ML17329A639

Responds to Jf Stang 920810 Request for Final Implementation Schedule for All Mods Required for NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs. NDT Concluded That No Cracks Exist in Spray Line

ML17329A639
Person / Time
Site:	Cook
Issue date:	10/19/1992
From:	Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AEP:NRC:1069F, IEB-88-008, IEB-88-8, NUDOCS 9210260202
Download: ML17329A639 (5)

Text

R I

SUBJECT:

Responds to JF Stang 920810 request for final implementation schedule for all mods required for NRC Bulletin 88-008, "Thermal Stresses in Piping Connected to RCS."

NDT concluded that no cracks exist in spray line.

DISTRIBUTION CODE:

IE16D COPIES RECEIVED:LTR ENCL 0 SIZE-TITLE: Bulletin Response 88-08 Thermal Stres in Piping to RCS.

NOTES:

ACCELERA'l'KUU "l'KMU'l'lUA UKLVIDIN'i'l'H.Al'l&W5 Y 5'l'KLVI REGULAY Y INFORMATION DISTRIBUTIO YSTEM (RIDE)

ACCESSION NBR:9210260202 DOC.DATE: 92/10/19 NOTARIZED: YES 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

& Michigan Ele RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

RECIPIENT ID CODE/NAME PD3-1 LA STANGFJ INTERNAL: AEOD/DOA NRR HUM,M NRR/DET/EMEB 7E NRR/DOEA/OGCB11 N

E2 EG FILE 02 N8~ ILE 01 EXTERNAL: NRC PDR COPIES LTTR ENCL RECIPIENT ID CODE/NAME PD3-1 PD NRR HARTZMANFM NRR MOZAFARIFB NRR/DOEA/OEABll NRR/DREP/PEPB9D NRR/PMAS/ILRB12 RES/DSIR/EIB NSIC COPIES LTTR ENCL R

I NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK.

ROOM PI-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED:

LTTR 18 ENCL ~V

Indiana hlichigan Power Company P.O. Box 16631 Columbus, OH 43216 lMOlAMA NICHIGAN PQWER AEP:NRC:1069F Donald CD 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" U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.

C.

20555 Attn:

T.

E. Murley October 19, 1992

Reference:

Letter, J.

F.

Stang (NRC) to E.

E. Fitzpatrick (AEP),

"NRC Bulletin 88-08, "Thermal Stresses in Piping Connected to Reactor Coolant Systems" (TAC NOS M69618 and M69619),

dated August 10, 1992.

2.

Letter AEP:NRC:1069A, "NRC Bulletin 88-8:

Action Item Status,"

dated August 8, 1989.

This letter responds to an August 10, 1992 letter from J.

F. Stang to E.

E. Fitzpatrick (Reference

1) which requested that Indiana Michigan Power Company provide a final implementation schedule for all modifications required for Bulletin 88-08.

As noted in previous correspondence (Reference 2), lines in three systems that meet the Bulletin's criteria were identified.

These are a

3" alternate charging line to the loop 1 cold leg, a 2" auxiliary pressurizer spray line, and four 1 1/2" high pressure emergency core cooling system injection lines (one line to each cold leg).

The 3"

alternate charging line to the loop 1 cold leg and the four 1 1/2" high-pressure emergency core cooling system injection lines (one to each cold leg), have been modified (Reference 2).

Non-destructive testing has shown that there are no cracks in the remaining line (the pressurizer auxiliary spray line).

We have contracted with Westinghouse Electric Corporation to install temperature monitoring equipment on this line in Unit 1

and to evaluate the data.

The monitoring equipment was installed on the Unit 1 auxiliary spray line during the 1992 refueling outage under minor modification 01-MM-336.

Data willbe obtained during the next

'P2i0260202 921019 PDR ADQCK 05000315 8

PDR

Dr. T.

E. Murley 2

AEP:NRC:1069F fuel cycle and taken for a further cycle if one cycle of data is not sufficient.

It is planned that the data will be recorded as follows:

a.

Modes 3, 4 and 5

- Two-minute intervals b.

Mode 2

- Two-minute.intervals until 100% power (Mode 1) is reached Mode 1

Two-minute intervals initially.

Data collection intervals may be adjusted after data are evaluated.

The data will be sent to Westinghouse for evaluation on a monthly basis.

The NRC will be informed of any required actions resulting from the data evaluation.

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

and, as such, an oath statement is enclosed.

Sincerely, ZE<

-p.aP E.

E. Fitzpatrick Vice President tjw CC:

D. H. Williams, Jr.

A. A. Blind - Bridgman J.

R. Padgett G. Charnoff NFEM Section Chief A. B. Davis

- Region III NRC Resident Inspector

- Bridgman

Dr. T.

E. Murley 3

AEP:NRC:1069F bc:

S. J.

Brewer D. H. Malin/M. S. Ackerman M. L. Horvath

- Bridgman J.

B. Shinnock W.

G. Smith, Jr.

J.

F. Stang, NRC - Washington, D.

C.

AEP:NRC:1069F DC-N-6015.1

(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 to 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 sworri to before me this ~~ ~~

day of NO Y PUBLIC