ML17265A400
| ML17265A400 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 08/11/1998 |
| From: | Vissing G NRC (Affiliation Not Assigned) |
| To: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| GL-97-05, GL-97-5, TAC-MA0466, TAC-MA466, NUDOCS 9808170157 | |
| Download: ML17265A400 (5) | |
Text
August 11, 1998 Dr. Robert C. Mecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649
SUBJECT:
REQUEST FOR ADDITIONALINFORMATIONRELATINGTO GENERIC LETTER 97-05 RESPONSE FOR THE R.
E. GINNA NUCLEAR POWER PLANT (TAC NO.
MA0466)
Dear Dr. Mecredy:
The NRC staff is currently reviewing your response to NRC Generic Letter (GL) 97-05, "Steam Generator Tube Inspection Techniques."
The staff has identified the need to request additional information in order to determine the acceptability of the inspection techniques utilized
~ at Ginna. The enclosure describes the specific information requested by the staff. Please provide your response within 30 days from receipt of this letter.
Sincerely, Original Signed by:
Guy S. Vissing, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosure:
As stated cc w/encl: See next page DISTRIBUTION:
Docket File PUBLIC PDI-1 R/F J. Zwolinski (A)
S. Bajwa S. Little OGC ACRS C. Hehl, Region I
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August ll, 1998 Dr. Robert C. Mecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649
SUBJECT:
REQUEST FOR ADDITIONALINFORMATIONRELATINGTO GENERIC LETTER 97-05 RESPONSE FOR THE R.
E. GINNA NUCLEAR POWER PLANT (TAC NO.
MA0466)
Dear Dr. Mecredy:
The NRC staff is currently reviewing your response to NRC Generic Letter (GL) 97-05, "Steam Generator Tube Inspection Techniques."
The staff has identified the need to request additional information in order to determine the acceptability of the inspection techniques utilized at Ginna. The enclosure describes the specific information requested by the staff. Please provide your response within 30 days from receipt of this letter.
Sincerely, Guy S. Vissing, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosure:
As stated ccw/encl:
See next page
Dr. Robert C. Mecredy Rochester Gas and Electric Company R.E. Ginna Nuclear Power Plant CC:
Peter D. Drysdale, 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. F. William Valentino, President New York State Energy, Research, and Development Authority Corporate Plaza West 286 Washington Avenue Extension Albany, NY 12203-6399 0
Charles Donaldson, Esquire Assistant Attorney General New York Department of Lalw 120 Broadway New York, NY 10271 Nicholas S. Reynolds Winston 8 Strawn 1400 S Street N.W.
Washington, DC 20005-3502 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 111 West Falls Road, Room 11 Rochester, NY 14620 Mr. Paul Eddy New York State Department of Public Service 3 Empire State Plaza, 10th Floor Albany, NY 12223
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REQUEST FOR ADDITIONALINFORMATION RELATEDTO THE LICENSEE'S RESPONSE TO NRC GENERIC LETTER 97-05 FOR GINNA NUCLEAR POWER PLANT DOCKET NO. 50-244 During the review of Rochester Gas 8 Electric Corporation's response to Generic Letter (GL) 97-05, "Steam Generator Tube Inspection Techniques," the staff noted one area that required additional clarification in order to assess the adequacy of inspection techniques employed at R.E.
Ginna Nuclear Power Plant.
In this regard, provide the following information to the NRC:
The response to GL 97-05 indicated that the licensee has qualified a technique to size the depth of small volume manufacturing burnish marks (MBM). It was noted that the response did not address performing a reexamination of preservice eddy current inspection data to confirm the presence of MBMindications identified during inservice inspections.
Discuss whether it is the practice at Ginna Station to review preservice inspection data to confirm the presence of MBM indications.
If this is not the practice employed by the licensee, discuss the qualification of eddy current inspection techniques used during inspections to adequately distinguish between MBMand other modes of volumetric tube degradation.
Enclosure