ML20141D594

Summary of 860320 Meeting W/Util Re in-house Reload Analysis Capability,Per Generic Ltr 83-11.Viewgraphs Encl

ML20141D594
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	03/31/1986
From:	Frank Akstulewicz Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
GL-83-11, NUDOCS 8604080165
Download: ML20141D594 (16)

Text

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March 31, 1986 s

~ Doc'ket No. 50-213 LICENSEE: Connecticut Yankee Atomic Power Company FACILITY: Haddam Nack Plant

SUMMARY

OF MEETING WITH LICENSEE REPRESENTATIVES REGARDING IN-HOUSE RELOAD ANALYSIS CAPABILITY On March 20, 1986, the staff met with the licensee to discuss the plans to perform core reload analyses. The licensee wanted to know if the staff could support-the licensee's schedule by completing the required reviews. In addition, the licensee solicited comments on the overall program plan.

The licensee described the progra, plan and their proposed schedule. The licensee stated that the data provided would be consistent with that described in Generic Letter 83-11. The computer codes that the licensee intends to use are the EPRI codes RETRAN and VIPRE. The licensee's reports for these codes have already been submitted. The proposed schedule was designed to get staff approval for use of the codes in sufficient time to submit a reload analysis package for Cycle 15 at Haddam Neck 90 days before startup. A copy of the licensee's presentation is enclosed.

The staff informed the licensee that the schedule seems reasonable, but the actual review time will depend on the quality of the information contained in the licensee's report for code qualification. Further, the staff informed the licensee that the staff review of the VIPRE code was complete and that a safety evaluation would be issued within the next two months. The review status of the RETRAN code was uncertain and the project manager stated that he would identify any schedular problems to the licensee once the review status was established.

Original signed by: F. Akstulewicz Francis Akstulewicz Integrated Safety Assessment Project Directorate Division of PWR Licensing - B

Enclosure:

DISTRIBUTION As Stated c 7 Docket FUe.0 7 ACRS(10) PAnderson ISAPD Reading FMiraglia NSIC cc: See Next Page L PDR FAkstulewicz OELD NRC PDR CGrimes BGrimes ISAPD:DPL-Bh ISNPL-B ISAPD:DPL-FAkstulewicv.lt PRIMfson CGrimes 03/$86 033f/86 03/j1/86 0604000165 [gg PDR ADOCK 06 PDR P

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((, g UNITED STATES NUCLEAR REGULATORY COMMISSION 5 l WASHINGTON, D. C. 20555 March 31,1986 Docket No. 50-213

, LICENSEE: Connecticut Yankee Atomic Power Company FACILITY: Haddam Neck Plant

SUBJECT:

SUPMARY OF MEETING WITH LICENSEE REPRESENTATIVES REGARDING IN-HOUSE RELOAD ANALYSIS CAPABILITY On March 20, 1986, the staff met with the licensee to discuss the pl.ns to perform core reload analyses. The licensee wanted to know if the staff could support the licensee's schedule by completing the required reviews. In addition, the licensee solicited coments on the overall program plan.

The licensee described the program plan and their proposed schedule. The licensee stated that the data provided would be consistent with that described in Generic Letter 83-11. The computer codes that the licensee intends to use are the EPRI codes RETRAN and VIPRE. The licensee's reports for these codes have already been submitted. The proposed schedule was designed to get staff approval for use of the codes in sufficient time to submit a reload analysis package for Cycle 15 at Haddam Neck 90 days before startup. A copy of the licensee's presentation is enclosed.

Toe staff informed the licensee that the schedule seems reasonable, but the actual review time will depend on the quality of the information contained in the licensee's report for code qualification. Further, the staff infonned the licensee that the staff review of the VIPRE code was complete and that a safety evaluation would be issued within the next two months. The review status of the RETRAN code was uncertain and the project manager stated that he would identify any schedular problems to the licensee once the review status was established.

h Francis Akstulewicz Integrated Safety Assessment Project Directorate Division of PWR Licensing - B

Enclosure:

As Stated cc: See Next Page

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'Mr. John F. Opeka Connecticut Yankee Atomic Power Company Haddam Neck Plant cc:

Gerald Garfield, Esquire Kevin McCarthy, Director Day, Berry & Howard Radiation Control Unit Counselors at Law Department of Environmental City Place Protection Hartford, Connecticut 06103-3499 State Office Building Hartford, Connecticut 06106 Superintendent Haddam Neck Plant Richard M. Kacich, Supervisor RDF #1 Operating Nuclear Plant Licensing Post Office Box 127E Northeast Utilities Service Company East Hampton, Connecticut 06424 Post Office Box 270 Hartford, Connecticut 06141-0270 Edward J. Mroczka Vice President, Nuclear Operations Northeast Utilities Service Company Post Office Box 270 Hartford, Connecticut 06141-0270 Board of Selectmen Town Hall Haddam, Connecticut 06103 State of Connecticut Office of Policy and Management ,

ATTN: Under Secretary Energy '

Division 80 Washington Street Hartford, Connecticut 06106 Resident Inspector Haddam Neck Nuclear Power Station clo U.S. NRC ,

East Haddam Post Office East Haddam, Connecticut 06423 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 b

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NORTHEAST UTILITIES SERVICE COMPANY NUCLEAR ANALYSIS RELOAD METHODOLOGY NUSCO/NRC MEETING MARCH 20, 1986

