ML20094A066

Final Significant Const Deficiency Rept Re Loosening of Antirotational Collar Setscrews in Anchor Darling Globe Valves.Setscrews Will Be Checked for Tightness.Qc Verification of Tightness Will Be Documented

ML20094A066
Person / Time
Site:	Hope Creek
Issue date:	09/28/1984
From:	Martin T Public Service Enterprise Group
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8411060231
Download: ML20094A066 (2)

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N g O Y Thomas J. Martin Public Service Electric and Gas Company 80 Park Plaza Newark, N.J.07101 201/4304316 Vice President Engineering and Construction September 28, 1984 Dr. Thomas E. Murley, Administrator -

U. S. Nuclear Regulatory Commission ,e0syYg Of fice of Inspection and Enforcement 9 Region I 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Dr. Murley:

SIGNIFICANT CONSTRUCTION DEFICIENCY ANCIIOR DARLING GLOBE VALVES HOPE CREEK GENERATING STATION On August 30, 1984, a verbal report was made to Region I.

Office of Inspection and Enforcement representative, Mr. E.

Kelly, advising of a significant construction deficiency concerning the potential loosening of anti-rotational collar setscrews in Anchor Darling globe valves. The following final report is provided in accordance with 10CFR50.55 (e) .

Description of the Deficiency NRC Information Notice 83-70 identifies a potential problem with Anchor Darling globe valves with non-rotating stems.

The valves are designed with a stem collar which prevents the stem from rotating. The stem collar is secured by one or more setscrews. If the setscrew (s) becomes loose, the stem collar will not prevent the stem from turning. This will result in the stem rotating in place rather than moving linearly, as required for the valve to operate. Our Architect /

Engineer and Constructor, Bechtel, has identified eighty-six (86) Anchor Darling globe valves with non-rotating stems at the Hope Creek site.

Corrective Action In accordance with Anchor Darling recommendations, the stem collar setscrews will be checked for tightness. QC verifi-

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cation of setscrew tightness will be documented on the indi-vidual installation records for fifty-nine (59) of the l eighty-six (86)_ valves. This work will be completed by December 31, 1984.

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Dr. T. E. Murley 2 9-28-84 Bechtel Engineering has determined that the remaining twenty-seven (27) globe valves are installed in systems subject to steady state vibration. The setscrews on these valves will be locked in accordance with the manufacturer's recommendations.

Verification of this corrective action will be documented on Nonconformance Report No. 4591. This work will be completed.

by November 9, 1984.

Safety Analysis We have determined that had the stem collar setscrews become loose the valve would fail to open or close upon demand.

Several cases exist where this failure could prevent the Emergency Core Cooling Systems from performing their function under accident conditions. Based upon the above analysis, it has been determined that safe operation / shutdown of the plant could have been adversely affected had the problem gone uncorrected. We therefore consider this condition to be reportable in accordance with 10CFR50.55 (e) .

Very truly yours, 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