ML20087F351
| ML20087F351 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 08/09/1995 |
| From: | Dennis Morey SOUTHERN NUCLEAR OPERATING CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-92-01, GL-92-1, NUDOCS 9508150237 | |
| Download: ML20087F351 (3) | |
Text
..,.
Southern Nuclear Operating Company Post Om Box 1295
' Birmingh".m A!abama 35201 Telephone (205) 868-5131 L
Southem Nudear Operating Company o.v. uor.y vice President Farley Project the Southem electoc system August 9, 1995 Docket Nos.
50-348 10 CFR 50.54 50-364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant Response to Generic Letter 92-01, Revision 1, Supplement 1 Reactor Vessel Structural Integrity Ladies and Gentlemen:
The NRC issued Generic Letter 92-01, Revision 1, Supplement 1 (GL92-01, R1, SI),
Reactor Vessel Structural Integrity, on May 19,1995. In the generic letter supplement, the NRC identified a concern that licensees may not have all of the relevant data pertinent to the evaluatien of the structural integrity of their reactor pressure vessels. The generic letter supplement requested licensees to respond within 90 days describing those actions taken or planned to locate all data relevant to the determination of reactor vessel integrity, or an explanation ofwhy the existing data is considered complete as previously submitted.
Additionally, GL92-01, R1, Si requested licensees to provide the following information within 6 months of the date of the generic letter supplement:
- an assessment of any change in best-estimate chemistry based on consideration of all relevant data;
- a determination regarding the need to use the ratio procedure described in Position 2.1 of Regulatory Guide 1.99, Revision 2; and
- a written report providing any newly acquired data and; (a) the results of any necessary revisions to the evaluation of RPV integrity in accordance with the requirements of 10 CFR 50.60,10 CFR 50.61, Appendices G and H to 10 CFR 50, and any potential impact on the LTOP or P-T limits or (b) a certification that allinformation previously submitted remains valid.
This letter provides the Southern Nuclear Operating Company (SNC) 90-day response to GL92-01, R1, Si for Farley I and 2.
..... m e,,
9508150237 950809 s
DR ADOCK 05000348 PDR
'e p
1 U. S. Nuclear Regulatory Commission Page 2 4
SNC was a charter.nember of the Combustion Engineering Reactor Vessel Group (CE-RVG) which was formed in 1991 for the purpose of collecting and organizing the original fabrication records for CE-fabricated reactor vessels. SNC has received the draft CE-RVG report and copies of the fabrication records for Farley 1 and 2. In addition, SNC will consider the following information to determine the impact on the Farley 1 and 2 reactor vesselintegrity analyses:
NRC Reactor Vessel Integrity Database (RVID)
CE-RVG Phase 11 Database e
ATI/WOG Database (including ORNL PR-EDB) e EPRI - RMATCH Database
. EPRI-PREP 3 Database Based on the information from the above sources, SNC will identify utilities that share a common material heat with the Farley reactor vessels and work closely with these utilities to resolve any discrepancies that may be identified in the material properties for the shared material heats. Due to the volume ofinformation that must be reviewed in order to ensure consideration of all relevant infccmation pertinent to reactor vessel integrity, SNC does not expect to provide a complc
grovide all newly acquired data to the NRC and will provide a schedule for evale ng the impact of the newly acquired information on the reactor vessel integrity ana.,es for Farley I and 2 prior to the 6-month requested response date.
As part of a long-term resolution of this issue, SNC is currently participating in the recently approved Combustion Engineering Owners Group - Reactor Vessel Working Group (CEOG-RVWG) weld chemistry variability task. The objective of this task is to determine best-estimate copper and nickel values for each weld material heat used in the beltline region of CE-fabricated reactor vessels. Completion of this task is currently projected to require a minimum of 18 months. Upon completion, the results of this task will be evaluated to determine the affect of any new information on the reactor vessel integrity analyses for Farley 1 and 2.
Should you have any questions, please advise.
SOUTHERN NUCLEAR OPERATING COMPANY
$ bld" Dave Morey DNM/TWS SWORN TO AND SUBSCRIBED BEFORE ME THIS 9 6 DAY OF Amam/. .1995 Y fl Notary Pub ' // My Commission Expires:_
- wM /997 C7
a Q gg 2:.: - Ui S.' Nucl:ar Regulatoiy Commission - Page 3 - 1 cc: Southern Nuclear Operating Company R. D. Hill, Plant Manager ] U. S. Nuclear Regulatory Commission: Washington. DC B. L. Siegel,: Licensing Project Manager, NRR - U. S. Nuclear Regulatory Commission. Region II ' S. D. Ebneter, Regional Administrator T. M. Ross,- Senior Resident Inspector - I l i .!') t Y b ? e ,['. J m .~,- ...s '..L.}}