ML17277A444

Forwards Corrected Page 2 of 830118 Evaluation of Containment Pressure Boundary Matls Re GDC 51,correcting Typographical Error

ML17277A444
Person / Time
Site:	Columbia
Issue date:	02/08/1983
From:	Bouchey G WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	Schwencer A Office of Nuclear Reactor Regulation
References
GO2-83-101, NUDOCS 8302150637
Download: ML17277A444 (5)

Text

REGULATORY I RMATION DISTRIBUTION SYST (RIDS)

ACCESSION NBR ~ 8302150637 DOC ~ DATE ~ 83/02/08 NOTARIZED ~

NO DOCKET FACIL!50 347 NPPSS Nuclear Projecti Unit 2i iflash.ington= Public.-Powe 05000397 AUTH'NAME AUTHOR AFFit IATION BOUCHEYPG ~ 0, Nashington Public Power Supply System HEC IP ~ NAMt'-

RECIPIENT AF F ILIATI ON SCHNENCERgA ~

Licensing Branch 2

SUBJECT:

Forwards corrected P 2,of 830118 evaluation of containment pressure boundary matls re GDC 51icorrecting typographical err or.

DISTRIBUTION CODE: 8001S,COPIES RECEIVED:LTR ENCL SIZE:,

TITLE: Licensing Submittal:

PSAR/FSAR Amdts 8, Related Correspondence NOTES:

REC IP IENT ID CODE/NAME NRR/DL/ADL'RR L82 LA INTERNAL: ELD/HDS2 IE/DEP EPOS 35 NRR/DE/AEAB NRR/DE/EQB 13 NRR/DE/HGEB 30 NRR/DE/MTEB 17 NRR/DE/SAB 20 NRR/DHFS/HFEBOO NRR/DL/SSPB NRR/DSI/ASB NRR/DSI/CS8 09 NRR/DSI/METB 12 22 G FIL.,

04 RM/DDA

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RECIPIENT ID CODE/NAME NRR LB2 BC AULUCKi R ~

01 IE FILE IE/DEP/EPLB 36 NRR/DE/CEB 11 NRR/DE/GB 28 NRR/DE/MEB 18 NRR/DE/QAB 21 NRR/DE/SEB 25 NRR/DHFS/LQB 32 NRR/DS I/AEB 26 NRR/DSI/CPB 10 NRR/DSI/ICSB 16 NRR/DSI/PSB 19 NRR/DS I/RSB 23 RGN5 COPIES LTTR ENCL 1

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Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richland, Washington 99352 (509) 372-5000 February 8, 1983 G02-83-101 Docket No. 50-397 Director of Nuclear Reactor Regulation Attention:

Mr. A. Schwencer, Chief Licensing Branch No.

2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Reference:

NUCLEAR PROJECT NO.

2 GENERAL DESIGN CRITERION 51, CLARIFICATION G02-83-048, G.D. Bouchey (SS) to A. Schwencer (NRC),

Same Subject, dated January 18, 1983 The attachment to the referenced letter provided an evaluation of WNP-2 containment pressure boundary materials with respect to GDC 51.

In the word processing of this evaluation a typographical error to Page 2 of the attachment was overlooked.

Please replace Page 2 of the evaluation with the attached correct page.

Should you have any questions, please contact Hr. R.M. Nelson,

Manager, WNP-2 Licensing.

Ltery truly yours, G.

D. Bouchey

Manager, Nuclear Safety and.Regulatory Programs THE/jca Attachment cc:

R Auluck -

NRC WS Chin

- BPA A

Toth NRC Site 8302150b37 830208

,PDR ADOCK 05000397 A

'DR

/

After obtaining the Kl

values, each value was compared to the K d Design-reference curve

( FiguN I) to determine the NDT tmnperature relative to the test temperature of the impact specimens.

This reference curve is the lower bound K d values for low and intermediate strength steels.

(Figure 2 provides a 3omparison of the KId reference curve to the ASNE Code KIR curve.)

NDT temperature was then determined by subtractin the difference between the NOT on the reference curve and the locatio o

the calculated KId value from the specimen test temperature for each component.

The plain strain limit (L) and yield-criterion (YC) were then calculated using the following equations:

B 2

1l2 t Value K

=

( ~d

)

Id 2.5 YC Value KId =

(

B (g d)

)

yd B

= thickness in inches o d

=

+ 20 ksi (equation from AAR R-451) c"

= CQe t<in. Yield Strength These values were then referenced to the K d refer ence curve to determine the NOT+T value for both the L and YC value.

These temperatures were plotted on a graph as the abscissa and stress levels as the ordinate (Figures 3-5).

The stress levels are in increments of the yield stress level and L corresponds to 0.2 X yield stress level.

A straight line was drawn between the two points corresponding to the L and YC values.

This line forms an arrest-transition curve.

The curve indicates the transition in stress required for propagation of through-thickness cracks.

The area to the right of the line indicates that fracture propagation of a through-thickness crack is not possible.

The minimum temperature above NOT required to provide fracture arrest of through-thickness cracks upon yield stress loading was then added to the NDT temperature previously determined from the KId reference curve to determine LSNT.

The thain Steam Isolation Valves LSMT were determined by the original analy-

sis, which used the material information provided in NUREG-0577 and the temperature correction factor from Summer 1977 Addenda of the ASHE Code.

The reason for the use of this analysis method was that impact test data was not available for the valves (see Section 5.2.3.3.1 of WNP-2 FSAR).

Conclusion This evaluation provides a more realistic LSNT for the limiting materials used in the containment pressure boundary at WNP-2 than the general analysis previously submitted to the NRC.

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