ML18009A353

Forwards Reactor Containment Bldg Integrated Leak Rate Test Conducted in Oct 1989.Util Believes That Packing Leaks Discovered Are Isolated Failures & That Repair Should Prevent Recurrence

ML18009A353
Person / Time
Site:	Harris
Issue date:	01/25/1990
From:	Richey R CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18009A355	List: ML18009A353 ML18009A356
References
HO-900019-(O), NUDOCS 9002050057
Download: ML18009A353 (5)

Text

ACCELERATED DIS .MBUTION DEMONS TION SYSTEM REGULATORY XNFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9002050057 DOC.DATE: 90/01/25 NOTARIZED: NO DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit , Carolina 05000400 AUTH. NAME AUTHOR AFFXLIATION RICHEY,R.B. Carolina Power 6 Light Co.

RECIP.NAME RECXPIENT AFFILXATION t Document Control Branch (Documen Contro Desk)

SUBJECT:

Forwards "Reactors Containment Bldg ILRT."

DISTRIBUTION CODE: A017D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal: Append J Containment Leak Rate Testing D NOTES:Application for permit renewal filed. o5ooo4oo s RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL A PD2-1 LA 1 0 PD2-1 PD 5 5 BECKER,D 1 1 D

INTERNAL: ACRS 6 6 NRR/DST/SPLB 8D 1 1 D'

NUDOCS-ABSTRACT 1 1 1 0 OGC/HDS 1 1 1 REG FILE 01 1 1 RES TELFORD i J 1 1 ~DE/SE 1 1 RES/DSIR/SAIB 1 1 RES/DSR/RPSB 1 1 EXTERNAL: LPDR 1 1 NRC PDR 1 1 NSIC 1 1 D

A D

D NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 25 ENCL 23

Carolina Power & Ught Company P. O. Box 165 ~ New Hill, N. C. 27562 R. B. RICHEY Manager Hanis Nuclear ProJect

~JAN 2 S 1990 Letter Number.'HO-900019 (0) 10 CFR 50 App. J United States Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, D. C. 20555 CAROLINA POWER AND LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO. 50-400 LICENSE NO. NPF-63 REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST Gentlemen:

In accordance with 10 CFR 50, Appendix J, Section V. B., the report of the Integrated Leak Rate Testing (ILRT) conducted for the Shearon Harris Nuclear Power Plant Unit 1 Reactor Containment Building during October 1989, is hereby submitted. A summary analysis of Types B and C testing performed subsequent to the preoperational ILRT is included in the report.

The initial pressurization testing performed yielded leakage rates exceeding the acceptance criteria specified by Technical Specifications. As stated in the report, valve packing leaks on the secondary system were discovered and repaired, using "live-Load" packing techniques, after which acceptable results were achieved.

CP&L believes that these packing leaks are isolated failures, and that the repair should prevent recurrence. The "live-load" packing method uses graphite packing rings which provide the sealing capability with minimum torque on the valve gland to minimize friction and wear, and which is very durable and resistive to deterioration. Belville washers are also installed on the gland studs to provide a spring action on the gland, which helps maintain a constant torque on the gland under fluctuations in process temperatures and pressures of the fluid system.

9002050057 900125 PDR ADOCK 05000400 P PDC MEM/HO-9000190/1/OS1 pci /

JIi

'ls '4- - f I W 4%.F

'V y

~,/'

U.,S. Nuclear Regulatory Commission Page 2 In addition, during design basis accidents, the secondary system remains pressurized by the Auxiliary Feedwater System until cold shutdown is achieved, at which time the secondary system is manually depressurized. Since containment pressure would be greatly reduced by that time, containment leakage through the secondary system would be significantly reduced compared to the leakage rates observed during the ILRT.

Based on these considerations, CP&L proposes to schedule the next ILRT at the normal 40 + 10 month interval. In accordance with Technical Specification 4.6.1.2.b and 10 CFR 50 Appendix J, Section III.A.6, approval of this proposed schedule is requested.

If further information is required, please contact Mr. Dean Tibbitts at (919) 362-2718.

Yours very truly, R. B. Richey, Man ger Harris Nuclear Project Attachment AJH:dgr cc: Mr. R. A. Becker (NRR)

Mr. S. D. Ebneter (NRC-RII)

Mr. J. E. Tedrow (NRC-SHNPP)

MEM/H0-9000190/2/Osl

l' L

C