ML20133F753

Summary of 850626 Meeting W/Util & Westinghouse Re Upcoming Changes to Reactor Internals & Impact on Tech Specs.Licensee Plans to Change from Exxon Fuel to Westinghouse Fuel.Agenda & Attendance List Encl

ML20133F753
Person / Time
Site:	Prairie Island
Issue date:	07/31/1985
From:	Diianni D Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8508080418
Download: ML20133F753 (6)

Text

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s July 31, 1985 Docket Nos. 50-282 and 50-306 FACILITY: Prairie Island Units Nos. I and 2 LICENSEE: Northern States Power Company

SUMMARY

OF JUNE 26, 1985 MEETING ASSOCIATED WITH UPCOMING CHANGES TO THE REACTOR INTERNALS AND IMPACT ON THE TECHNICAL SPECIFICATIONS On June 26, 1985, the staff met with Northern States Power Company, the licensee for the Prairie Island Nuclear Generating Plant Units Nos. I and 2, and Westinghouse to discuss future changes to the reactor internals and to the analysis methods including the impact on the technical specifications. This meeting was requested by the licensee for the purpose of informing the staff of the interrelationship of these changes even though each change was individually discussed in the past. The licensee has scheduled all of the changes to be in place for Cycle 11 for Unit 1 startup in March 1986. The licensee requested that the meeting be proprietary based on the nature of the material to be presented. However, the staff questioned the sensitive nature of the material at the conclusion of the meeting. The agenda and a list of attendees are enclosed (Enclosures 1 and 2).

Northern States Power Company is proceeding with the following changes that would become effective for Cycle 11 for Unit 1 (March 1986).

1. Thimble plug removal will impact the safety evaluation and the operation transient analysis for Cycle 11 for Unit 1. Both evaluations will be performed by NSP under 10 CFR 50.59. The staff is currently reviewing the reactor hydraulic effects of the thimble plug removal.

2. A method change for analyzing the thermal / hydraulic hot channel analysis consists of replacing COBRA IIIC/MIT with the VIPRE-01 code which includes WRB-1 CHF correlation for use with Westinghouse fuel. The licensee plans to use VIPRE-01 for Cycle 11 Unit 1 operation transient analyses. VIPRE-01 Code is currently being reviewed generically by the staff and the plant specific analysis results for Prairie Island have been submitted by letter dated April 19, 1985. The staff expects the generic and plant specific analyses (Prairie Island) to be completed by January 2,1986.

3. The licensee plans to change fuel vendors from the present EXXON fuel to Westinghouse fuel. The mechanical design and analysis will be performed by Westinghouse under 10 CFR 50.59 for the 8508080418 85073122 PDR ADOCK 05

-2 licensee. The mechanical design and analysis is part of the Cycle 11 Unit I reload analysis and NRR review is not necessary since reloads are normally done under 10 CFR 50.59 for Prairie Island.

4 The licensee plans to use the LOCA model NOTRUMP for analyzing the small break LOCA for Cycle 11 (Unit 1) analyses. By letter dated June 6, 1985, the licensee was informed of the NRC approval of the new Westinghouse small break LOCA model NOTRUMP, for use in satisfying the TMI Action Item II.K.3.30 and permitted the start of the plant specific analysis in accordance with Item II.K.3.31. The licensee plans to perfonn the plant specific analysis satisfying II.K.3.31 on the Cycle 11 fuel core.

Subsequent to the meeting, the licensee informed the Prairie Island project manager that the Cycle 11 Unit I core will have a mix of EXXON and Westinghouse fuel assemblies and there is an open question on whether the NOTRUMP model can be applied to the EXXON fuel. This matter will be resolved within 60 days from June 6,1985(i.e.,theletterdateapprovingtheNOTRUMPmodel).

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! 5. The licensee plans to replace the reactor upper internals with an upgraded design known as " Top Hat Design" during Cycle 11 Unit I refueling. Details of the replacement of the reactor upper internals were covered in a meeting sumary issued on April 16, 1985 in regard to a meeting held with the licensee on March 7, 1985. The licensee expects to issue a safety evaluation report <

for NRR review by November 1985 and the replacement is being performed under 10 CFR 50.59.

6. By October 1985, the licensee plans to submit an amendn.ent request involving technical specification changes to Fg, FA H, K7 , and rod drop time.

