ML19262A536
| ML19262A536 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/27/1978 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Herbein J METROPOLITAN EDISON CO. |
| References | |
| IEB-78-10, NUDOCS 7911130546 | |
| Download: ML19262A536 (1) | |
Text
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UNITED STATES 8
t NUCLEAR R EGULATOR Y COMMisslON
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June 27, 1978 Docket Nos. ',89 Metropolitan Edison Company ATTN:
Mr. J. G. Herbein Vice President P. O. Box 542 Reading, Pennsylvania 19603 Gentlemen:
Enclosed is IE Bulletin No. 78-10 which requires action by you with regard to your power reactor facility (ies) with an operating license or a construction permit.
Should you have questions regarding this Bulletin or the actions required of you, please contact this office.
Sincerely, WM f a
n Boyce H. Grier Director
Enclosures:
1.
List of IE Bulletins Issued in 1978 cc w/encls:
R. L. Wayne, QA Manager, Design & Construction T. Broughton, Safety & l.icensing Manager R. W. Heward, Jr., Project Manager R. C. Arnold, Vice President, Generation L. L. Lawyer, Manager, Generation Operations - Nuclear
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G. P. Miller, Superintendent J. P. O'Hanlon, Unit 1 Superintendent J. L. Seelinger, Unit 2 Superintendent Gerald Charnoff, Esquire I. R. Finfrock, Jr.
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Miss Mary V. Southard, Chainnan, Citizens for a Safe Environment n
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UNITED STATES NUCLEAR REGULATORY CCfMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D. C.
20555 IE Bulletin No. 78-10 Date: June 27, 1978 Page 1 of 2 BERGEN-PATERSON HYDRAULIC SHOCK SUPPRESSOR ACCUMULATOR SPRING COILS Description of Circumstances:
During the conduct of hydraulic shock suppressor (snubber) functional testing and seal replacement programs at several licensed facilities, a number of broken accumulator spring coils have been found in early model Bergen-Paterson hydraulic snubbers.
The attached extract from a Bergen-Paterson advisory letter, dated April 6,1978, states that a broken accumulator spring alone would not render the snubber incapable of perfonning its design function; however, the broken spring could cause internal damage to the accumulator which could result in unit inoperability.
The subject snubbers are of the external pipe design with serial numbers 487,000 to 515,000 and F60,635 throug" F75,000.
The accumulator springs in these snubbers are basically carbon steel and were coated with a petro-chemical rust preventative by the vendor.
Despite this initial protective coating, those springs found broken exhibited advanced stages of corrosion. The factors which caused the spring corrosion are unde-termined.
Bergen-Paterson has recormended that corrosion susceptible accumulator spring coils be replaced with teflon coated or stainless steel coils during the next refueling shutdown.
Action to be Taken by Licensees:
For all power reactor facilities with an operating license or a con-struction pennit:
1.
If you have received the enclosed Bergen-Paterson letter addressing the accumulator spring problem, and if you have these units installed or in ready spares at your facility, it is requested that you describe what corrective action you have taken or plan to take to assure that the operability of snubbers in safety related systems is not impaired.
It is also requested that you describe the condition of any springs that were observed during the performance of the corrective action.
221a 093 Dya-myt enP
IE Bulletin No. 78-10 Date: June 27, 1978 Page 2 of 2 2.
If you have not received the enclosed Bergen-Paterson letter, it is requested that you describe what action you plan to take if the subject snubbers are installed or in ready spares at your facility to assure that the operability of snubbers in safety related systems is not impaired.
3.
If the snubbers are currently installed in safety related systems, it is requested that you identify their location in ycur response to this Bulletin.
4.
Report in writing within 45 days for facilities with an operating license and within 60 days for facilities with a construction permit, your plan of action and schedule with regard to Items 1 and 2.
Reports should be submitted to the Director of the appro-priate NRC Regional Office and a copy should be foraarded to the NRC Office of Inspection and Enforcement, Division of Reactor Operations Inspection, Washington D. C.
