ML17254A744
| ML17254A744 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 01/29/1986 |
| From: | Kober R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Lear G Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8602050111 | |
| Download: ML17254A744 (4) | |
Text
REGUL*TO INFORMATION DISTRIBUTION TEM (RIDS)
ACCESSION NBR:8602050111 DOC. DATE: 86/01/2V NOTARIZED:
NQ DOCKET 0 FACIL: 50-244 Robert Emmet Ginna Nuclear Plant>
Unit 1> Rochester G
05000244
, AUTH. NAME AUTHOR AFFILlATIQN KOBER> R. W.
Rochester Gas Zc Electric Cov p.
RECIP. NAME REC IP IENT *FFILIATION LEAR> G. E.
PWR Pv object Directov ate 1
SUBJECT:
Confirms that inservice insp pv ogram will be v evised priov to 1987 refueling to v ef lect eav lg notification requirement when unusual numbev of steam genev ator tubes exhibit degradation as established bg eddy curv ent testing.
DISTRIBUTION CODE'O47D COPIEB RECEIVED; LTR I
ENCL 0 SIZE:
TITLE:
OR Submittal:
Inservice Inspection/Testing NOTES: NRR PWR-B ISAPD ice.
QL: 09/19/69 05000244 RECIPIENT ID CODE/NAME PWR-A PD1 PD 01 INTERNAL:
ACRS ih ELD/HDS4 NRR BWR EB NRR PWR-A EB N
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RECIPIENT ID CODE/NAME CLIFFORD> J ADM/LFMB NRR BWR *DTS NRR PWR-A ADTS NRR PWR-B ADTS NRR/TAMB RGN1 CQP IES LTTR ENCL EXTERNAL: 24X NRC PDR NOTES:
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i8 biz"'zz zzrzz ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649-0001 55AlK
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ROGER W. KOBER VICE PRESIOENT ELECTRIC &STEAM PROOUCTIOM January 29 I 1986 7 KI.LP H0 N K
- RKAcooK Tls 546-2700 Director of Nuclear Reactor Regulation Attention:
Mr. George E. Leari Chief PWR Project Directorate No.
1 U.S. Nuclear Regulatory Commission Washingtoni D.C.
20555
Subject:
Steam Generator Sleeving R. E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Lear:
Rochester Gas and Electric submitted information concerning steam generator tube sheet sleeving and welded sleeve installation by letters dated October 4, December 13 and December 23>
1985.
Discussion with the NRC Staff has indicated a desire on the part of the Nuclear Reactor Regulation (NRR) Staff to receive early notification whenever an unusual number of steam generator tubes exhibit degradation as established by eddy current testing.
Accordinglyi RGGE will orally notify NRR within 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />s> but no sooner than the next normal working day, whenever the final review of eddy current results indicates the occurrence of either (a) or (b) below.
(a)
More than 10% of the total tubes inspected are degraded (imperfections greater than 20% of the nominal wall thickness).
Howeveri previously degraded tubes must exhibit at least 10% further wall penetration to be included in this calculation.
(b)
More than 1% of the total tubes inspected are degraded (imperfections greater than the repair limit).
RG6E will revise the Ginna Inservice Inspection (ISI) Program to reflect this notification prior to the 1987 refueling outage.
Additional written notification within thirty days of the occurrence of (a) or (b) above is currently required by the ISI Program and will be retained.
V truly yoursi Roc/br W. Kober 8602050111 860129 I)
PDR ADDCK 05000244 I(I 8
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