ML17331B214

Provides Update of Temp Monitoring Effort Undertaken in Response to NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Reactor Coolant Sys

ML17331B214
Person / Time
Site:	Cook
Issue date:	02/01/1994
From:	Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AEP:NRC:1069E, IEB-88-008, IEB-88-8, NUDOCS 9402100270
Download: ML17331B214 (6)

Text

ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM e

t~~

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9402100270 DOC.DATE: 94/02/01 NOTARIZED: NO DOCKET FACIL:50-315 Donald C.

Cook Nuclear Power Plant, Unit 1, Indiana M

05000315 50-316 Donald C.

Cook Nuclear Power Plant, Unit 2, Indiana M

05000316 AUTH.NAME AUTHOR AFFILIATION FITZPATRICK,E.

Indiana Michigan Power Co.

(formerly Indiana 6 Michigan Ele RECZP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Provides update of temp monitoring effort undertaken in response to NRC Bulletin 88-008, "Thermal Stresses in Piping Connected to Reactor Coolant Sys."

DISTRIBUTION CODE:

IE16D COPIES RECEIVED:LTR ENCL SIZE'-

TITLE: Bulletin Response 88-08 Thermal Stress in Piping to RCS.

NOTES R

D RECIPIENT ID CODE/NAME PD3-1 PD INTERNAL: AEOD/DOA NRR/DE/EMEB RRgJPSSA REG FILETS 02 RGN~FILE 01 EXTERNAL: NRC PDR COPIES LTTR ENCL 1

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1 RECIPIENT ID CODE/NAME HICKMAN,J.

NRR/DE/EMCB NRR/DORS/OGCB NRR/PDII-1 RES/DSIR/EIB NSIC COPIES LTTR ENCL 1

1 1

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NOTE TO ALL"RIDS" RECIPIENTS:

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PLEASE HELP US TO REDUCE IVASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAIVE FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'7 NEED!

TOTAL NUMBER OF COPIES REQUIRED:

LTTR 13 ENCL 13

Indiana Michigan Power Company P.O. Box 16631 Columbus, OH 43216

~,

INOlANA MICHf6AN POWER AEP NRC:1069E Donald C.

Cook Nuclear Plant Units 1 and 2

Docket Nos.

50-315 and 50-316 License Nos.

DPR-58 and DPR-74 NRC BULLETIN NO. 88-08, "THERMAL STRESSES IN PIPING CONNECTED TO REACTOR COOLANT SYSTEMS"'.

S. Nuclear Regulatory Commission Document Control Desk Washington, D.

C.

20555 Attn: T.

E. Murley February 1,

1994

Reference:

Letter, AEP:NRC:1069A, E.

E. Fitzpatrick (AEP) to Dr. T ~ E. Murley (NRC),

NRC Bulletin 88-08, "Thermal Stresses in Piping Connected to Reactor Coolant Systems,"

dated October 29, 1992 This letter provides an update of the temperature monitoring effort undertaken in response to your staff's concern about thermal stratification in the auxiliary spray line.

In our October 29,

1992, submittal, Indiana Michigan Power Company committed to instrument the Unit 1 auxiliary spray line, and obtain data for one fuel cycle to determine if the line was susceptible to fatigue cracking due to leakage past the auxiliary spray line isolation valves.

We retained the option to take data for a second cycle if the first cycle's data were determined to be inconclusive.

Subsequent to issuing the reference letter, the Unit 1 auxiliary spray line was instrumented and data collected during the latest Unit 1 fuel cycle, which is scheduled to end in February 1994.

The data obtained have been evaluated by Westinghouse, and a

preliminary assessment has been completed.

The data,.which were

taken, include upper and lower

. pipe temperatures at six locations (see Figure attached),

main spray flows, pressurizer steam and liquid space temperatures, charging temperature, reactor coolant system temperatures, and primary loop flows.

A P;AA E).f.

9402100270

'P4020i PDR ADOCK 05000315 Q

PDR

Dr. T. E. Murley AEP:NRC:1069E The analysis of the data has led to the conclusion 'that there is leakage past the normally closed auxiliary valve, and thermal stratification does occur in the piping.

Preliminary stress and fatigue analysis results indicate that the structural integrity of the auxiliary spray line would not be challenged due to leaks in the auxiliary spray isolation valve.

Since the concern no longer exists regarding the adequacy of the data collected to

,date, it is our intention to terminate data collection at the end of the current cycle.

After we have evaluated the final Westinghouse report, which we expect to receive by July 1994, we will inform you of any action to be taken.

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

such, an oath statement is attached.

Sincerely, gg+p<V)

E.

E. Fitz atrick Vice President RGV/cad Attachments 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 LIN)

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.

Snbsoribed end sworn to before me this ~o day of @Ox'I NOTARY PUBLIC AIL'; D. HlLL NOTA"aY I'UOI.IG. STATF. OF CHIC

ATTACHMENT TO AEP:NRC: 1069E AEP AUXILIARYSPRAY LINE FIGURE

Attachment to AEP:N 069E Page 1

1L312P 54125PCH 1N) 2'PCH1N)

O'PCH 120) 2'2SI hQlHSPRAY 1P AEP AUXILIARYSPRAY LINE FIGURE