ML032870105
| ML032870105 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 10/14/2003 |
| From: | Rinaldi F NRC/NRR/DLPM/LPD2 |
| To: | Gasser J Southern Nuclear Operating Co |
| Rinaldi F, NRR/DLPM/LPD2-1, 415-1447 | |
| References | |
| GL-96-006, TAC MA8627, TAC MA8628 | |
| Download: ML032870105 (5) | |
Text
October 14, 2003 Mr. J. T. Gasser Vice President - Vogtle Project Southern Nuclear Operating Company, Inc.
Post Office Box 1295 Birmingham, Alabama 35201-1295
SUBJECT:
VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 RE: REQUEST FOR ADDITIONAL INFORMATION - RESOLUTION OF GENERIC LETTER 96 WATER HAMMER ISSUES (TAC NOS. MA8627 AND MA8628)
Dear Mr. Gasser:
On August 19, 2003, during a conference call between Southern Nuclear Operating Company and the NRC staff, we discussed NRC staffs concerns related to our review of your response to Generic Letter 96-06, Assurance of Equipment Operability and Containment Integrity During Design Basis Accident Conditions. The NRC staff requests the following information in order to continue with its review:
- 1.
As stated in your submittal of March 23, 2003, in analyzing the nuclear service water system for the waterhammer event, you found that two mechanical snubbers exceeded the allowable loads. You then removed the snubber supports from the piping analysis model and a subsequent analysis determined that the remaining supports did not exceed the allowable stresses. The NRC staff has identified some issues regarding your approach in this analysis. The model for the piping system eliminates some supports that are part of the actual piping configuration. The NRC staff does not consider this approach to be conservative. If the overloaded supports are actually loaded to complete failure (i.e., breaking), there would be a dynamic load transfer on to the remaining supports and piping that is not adequately modeled. Particularly, where there are one-way supports, the sudden application of loads could result in gaps that are not predicted utilizing your proposed method. Provide a discussion regarding the configuration of the overloaded supports and the nature of the possible failure modes.
Also, provide the margin present in the adjacent supports and in the piping. Provide sufficient details that demonstrate the fact that the structure will not be overloaded.
- 2.
In your submittal of March 23, 2003, you provided the results of an initial engineering assessment and stated that final documentation of these evaluations has not been completed. Provide the schedule for the completion of these evaluations. Further, for the initial assessment, you referenced the Energy Power Research Institute (EPRI) document NP-6041, Revision 1, criteria for the acceptance criteria for stresses in certain piping and support components. However, it should be noted that NP-6041 was developed to assess seismic margins and is not a substitute for the licensing-basis acceptance criteria documented in your plants Final Safety Analysis Report. Verify that the final evaluation will be based on the plant licensing-basis criteria, not the criteria provided in EPRI document NP-6041, Revision 1.
This request was discussed with J. Stringfellow of your staff on October 6, 2003, and it was agreed that a response would be provided within 30 days of receipt of this letter.
If you have any questions, please contact me at 301-415-1447.
Sincerely,
/RA/
Frank Rinaldi, Project Manager, Section 1 Project Directorate II-1 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50- 424 and 50-425
Enclosure:
As stated cc w/encl: See next page
This request was discussed with J. Stringfellow of your staff on October 6, 2003, and it was agreed that a response would be provided within 30 days of receipt of this letter.
If you have any questions, please contact me at 301-415-1447.
Sincerely,
/RA/
Frank Rinaldi, Project Manager, Section 1 Project Directorate II-1 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50- 424 and 50-425
Enclosure:
As stated cc w/encl: See next page DISTRIBUTION:
PUBLIC FRinaldi OGC WBeckner KManoly PDII-1 R/F CHawes ACRS GHammer JHannon JNakoski JTatum BBonser, RII ACCESSION NO. ML032870105 OFFICE PDII-1/PM PDII-1/LA PDII-1/SC NAME FRinaldi CHawes CGratton for JNakoski DATE 10/6/03 10/6/03 10/14/03 OFFICIAL RECORD COPY
Vogtle Electric Generating Plant cc:
Mr. N.J. Stringfellow Manager, Licensing Southern Nuclear Operating Company, Inc.
P. O. Box 1295 Birmingham, Alabama 35201-1295 Mr.G. R. Frederick General Manager, Vogtle Electric Generating Plant Southern Nuclear Operating Company, Inc.
P. O. Box 1600 Waynesboro, Georgia 30830 Mr. J. D. Woodard Executive Vice President Southern Nuclear Operating Company, Inc.
P. O. Box 1295 Birmingham, Alabama 35201-1295 Steven M. Jackson Senior Engineer - Power Supply Municipal Electric Authority of Georgia 1470 Riveredge Parkway, NW.
Atlanta, Georgia 30328-4684 Mr. Reece McAlister Executive Secretary Georgia Public Service Commission 244 Washington St., S. W.
Atlanta, Ga. 30334 Harold Reheis, Director Department of Natural Resources 205 Butler Street, SE. Suite 1252 Atlanta, Georgia 30334 Attorney General Law Department 132 Judicial Building Atlanta, Georgia 30334 Mr. J. D. Sharpe Resident Manager Oglethorpe Power Corporation Alvin W. Vogtle Nuclear Plant P. O. Box 1600 Waynesboro, Georgia 30830 Charles A. Patrizia, Esquire Paul, Hastings, Janofsky & Walker 10th Floor 1299 Pennsylvania Avenue Washington, DC 20004-9500 Arthur H. Domby, Esquire Troutman Sanders NationsBank Plaza 600 Peachtree Street, NE.
Suite 5200 Atlanta, Georgia 30308-2216 Resident Inspector Vogtle Plant 8805 River Road Waynesboro, Georgia 30830 Office of the County Commissioner Burke County Commission Waynesboro, Georgia 30830