ML20079S220
| ML20079S220 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 01/27/1984 |
| From: | Edelman M CLEVELAND ELECTRIC ILLUMINATING CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| RDC-88(84), NUDOCS 8402030248 | |
| Download: ML20079S220 (2) | |
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P.O. box $000 - CLEVELAND OHIO 44101 - TELEPHONE (216) 622-9800 - ILLbMtNATING BLDG. - 55 PUBLIC SOUARE Serving The Best Location in the Nation MURRAY R. EDELMAN VICE PREStoENT NUCMAR January 27, 1984 Mr. James G. Keppler Regional Administrator, Region III Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 RE:
Perry Nuclear Power Plant Docke t Nos. 50-440; 50-441 Significant Deficiency Concerning Anchor Darling Globe Valves
[RDC 88(84)]
Dear Mr. Keppler:
This letter serves as the final report as required by 10CFR50.55(e) on the significant deficiency concerning Anchor Darling Globe Valves supplied by General Electric. This item was identified to Mr. Pelke of the NRC, Region III, Office of Inspection and Enforcement, on December 29, 1983, by Mr. Shuster of The Cleveland Electric Illuminating Company.
This letter contains a Description of the Deficiency, an Analysis of Safety Implications, and the Corrective Action Taken.
Description of Deficiency The Anchor Darling Globe Valves supplied by GE contain a defect in the anti-rotational setscrew which holds the stem collar in position on the valve stem.
During valve operation, the setscrew vibrates loose which allows the key between the stem and stem collar to be displaced. This displaced key allows 3
the stem collar to slide down the stem resulting in free rotation of the stem rendering the valve Inoperable.
This condition was identified to The Cleveland Electric Illuminating Company by General Electric on December 27, 1983.
This deficiency affects the High Pressure Core Spray Valves E22-F010 and E22-F011 for Units 1 and 2.
Analysis of Safety Implications The loss of the scem collar setscrews on both HPCS test return valves would represent a common mode failure. These valves, normally closed upon comple tion or a test, could remain opan without the awareness of the Control Room Operator.
It can be postulated that during a LOCA, radioactive suppression pool water might enter the Condenrate Storage Tank which is outside the containment.
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DAN 30.m
, s PDR
C' Mr. James G. Kipplar Janusry 27, 1984
~ Corrective Action Taken The corrective action identified to assure valve operability will be to lock the setscrews by staking. the stem collar threads with a center punch.
Corrective action for the Unit 1 valves was completed January 11, 1984.
Corrective action for the Unit 2 valves will be completed by September 15, 1984.
Please contact us if you have any questions.
Sincerely, Murray R. Edelman Vice President Nuclear Group I'
MPE:pab cc:
Mr. M. L. Gildner
-NRC Site Office Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.
20555 U.S. Nuclear Regulatory Commission c/o Document Management Branch Washington, D.C.
20555
' Records Center, SEE-IN Ins titute of Nuclear Power Operations 1100 circle 75 Parkway, Suite 1500 Atlanta, Georgia 30339
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