ML20087G325
| ML20087G325 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 08/09/1995 |
| From: | Mccoy C GEORGIA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-92-01, GL-92-1, LCV-0648, LCV-648, NUDOCS 9508160335 | |
| Download: ML20087G325 (3) | |
Text
@[
Mi [#
Georg<a Power Company.
$,1 40 inverness Center Parkwap Post Office Box 1295 B>rmingham. Alabama 35201
. Telephone 205 877-7122 l
~
GeorgiaPower
- c. x. ucco, --
vNNIOf August 9, 1995 I
Docket Nos.
50-424 LCV-0648 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Vogtle Electric Generating 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, S1),
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 evaluation of the structuralintegrity 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 RPV integrity, or en explanation of why the existing data is considered complete as previously submitted.
Additionally, GL92-01, R1, S1 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 j
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 j
all information previously submitted remains valid.
This letter provides the Georgia Power Company (GPC) 90-day response to GL92-01, R1, S1 for Vogtle 1 and 2.
i 950816o335 95oa09 1 0l PDR ADOCK 05000424 i
P PDR_
i
?
a Y
/
]
GeorgiaPower d U. S. Nuclear Reg'ulatory Commission Page 2 GPC was a charter member 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. GPC has received the draft CE-RVG report and copies of the fabrication records for Vogtle 1 and 2. In addition, GPC will consider the following information to determine the impact on the Vogtle I and 2 reactor vessel integrity analyses:
NRC Reactor Vessel Integrity Database (RVID)
- CE-RVG Phase 11 Database ATI/WOG Database (including ORNL PR-EDB)
EPRI - RMATCH Database e
EPRI-PREP 3 Database Based on the information from the above sources, GPC will identify utilities that share a common material heat with the Vogtle 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. Based on the currently available information, GPC expects to provide any change to the best-estimate chemistry values used in the Vogtle 1 and 2 reactor vessel integrity analyses, including the impact of these changes on the reactor vessel integrity analyses, to the NRC within the 6-month timeframe requested in the generic letter supplement. GPC will advise prior to the 6-month requested response date ifit becomes necessary to request an extension for completion of this activity.
As part of a long-term resolution of this issue, GPC 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 alTect of any new information on the reactor vessel integrity analyses for Vogtle I and 2.
)
LCV-0648 i
N,
.+
- c;, g
.y L-
- GeorgiaPower1
- U! S.- Nuclear Reg 61atory Commission Page 3 Should you have any questions, please advise.
Respectfully submitted, C. K. McCoy CKM/TWS SWORN TO AN SUBSpRIBED BEFORE ME Tills T* DAY OF Augd _,1995 f
Y d% M. bb
' Notary Public My Commission Expires: N A 9-/999...
g_
.cc:
Georgia Power Company 1
J. B. Beasley, General Manager - Vogtle Electric Generating Plant i
i.
U. S. Nuclear Regulatory Commission. Washington. DC I
L. L. Wheeler, Licensing Project Manager, Vogtle U. S. Nuclear Regulatory Cornmission. Region II
")
S. D. Ebneter, Regional Administrator C. R. Ogle, Senior Resident Inspector - Vogtle 1
\\
l j.
i LCV-0648 -
-1 i......
1