ML031210621
| ML031210621 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/01/2003 |
| From: | Clark R NRC/NRR/DLPM/LPD1 |
| To: | Mecredy R Rochester Gas & Electric Corp |
| Clark R, NRR/DLPM, 415-2297 | |
| References | |
| TAC MB1887 | |
| Download: ML031210621 (5) | |
Text
May 1, 2003 Dr. Robert C. Mecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION RE: R. E. GINNA NUCLEAR POWER PLANT 2002 STEAM GENERATOR INSERVICE INSPECTION REPORT (TAC NO. MB6467)
Dear Dr. Mecredy:
By letter dated July 9, 2002, as supplemented on October 17, 2002, Rochester Gas and Electric Corporation submitted the results of their 2002 steam generator inservice inspection at Ginna Nuclear Power Plant.
The Nuclear Regulatory Commission (NRC) staff has reviewed the information and based on our review, we have determined that additional information is required in order for the staff to complete its review. Enclosed is the NRC staffs request for additional information. These questions were discussed with your staff on April 29, 2003, and a mutually agreeable response date of May 30, 2003, was established.
If you have any questions, please contact me at 301-415-2297.
Sincerely,
/RA/
Robert Clark, Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosure:
As Stated cc w/encl: See next page
May 1, 2003 Dr. Robert C. Mecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION RE: R. E. GINNA NUCLEAR POWER PLANT 2002 STEAM GENERATOR INSERVICE INSPECTION REPORT (TAC NO. MB1887)
Dear Dr. Mecredy:
By letter dated July 9, 2002, as supplemented on October 17, 2002, Rochester Gas and Electric Corporation submitted the results of their 2002 steam generator inservice inspection at Ginna Nuclear Power Plant.
The Nuclear Regulatory Commission (NRC) staff has reviewed the information and based on our review, we have determined that additional information is required in order for the staff to complete its review. Enclosed is the NRC staffs request for additional information. These questions were discussed with your staff on April 29, 2003, and a mutually agreeable response date of May 30, 2003, was established.
If you have any questions, please contact me at 301-415-2297.
Sincerely,
/RA/
Robert Clark, Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosure:
As Stated cc w/encl: See next page DISTRIBUTION:
PUBLIC RLaufer OGC PDI-1 R/F RClark ACRS LLund JJimenez BPlatchek, RGI ACCESSION NO. ML031210621
- See previous concurrence OFFICE PDI-1/PM PDI-1/LA EMCB*
PDI-1/SC NAME RClark SLittle LLund RLaufer DATE 4/29/03 4/30/03 04/23/03 4/30/03 OFFICIAL RECORD COPY
R.E. Ginna Nuclear Power Plant cc:
Kenneth Kolaczyk, Sr. Resident Inspector R.E. Ginna Plant U.S. Nuclear Regulatory Commission 1503 Lake Road Ontario, NY 14519 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. William M. Flynn, President New York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399 Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Daniel F. Stenger Ballard Spahr Andrews & Ingersoll, LLP 601 13th Street, N.W., Suite 1000 South Washington, DC 20005 Ms. Thelma Wideman, Director Wayne County Emergency Management Office Wayne County Emergency Operations Center 7336 Route 31 Lyons, NY 14489 Ms. Mary Louise Meisenzahl Administrator, Monroe County Office of Emergency Preparedness 1190 Scottsville Road, Suite 200 Rochester, NY 14624 Mr. Paul Eddy New York State Department of Public Service 3 Empire State Plaza, 10th Floor Albany, NY 12223
Enclosure REQUEST FOR ADDITIONAL INFORMATION REGARDING 2002 STEAM GENERATOR TUBE INSPECTION REPORT R. E. GINNA NUCLEAR POWER PLANT DOCKET NO. 50-244 In order for the staff to complete its review, responses to the following questions are requested.
1.
In Section 8.2 of Attachment 1 to your October 17, 2002, submittal it was indicated that some thermally treated alloy 690 tubes were plugged for preventive reasons such as proximity to baffle plate edges. Please clarify the concern with respect to the baffle plate edges.
2.
Section 9.2.1 of Attachment 1 to your October 17, 2002, letter discusses a tube proximity issue. From the description provided, it appears that the outermost tube in a column and the tube below it may be in close proximity as a result of the fabrication procedure. However, in other sections (Section 2.4 and Section 9.2.3) the report appears to be discussing the potential for wear to occur as a result of the tube proximity issue in all tubes in a given column. Provide information that would clarify if the tube proximity issue is one that would be applicable to all tubes in a column or a subset of tubes in a column. Also, provide information clarifying whether the wear observed in McGuire 1 and St. Lucie 1 occurred only in the outermost columns, the tube in an adjacent column, or along the entire column and how this information applies to Ginna.
3.
In Section 10.6.5.a of Attachment 1 to your October 17, 2002, letter there was some discussion about hot-leg accessible indications. Please clarify what is meant by that statement, especially if it has any implications that some tubes cannot be inspected because they are not accessible.
4.
Concerning the scored tube hole discussed in Section 10.2.2 of Attachment 1 to your October 17, 2002, letter, please clarify whether any special examination requirements have been, or will be, implemented for this tube.
5.
On page 9 of Attachment 2 to your October 17, 2002, letter there was reference to rotating probe examinations of gripper locations. Please clarify what gripper locations are.