ML17256A695

Summary of 830512 Site Meeting W/Util Re Steam Generator Sleeving Program.Sleeving Mods Adequate Pending Formal Submittal of Mod Procedures,Review of Insp Results & Stress Analysis.Next Meeting Scheduled for 830520

ML17256A695
Person / Time
Site:	Ginna
Issue date:	05/24/1983
From:	Dick G Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
LSO5-83-05-053, LSO5-83-5-53, NUDOCS 8305260237
Download: ML17256A695 (12)

Text

May 24, 1983 Docket No. 50-244 LS05-83-05-053

. LICENSEE:

ROCHESTER GAS AND ELECTRIC CORPORATION FACILITY:

R. E. Ginna

SUMMARY

OF MAY 12, 1983 MEETING WITH ROCHESTER GAS AND ELECTRIC CORPORATION (RGLE)

ON STEAM GENERATOR SLEEVING PROGRAM On May 12, 1983, members of the NRC staff met with representatives of Rochester Gas and Electric Corporation (RGIlE) to discuss the history and status of the steam~ generator tube sleeving at Ginna.

The licensee informed the staff of modifications made to the basic steam generator tube sleeving procedure that was approved on April 1, 1983.

The ma)or modifications include the use of sleeves which are entirely within the tube sheet and the pre-tensioning of'ubes prior to brazing.

The discussions were general and covered tube inspections and criteria for acceptance, sleeving procedures, and sleeving in-spection techniques.

A meeting to discuss the details of the sleeving inspection results is scheduled for tIay 20, 1983.

The attendance list (Enclosure

1) and a copy of the slides used by RGSE (Enclosure

2) are enclosed.

The meeting began with a review of the Ieddy current inspection technique and the results ot the eddy current$ ng sections of the "g"

+$01 steam generator.

Historically, damaged tubes were removed from service through plugging-.

However improvements, such as sleeving techniques have permitted the licensee to keep more tubes in service.

Before the current outage which began March, 1983, 21 sleeves were installed in the "B" steam generator.,

g,hC Eddy current inspections during this current outage identified 78 tubes in the "B" steam generator and 4 in the "A" generator with vary-ing degrees of defects.

Of the 78 defects found in the "B" steam generator, 23 were above 405 which would have required either plugging or sleeving, The Safety Evaluation issued by the staff on April 1, 1983 covered the use of 36 inch sleeves which were explosively welded at the bottom: to the tubes within the tubesheet and brazed at the top to the tubes as they extended above the tubesheet.

Some of the damaged tubes were near the periphery of the bundle.

Space limitations would not permit the 8305260237 830524 PDR *DDCK 05000244 P

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DATE Ih NRC FOAM 318 (10-80j NRROM 0240

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May 24, 1983 use of the standard sleeve.

Consequently, a 22 inch sleeve which was explosively welded at both top and bottom was subsequently used on 29 of the tubes.

The sleeve installation and eddy current inspection procedures were reviewed with the staff.

During installation of the standard

sleeves, the licensee'oted that the ultrasonic inspections indicated inadequate braze joints.

An investigation concluded that movement of the %t'ubes was restricted at the lowest tube support plate.

The tube "~lockup" situation restricted thermal growth during brazing.

instead of axial movement the tube would bulge (about 30 mil increase in diameter) at the braze joint.

The licensee modified the procedure by heating the tube belovi the upper joint prior to brazing thus increasing the diameter at that point.

When the upper joint was brazed, no additional stresses were introduced and acceptable seals were obtained.

The licensee is performing an analysis of the additional stresses introduce'd to determine if they were significant.

The staff considered the sleeving modifications to be adequate pending formal submittal of the modified procedures and review of the inspection results and stres's analysis.

Enclosures:

As sta.ted Original signed by/

George F. Dick, Jr., Project Manager Operating Reactors Branch 85 Division of Licensing DISTRIBUTION

.'ocket, NRC PDR Local PDR ORB Reading NSIC DCrutchfield HSmith GDick OELD ELJordan JMTaylor ACRS (10)

SEPB HFConrad BDLiaw CYCheng LFrank JRa jan SVarga DVassallo RClark JStolz OFFICE/

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83 NRC FORM 318 (10-80) NRCM 0240 OFFlCIAL R ECOR D COPY USQPO: 1991 335.969

CC Harry H. Voigt, Esqttire

LeBoeuf, Lamb, Leiby and HacRae 1333 Hew Hampshire

Avenue, N.

