ML17331B211

Discusses Info Re NRC Bulletin 88-002, Rapidly Propagating Fatigue Cracks in SG Tubes

ML17331B211
Person / Time
Site:	Cook
Issue date:	01/28/1994
From:	Fitzpatrick E INDIANA MICHIGAN POWER CO.
To:	Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AEP:NRC:1056E, IEB-88-002, IEB-88-2, NUDOCS 9402090011
Download: ML17331B211 (5)

Text

ACCELERATED DISTRIBUTION DEMONS C ION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9402090011 DOC.DATE: 94/01/28 NOTARIZED: YES DOCKET FACIL:50-315 Donald C.

Cook Nuclear Power Plant, Unit 1, Indiana M

05000315 AUTH.NAME AUTHOR AFFILIATION FITZPATRICK,E.

Indiana Michigan Power Co.

RECIP.NAME RECIPIENT AFFILIATION MURLEY,T.E.

Document Control Branch (Document Control Desk)

R

SUBJECT:

Discusses info re NRC Bulletin 88-002, "Rapidly Propagating Fatigue Cracks In SG Tubes.

D1STRIBUTION CODE:

IE13D COPIES RECEIVED:LTR I

ENCL J "SIZE:

TITLE: Bulletin Response, 88-02 Rapidly Propagating Fatigue Cracks zn NOTES:

Steam D

RECIPIENT ID CODE/NAME PD3-1 PD INTERNAL: AEOD/DSP/ROAB NRR/DSSA NRR/PD1-1 RES/DSIR/EIB EXTERNAL: NRC PDR COPIES LTTR ENCL 1

1 1

1 1

1 1

1 1

1 RECIPIENT ID CODE/NAME HICKMAN,J NRR/DRPW/OGCB NRR Ej5.

R G FILE 02 RGN3 FILE 01 NSIC COPIES LTTR ENCL 1

1 1

1 1

1 1

1 1

1' 1

A D

D D

NOTE TO ALL"RIDS" RECIPIENIS:

D D

PLEASE HELP US TO REDUCE WASTE! CONTACI'HE DOCUMENT CONTROL DESK, ROOM P !-37 (EXT. 20079) TO ELIMINATEYOUR NAMEFROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED:

LTTR 12 ENCL 12

Indiana Michigan Power Company P.O. Box 16631 Coiumbus, OH 43216 INDIANA NICHIGiAN POWER AEP:NRC:1056E Donald C.

Cook Nuclear Plant Unit 1 Docket No. 50-315 License No.

DPR-58 NRC BULLETIN NO. 88-02, "RAPIDLY PROPAGATING FATIGUE CRACKS IN STEAM GENERATOR TUBES" U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.

C.

20555 Attn: T.

E. Murley January 28,,

1994

Reference:

Letter, AEP:NRC:1056A, ED E. Fitzpatrick (AEP) to Dr. T. E. Murley (NRC),

NRC Bulletin 88-02, "Rapidly Propagating Fatigue Cracks in Steam Generator Tubes",

dated October 16, 1992 In our October 16,

1992, submittal, Indiana Michigan Power Company committed to implement a program for Unit 1 to minimize the probability of a rapidly propagating fatigue failure of a steam generator

tube, the program to be based on analysis performed by Westinghouse Electric Corporation.

Westinghouse Electric Corporation has performed the evaluation for tube vibration induced fatigue for Donald C.

Cook Nuclear Plant Unit 1

steam generator tubes.

The evaluation utilized operating conditions specific to Unit 1 to account for the plant specific nature of the tube loadings and response, including reviews of eddy current data to establish anti-vibration bar locations.

The potential for vibration induced fatigue of Unit 1

tubes was evaluated for current operating conditions, and projected conditions for 30% steam generator tube plugging.

The results of the Westinghouse evaluation identified a total of five tubes in three steam generators that may require preventive or corrective action under the above referenced operating conditions.

Projected tube fatigue usage factors indicate that all five tubes are acceptable for operation through the current fuel cycle, which is scheduled to end in February 1994.

The fatigue usage factor for tube RBC35 (Row 8, Column 35) in SGll (Unit 1 steam generator number 1), while still less than 1.0, is A

~ A A 94020900ii 940128 PDR ADOCK 05000315 Q

PDR QYi~~

I

4

Dr. T.

ED Murley AEP:NRC:1056E projected to eventually exceed 1.0 under current operating conditions during the remainder of Cook Nuclear Plant Unit 1 operating license.

As a preventive/corrective

measure, this tube will be removed from service during, the upcoming refueling outage.

N The four remaining

tubes, R8C60 and R9C35 in SG12, R8C35 and R9C60 in SG13, are projected to have an acceptable fatigue usage factor of less than 1.0 for the current operating conditions, but could exceed 1.0 if tube plugging levels reached 30%.

Current plugging levels for these steam generators are:

Steam Generator Number ll Steam Generator Number 12 Steam Generator Number 13 10.2%

7. Oa.

6.9s The four tubes will be evaluated for preventive or corrective measures if steam generator tube plugging levels approach 30% in the respective steam generator.

All tubes in steam generator number 4 were found to be acceptable.

The plugging level for the steam generator number 14 is 6.3S.

Details of the Mestinghouse evaluation are contained in WCAP-13814, dated December

1993, which will be on file at Cook Nuclear Plant site.

This letter is submitted pursuant to 10CFR50.54(f),

and, as such, an oath statement is attached.

Sincerely, E.

E. Fitzpatrick Vice President RGV/cad Attachment CC:

A. A. Blind G. Charnoff J.

B. Martin - Region III NFEM Section Chief NRC Resident Inspector

- Bridgman J.

R. Padgett

STATE OF OHIO)

COUNTY OF FRANKLIN)

E. E. Fitzpatrick, being duly sworn, deposes and says that he is the Vice President of licensee Indiana Michigan Power Company, that he has read the forgoing response concerning Bulletin 88-08, "Thermal Stresses in Piping Connected to Reactor Coolant Systems,"

and that said contents are true to the best of his knowledge and belief.

Subscribed and sworn to before me this ~r n

day of 19~.

I), i

)

NOTARY PUBLIC PilL" D. H!LL t>0'll s

~ 4

~ SC STnlE GF OHIQ