ML20062C698

Forwards Updated PHOENIX-P/ANC Topical Review Schedule,Per 900221 & 0713 Ltrs

ML20062C698
Person / Time
Site:	Byron, Braidwood
Issue date:	10/23/1990
From:	Schuster T COMMONWEALTH EDISON CO.
To:	Murley T Office of Nuclear Reactor Regulation
References
NUDOCS 9011020068
Download: ML20062C698 (3)

Text

i C mmInwealth Edistn

, 1400 Opus Pitce C7 Down:rs Grove, Illinois 60515 j

i October 23, 1990

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Dr. Thomas E. Murley Office of Nuclear Reactor Regulation  !

U.S Nuclear Regulatory Commission  ;

Hashington, D.C. 20555  ;

Attn: U.S. NRC Document Control Desk  !

Subject:

Braldwood Nuclear Power Station Unit i Byron Nuclear Power Station Unit 2 l Revised Schedule for Transition in Neutronics Codes-for PHR Reload Design NRC Docket Nos. 50-456 and 50-455

References:

1. Letter from J.- A. Silady to-T.E. Murley, dated February 21, 1990 " Transition in Neutronics Codes-for PHR Reload Design".

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2. Conference call between Ceco (J.A. Silady and B.J. Adams).and NRR (D.B. Fleno), on June 26, 1990, i

3. Letter from J.A. Silady to T.E. Murley' dated i

July 13, 1990 submitting "Commonweelth Edison Company Topical Report on Benchmark oflPHR~ Nuclear Design Methods using the. PHOENIX-Pland ANC Computer Codes", CECO report NFSR O F

Dear Dr. Murley:

References 1 and 2 described Commonwealth Edison, Company (CECO). plans to implement the NRC-approved Hestinghouse Codes PHOENIX-Pland ANC,to replace the existing ARK and'2D codes which CECO uses to perform neutronic analyses '

for PHR reload designs. Reference 3 submitted the CECO' Topical Report in.

support of the implementation of PHOENIX-P and ANC-for.use by: CECO: Nuclear Fuel Services (NFS) reload design engineers.

Reference 3 also provided the planned transition scheduN and

, requested date for receipt of NRC hpproval (December 15, 1990). CECO has-recently reevaluated this schedule-in. light of a workscope change-between NFS j and the Hestinghouse N% lear Fuel Division.(HNFD) for Braidwood 1 Cycle 3 ,

(BHIC3) reload licr. sing inalyses. Although'both organizations.are currently utilizing PHOENP.iANC in-Juppo.t of the BHIC3 relorJ in a parallel effort, the-

' official "anaiyses of record" for input to the Reload Safety Evaluation will' now be'provided by HNFD. The remaining workscope ofLgenerating,the Nuclear Design Report (NDR), Station Curvebook, and the Core Operating Limits-Report' (COLR) will be provided by NFS after appropriate consistency checks-wit the HNFD analyses. '

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i October 23, 1990

. Dr. Thom:s Murley i

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. Since CECO will have primary responsibility for specifying parameters for the Core Operating Limits Report as well as the NDR and Station Curvebook, an NRC Safety Evaluation Report approving CECO's use of these-codes is needed q by January 15, 1991. This date is based on the expected transmittal date for the final COLR to the station for Onsite Review and subsequent Offsite Review.

The revised SER date of January 15, 1991 represents a six month review period from the mid-July Topical submittal. Because the codes and methodology have been previously reviewed and approved by the Stdff based on Hestinghouse submittals, CECO believes this schedule is reasonable for review of CECO's Topical Report on the same codes and methods. It is also consistent with the approval timeframe needed to support the related administrative license amendment to add a reference for the PHOENIX /ANC Topical Report to'the Technical. Specification 6.9.1.9 discussion of the approved methods upon which the COLR is based. This proposed change will be' submitted as-part of a dual station arendment which also incorporates other administracive changes'in Section 6 of the Byron and Braidwood Technical Specifications. The planned submittal in late November, 1990 should allow adequate time for review prior.

the Spring 1991 refueling outage (i.e., prior to start of BH1C3)..

• The Attachment updates the review. schedule previously transmitted to you in References 1 and 3. As noted in References 2 and 3, the-reload design, safety analysis input, and COLR for Byron 2 Cycle 3 (BY2C3) were determined using ARK /20 so that only the NDR and Curvebook are being generated with PHOENIX-P/ANC (for enhanced critical-predictions, etc.). LBased on;the Reference 2 and 3 discussions, this limited scope application for BY2C3 will therefra proceed in advancs of SER issuance for.the Topical Report.

Please contact this office if this understanding.is incorrect or should further information be required.

Very truly yours,

(

Nuclear Licensing Administrator T.K. Schuster Attachment 1 Updated Proposed CECO PH0ENIX-P/ANC Topical' Review Schedule-cc: A. B. Davis - Regional Administrator,'RIII. 1 C. P. Patel - Zion Project Manager,L HRR: ..

S. P. Sands - Braldwood. Project Manager, NRR T. dovce - Byron Project Manger, NRR 1 R. C. hnes - Reactor Systems Branch Chief, NRR Senior Reident Inspector - Zion Senior Resident Inspector - Byron 1 Senior Residet,+ Inspector - Braidwood l

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, Attachment

. Updated CECO PHOEMIX-P/ANC-Topical Review Schedule i

Datt Sittui i l

Initial Discussion of CECO Plans with NRR 10/20/89 Complete  ;

.I CECO Discusses PHOENIX-P/ANC Topical Scope 01/10/90- Complete 1 i

CECO Discusses Curvebook/ Nuclear Design Report 06/26/90 Complete i Use of PHOENIX-P/ANC for Byron Unit 2 Cycle 3 l

, i Ceco Submit PHOENIX-P/ANC Topical to NRC 07/13/90 Complete- j Meeting (s) to Address Staff Questions As Needed Ceco use of PHOENIX-P/ANC for Curvebook and~ 11/01/90*

NDR Calculations for Byron Unit 2 Cycle 3 CECO Submits BY/BH Administrative Tech 1 Spec Changes 11/28/90  !

(including new Topical reference in Sect. 6) l

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Topical Approval (SER) Needed from NRC 01/15/91** l Ceco use of PHOENIX-P/ANC for.COLR, Curvebook- 01/15/91**

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and NDR for-Braidwood Unit 1 Cycle 3-Target for NRC Issuance of Tech Spec. Change 03/15/91*** -;

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• BY2C3 Expected Startup

** BHIC3 COLR Transmittal for Onsite and Offsite Review

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• • • Approximately two weeks into the Refuel Outage prior to BWIC3-8 ti i

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