new fuel channel during the November 2005 Unit 1 maintenance outage.

The changes to the Unit 1 Cycle 15 core loading do not change the proposed 2-loop and single loop MCPR Safety Limits previously submitted in PLA-5990. In addition, the core composition provided in PLA-5990, Attachment 4, remains unchanged.

Also, note that the ANF-524(P)(A) methodology explicitly accounts for the effect of channel bow on the MCPR Safety Limit and thus remains applicable to the MCPR Safety 18~ (- 0

Document Control Desk PLA-6017 Limit calculation for UlC 15. ANF-524(P)(A), Supplement 1, Rev. 2, describes the way in which channel bow is analyzed and included in the Safety Limit methodology. This methodology was used for the proposed UlC15 MCPR Safety Limit analysis.

The neutronics effects of bow (increase in fuel pin local peaking vs. channel bow) are computed using the CASMO4 lattice physics code. Results of this calculation and the uncertainty in channel bow are then used to generate an uncertainty in local peaking, which is. included in the Safety Limit analysis. This bow related uncertainty is entered into the statistical (Monte Carlo) Safety Limit analysis along with the other uncertainties as described in ANF-524(P)(A), Rev. 2. The result is a value of the MCPR Safety Limit, which explicitly accounts for the effects of channel bow.

PPL has reviewed the No Significant Hazards Consideration and the Environmental Consideration submitted with Reference I relative to this supplemental information.

We have determined that there are no changes required to either of these documents.

Any questions regarding this request should be directed to Mr. Michael H. Crowthers at (610) 774-7766.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on: .? 77 oO>

George '. es

Attachment:

Supplemental Information cc: NRC Region I Mr. A. J. Blarney, NRC Sr. Resident Inspector Mr. R. V. Guzman, NRC Project Manager Mr. R. Janati, DEP/BRP

Attachment to PLA-6017 Supplemental Information

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