ML17254A688

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Discusses Steam Generator Tube Sleeving Program.Only Bobbin Coil Technique Exam Will Be Performed After Initial Sleeve Installation as Baseline Insp.Dual Cross Weld Technique Will Be Used as Supplemental Exam Technique
ML17254A688
Person / Time
Site: Ginna Constellation icon.png
Issue date: 12/23/1985
From: Kober R
ROCHESTER GAS & ELECTRIC CORP.
To: Lear G
Office of Nuclear Reactor Regulation
References
NUDOCS 8512310068
Download: ML17254A688 (5)


Text

REQVLATO~ INFORNATION DISTRIBUTION AUSTEN'RIDS)

I ACCESSION NBR: 85123100b8 DOC. DATE: 85/12/23 NOTARIZED:

NO DOCKET 0 FACIL:50-244 Robert Emmet Qinna Nuclear Planti Unit 1. Rochester 0

05000244 AUTH. NAlfE AUTHOR AFFILIATION KOBER> R. W.

Rochester Qas Sc Electric Corp.

REG IP. NAME RECIPIENT AFFILIATION LEARN Q. E.

PWR Prospect Directorate 1

SUBJECT:

Discusses steam generator tube'leeving program.Only bobbin coi) techni que exam ei) I. be per formed after initial sl eeve installation as baseline insp. Dual CRDSS tueld technique mill be used on supplemental exam technique.

DISTR IBUTION CODE'001D COPIES RECEIVED: LTR ENCL~ SIZE; TITLE:

OR Submittal:

Qeneral Distribution NOTES'RR PWR-B ISAPD icy.

OL: 09/19/69 05000244 RECIPIENT ID CODE/NANE PWR-A PD1 PD 01 INTERNAL: ACRS 09 ELD/HDS4 NRR PWR-A EB NRR/DHFT/TSCB N

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~IIBI7EII(llIPlelu 555TH ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.K 1464g-gpg1 ROGER W. KOBER VICE PRESIOENT ELECTRIC &STEAM PROOVCTION THLepHoNe ARHA cooe TIe 546 2700 December 23, 1985

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PIIR -.A/BC's TECH BVPPQHT Director of Nuclear Reactor Regulation Attention:

Mr. George E. f.ear, Chief PWR Project Directorate No.

1 U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Subject:

Steam Generator Tube Sleeving Program R. E. Ginna Nuclear Power Plant Docket No. 50-244 AD J. Knight (1tr only)

EB (BALLARD)

EICSB (ROSA)

PSB (GAMMILL)

RSB (BERLINGER)

FOB (BENAROYA)

Dear Mr. f.ear:

By letter dated December 13,

1985, Rochester Gas and Electric Corporation submitted a report prepared by Combustion Engineering (CE) for the application of the CE steam generator sleeve design and installation process to Ginna.

Application of the CE sleeves at Ginna was also discussed with NRC staff members at a meeting in Bethesda on December 16, 1985.

Two differences, which were discussed at the meeting, exist between a standard CE process described in the submitted report and the process intended to be used at Ginna during the 1986 outage.

Those differences are in the repair welding technique which may be used if an initial tube sleeve weld is not acceptable and in the baseline eddy current inspection technique to be used following installation of the sleeves.

If the ultrasonic examination results of the upper weld are unacceptable, a repair weld will be attempted by rewelding over the initial weld profile.

Then if the second post reweld ultra sonic examination results are unacceptable, a

new expansion will be performed and a

new weld installed approximately one inch below the first expansion.

Consistent with standard inspection practice, only a bobbin coil technique examination will be performed after initial sleeve installation as the baseline iospection.

This bobbin coil technique will also be the normal inservice inspection technique.

The dual cross wound technique will be used as a supplemental examination technique if a distorted signal is seen in an area where this technique can provide greater sensitivity for charact-erization.

yes 85l23100bB 85l228 PDR ADOCH, 05000244 I

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t ROCHESTER GAS AND ELECTRIC CORP.

December 23, 1985 To Mr. George E. Lear, Chief SHEET NO.

Our understanding is that the Staff intends to issue an SER for the use of CE sleeves at Ginna by the end of January, 1986.

RGS E will be available at your convenience to answer questions if they arise in the course of your review.

V r truly yours,

'phl./

Roger W. Kober