ML18040A969

Forwards Revised Proposed Amend 227 to License NPF-14, Proposing Changes to ANFB-10 Critical Power Correlation & MCPR Safety Limits

ML18040A969
Person / Time
Site:	Susquehanna
Issue date:	03/12/1999
From:	Byram R PENNSYLVANIA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17164A990	List: ML17164A989 ML18040A969 ML18040A970 ML18040B289
References
PLA-5040, NUDOCS 9903290101
Download: ML18040A969 (4)

Text

g s rL s Robert G. Byram PPtLL, Inc. Q~w Senior Vice President Two North Ninth Street Generation and Chief Nuclear Officer Allentown, PA 18101-1179 +e Tel. 610.774.7502 Fax 610.774.5019 Tel. 610.774.51 51 m E-mail:rgbyrame papl.corn http:ltwww.pap!.corn/

BAR 1:2 1999 U. S. Nuclear Regulatory Commission Attn.: Document Control Desk Mail Station P 1-137 Washington, D. C. 20555 SUSQUEHANNA STEAM ELECTRIC STATION PROPOSED AMENDMENTNO. 227 TO LICENSE NPF-14:

ANFB-10 CRITICAL.POWER. CORRELATION AND. %1 I MCPR SAFETY LIMITS PLA-5040 Docket No. 50-387

References:

1. LetterPom Victor Nerses (NRC) to Robert G. Byram (PP&L), "Susquehanna Steam Electric Station, Unit 2 PAC No. MA2434), "February 17, 1999.

2. EMF-1997 (P)(A) Revision 0, "ANFB-10 Critical Power Correlation, "July 1998, and EMF-1997 (P)(A) Supplement 1 Revision 0, "ANFB-10 Cr'itical Power Correlation: High Local Peaking Results, "July 1998.

3. ANF-I125 (P)(A) and ANF-1 125 (P)(A), Supplement 1, "ANFB Critical Power Correlation, "April 1990.

4. PL-NF-90-001-A, "Application ofReactor Analysis Methods for BWR Design and Analysis, "July 1992, plus Supplements 1-A (August 1995) and 2-A (July 1996).

5.'MF-97-010(P), Rev. 1, "Application ofANFB to ATRlUMrM-10for Susquehanna Reloads, "

March 1997.

6. PLA-4595, "Response to NRC Request for Additional Information on Siemens 'eport EMF i Revision 1, "Mar'ch 27, 199'7. '.

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ANF-524(P)(A), Revision 2 and Supplement 1, Revision 2, "Advanced Nuclear Fuels Corporation Critical Power Methodology for Boiling Water Reactors, " November 1990.

8. CENPD-300-P, "Reference Safety Report for Boiling Water Reactor Reload Fuel, "ABB Combustion Engineering Nuclear Operations, November 1994.

The purpose of this letter is to propose changes to the Susquehanna Steam Electric Station Unit 1 Technical Specifications, which are similar to those recently approved in February 1999 for Unit2 (Reference 1). Reference 2 documents the NRC approved critical power 'correlation applicable to Siemens Power Corporation (SPC) ATRIUM'-10fuel (referred to as ANFB-10).

This proposed change entails the inclusion of Reference 2 in Section 5.6.5 and the inclusion of revised MCPR Safety Limits in Section 2.1.1.2. An administrative change to Section 5.6.5 is included. A number of references from Section 5.6.5 are removed in order to include only those references which directly support the generation of the Core Operating Limits and to remove the reference for the ABB Lead Use Assemblies (Reference 8), which will be discharged during the next Unit 1 outage. Associated BASES changes are also included.

9903290101. 9'70312 pPOI i PDR ADOCK 05000387 I' P PDR b

PLA-5040 Document Control Desk The ANFB-10 correlation will be used in the analysis of ATRIUM'-10fuel in place of the ANFB critical power correlation and methodology described in References 5 and 6. The ANFB correlation (Reference 3) will continue to be used in the analysis of SPC 9x9-2 fuel. The ANFB (for 9x9-2) and ANFB-10 (for ATRIUM~-10) correlations will be used with PP &L's and SPC's NRC approved methods, and analyses will be performed (consistent with those methods) to generate Core Operating Limits. Therefore, PP&L will not be submitting a change to its NRC-approved Topical Reports (Reference 4) since the methodology is the same except ANFB-10 will be used to analyze ATRIUM -10 fuel.

SPC report EMF-1997, gggA), Rev. 0 and Supplement 1, Rev. 0 (proposed,to Qe.added to the,.

Technical Specification Administrative Controls section) describes the ANFB-10 critical power correlation, which has been approved by'the NRC.

Enclosure A to this letter is the "Safety Assessment" supporting this change. Enclosure B is the "No Significant Hazards Considerations and Environmental Assessment" evaluation performed in accordance with the criteria of 10 CFR 50.92. Enclosure C to this letter contains the applicable pages of the Susquehanna SES Unit 1 Technical Specifications, marked to show the proposed changes as well as the associated BASES changes. The proposed changes have been approved by the Susquehanna SES Plant Operations Review Committee, and reviewed by the Susquehanna Review Committee.

To assist in your review, Attachments D and E have been provided. Attachment D provides the Unit 1 Cycle 12 Core Composition. Attachment E provides a cross-reference to applicable Technical Specifications for those references specified in Section 5.6.5 of Technical Specifications. * '

PP&L plans to implement the proposed changes in May 2000 to support the startup of Unit 1 Cycle 12 operation. Therefore, we request NRC complete its review of this change by February 11, 2000 with the changes effective upon startup following the Unit 1 11~ Refueling and Inspection Outage to support our scheduled implementation date.

Any questions regarding this request should be directed to. Mr. R. R. Sgarro at (610) 774-7552.'ery truly yours, R.. By

PLA-5040 Document Control Desk copy: NRC Region I Mr. V. Nerses, NRC Sr. Project Manager - QWFN Mr. S. L. Hansell, Acting NRC Sr. Resident Inspector- SSES Mr. D. J. Allard, Pa. DEP

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