ML20055A297
| ML20055A297 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 07/06/1982 |
| From: | Diianni D Office of Nuclear Reactor Regulation |
| To: | Clark R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8207160097 | |
| Download: ML20055A297 (4) | |
Text
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s JUL 6 1982 s Als<tb Docket Nos. 50-282 and 50-306
!!EMORANDUM FOR: Robert A. Clark, Chief Operating Reactors Branch #3, DL FROM:
Dominic C. Dilanni, Project Manager Operating Reactors Branch #3, DL SUBJECT FORTHCOMING MEETING WITH il0RTHERN STATES POWER COMPNiY (fiSP) TO DISCUSS FUEL RELOAD METHODOLOGY FOR PRAIRIE ISLAND UNITSNos. 1 & 2 TIME & DATE:
9:00 AM - Wednesday July 21, 1982 PLACE:
6110 Maryland National Bank Building PURPOSE:
The licensee (NSP) is to furnish a description of the qualification of Reactor Physics and Safety evaluation methods for fuel reloads for Prairie Island Unit Hos. 1
& 2 as presented in NSP reports NSPNAD8101P and - 8102P.
The agenda is attached.
Participants:
NRC NSP OTHERS Ed dividison Tom Parker NAI Jack Fisher Wayne Hodges Roger Anderson Dick Kern Brian Sheron, RSB Dave Rautmann Larry Kcpp Cliff Bonneau Larry Phillips Jerry Hiles Dan Fieno Ralph Meyer Yihsiung Hsii John Vogelewede Carl Berlinger, CPA Dom Dilanni Bobert Clark, ORB #3 Crh st '~ rad by 8207160097 820706 PDR ADOCK 05000282
- 0. C. Dilanni, Project Manager P
PDR Operating Reactors Branch #3 Division of Licensing cc: See back of page
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4 cc: Docket File flRC PDR Local PDR ORB!3 Rdg T. Novak T. Ippolito, ORAB H. Denton B. Grimes Project Manager OELD I&E Receptionist NSIC ACRS-10 Resident Inspector Regional Administrator M. Schaaf flRC Participants D. Musolf - 8 4
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6[//[9 L SUGGESTED MEETING AGENDA ON REPORT N05. NSPNAD-8102P Afl0 -8101P PURPOSE:
(a) Northern States Power Company (NSP) is to furnish a description of the qualification of Reactor Physics and safety evaluation methods for fuel reloads for the Prairie Island Nuclear Generating Plant Unit Nos. 1 and 2 as presented in NSP reports NSPNAD-8101P and -8102P.
I.
INTRODUCTION II. GENERAL (ADMINISTRATIVE)
(a) NSP organization that would be responsible for performing the reload analysis and safety evaluations.
(b) Personnel qualifications and NSP's analytical capabilities.
(c) Objectives of the analytical programs.
(d) Scope of work performed by NSP and work performed by others (i.e., consultants, fuel vendors, etc.).
(e) Schedule for having the NSP's reload capabilities in place regarding analytical code development.
III. D.ESCRIPTION OF NSP's ANALYTICAL METHODS (a) Steady State Neutronic (b) Fuel Design Analytical Methods (c) Thermal / Hydraulic Analytical Methods (d) Transient and Accident Analysis (e) Description of all Computer Codes (i.e., COBRA, T00DEE, etc.)
used in the above Analytical Methods (a, b, c & d) including benchmarking against other codes and experiments and uncertainties.
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4 IV. DESCRIPTION OF RELOAD PROCEDURES (a) Determination of the type of transients and accidents that would be analyzed.
(b) Use of key parameters to determine the need for transient l
analysis.
(c) Determination of key parameters for evaluation of each tran-sients and/or accidents.
(d) Procedural descriptions of analyses performed by consultant or vendors.
V.
SUMMARY
Prepa->d by b,
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D. C. Dianni PM
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