ML19340A995
| ML19340A995 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Byron, Braidwood, Quad Cities, Zion, LaSalle  |
| Issue date: | 05/31/1978 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Brian Lee COMMONWEALTH EDISON CO. |
| References | |
| NUDOCS 8009240823 | |
| Download: ML19340A995 (1) | |
Text
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UNITED STATES NUOLEAR REGULATORY COMMISSION 4
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N 799 ROOSEVELT RoAo er oLEN ELLYN,lLLINols 60137
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Docket Nos.
-1 50-237, 50-249, 50-254, 2! 5 M*
50-265, 50
, 50-304, 50-373, 50-374, 7
40-454, 50-455, 50-456, 50-457 Qh g
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Come.onwealth Edison Company ATTN:
Mr. Byron Lee, Jr.
- Mw Vice President Qf rn r P. O. Box 767 U
{g Chicago, IL 60690 Gentlemen:
The enclosed IE Circular No. 78-07 is forwarded to you for information. If there are any questions related to your under-standing of suggested actions, please contact this office.
Sincerely, CL, ~ b h - k _
kamesG.Kehlir Director
Enclosures:
- 1. IE Circular No.~ 78-07 C.
- 2. List of IE Circulars Issued in 1978 cc w/encls:
Mr. B. B. Stephenson, Mr. R. Cosaro, Project Station Superintendent Superintendent Mr. N. Kalivianakis, Central Files Station Superintendent Director, NRR/DPM Mr. N. Vandke, Station Director, NRR/D0r Superintendent PDR Mr. L. J. Burke, Site Local PDR Project Superintendent NSIC Mr. Gunnar Sorensen, Site TIC Project Superintendent Anthony Roisman, Esq.,
Attorney
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4 U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION III May 3,1, 1978 IE Circular No. 78-07 DAMAGED COMPONENTS OF A BERGEN-PATERSON SERIES 25000 HYDRAULIC TEST STAND Description of Circumstances:
During functional testing of hydraulic snubbers at a power reactor
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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 o'f the problem together with recommended procedures to avoid such problems in the future:
A number of ESSA-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 series 25000 test stand utilizes a 2 pin loading system to simulate actual strut load connections which does not allow transmission of bending moments in the vertical plane. Unlike the actual strut which
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employs a ball bushing, the test stand'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 damage! components induced bending moments into the test units which prodwed mechanical binding between the piston rod and its bearing.
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 end of the strut, providing a universal action thereby assuring pure axial loading.
Bergen-Paterson recom= ends that the pinned conn.ctions and fixtures of the Series 25000 test stand or other test equipment used for snubber testing be periodically inspected and replaced if indications of damage are noted.
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IE Circular No. 78-07' May 31, 1978
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Bergen-Paterson's reco= mended, inspection frequency should be as follows:
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Prior to initial start of a Test Program.
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After each 60 credits of units tested - with credits assigned per the following schedule:
ESSA UNIT SIZE CREDITS
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10 1
20 2
30 3 ' ' ".~.
$0 5'
70 5
Inspection acceptance criteria for Test Fixture Components are:
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Cross' Pins Straightness 0.015 in.
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Bushings cylindricity 0.015 in.
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.020 in. Max Diametral While there are a limited number of this specific test. stand currently in use, it is corisidered likely that similar hydraulic snubber test equipment may heve comparable problems. All holders of Reactor C'
Operating Licenses or Construction permits should consider the following items in their review of this matter:
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Review the snubber testing device utilized at your facility to determine if a comparable problem could develop in the mounting fixtures.
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Consider the need for a periodic inspection and replacement of components that could adversely affect the test results.
No written ress this Circular is required.
If your require additional information regarding this matter, contact the Dirt.: tor of 1
the appropriate NRC Regional Office.
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IE. Circular No. 78-07 May 31, 1978 LISTING OF IE CIRCULARS ISSUED IN 1978 Circular Subj ect 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 Propa.r Lubricating 011 4/20/78 -
All Holders of for Terry Turbines Reactor OLs or cps C
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 Insdvertent Safety 5/23/78 All Holders of Injection During Reactor OLs or Cooldown cps 78-06 Potential Common Mode 5/25/78 All Holders of C'-
Flooding of ECCS Equip-Reactor OLs or i
ment Rooms at BWR cps Facilities e
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Enclosure Page 1 of 1
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