PLA-5040, 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: |
| References | |
| PLA-5040, NUDOCS 9903290101 | |
| Download: ML18040A969 (4) | |
Text
Robert G. Byram Senior Vice President Generation and Chief Nuclear Officer Tel. 610.774.7502 Fax 610.774.5019 E-mail:rgbyrame papl.corn BAR 1:2 1999 PPtLL, Inc.
Two North Ninth Street Allentown, PA 18101-1179 Tel. 610.774.51 51 http:ltwww.pap!.corn/
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U. S. Nuclear Regulatory Commission Attn.: Document Control Desk Mail Station P 1-137 Washington, D. C. 20555 SUSQUEHANNA STEAMELECTRIC STATION PROPOSED AMENDMENTNO. 227 TO LICENSE NPF-14:
ANFB-10 CRITICAL.POWER.CORRELATIONAND.
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Docket No. 50-387
References:
1.
LetterPom VictorNerses (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-10CriticalPower Correlation, "July 1998, and EMF-1997 (P)(A) Supplement 1 Revision 0, "ANFB-10Cr'itical Power Correlation: High Local Peaking Results, "July 1998.
3.
ANF-I125 (P)(A) and ANF-1125 (P)(A), Supplement 1, "ANFBCriticalPower Correlation, "April 1990.
4.
PL-NF-90-001-A, "Application ofReactor Analysis Methods forBWR 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-10forSusquehanna Reloads, "
March 1997.
6.
PLA-4595, "Response to NRC Request forAdditionalInformation on Siemens 'eport EMF '1'0, Revision 1, "Mar'ch 27, 199'7.
ANF-524(P)(A), Revision 2 and Supplement 1, Revision 2, "Advanced Nuclear Fuels Corporation CriticalPower MethodologyforBoiling Water Reactors, "November 1990.
8.
CENPD-300-P, "Reference Safety ReportforBoiling Water Reactor Reload Fuel, "ABB Combustion Engineering Nuclear Operations, November 1994.
~ i The purpose ofthis 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 ofReference 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 ofreferences from Section 5.6.5 are removed in order to include only those references which directly support the generation ofthe Core Operating Limits and to remove the reference for the ABB Lead Use Assemblies (Reference 8), which willbe discharged during the next Unit 1 outage.
Associated BASES changes are also included.
9903290101.
9'70312 PDR ADOCK 05000387 I' P
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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) willcontinue to be used in the analysis of SPC 9x9-2 fuel. The ANFB (for 9x9-2) and ANFB-10 (for ATRIUM~-10)correlations willbe 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 willnot 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 Unit 1 Cycle 12 Core Composition.
Technical Specifications for those Specifications.
D and E have been provided.
Attachment D provides the Attachment E provides a cross-reference to applicable references specified in Section 5.6.5 of Technical 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, ActingNRC Sr. Resident Inspector-SSES Mr. D. J. Allard, Pa. DEP
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