ML17263A823

Provides Updated Table 1 Re GL 92-01,rev 1, Reactor Structural Integrity

ML17263A823
Person / Time
Site:	Ginna
Issue date:	10/25/1994
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-92-01, GL-92-1, NUDOCS 9411020143
Download: ML17263A823 (6)

Text

PR.I(3R.I EY (ACCELERATED RIDS P ROCESSIX REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9411020143 DOC.DATE: 94/10/25 NOTARIZED-NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G

05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.

Rochester Gas 6 Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

P

SUBJECT:

Provides updated Table 1 re GL 92-0l,revl, "Reactor R

Structural Integrity."

I DISTRIBUTION CODE:

A028D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: Generic Letter 92-01 Responses (Reactor Vessel S ructural Integrity 1 NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).

05000244 R

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C U

N NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE O'ASTE! CONTACT'I'IIE DOCI:CLIENTCONTROL DESK, ROOKI PI-37 (EXT. 504-2083 ) TO ELIAIINATEYOUR NAi!EFROil DISTRIBUTION LISTS I:OR DOCI. h,IEN'I'S YOI'ON"I'LED!

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AND ROCHESIER GASAWDEIECIRICCORPORATION ~ 89 FASI'AVENUE, ROCHESTER, N. Y Id649-000I ARFA CODE716 54'6-2700 ROBERT C. MECREDY Vice President hlvcleoroperotions October 25, 1994 U.S. Nuclear Regulatory Commission Document Control Desk Attn:

Allen R. Johnson Project Directorate I-3 Washington, D.C.

20555

Subject:

Generic Letter 92-01, Revision 1,

"Reactor Structural Integrity," Data Table Update R.E.

Ginna Nuclear Power Plant Docket No. 50-244 Ref.(a):

Letter from R. C. Mecredy (RG&E), to A. R. Johnson (NRC),

"Response to Generic Letter 92-01, Request for Closure Information," dated June 30, 1994.

Dear Mr. Johnson:

The referenced letter provided data for the R.E.

Ginna reactor vessel.

Table 1 of the letter listed IRT>> for "SA-847 IS to LS Circ. Weld" and "SA-848 LS to Dutch Circ. Weld" as -5'F(ot=19.7'F).

Further evaluation with the B&W Owner's Group has shown that this value should be -19.5'F (at=18.5'F) as reflected by previous B&W reports 1801 Rl, 1543 Rev.

4, and

1920P, April 1991.

Please replace the Table 1 submitted in the referenced letter with the enclosed updated Table 1.

Very truly yours, Robert C.

Me edy REJ/350 xc:

Mr. Allen R. Johnson (Mail Stop 14D1)

Project Directorate I-3 Washington, D.C.

20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector

'st411020143 941025 PDR ADOCK 05000244 C

PDR

Table 1.

R. E. Ginna Data Summar for Pressurized Thermal Shock Calculation Beltline Material Upper Shell Forging Heat No.

123P118VA1 IS Neut.

Fluence at EOL/EFPY 3.69E+18i IRT~

oF

+30s (apo)

Method of Determin.

IRTNDr Plant Specific Chemistry Factor 223.6 Method of Determin.

CF RG1.99 Table 2

%Cu O.3S'nterm.

Shell Forging Lower Shell Forging SA-1101 US to IS Circ. Weld SA-847 IS to LS Circ. Weld SA-848 LS to Dutch. Circ.

Weld 1258255VA1 125P666VA1 71249 61782 61782 3.68E+19~

3.68E+19~

3 72E+18 3.68E+19~

N/Ai

+20s (ai=o)

+40'ai=o)

+10'ai=o) 19 ss

( al=18. 5 )

19 5s (ai=18. 5)

Plant Specific Plant Specific Plant Specific Generic Generic

27. 806 173.56~

147 19s 147 19s Calculated 0

07'alculated 0.05'alculated0.26" Calculated 0.25" Calculated 0.25'~

Table 1.

cont.

R. E. Ginna

- Data Summar for Pressurized Thermal Shock Calculations NOTES:

1.

- Values from July 2, 1992 letter from R.

C. Mecredy (RGB) to A. R. Johnson (USNRC)

Subject:

Reactor Vessel Structural Integrity, 10CFR50.54(f),

Response

to Generic Letter 92-01, Revision 1, R. E.-Ginna Nuclear Power Plant.

2.

Values determined from WCAP-13902 and WCAP-13893.

3.

Values determined from data in Material Test Report.

4.

Value determined from data in EPRI NP-373.

5.

Mean values from data in BAW-1803, Revision 1; BAW-1543, Revision 4; BAW-1920P, April 1991.

6.

7 ~

8.

Chemistry Factors for forging 125S255VA1 and forging 125P666VA1 were determined using REG surveillance data as reported in WCAP-13902 and WCAP 13893.

Chemistry Factor for weld metal SA-1101 was determined using TP3 surveillance data for weld metal SA-1101.

The TP3 30 ft-lb transition temperature shift data were obtained from BAW-1803, Revision 1, while the fluence data for the capsules were obtained from BAW-1803, Revision 1 and NUREG CR-3319, Revision 1.

Chemistry Factor for weld metal SA-847 and weld metal SA-848 was determined using B6WOG surveillance data for weld metal SA-1135 and REG surveillance data for weld metal SA-1036.

These surveillance welds were fabricated with the same wire heat as weld metal SA-847 and weld metal SA-848.

The BGWOG surveillance data were obtained from BAW-1803, Revision 1.

The REG surveillance data were obtained from WCAP-13902.

9.

No data available for this material, therefore, 0.35% is specified as defined in Regulatory Guide 1.99, Revision 2.

10.

Values obtained from BAW-2150.

ll. Values obtained from BAW-2121P.

12.

Values obtained from BAW-1500.

A L