ML17254A842

Forwards Westinghouse Justification for Use of W-3 Correlation w/1.3 Design Limit DNBR at Pressure Below 1,000 Psia for Steamline Break Analysis.Approach Taken in No Longer Required

ML17254A842
Person / Time
Site:	Ginna
Issue date:	06/28/1984
From:	Kober R ROCHESTER GAS & ELECTRIC CORP.
To:	Crutchfield D Office of Nuclear Reactor Regulation
References
NUDOCS 8407030231
Download: ML17254A842 (12)

Text

REGULATORY NFORMATION DISTRIBUTION SY fEM (RIDS)

ACCESSION NBR;8407030231 DOC ~ DATE: 84/06/28 NOTARIZED;,NO FACIL:50 244 Robert'mmet Ginna Nuclear Planti Uni;t li Rochester G

AUTH'AME AUTHOR AF F ILIATI ON KOBERrR ~ Hi Rochester Gas-8 Electric Corp+

RECIP ~ NAME RECIPIENT AFFILIATION CRUCTHF IELDi D ~

Oper ating Reactor s Branch

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SUBJECT:

" ForwardsNestinghouse Justification for use of I'( 3 correlation w/1.3 design limit DBNR at pressure below ii000 psia for steamline brea/ analysis. Approach taken in 840412 ltr no longer required.

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ROCHESTER GAS AND ELECTRIC CORPORA77ON o 89 EAST AVENUE, ROCHESTER, N.K 14649-0001 ROGER W. KOBER VICE PRESIDENT ELECTRIC &STEAM PRODUCTION TELEPHONE AREA CODE TIS 546.2700 June 28, 1984 Director of Nuclear Reactor Regulation Attention:

Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch No.

5 U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Subject:

Justification for W-3 Correlation Below 1000 PSIA R.

E. Ginna Nuclear Power Plant Docket No.

50-244

Dear Mr. Crutchfield:

Reference (a) provided clarification to responses to NRC Staff questions submitted by our Reference (b).

Reference (a) provided justification that the DNB design basis was met for Ginna steamline break analysis.

That justification used the approach of demonstrating that the minimum W-3 DNBR calculated for the transient exceeded a reference value which itself included con-siderable margin to the design basis limit of 1.3.

That approach was taken in order to resolve NRC concerns about the validity of the W-3 correlation at pressures below 1000 psia.

In Reference (c) the NRC informed us that the Commission did not consider the reference value cited in Reference (a) to be proprietary.

The NRC further stated that in not less than 30 days (from June

1) Reference (a) would be placed in the Public Documents Room, unless sufficient reason for withdrawing the document is provided.

8407030231 8406 ADOCK 05000244 PDR

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ROCHESTER GAS AND ELECTRI ORP.

DATE June 28, 1984 Mr. Dennis M. Crutchfield SHEET NO.

The enclosure to this letter provides the Westinghouse justification for the use of the W-3 correlation with a 1.3 design limit DNBR at pressures below 1000 psia.

In light of the additional information provided, it is the Westinghouse position that the approach taken in Reference (a) is no longer required.

We propose that the information provided in the enclosure be used as justification of the Ginna steamline break analysis.

Please note that the information in the enclosure has already been provided to the NRC in support of the Trojan Bit concentration reduction study.

Pending resolution of this issue, we request that the information contained in Reference (a) be withheld from the Public Document Room.

V r truly yours, Ro r W. Kober References (a)

Letter from R.

W. Kober (Rochester Gas and Electric) to D.

M.

Crutchfield (NRC),

"Responses to NRC Staff Questions," April 12, 1984.

(b)

Letter from R.

W. Kober (Rochester Gas and Electric) to D.

M.

Crutchfield (NRC),

"Responses to NRC Staff Questions,"

March 19, 1984.

(c)

Letter from D.

M. Crutchfield (NRC),

"Responses to NRC Staff Questions'equest for Withholding of Information Use of Westinghouse Optimized Fuel," June 1,

1984.

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Enclosure 1

Justification of 1.3 Design Limit DNBR for the W-3 Correlation at Pressures Below 1000 PSXA Reference 1 describes the results of applying the W-3 correlation over its original pressure

range, 1000 to 2300 psia.

The mean measured-to-predicted critical heat flux rato and sample standard deviation from that analysis are shown in Table 1.

Reference 2 contains the results of an'analysis "of low pressure (700 1000 psia) data using the W-3 correlation.

Those data were taken from the same sources as those used in the development of the W-3 corr'elation.

As shown'n, the 'attached figure (taken from Reference >2)'o,anomalous behave.ore'is, observed for the low pressure data.

The W-3 correlation statistics have been recalculated for the extended database.

The revised statistics'are essentially unchanged from the original values (Table 1).

The limit DNBR was also recalculated using the method of Owen (Reference 3).

As shown in Table 1, the revised correlation statistics demonstrate that there is a

95% probability with 95% confidence that DNB will not occur if the minimum DNBR is maintained in excess of 1.31.

Again, this value is essentially unchanged from the limit DNBR associated with the original database.

This evaluation demonstrates that extending the pressure range of the W-3 correlation database by a significant amount has a negligible effect on the correlation statistics.

Therefore, continued use of the 1.3 limit DNBR for the Ginna steambreak analysisis justified.

References 1)

Tong, L. S.

, "Prediction of Departure from Nucleate Boiling for Axially Non-Uniform Heat Flux Distribution," J. Nuclear

~nercny, Vol. 21, pp 241-248 (1967).

2)

Prairie Island FSAR Amendment 20, p. 14.2-30, Docket 550-282, August 4, 1972.

3)

Owen, D. B., "Factors for One-Sided Tolerance Limits and for Variable Sampling Plans,"

SCR-607, l1arch 1963.

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TABLE "'1

-'M-'3 CHF CORRELATION STATISTICS Pressure Range Number of sia Data Points Sampl e Standard H/P Deviation Limit DNBR 1000 - 2300 809

0. 996

0. 132 1.30 700 - 2300 885

1. 001 0.137 1.31

P

.k

Cl Go oo 0

0 0

0 o

o g B

0 Cl Cl 0

Cl Cl CO (p s e

%55%

ce 4 0

0 Cl Cl Cl C)

Cl Cl C7 Cl xn[g q.eaH gwg (paznsesjj/pay.otpavd)

(Predicted/Measured)

DNB Heat Flux vs Pressure Figure 14.2-11

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