20555.
Approved by GAO, B180225 (R0072); clearance expires 7-31-80.
Approval was given under a blanket clearance specifically for identified generic problems.
ATTACHMENT:
Extract from Bergen-Paterson letter dated April 6, 1978 22:3 094
Attachment Extract from Bergen-Paterson Advisory Letter
SUBJECT:
8/P Hydraulic Snubbers HSSA Accumulator Spring Advisory Letter Gentlemen:
Bergen-Paterson advises that broken accumulator spring coils have been found in a number of early model hydraulic snubbers at the time when units were being disassembled for seal replacement purcoses. The early models noted are identified as being the external pipe design having serial numbers between 487,000 and 515,000 and F60,635 through F75,000.
These units were initially furnished with music wire or chrome silicone spring material both coated with a rust preventative.
All later external pipe design units were initially furnished with springs having the same material as noted above; however, all coils were teflen coated.
Our current model units are furnished with stainless stees coils.
Both the teflon coated and stainless coils have been found to r 5 satisfactory service.
It is specifically pointed out that a unit remains functional even with a broken spring; however, the possibility does exist that the deiris from a broken spring coil could in fact cause damage to the Accumula'.ar Piston U-Cup Seal resulting in possible leakage of fluid.
The remote possibility for the Accumulator Piston to become jammed in the tube also exists although, however, this has not been experienced.
Bergen-Paterson has issued this advisement to make users aware of the possibility of broken accumulator springs and recommends that units having uncoated coils be refitted with either teflon coated or stainless steel coils at the next refueling shutdown.
Very truly yours, BERGEN-PATERSON PIPESUPPORT CORP.
Attachment I Page 1 of 1 22io 095
IE Bulletin No. 78-10 June 27, 1978 Page 1 of ?
LISTING OF BULLETINS ISSUED IN 1978 Bulletin Subject Date Issued Issued
.~o No.
78-01 Flammable Contact -
1/16/78 All Power Reactor Arm Retainers in G.E.
Facilities with an CR120A Relays Operating License (OL) or Construction Permit (CP) 78-02 Terminal Block 1/30/78 All Power Reactor Qualification Facilities with an Operating License (OL) or Construction Permit (CP) 78-03 Potential Explosive 2/8/78 All BWR Power Gas Mixture Accumula-Reactor Facilities tions Associated with with an Operating BWR Offgas System License (0L) or Operations Construction Permit (CP) 78-04 Environmental Quali-2/ 21 / 78 All Power Reactor fication of Certain Facilities with an Stem Mounted Limit Operating License Switches Inside (0L) or Construction Reactor Containment Permit (CP) 78-05 Malfunctioning of 4/14/78 All Power Reactor Circuit Breaker Facilities with an Auxiliary Contact Operating License Mechani sm-General (OL) or Construction Electric Model CR105X Pennit (CP) 78-06 Defective Cutler-Hammer 5/31/78 All Power Reactor Type M Relays with Facilities with an DC Coils Operating License (OL) or Constrtction Permit (CP) 22i; 096
s IE Bulletin No. 78-10 June 27, 1978 Page 2 of 2 LISTING OF BULLETINS (CONTINUED)
ISSUED IN 1978 Bulletin Subj ect Date Issued Issued To No.
78-07 Pretection Afforded By 6/12/78 All Power Reactor A-lr-Line Respirators Facilities with and Supplied-l,ir Hoods an Operating License (OL),
all Class E and F research reactors with an operating license, all fuel cycle facilities with an operating license, and all Priority I material licensees 78-08 Radiation Levels from 6/12/78 All Power, Test, Fuel Element Transfer and Research Reactor Tubes Facilities with an Operating License (OL) having Fuel Element Transfer Tubes 78-09 BWR Drywell Leakage Paths 6/14/78 All BWR Power Reactor Associated with Inadequate Facilities with an Drywell Closures Operating License (0L)
(for Action), or Construction Permit (CP) (for Information) 22; 097