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 1 1 1 1 1 1 1 1 0 RECIPIENT ID CODE/NAME JOHNSON,A NRR/DE/EMCB NRR/DRPE/PDI-1 NUDOCS-ABSTRACT RES/DE/MEB NRC PDR COPIES LTTR ENCL 2 2 2 2 1 1 1 1 1 1 1 1 D C U N NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE O'ASTE!CONTACT'I'I IE DOCI:CLIENT CONTROL DESK, ROOKI PI-37 (EXT.504-2083)TO ELIAIINATE YOUR NAi!E FROil DISTRIBUTION LISTS I:OR DOCI.h,I EN'I'S YOI'ON" I'LED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 14 ENCL 13 C J~,t AND ROCHESIER GAS AWD EIECIRIC CORPORATION
~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'alculated 0.26" 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.
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