W.

Suite 1100 Washington, D. C.

20036 Mr. hlichael Slade 12 Trailwood Circle Rochester, New York 14618 Ezra Bialik Assistant Attorney General Environmental Protection Bureau Hew-York State Department of Law 2 World Trade Center New York, Hew York 10047 Resident Inspector R.

E. Ginna Plant c/o U. S.

NRC 1503 Lake Road

Ontario, Hew York 14519

Director, Bureau of Huclear Operations State of New York Energy Office Agency Building 2

Etrpire State Plaza

Albany, Hew York 12223 Dr.

Emmeth A. Luebke Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Dr. Richard F. Cole Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C.

20555 U. S. Environmental Protection Agency Region II Office ATTN:

Regi onal Radi ati on Representati ve 26 Federal Plaza New York, New York 10007 Herbert Grossman, Esq.,

Chairman Atomic Safety and Licensing Board U.

S. Nuclear Regulatory Comnission Washington, D. C.

20555 Supervisor of the Town of Ontari o 107 Ridge Road West

Ontario, Hew York 14519 Jay Dunkleberger Hew York State Energy Office Agency Building 2, Empire State Plaza

Albany, Hew York 12223 Stanley B. Klimberg, Esquire General Counsel New York State Energy Office Agency Building 2 Empire State Plaza

Albany, Hew York 12223 Hr. John E. t3aier Vice President Electric and Steam Production Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649 Dr. Thomas E. Nurley, Regional Administrator Nuclear Regulatory Comnission, Region I 631 Park Avenue King of Prussia, Pennsylvania 19406

ENCLOSURE 1

ATTENDANCE LIST MAY 12 1983 MEETING Name George Dick H.

F. Conrad Robert Mecredy J.

C. 8utton Albert E. Curtis III B.

D. Liaw C,

Y. Cheng.

Louis Frank Jai Rajan Affiliation NRC NRC RG8E RGRE RGEE NRC/MTEB NRC/MTEB NRC/MTEB NRC/MEB

ENCLOSURE 2

Ginna Station Steam Generator Sleeving NRC Meeting Agenda 2

A.

Introduction Bob Mecredy.

B.

Edd Current Results Al Curtis o

Spring 1983 o

summary C.

Ginna Sleevina Back round Al Curtis o

Fall 1980 o

Spring 1981 o

Spring 1983 D.

Tubesheet Sleeves Al Curtis o

sleeve design o

inspectability E.

Brazed Sleeves Jim Hutton 0

0 0

0 process overview tube lockup braze procedure changes ultrasonic examination F.

Anal sis/Test Program Jim Hutton o

analyses o

tests G.

Conclusion Bob Mecredy

Ginna Station Steam Generator Sleeving NRC Meeting B Steam Generator Eddy Current Data Review not sizeable 0-25%

26-50%

51-75%

76-100%

TOTAL March 1979 December 1979 April 1980*

November 1980 April 1981

~February 1982 October '1982'-

Aoril 1983 0

18 0

28 38 87 0

13 0

20 38 40 16 15 38 31 13 59('31**)

78 211 Crevice lush ing implemented Number of tubes repaired (plugged )

Ginna Station Steam Generator Sleeving NRC Yieeting B-Steam Generator EDDY CURRENT DATA REVXEW A.

Tubes above plugging criteria 40%

23 tubes 16 ~igeie,'

~ej/C B.

Tubes below plugging criteria

(

40%

55 tubes 35 new 20 old C.

Out of 78 tubes 5l were new defects 27 were there in the f all

of the 27, 24 had chanoed since the fall.

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RGSE GLcam Generator 5f~iay Ei ~

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~Cat.eaor U/T Exam Tested Ance ted Pressure Test Tested Ance ted Fall 1980 Spring 1981 Spr'g '83 16 15 2

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0 o tubesheet o 36" o 36" PTD o 28" PTD 22.

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N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A

Ginna Station Steam Generator Sleeving

>~AC Nee t ing Anal sis/Testin A.

T~estin o

locked tube braze o

tube material tensile o

bulged tube tensile o

cold lockup o

bulged brazed cIualification B.

A~nal sis o

main steam line break o

operating transient loads o

tube code stress calculations o

sleeve code stress calculations