In conclusion, Northern States Power Company felt this meeting served to give the staff an overview of all tasks that are currently underway for the <

Prairie Island Nuclear Generating Plant so that the NRC's reviews can be adequately coordinated with the licensee's efforts.

0 Dominic C. l'i Ianni, Project Manager 1

Operating Reactors Branch No. 3 Division of Licensing

Enclosures:

As stated cc w/ enclosures:

See next page ORBf3:DL ORBf3:DL)Og DDilanni J

r 7 /85 / /.sf/85

O Mr. D. M. Musolf Prairie Island Nuclear Generating Northern States Power Company Plant l cc:

Gerald Charnoff, Esq.

! Shaw, Pittman, Potts and Trowbridge 1800 M Street NW Washington, DC 20036 Executive Director Minnesota Pollution Control Agency 1935 W. County Road, B2 Roseville, Minnesota 55113 Mr. E. L. Watzl, Plant Manager Prairie Island Nuclear Generating Plant Northern States Power Company Route 2 Welch, Minnesota 55089 Jocelyn F. Olson, Esq.

Special Assistant Attorney General Ninnesota Pollution Control Agency 1935 W. County Road, B2 Roseville, Minnesota 55113 l U.S. Nuclear Regulatory Comission l Resident Inspector's Office l Route #2, Box 500A l

Welch, Minnesota 55089 i Regional Administrator, Region !!!

U.S. Nuclear Regulatory Comission Office of Executive Director for Operations 799 Roosevelt Road Glen Ellyn, Illinois 60137 Mr. William Miller, Auditor Goodhue County Courthouse Red Wing, Minnesota 55066 l

ENCLOSURE 1 NORTHERN STATES POWER COMPANY'S MEETING WITH THE NRC STAFF ON THE TRANSITION FROM EXXON M WESTINGHOUSE FUEL FOR PRAIRIE ISLAND NUCLEAR GENERATING PLANT June 26, 1985 I. Introduction -

10 min T Parker II. NSP Analysis - 10 min R Anderson A. Core Design - 30 min C Bonneau (General Discussion and application of .

V(z) to Westinghouse Fuel)

5. Operational Transient Analysis - 30 min D Raut==nn j (using WRB-1 and VIPRE, and assuming i i

thimble removal - areas currently being reviewed by the staff)

III. Westinghouse Analysis Mechanical Design and Analysis - 30 min Westinghouse (Comparison of the Westinghouse and Exxon fuel design) I IV. IDCA 4 i

A. Large Break and Small Break - 15 min T Parker B. E(z) Curve and UPI Program - 5 min T Parker V. Schedule and Sissmary T Parker (including a discussion of planned submittals)

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. ENCLOSURE 2 NORTHERN STATES POWER COMPANY l

l MEETING JUNE 26, 1985 THE TRANSITION FROM EXXON TO WESTINGHOUSE FUEL PRAIRIE ISLAND NUCLEAR GENERATING PLANT ATTENDEES LIST Attendees Organization Dominic Di Ianni CRBf3 PM Amira M. Gill CPB/DSI/NRR Nuclear Engineer John Sharitha Westinghouse /NFD - Fuel Licensing Robert F. Meyer Westinghouse /NFD - Project Eng.

Bill Wright W NFD - Mechanical Design Clifford Bonneau NSP - Supt. Core Analysis  ;

Roger 0. Anderson. NSP - Manager Nuclear Analysis '

Dave Rautenaun NSP- Supt. Safety Analysis R. S. Miller W NFD Mgr. Performance Analysis Paul J. Kersting W NFD Performance Analysis David Langford NkR-DSI-RSB UPI Reviewer Tom Parker NSP licensing Daniel Fieno NRC/CPB Richard Lobel NRC/CPB Shih-Liang Wu NRC/DSI/CPB Harry Balukjian NRC/DSI/CPB Gene Hsii NRC/DSI/CPB Norm Lauben NRC/DSI/RSB Robert Jones NRC/DSI/RSB r

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o MEETING

SUMMARY

DISTRIBUTION Licensee: Northern States Power Company

• Copies also sent to those people on service (cc) list for subject plant (s).

• DechetiVile' NRC POR L PDR ORBf3 Meeting Sumary File DDilanni EButcher BGrimes OELD EJordan, IE ACRS-10 PMorriette -

All Meeting

Participants:

AG111 DLangford DFieno RLobel SMu HBalukjian GHsii NLauben RJones I

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