ML17265A746
| ML17265A746 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 08/31/1999 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Vissing G NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| AL-95-03, NUDOCS 9909080039 | |
| Download: ML17265A746 (3) | |
Text
CATEGORY 1 REGULA'JRY 1NFORMATION DISTRIBUTI(%SYSTEM (RIDS)
ACCESSION NBR:9909080039 DOC.DATE: 99/08/31 NOTARIZED: NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
AUTH.NAME AUTHOR AFFILIATION MECREGY,R.C.
Rochester Gas
& Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION VISSING,G.S.
DOCKET ¹ 05000244
SUBJECT:
Submits response to NRC Administrative Ltr 95-03,rev 2,
",Availability of Reactor Vessel Integrity Database, Version,"
dtd 990726.
DISTRIBUTION CODE: A001D COPIES RECEIVED:LTRj ENCL Q SIZE:
Zl TITLE: OR Submittal: General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 E
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X/DSSA/SRXB OGC/RP COPIES LTTR ENCL RECIPIENT ID CODE/NAME VISSING,G.
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NOTE TO ALL MRZDSM RECIPIENTS:
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AND ROCHESTER GAS ANDELECTRIC CORPORATION.89 EASTAVENLIE, ROCHESTER, N.Y. 14649-0001 AREA CODE 716-546-2700 ROBERT C. MECREDY Vice President Nucteor Operotions August 31, 1999 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Guy S. Vissing Project Directorate I Washington, D.C. 20555
Subject:
Response to NRC Administrative Letter 95-03, Revision 2, "Availabilityofthe Reactor Vessel Integrity Database, Version 2", July 26, 1999
References:
- 1. Letter from R, C, Mecredy (RGB) to Guy S. Vissing (NRC), "RAIRelated to Reactor Pressure Vessel Integrity", August 25, 1998.
- 2. Letter from G. S. Vissing (NRC) to R. C. Mecredy (RGB'), July 6, 1999.
- 3. NRC Administrative Letter 95-03, Revision 2, July 26, 1999.
Dear Mr. Vissing:
References 2 S 3 mentioned the availability ofthe subject database on the NRC website and gave access instructions. Rochester Gas 0 Electric PGSE) retrieved and reviewed the database, particularly as it pertains to the R. E. Ginna Nuclear Power Plant.
Reviewing the database, we found that for the Ginna reactor vessel (RV) limitingmaterial, which is Heat ID 61782, Circ. Weld, SA-847, the calculated values ofseveral parameters derived &om information submitted in Reference 1 had not been incorporated in the new version 2 ofthe database.
These parameters are listed below:
Parameter RVIDVer.2 Current Value (per Ref. 1) 1.
Chemistry Factor 2.
Delta RTndt@EOL 3.
RTpts @ EOL sttctt0ttt08003ttt 'stt9083i PDR ADOCK 05000244 P
PDR 158.7 F 210.4 F 253.9 F 160.7 F 213.08 F 256.58 F Pod
These parameters are entered in two parts ofthe RVID, the Weld Detail Data Page and the PTS Summary Report Page.
Data for other welds, forgings, and plate materials are correct as we found no other discrepancies.
We request that in your next revision ofthe RVID, the above parameters be updated to reflect the new data that we submitted in Reference 1, as shown above. This is particularly important since the data pertains to the Ginna RV limitingweld which has been utilized to generate Ginna heat up Ec cooldown curves up to 40 EFPY (Effective Full Power Years).
We sincerely appreciate and offer our thanks for your consideration ofthis request.
Very t lyyours, Robert C. Mecredy xc:
Mr. Guy S. Vissing (Mail Stop 8C2)
Project Directorate I Division ofLicensing Project Management Office ofNuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King ofPrussia, PA 19406 U.S. NRC Ginna Senior Resident Inspector Andrea Lee