ML17263A823
| 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
RECIPIENT ID CODE/NAME PD1-3 PD INTERN/': FILE CENTER 01 NRR/DORS/OGCB NRR/DRPW OGC/HDS3 EXTERNAL: NOAC COPIES LTTR ENCL 1
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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
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.
%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