ML20141E441
| ML20141E441 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 04/01/1986 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 8604210470 | |
| Download: ML20141E441 (2) | |
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Pubhc Service Electric and Gas Company Corbin A. McNeill, Jr.
Public Service Electric and Gas Company P.O. Box 236.Hancocks Bridge.NJ 08038 609 339-4800 Mce Presdent -
Nuclear April 1, 1986 Dr. Thomas E. Murley, Administrator U.
S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania 19406
Dear Dr. Murley:
SIGNIFICANT CONSTRUCTION DEFICIENCY ANCHOR-DARLING TESTABLE CHECK VALVES HOPE CREEK GENERATING STATION l
O'n March 5, 1986, a verbal report was made to Region I, Office
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of Inspection and Enforcement representative, Mr.
R.
- Blough, advising of a potentially significant construction deficiency concerning the operation of Anchor-Darling testable check valves.
The following final report is provided in accordance with 10CFR50.55(e).
Description of the Deficiency Deficiency Report HMD-86-099 describes a construction deficiency with testable check valves supplied by Anchor-Darling in that the valve disc would not open or close under normal flow operation conditions.
The actuator shaft must rotate in the packing to permit smooth opening and closing of the disc without external assistance.
The actual condition discovered with the check valves revealed that the valves did in fact open during system operation, however the disc did not close when fluid flow was stopped.
This condition was discussed with Operations, Main-tenance and Station System Engineering.
Surveillance inspection that was performed to determine if the disc would open and close revealed that less than optimum rotation of the disc is occurring.
Maintenance personnel stated that some of the check valves had the packing gland tightened to eliminate leakage.
This field adjustment may have contributed to the less than optimum rotation of the disc.
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Dr.
T.
E. Murley 2
4-1-86 f,afety Analysis Valves located in the RCIC/HPCI Turbine Steam System which remain open could result in the increase of radioactivity outside con-tainment and valves in the HPCI system could result in excessive loading of the suppression pool.
We therefore conclude that the subject deficiency is reportable in accordance with 10CFR50.55(e).
Corrective Action The deficiency is being corrected as outlined in Design Change Package 7189 which eliminates the actuator shaft from rotating in the packing and allows the valve to function as a simple swing check valve with assist open levers.
The valves are being modified in order to improve the mechanism for opening and closing the disc.
Modification of nine (9) valves has been completed to satisfy our fuel load commitments.
An additional seven (7) valves will be completed before initial criticality.
A copy of DCP 7189 has been provided to your Resident Inspector.
Sincerely, N
Q C
Office of Inspection and Enforcement Division of Reactor Construction Inspection Washington, D.
C.
20555 NRC Resident Inspector P.
O.
Box 241 Hancocks Bridge, NJ 08038 Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, GA 30339
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