ML19329G125

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

ML19329G125
Person / Time
Site:	Millstone
Issue date:	06/16/1980
From:	Conner E, Conners E Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
TAC-11348, TAC-11561, TAC-12505, TAC-42846, NUDOCS 8007140027
Download: ML19329G125 (3)

Text

.

..e MEETING

SUMMARY

' DISTRIBUTION Licensee:

Northeast Nuclear Energy Company

• Distribution with Enclosures 1 thru 5

• • Distribution with Enclosures 1 and 2 Only

• • H.

Der. ton

• • E. G. Case

• Docket File

• • NRC PDR

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• • L PDR i

"M

• • NSIC

• • 0RBf4 Rdg

• • NRR Rdg

• • DEisenhut /RPurple

'**RTedesco

• • TNovak

• • Glainss

• • 0RB Branch Chiefs (5)

• 0RB Project Manager - MConner

• • 0RB Licensing Assistant -PKreutzer

• • 0 ELD

• • AE00

• • IE-3

• • RFraley, ACRS-16

• • Program Support Branch

• • Meeting Summary File NRC Participa..:.s

• SDiab

• Larry Kopp

• H. Richings

• W. L. Brooks

• Daniel Fieno

• MDunenfeld

• DPowers

• Chang Li

• Joseph T. DiMarzo

• Harry Balukjian 8007140011

• • fa neagd UNITED' STATES NUCLEAR REGULATORY COMMISSION

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WASHINGTON, D. C. 20555 a

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June 16 -1930 l

Docket No. 50-336 i

LICENSEE: Northeast Nuclear Energy Company (NNECO) 1

' FACILITY: Millstone Unit No. 2

SUMMARY

OF MEETING HELD ON JUNE 4,1980 TO DISCUSS THE CYCLE 4 1

RELOAD OF MILLSTONE 2 WITH WESTINGHOUSE FUEL The meeting had been requested by the NRC staff to discuss:

(1) core power distribution; (2) setpoint methodology; (3) uncertainty analysis; and, (4) 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.

e i

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 i

discussed, NNECO (Kacich) passed out the Enclosure 2 agenda.

W (Alsop) presented the power distribution methodology.

The viewgraphs used W.

The analysis shows TEnclosure 3) are considered Proprietary Class 2 by % of the Cycle 4 (M values that the Cycle 3 (CE) peaking factors are within 0.5 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.

l, They plan to use the same rod insertion limits, have assumed all accidents originated from expected conditions, and have developed 90,000 axial power i

shapes for use in the axial power shape methodology.

i Inc(Miranda) described the setpoint calculations (see Proprietary Class 2For DNB W

losure 4).

with a 1.3 limit -instead of the present CE-1 correlation with a 1.19 value.

i 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 Nel when the plant computer is out of service.

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

L The NRC (Fieno) indicated an interest in comparison of INCA differences between

-CE and W.

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v E. L.

onner, project Manager Operating Reactors Branch #3 i

Division'of Licensi.ng

Enclosures:

'As Stated u

NNECO & )[ MEETING ON MILLSTONE 2, CYCLE 4 RELOAD June 4, 1980 NRC NNECO Monte Conner Joe Parillo S. Diab Mike Cass Larry Kopp Byron Maddox-H. Richings

. W. L. Brooks Daniel Fieno h[

M. Dunenfeld B. H. Alsop.

D. Powers Bob Steither Chang Li Gary Jacob Joseph T. DiMarzo Harry Balukjian 6

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MILLSTONE UNIT NO. 2 MEETING AGENDA NNEC0/W/NRC MEETINa, 1980 REFUELING JUNE 4, 1980

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AGENDA / INTRODUCTION MIxE CASS II.

POWER DISTRIBUTIONS BRIAN ALSOP III.

SET POINTS ~

SAM UIRANDA BRIAN ALSOP IV.

UNCERTAINTY ANALYSIS BRIAN ALSOP V.

TECHNICAL SPECIFICATIONS NIKE CASS VI.

SUMMARY

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