NU PARTICIPANTS JOHN R. GUERCI SUPERVISOR, RELOAD ANALYSIS i

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A. 2. LIVOLSI STAFF ENGINEER, RELOAD ANALYSIS '

G. VAN NOORDENNEN ENGINEER, LICENSING l

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NUSCO NUCLEAR ANALYSIS METHODOLOGY AGENDA INTRODUCTION -

G. VAN NOORDENNEN i l

NUSCO ANALYSIS ACTIVITIES -

J. R. GUERCI FOR THE HADDAM NECK PLANT NUCLEAR DESIGN METHODOLOGY - J. R. GUERCI NUSCO TOPICAL REPORT -

A. 2. LIVOLSI CLOSING REMARKS -

G. VAN NOORDENNEN t

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i NUSCO ANALYSIS ACTIVITIES FOR llADDEH NECK j -. '

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PLANT OPERATION CYCLE 13 CYCLE 14 CYCI.E IS SHALL BREAK LOCA (SUBHITTAL) COMPl.UTUU i

PROBABILISTIC SAFETY STUDY

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INTEGRATED SAFETY ASSES. PROGRAM _

l ON GOING i STANDARD TECil SPEC CONVERSION i

{ CIIAPTER 10 REANALYSIS NUCLEAR ANALYSIS TOPICAL REPORT ,

I CYCLE 15 RELOAD SAFETY EVAL.

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LARGE BREAK LOCA 3 ON GOING FDSA UPGRADE i

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NUSCO NUCLEAR DESIGN METHODOLOGY.

NUSCO ORGANIZATION NUSCO APPROACH RELOAD ANALYSIS STAFF I

RELOAD ANALYSIS TRAINING / EXPERIENCE W METHODS APPLICABILITY TO NU'S PWRS TOPICAL REPORT f

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NUSCO ENGINEERING ORGANIZATION l-REACTOR ENGINEERING l i

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l SAFETY ANALYSIS NUCLEAR ANALYSIS REACTOR PERFORMANCE i SECTIONS SECTIOliS SECTION I

i I-l L RELOAD ANALYSIS NUCLEAR ANALYSIS l

o INCORE Fuel Management o Core Follow i

o Reload Design o Process Computer I o Safety Related Physics Data o Vendor Nuclear Analysis l

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t NUSCO APPROACH SINGLE METHODOLOGY FOR ALL PWRS USE OF WESTINGHOUSE DESIGN METHODOLOGY o Manpower and Schedular Requirements o Codes Licensed and Approved o Methodology Licensed and Approved o W Modeling Procedures i

INITIAL DESIGN UNDER W GUIDANCE o Models Independently Verified by W o Cycle 15 Design Independently VerTfied by W I

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. 1 RELOAD ANALYSIS STAFF STAFFING LEVEL o 7 Engineers o 1 Technician

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EDUCATION 1

o 3 PH.D's o 3 MS o 1 BS ,

o 1 AS EXPERIENCE o 1 TO 28 Years f TOTAL MAN YEARS '

o 63 PREVIOUS ANALYSIS EXPERIENCE i o Babcock & Wilcox o Exxon '

o General Electric l

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i RELOAD ANALYSIS TRAINING / EXPERIENCE l

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I N RELOAD CORE DESIGN METHODS TRAINING TOTAL OF 100 MAN MONTHS l-l o 50 Ma.n Months at W-NFD f o 50 Man-Months at RUSCO I

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l CPRI CODE PACKAGE i

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o Many Man Years Evaluating Core Follow and Design Models I

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APPLICABILITY OF W METHODOLOGY TO '

NORTHEAST UTILITIES'S PWRS -

MILLSTONE UNIT 2 -

CURRENTLY LICENSED ON -

W ANALYSES MILLSTONE UNIT 3 -

CURRENTLY LICENSED ON W ANALYSES s

CONNECTICUT YANKEE -

W - NSSS W - METHODOLOGY

APPLICABILITY OF W METHODOLOGY TO CONNECTICUT YANKEE W - NSSS o Enrichments Are Standard o Steel and 2r Clad Are Analyzed by W o Fuel Design is Compatible

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W PERFORMS "OTHER VENDOR" ANALYSES o Analyses of Non-W Fabricated Fuel o Analyses of Non-W Fuel Designs i

MIXED CORES ANALYZED BY W METHODS o Zr and SS in Early Connecticut Yankee and Yankee Rowe Cores UNCERTAINTIES - STANDARD W APPROACH NEUTRONICS METHODS- STANDARD }[ APPROACH W CODES WITH W METHODOLOGY i

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4 TOPICAL REPORT CONTENTS o Introduction o W Codes and Methods Description o Connecticut Yankee Specific Models o Application of Models o NUSCO Qualification Through Connecticut Yankee Data Comparison o Conclusion UNCERTAINTIES o Standard W App $ bach DATA COMPARISONS o Cycles 12, 13, and 14 (Startup Physics Data) o Cycles 12 and 13 (Power Distributions)

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CONCLUSION o THE TOPICAL REPORT WILL DEMONSTRATE NUSCO'S QUALIFICATIONS TO PERFORM RELOAD DESIGN ANALYSES FOR NORTHEAST UTILITIES' PWRS USING WESTINGHOUSE METHODOLOGY i

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