05000271/LER-1986-001, :on 860107,during Pipe Replacement Outage, Discovered That Containment Isolation Valves Not Accounted for in App J Program.Caused by Failure of Personnel.App J Program Will Be Updated to Include Subj Valves
| ML20137R583 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 02/05/1986 |
| From: | Pelletier J VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | NRC OFFICE OF ADMINISTRATION (ADM) |
| References | |
| LER-86-001, LER-86-1, VYV86-030, VYV86-30, NUDOCS 8602130312 | |
| Download: ML20137R583 (4) | |
text
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.--,n During the 1985/86 Recirculation Pipe Replacement Outage, plant personnel determined by direct observation / evaluation that small bore piping (1j in.)
entering containment through penetration X-48 was not accounted for in the Vermont Yankee Primary Containment Leak Rate Testing Program, and subsequently e
not leak tested.
The cause resulted from a failure of plant personnel to per-form a thorough evaluation of all catainment spare penetrations during develop-ment of the Appendix J program.
Technical Specification section 4.7.A.2 requires that containment integrity be demonstrated as required by Appendix J to 10CFR Part 50.. Appendix J requires that all isolation valves, which penetrate containment, be addressed in a Reactor Containment Leakage Test program.
Vermont Yankee will update the Primary Containment Leak Rate Testing Program to reflect the ultimate configuration / testing requirements of penetration X-48 prior to startup following the 1985/86 outage.
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Description of Event
On 1/7/86, with the plant shutdown and defueled for the 1985/86 pipe repla-cement outage, plant personnel determined by direct observation /evalmtion that piping (lj in.) entering containment through penetration X-48 was not accounted for in the Vermont Yankee Tech. Specs, and the Primary Containment Leak Rate Testing Program. The program listed penetration X-48 as a spare.
The small bore piping is part of the condensate and demineralized water transfer system. The line provides condensate water to hose connections at sta-tions located in containment. Plant procedures controlling the system valve line up for the isolation valves show them to be normally closed.
Cause of Event
The cause of the event resulted from the failure of plant personnel to per-form a thorough evaluation of all containment spare penetrations during develop-ment of the Appendix J leak rate test program.
The Primary Containment Leak Rate Testing Program was developed consistent with plant Technical Specifications which does not identify the valves at penetration X-48 as containment isolation valves subject to Type C leakage tests (Ref. Table 4.7.2.a).
The piping was most likely installed during original construction (1968-1972) to facilitate construction activities and was intended to be removed.
Analysis g Event:
Technical Specification Section 4.7.A.2 requires that the containment integrity be demonstrated as required by Appendix J to 10CFR Part 50. Appendix J requires that all isolation valves, which penetrate containment, be addressed in a Reactor Containment Leakage Test program. Although this criteria has not been formally met, no significant adverse safety consequences resulted from this event in that:
1.
The normal position for the isolation valves at penetration X-48 is closed.
2.
Containment was ensured by the water seal on the outboard isolation valve provided by the Condensate System that normally operates at pressures that exceed maximum design basis containment pressures (Pa).
3.
Failure of the penetration would not reduce rne plants ability to safety shutdown.
4.
All past integrated leak rate Type A tests clearly show Primary Containment was satisfied without any additional local testing for this penetration.
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Corrective Action
- - 4 No immediate operator actions were necessary on X-48 due to the shutdown status of the plant.
Vermont Yankee has completed a verification program _of all penetrations identified as spares in the Vermont Yankee Primary Containment Leak Rate Testing program and no other discrepancies were found.
Vermont Yankee will update the program to reflect the ultimate configuration (pipe cap addition or equivalent) and testing requirements (Appendix J update, plant procedures) of penetration X-48 prior to startup following the 1985/86 pipe replacement outage.
No similar events have been reported to the Commission in the last 5 years.
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V$RMONT YANKEE NUCLEAR POWER CORPORATION P. O. BOX 157 GOVERNOR IIUNT ROAD VERNON, VERMONT 05354 February 5,1986 VYV86-030 U.S. Nuclear Regulatory Commission
- - Document No. 50-271 Washington, D.C.
20555 REFERENCE: Operating License DPR-28 Docket No.~50-271 Reportable Occurrence No. LER 86-01
Dear Sirs:
As defined by 10CFR50.73, we are reporting the attached Reportable Occurrence as LER 86-01.
Very truly yours, VERWNT YAWEE NUCLEAR POWER CDRPORATION n
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ames P. Pelletier Plant Manager H /dre cc Regional Administrator USNRC Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania ~ 19406