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 P Document Control Branch (Document Control Desk)
R
SUBJECT:
Provides updated Table 1 re GL 92-0l,revl, "Reactor 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 COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-3 PD 1 1 JOHNSON,A 2 2 INTERN/': FILE CENTER 01 1 1 NRR/DE/EMCB 2 2 NRR/DORS/OGCB 1 1 NRR/DRPE/PDI-1 1 1 NRR/DRPW 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS3 1 0 RES/DE/MEB 1 1 EXTERNAL: NOAC NRC PDR 1 1 D
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N NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE O'ASTE! CONTACT'I'IIE DOCI:CLIENT CONTROL DESK, ROOKI PI-37 (EXT. 504-2083 ) TO ELIAIINATEYOUR NAi!E FROil DISTRIBUTION LISTS I:OR DOCI. h,I EN'I'S YOI 'ON"I'LED!
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AND ROCHESIER GAS AWD EIECIRIC CORPORATION ~ 89 FASI'AVENUE, ROCHESTER, N. Y Id649-000I ARFA CODE716 54'6-2700 ROBERT C. MECREDY Vice President October 25, 1994 hlvcleoroperotions 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 IS Neut. Method of Method of Beltline Fluence at IRT~ Determin. Chemistry Determin.
Material Heat No. EOL/EFPY oF IRTNDr Factor CF %Cu Upper Shell 123P118VA1 3.69E+18i +30s Plant 223.6 RG1.99 Forging (apo) Specific Table 2 O.3S'nterm.
Shell 1258255VA1 3.68E+19~ +20s Plant Calculated 0 Forging (ai=o) Specific Lower Shell 3.68E+19~ Plant 07'alculated 125P666VA1 27. 806 Forging +40'ai=o)
Specific 0.05'alculated SA-1101 US to 71249 3 72E+18 Plant 173.56~ 0.26" IS Circ. Weld +10'ai=o)
Specific SA-847 IS to LS 61782 3.68E+19~ 19 ss Generic 147 19s Calculated 0.25" Circ. Weld ( al=18. 5 )
SA-848 LS to 61782 N/Ai 19 5s Generic 147 19s Calculated 0.25'~
Dutch. Circ. (ai=18. 5)
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. Chemistry Factors for forging 125S255VA1 and forging 125P666VA1 were determined using REG surveillance data as reported in WCAP-13902 and WCAP 13893.
7 ~ 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.
- 8. 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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