ML20084E297

AO 50-244/74-02:on 740101,eddy Current Test Results Indicated Wastage Problem Localized in Steam Generator a Hot Leg in Ctr Area of Tube Sheet.After Results of Tests Analyzed,Tube Plugging Will Be Initiated

ML20084E297
Person / Time
Site:	Ginna
Issue date:	02/07/1974
From:	Platt C ROCHESTER GAS & ELECTRIC CORP.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20084E289	List: ML20084E285 ML20084E291 ML20084E293 ML20084E297
References
AO-50-244-74-02, AO-50-244-74-2, NUDOCS 8304150012
Download: ML20084E297 (1)

Text

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CDCHESTER GAS t.ND ELECTRIC CORPORATION e 69 EAST AVENLIE, ROCHESTER. N.Y.14649

. . E Y..To.2 co February 7,1974 Mr. James P. O'Reilly, Director (Telecopied 2-7-74 1515 hours0.0175 days <br />0.421 hours <br />0.0025 weeks <br />5.764575e-4 months <br /> Directorate of Regulatory Operations Region I U.S. Atomic Energy Commission 631 Park Avenue ~

King of Prussia, Pennsylvania 19406

Subject:

Abnormal occurrence 74-2: Abnormal degradation of one of the several boundaries designed to contain the radioactive materials resulting from the fission process R. E. Ginna Nuclear Power Plant, Unit No.1 Docket No. 50-244

Dear Mr. O'Reilly:

In accordance with the Technical Specification 6.6.2A, Abnormal Occurrence Reports, which requires notification by telephone and telegraph, the following report is

. submitted.

During our present outage to repair turbine damage resulting from a broken turbine blade, it was decided to go into a refueling outage. As previously reported to the AEC, a refueling outage called for eddy current testing the tubes of both steam generators .

To date, one-half of the tubes have been eddy current tested in the "A" Steam Generator hot leg, and one-third of the tubes tested in the "B" Steam Generator hot leg. In addition.16% of the tubes in both the "A" and "B" Steam Generator.

cold legs have been tested. Results to date indicate the wastage problem to be localized and more severe in the "A" Steam Generator hot leg, approximately in the center area of the tube sheet opposite the primary coolant water hot leg inlet nozzle and between 11/2 to 3 inches above the tube sheet.

All of the remaining untested tubes in the "A" steam generator hot leg will be given the eddy current test and the other tubes examined on a statistical basis. After the results of all tests have been analyzed, a program of tube plugging will be initiated.

To date, there has been no indication of any primary to secondary leakage in either Steam Generator.

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N Very truly yours,

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C. E. Platt, Superintendent Ginna Station y ., . . . l- .i xc: Mr. J. F. O' Leary Nk; d }# f

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i ROCIICSTER GAS AND ELECTRIC CORPORATIDH e 69 GAST AVCHUE, RCCHESTLR, N.Y.

...u,llY7Eo.27oo l Pobruary 7,1974 l

Mr. James P. O'Reilly, Director

Directorate of Regulatory Operations

! Region !

U.S. Atomic Energy Commission 631 Park Avenue V.ing of Prussia, Pennsylvania 19406 l

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Subject:

Abnormal occurrence 74-2: Abnormal degradation of one of the soveral 4 boundarica designed to contain the radioactive materials resulting

! from the fission i ocons i R. E. Ginna Nuclear Powcr Plant, Unit No.1 i -

Dockot No. 50-244 ,

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Dear Mr. O'Ro!!!y:

In accordanco with the Technical Specification 6.6.2A, Abnormal Occurrence Reports, l which requires notification by telephone and toicoraph, the following report is submitted. ,

During our prosent outage to repair turbino damage resulting from a broken turbine i

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blade, it was docided to go into a refueling outago. As previously reported to the AEC, a refueling, outage called for cddy current testing tho tubes of both steam generators.

3 To date, one-half of the tubos have been eddy curront tested in the "A" Steam l < Generator hot leg, and one-third of the tubos tested in the "B" Steam Generator hot leg. In addition.16%.of the tubos in both the "A" and "B" Steam Generator

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i cold lege have boon tested. Results to date indicate tho wastage problem to bo 4

localized and more severo in the "A" Steam Generator hot Icg, approximately in the conter area of the tube chcot opposito the primary coolant water hot leg inlet j nozzle and betwocn 11/2 to 3 inches above the tube shoct.

l All of the remaining untotted tubes in the "A" steam generator hot leg will be given the oddy current test and the other tubes examined on a statistical basis. After the

! . results of all tests.have been analy::cd, a program of tube plugging will be initiated.

To date, there has been no indication of any primary to secondary leakage in either i Steam Generator. .

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g Very truly yours, .

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.. C. E. Platt, Sup'erintendent j Ginna Station g/

q4 xc: Mr. J. I'. O' Leary '

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MEMO ROUTE SLIP _

su mno ui vo.. Forconcunenu.- r r anson.

Form A F C-94 i Rev. Af av I 4.1941) Ali.51 0240 Note med return For signature. X For leforrea tion.

TO (Name and unit) IM TI ALS REMARK $

RO Chief, FS&EB ROCHESTER GAS AND ELECTRIC R0: LIQ (4)

RO Licensin (4) cat GINNA R0 Files DR Central Files A0 74-2 TO (Nemo and uneti (N4TIALS REMARa$

OGC The above A0 is forwarded for inforraation.

om Distribution will be made by this office to the PDR, Local PDR, NSIC, DTIE, and State 1O (Name and umt) IN TLALS REMARKS Representatives after review by the licensee e

em for proprietary information.

FROM (Name and i.e t) REM APR$

(fl. Ons',~

L(.*J. Brunner Region I f

PHONE N(A DATE 8-337-1246 2/8/74' U$f OTHER $1CE FOR ADDeisONAL REMARKS Cro : 19it 0 - 4n-40

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