ML20141M269
| ML20141M269 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom, Limerick  |
| Issue date: | 08/03/1992 |
| From: | Beck G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9208110001 | |
| Download: ML20141M269 (2) | |
Text
p PHILADELPHIA ELECTRIC COMPANY o
NUCLEAR GROUP HEADQUARTERS 955-65 CHESTERBROOK BLVD.
August 3, 1992 WAYNE, PA 19087-569; (215) s40 sono Docket Nos. 50-277 50-278 50-352 50-353 License Nos. DPR-44 DPR-56 NPF-39 NPF-85 U.S._ Nuclear Regulatory Commission
-Attn: Document Control Desk Washington, DC 2055F
SUBJECT:
_ Peach Bottom' Atomic Power Station, Units 2 and 3 himerick Generating Station, Units 1 and 2 Request for Approval to'Use General Electric Company
-Reactor _ Analysis Methods - Supplemental Information Gentleten:
As.?-follow-up to a July 7, 1992 conference call between Messrs.-Shca and Kendrick of the NRC and' representatives of Philadelphia Electric Company (PECo), this letter supplements our
-letter to the NRC dated June 16, 1992 requesting NRC approval to use General Electric (GE) Company reload methc. ology, and provides a discussion of PECo's intended method of-performing reactor analysis calculations as required to. design and manage
.PeachiBottom' Atomic Power Station (PBAPS),. Units 2 and 3_and 1 Limerick Generating Station (LGS), Units 1 and 2 reload cores.
As a result of several factors, including the introduction of_the_GE-ll product line into the PBAPS, Units 2 and 3 cores-and LGS, Units 1-and 2 cores, we have altered our reactor analysis.
strategygfor_both PBAPS_ Units 2--and 3 and LGS Units _1 and 2.
PECo will continue to perform all~ production reload design and cycle management' evaluations.in-house, including the Technical Specifications related cold shutdown margin (CSDM) demonstration.
and reactivity anomaly calculation sequences, ilowever, beginning-Lwith the introduction of GE-ll reloads, the methodology used by PECo to-perform'these calculations will be-the NRC approved GEu LGENIE compcter code system.- We_ expect that the GENIE ~ computer code system will: eventually be applied-to GE-13 and other GE fuel designs:at such time as GE_receivos NRC approval to apply GENIE to these designs.
Furthermore, PECo will rely exclusively on GE generated databases ~(e.g., nuclide cross section sets, reactor hydraulics parameters) when performing production reload design-k 9208110001 920803-j
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j.~U.S??Nuclocr Regulatory Commission August 3, 1992
= Document Control' Desk Page 2
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- hydraulics parameters).when performing production reload design tand cycle. management calculations.
PECo has previously provided sinformation which demonstrated proficiency in the application of the'GE: methodology and models for nodal analysis-applications in
=our-letter dated November 18,-1992, specifically addressing-CSDM and reactivity anomaly calculations.
The NRC has approved this
' scope of application by NRC letter dated February 21, 1992 for
. LGS Unit I re.oad 4 only.
We now request NRC approval for PdCc personnel to apply.these GE reactor analysis methods to any future PBAPS, Unit 2 andLUnit 3, and LGS, Unit 1 anu Unit 2 core reload designs and cycle management evaluations.
We will continue to assure that the. GENIE system is subjected to appropriate ongoing benchmark evaluations such that PECo can maintain-an adequate basis for confidence in the continuing
. applicability of this computer code system to current fuel technology and operating strategies.
We would appreciate
' receiving your approval as soon as possible.
'With regard to reload system transient calculations, PECo intends to_have GE continue to perform these calculations, at this time.-
We are currently evaluating our longer term options-with regard to_this need, and will advise the NRC of the direction to be taken at a later date.
Please note that PECo will continue support for the existing,flicensed PECo reload analysis methodology as described in NRC approved topical reports PECo-FMS-0001-A through PECo-FMS-0006 c..;
Current plans call for upgrading this computer: code system to-explicitly and accurately represent advanced fuel designs, and to ultimately apply the computer code system to
- independent-in-house " case study" calculations.
We expect that this methodology will, for_ example, be used to evaluate alternate.
- vendor / mixed core scenarios, respond to specific system related
. questions originated at the plant' sites and to provide a basis for plant simulator benchmarks.
If you have any questions or need aiditional information,
.pleaseLcontact us.
Very.truly yours,
/
7 George J. Beck, Manager Licensing Section Nuclear Services Department cc:
T. T. Martin, Administrator Region I, USNRC J. J..Lyash, USNRC Senior. Resident Inspector, PBAPS T. J.-Kenny, USNRC. Senior Resident Inspector, LGS