ML19329E394
| ML19329E394 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 05/31/1978 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Howell S CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| NUDOCS 8006120713 | |
| Download: ML19329E394 (1) | |
Text
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(Ep(IM OS MAY 311978 Docket No. 50-329 Docket No. 50-330 Consumers Power Cocpany ATTH:
lir. Stephen H. Howell Vice President 1945 West Parnall Road Jackson, MI 49201 Gentleinen:
The enclosed IE Circular No. 76-07 is forwarded to you for information. If there are any questions related to your under-standing of suggested actions, please contact this office.
Sincerely, James G. Keppler Director
Enclosures:
- 1. IE Circular No. 78-07
- 2. List of IE Circulars Issued in 1978 cc w/encls:
Central Files Director, NRR/DPM Director, NRR/ DOR PDR Local PDR NSIC TIC Ronald Callen, Michigan Public Setvice Coe:nission Dr. Wayne E. North Myron M. Cherry, Chicago 80061207/3 RIII I RIII
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NRC Form 318A (R2II) (5-76) NRcM 02040
.U. S. GOVERNMENT PRINTING OFFICE:
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4 U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION III May 31,'1978 f
IE Circular No. 78-07 t
DAMAGED COMPONENTS OF A BERGEN-PATERSON SERIES 25000 HYDRAULIC TEST STAND Description of Circumstances:
During functional testing of hydraulic snubbers at a power reactor facility, test results were adversely influenced by the use of damaged components in the test stand connectors to the snubber being tested.
The following paragraphs are the manufacturer's (Bergen-Paterson) description of the problem together with recommended procedures to avoid such problems in the future:
A number of HSSA-3 (Hydraulic Shock and Sway Arrester) Units, 1-1/2" bore x 6" stroke, with 3,000 pound load rating, exhibited nonuniform performance. The bleed rates were erratic and in some instances a structural lockup was observed. A sample of units were disassembled and found to be in proper working order.
Attention was then directed to the testing machine's fixturing. The i
series 25000 test stand utilizes a 2 pin loading system to simulate i
actual strut load connections which does not allow transmission of i
bending moments in the vertical plane. Unlike the actual strut which employs a ball bushing, the test r.tand's fixturing is a simplified pin connection.
An inspection of the load pins and bushings during the review of the test fixturing indicated that they were damaged due to a prior overload condition. These damaged components induced bending moments into the test units which produced mechanical binding between the piston rod and its bearing, i
The noted moment type loading condition does not occur on units in service since all strut assemblies incorporate ball bushings in the cross-pin connection at each and of the strut, providing a universal action thereby assuring pure axial loading.
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3 Bergen-Patarson recommends that the pinned connections and fixtures of V(fhf'.
the Series 25000 test stand or other test equipment used for snubber 4
990 testing be periodically inspected and replaced if indications of damage epOI are noted.
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m IE Circular No. 78-07 May 31, 1978 Bergen-Paterson's recommended inspection frequency should be as follows:
A.
Prior to initial start of a Test Program.
B.
After each 60 credits of units tested - with credits assigned per the following schedule:
HSSA UNIT SIZE CREDITS 3
1 10 1
20 2
30 3
50 5
70 5
Inspection acceptance criteria for Test Fixture Cotr 3onents are:
Cross Pins Straightness 0.015 in.
Bushings Cylindricity 0.015 in.
Fit
.020 in. Max Diametral While there are a limited number of this specific test stand currently in use, it is considered likely that similar hydraulic snubber test equipment may have comparable problems. All holders of Reactor Operating Licenses or Construction permits should consider the following items in their review of this matter:
1.
Review the snubber testing device utilized at your facility to determine if a comparable problem could develop in the maunting fixtures.
2.
Consider the need for a periodic inspection and replacement of components that could adversely affect the test results.
No written response to this Circular is required. If your require additional information regarding this matter, contact the Director of the appropriate NRC Regional Office.
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l IE Circular No. 78-07 May 31, 1978 LISTING OF IE CIRCULARS ISSUED IN 1978 Circular Subject Data Issued To No.
of Issue 78-01 Loss of Well Logging 4/5/78 All Holders of Source Well Logging Source Licenses 78-02 Proper Lubricating 011 4/20/78 All Holders of for Terry Turbines Reactor OLs or cps r.'
78-03 Packaging Greater Than 5/12/78 All Holders of Type A Quantities of Reactor OLs, cps, Few Specific Activity Fuel Cycle, Radioactive Material Priority I Material for Transport and Waste Disposal Licenses 78-04 Installation Errors that 5/15/78 All Holders of Could Prevent Closing of Reactor OLs or Fire Doors cps 78-05 Inadvertent Safety 5/23/78 All Holdere of Injection During Reactor OLs or Cooldown cps 78-06 Potential Common Mode 5/25/78 All Holders of Flooding of ECCS Equip-Reactor OLs or ment Rooms at %'R cps Facilities i
Enclosure Page 1 of 1
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