JPN-89-077, Informs of Delay in Containment Isolation Valve Replacement Schedule Due to Procurement Difficulty.Existing Outboard Containment Isolation Valve Will Be Type C Local Leak Rate Tested & Repaired to Assure Leak Tightness Prior to Startup
| ML19332C870 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 11/17/1989 |
| From: | Brons J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| JPN-89-077, JPN-89-77, NUDOCS 8911290117 | |
| Download: ML19332C870 (2) | |
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1123 Man street
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' White Plains, New York 10601 914 08t6240 -
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John C. Brons Executive vice President Of Nuclear Genera; ion
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November 17,1989 -
~JPN 89-077 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk-Mall Station P1 137
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Washington, D.C. 20555
SUBJECT:
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Containment isolat6a Vs,1ve Replacement Schedule
Reference:
. NYPA letter, J. C. Brons to the NRC, " Request for Exemption from Containment Integrated Leak Rate Test Retest Schedute,"
dated April 8,1989 (JPN-88 012).
q Dear Sir.
Attachment ll to the referenced letter provided a schedule for the replacement of 33 containment isolation valves (CIV). Twenty one CIVs were scheduled for replacement
~ during the 1988 refueling outage and the remainder during the 1990 refueling outage. All of the valves scheduled for replacement during 1988 were replaced on schedule. The replacement of four valves scheduled for the 1990 outage had been accelerated, and these' valves were replaced during the 1989 maintenance outage. One of the remaining
.i eight valves cannot be replaced during the 1990 outage as had been originally scheduled.
i The Authority is having difficulty procuring a replacement for valve 20AOV 95 from the original manufactur6r. Valve 20AOV 95 is a rion-lubricated air operated plug valve,
-and the original manufacturer is the only supplier of this type of valve with a qualified 1
- Quality Assurance program in accordance with 10 CFR 50 Appendix B. The Authority j
evaluated replacing this valve with a different style valve, but this was deemed infeasible 1
due to space limitations. Depending on the procurement problems, the Authority will 1
either upgrade valve 20AOV 95 or replace this valve no later than the 1991 refueling j
outage.
Valve 20AOV-95 is the outboard CIV on the equipment drain sump to the radwaste system. The inboard CIV on this penetration,20MOV 94, will be replaced during the i
1990 refueling outace. This alone will effect a significant improvement in the penetration's long term integrated leakage characteristics. The existing outboard CIV 20AOV 95 w!Il be Type C local leak rate tested in accordance with 10 CFR 50 Appendix J and repaired as necessary to assure its leak tightness prior to the startup following the 4
refueling outage.
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8911290117 891117 PDR ADOCK 05000333 P
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i Should you or your staff have any questions regarding thls matter, please contact
- 3. M. Toth of my sta'f.
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. Very truly ours,.
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John C. brons
' Executive Vice President.
Nuclear Generation cc:
Regional Administrator.
U.S. Nuclear Regulatory Commission
~ 475 Allendale Road King of Prussia, PA 19406 Office of the Resident inspector U.S. Nuclear Regulatory Commission P.O. Box 136 Lycoming, NY 13093 C
' Mr. David E. LaBarge Project Directorate I 1 Division of Reactor Projects-1/11 U.S. Nuclear Regulatory Commission Mail Stop 14 B2 Washington, D.C. 20555 i
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