ML20030C841
| ML20030C841 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 08/20/1981 |
| From: | Parker W DUKE POWER CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, NUDOCS 8108280230 | |
| Download: ML20030C841 (2) | |
Text
,
\\
b Duxe POWER CO>fPANY Powen Ilcin.nnso 422 Socrn Cucac9r STaner, CHARI.OTTe, N. C. 28242
."1 35
,, g g~
TcLEPHONC ARE A 704 v.cr Pers orut 313-4063 Straw Paoovctiog Aggggg 2Q, 1g31 O
Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Commission
'S (sk s
Region II 101 Marietta Street, Suite 3100 y
~
Atlanta, Georgia 30303 g'
g 7,7 Re: Catawba Nuclear Station 4'h Units 1 & 2 4
Docket Nos. 50-413 & -414 p
4
Dear Mr. O'Reilly:
Pursuant to 10 CFR 50.55e, please find attached Significant Deficiency Report IE-78/02-SPS-413/414 (Final Report).
Very truly yours, O b
(
/
William O. Parker, Jr.
ROS/php Attachment cc: Director Resident Inspector Office of Inspection and Enforcement Nuclear Regulatory Commission U. S. Nuclear Regulatory Commission Catawba Nuclear Station Washington, D. C. 20555 h//
8108280230 810820 PDR ADOCK 05000413 S
d
/
REPORT NO: IE-78/02-SPS-413/414 Dated September 19, 1978 i
PROGRESS REPORT DATE: July 29, 1981 FACILITY:
Catawba Nuclear Station, Units 1 & 2 IDENTIFICATION OF DEFICIENCY:
Safety Related Containm..c Isolation Valve Type C Leakage Deficiency li i
i INITIAL REPORT:
1 An initial formal written report (1578/02-SPS-413/414 dated September 19,1978)
]
was provided to the NRC on this deficiency.
1 l
DESCRIPTION OF DEFICIENCY:
1 During preliminary seat leakage air testing of hard seat containment isolation valves, actual valve seat air leakage exceeded Type C containment isolation valve leakage criteria.
Low air pressure valve seat leakage testing similar i
to containment Type C leakage testing was not a requirement of applicable Duke valve procurement specifications.
1 ANALYSIS OF SAFETY IMPLICATIONS:
Had this deficiency not been identified and requirements of 10CFR50 Appendix J i
imposed, overall containment isolation leakage allowables would have been exceeded.
CORRECTIVE ACTION:
Duke document DCA-MEQP-0004 identifies all affected valves and corrective action /
l modifications required to be done by Catawba Construction Department.
Design Engineering corrective action is complete.
Modifications made were:
(1) For l
some of the affected gate valves, a seal water system (System NW) was added.
The purpose of the seal water system is to eliminate air leakage through the gate valve by sealing valve body with water at higher pressure than containment accident pressure.
(2) For other affected containment isolation valves, the valves were either modified or replaced to obtain valves with elastomeric seating materials. The effect of replacing metal valve seats by elastomeric seats results in reduction of seat leakage to acceptable limits.
Acceptable seat leakage tests were performed by the manufacturers of replac. ment' valves and by manufacturers of valves modified by manufacturer.
All replacement valves and valve parts have been delivered to the site.
Duke will perform seat leakage tests on valves modified at the site.
Valve modifications and seat leakage tests will be completed before final Type C containment isolation valve leakage tests, m