ML17251A981
| ML17251A981 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 03/07/1988 |
| From: | Snow B ROCHESTER GAS & ELECTRIC CORP. |
| To: | Stahle C NRC, NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML17251A982 | List: |
| References | |
| IEB-88-002, IEB-88-2, NUDOCS 8803180001 | |
| Download: ML17251A981 (3) | |
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ACCELERkTEO DISIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
- EKCCESSION NBR
- 8803180001 DOC.DATE: 88/03/07 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AUTH.NAME AUTHOR AFFILIATION SNOW,B.A.
Rochester Gas 6 Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION STAHLE,C.
NRC No Detailed AffiliationGiven
SUBJECT:
Forwards "Summary Exam Rept for 1988 Steam Generator Eddy Current Insp."
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TITLE: OR Submittal: Inservice Inspection/TestXBg/Relief from ASME Code NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
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IIIII'IIII tlIlla',llllll'SASE ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649-0001 March 7, 1988 YES.EPHONE AREA CODE 7S8 546.2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Mr. Carl Stahle PWR Project Directorate No.
1 Washington, D.C.
-20555
Subject:
1988 Steam Generator Tube Inservice Inspection Special Report R.E.
Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Stahle:
In accordance
,with Section 6.9.2.4 of the Ginna Station Technical Specifications and Appendix B Paragraphs 5.7.1 and 5.7.2 of the Ginna Station Quality Assurance
- Manual, we are submitting the 1988 Steam Generator Eddy Current Examination Summary Report for R.E.
Ginna Nuclear Power Plant.
This report summarizes observations and corrective action resulting from inspections performed during the 1988 outage and identifies the tubes inspected, the location and extent of each indication and the tubes which have been plugged or sleeved.
Note that the report identifies inspections performed in response to North Anna type tube ruptures.
The corrective actions taken to minimize the consequences of this potential event will be addressed in our response to NRC Bulletin 88-02.
Sincerely, Bruce A. Snow Superintendent Nuclear Production xc:
U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Resident Inspector Ginna Station 8303180001 880307 PDR ADOCK 05000244 9
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