ML20244B059

Summary of 800604 Meeting W/Util in Bethesda,Md Re Cycle 4 Reload at Facility W/Westinghouse Fuel.List of Attendees & Agenda Encl

ML20244B059
Person / Time
Site:	Millstone
Issue date:	06/16/1980
From:	Conner E Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
Shared Package
ML19292H640	List: ML20244B059
References
TAC-11348, TAC-11561, TAC-12505, TAC-42846, NUDOCS 8007140027
Download: ML20244B059 (3)

Text

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[ **'t UNITED STATES NUCLEAR REGULATORY COMMISSION

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June 16, 1980 Docket No. 50-336 j

I LICENSEE: Northeast Nuclear Energy Company (NNECO)

FACILITY: Millstone Unit No. 2 g

SUMMARY

OFMEETINGHELDONDUNEI439001TODISCUSSTHECYCLE4 RELOAD OF MILLSTONE 2 WITH WESTINGHOUSE FUEL i

The meeting had been requested by the NRC staff to discuss:

(1) core power distribution; (2) setpoint methodology; (3) uncertainty analysis; and, (4) j proposed Technical Specification (TS) changes for. the Cycle 4 reload with Westinghouse (_W) designed fuel. The meeting was held at the NRC's offices in Bethesda, Maryland. A list of attendees is given in Enclosure 1.

After introductions and opening remarks by the NRC (Conner and-Fieno) in which the recent reorganization of NRR was explained and the type of review discussed, NNECO (Grs5Kae4eh) passed out the Enclosure 2 agenda.

W (Alsop) presented the power' distribution methodology. The viewgraphs used TEnclosure3)-areconsideredProprietaryClass2byW. The analysis shows that the Cycle 3 (CE) peaking factors are within 0.5Y of the Cycle 4 (Wl, values and are less than TS limits. - W has followed the Millstone 2 core since Cycle

- 1 so they have the same data as if it was a W unit, j

They plan to use the same rod insertion limits, have assumed all accidents originated from expected ~ conditions, and have developed 90,000 axial power shapes for use in the axial power shape methodology.

W (Miranda) described the setpoint calculations (see Proprietary Class 2 ).

For DNB determination, they will be using the W-3 correlation with a 1.3 limit instead of the present CE-1 correlation with a 1.19 value.

The nuclear peaking factor uncertainties analysis was presented by Mr. Alsop of W (see Proprietary Class 2 Enclosure 5). He pointed out that Millstone 2 must be derated to 89% power level when the plant computer is out of service.

The uncertainty analysis was presented in the addendum to the basis safety report.

The NRC (Fieno) indicated an interest in comparison of INCA differences between CE and W.

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onner, Project Manager Operating Reactors Branch #3 Q

Division of Licensing }lrm shM ik

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Enclosures:

As Stated 0

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..NNECO & )[ MEETING ON MILLSTONE 2, CYCLE 4 RELOAD -

June 4,'1980 g

- NRC

NNECO a.

LMonte Conner.

Joe Parillu I'

$. Diab Mike Cass

Larry Kopp.

Byron Maddox -

'H. Richings-W. L. Brooks

Daniel. Fieno.

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M. Dunenfeld B. H. Alsop

- D.' Powers Bob Steither.

Chang Li Gary. Jacob.

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' Joseph T. DiMarzo

. Harry Balukjian 1

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4 MILLSTONE UNIT NO. 2 i

MEETING AGENDA NNEC0/W/NRC MEETING,1980 REFUELING.

JUNE II, 1980' I

' AGENDA / INTRODUCTION MIKE CASS i

II.

POWER DISTRIBUTIONS BRIAN ALSOP III.

SET POINTS SAM fl!RANDA-BRIAN ALSor IV.

UNCERTAINTY ANALYSIS BRIAN ALSOP.

V.

TECHNICAL SPECIFICATIONS filKE CASS VI.

SUMMARY

MIKE CASS 1

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