0CAN118915, Forwards Rev 1 to Svc Water Sys Piping Insp/Repair Procedure 1309.014, Svc Water Piping Thickness Evaluation, Per 890906,7 & 8 Telcons Re Pinhole Leak in Piping

From kanterella
(Redirected from ML19332D235)
Jump to navigation Jump to search
Forwards Rev 1 to Svc Water Sys Piping Insp/Repair Procedure 1309.014, Svc Water Piping Thickness Evaluation, Per 890906,7 & 8 Telcons Re Pinhole Leak in Piping
ML19332D235
Person / Time
Site: Arkansas Nuclear  Entergy icon.png
Issue date: 11/22/1989
From: James Fisicaro
ARKANSAS POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19332D236 List:
References
0CAN118915, CAN118915, NUDOCS 8911300192
Download: ML19332D235 (2)


Text

.a

.e Arkansa, Power & Ught Company

/

d2 St PM L ftte Rack. AR 72203 h! SDI 377 43Q l

t November 22, 1989 9CAN118915 l

U. S. Nuclear Regulatory Commission Document Control Desk Mail Station PI-137 1

Washington, DC 20555

~

Subject:

Arkansas Nuclear One - Units 1 & 2 l

Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6 Transmittal of Service Water System Piping Inspection / Repair Program Procedure Gentlemen:

AP&L described the identification, inspection and temporary repair of a l

pinhole leak in the ANO-1 Service Water (SW) System piping during conference r

calls between various members of AP&L and NRC/NRR and NRC/RIV staffs on September 6, 7, and 8, 1989. A temporary, non-ASME Code repair was used until the piping can be repaired or replaced in accordance with the ASME Code during the IR9 refueling outage, presently scheduled to begin October 1990.

- AP&L's internal program for inspection of pipe wall thickness, temporary repair methods and-associated acceptance criteria for the SW System piping at ANO were also discussed.

During those calls, and subsequent calls with the ANO-1 NRR Project Manager,.

AP&L conunitted to transmit a copy of the subject procedure for NRC's information in. preparation of an evaluation which would allow AP&L, unaer E

certain circumstances, to temporarily deviate from the ASME Code pending o

permanent Code repair at the next scheduled refueling outage.

Prior to

. receipt of formal NRC approval of our approach, AP&L will inform the staff I

of any non-Code conditions found and addressed by this procedure. Attached is a copy of the this procedure; the information in it should be sufficient to address the questions raised by your staff during the conference calls i

mentioned above.

1 Please feel free to contact me should you have any additional questions.

Very truly yours,

$0f James [U. Fisicaro M %

l I i Manager, Licensing p

s91:300192 891122 ADOCK0500gj3 PDR Q.

1, r

-U. S. NRC Page 2 November 22,:1989 l.

[L JJF/RBT _

i Attachment cc:

Mr. Robert Martin L

U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington,.TX 76011 NRC Senior Resident Inspector Arkansas Nuclear One - ANO-1 & 2 i

Number 1, Nuclear Plant Road Russellville, AR 72801 Mr. C. Craig Harbuck A

NRR Project Manager, Region IV/ANO-1 U. S. Nuclear Regulatory Comission NRR Mail Stop 13-D-18 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852 Mr. Chester Poslusny NRR Project Manager, Region IV/ANO-2 U. S. Nuclear Regulatory Comission NRR Mail Stop 13-D-18 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852

?

I