ML19340A982
| ML19340A982 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Byron, Braidwood, Quad Cities, Zion, LaSalle  |
| Issue date: | 06/27/1978 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Brian Lee COMMONWEALTH EDISON CO. |
| References | |
| NUDOCS 8009240795 | |
| Download: ML19340A982 (1) | |
Text
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i JUN 2 71978 i
Docket Nos 456, 50-457, 50-454, 50-455, 1 )S0-237, 50-249, 50-373, 50-374, 5
, 5%265, 50-295 and 50-304 i
Conc:tonwealth Edison Company ATTN:
Mr. Byron Lee, Jr.
Vice President Post Office Box 767 Chicago, IL 60690 l
Gentlemen:
)
Enclosed is IE Bulletin No. 78-10 which requires action by you with j
regard to your power reactor facilities with an operating license 1
or a construction permit.
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Should you have questions regarding this Bulletin or the actions j
required of you, please contact this office.
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Sincerely, i
i James G. Keppler j
Director j
Enclosures:
i 1.
List of IE Bulletins Issued in 1978 f
cc w/encis:
l Mr. B. B. Stephenson, Mr. R. Cosaro, Project i
Station Superintendent Superintendent
'3,
Mr. N. Kalivianakis, W utral Files F Qt 'V
[,
Station Superintendent Director, NRR/DPM p
8 Mr. N. Vandke, Station Director, NRR/ DOR
(
Superintendent PDR Mr. L. J. Burke, Site Local PDR Project Superintendent NSIC Mr. Cunner Sorensen, Site TIC Project Superintendent Anthony Roisman, Esq., Atto o rricE >
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_______,_l SURNAME > ___Fior,e_lly_/@al __ He_
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a cave > _ __ _6 -2 6.-18_ ___ ______g-26:78__..___g:26:n _.. _ _ _ _ _ _ _ _ _ _ _.. _ _ _ _ _ _ _ _ _______ _ _ i NRC Form 318A (R3ZI) (5-76) NRCM 02040
- U. 5. GOVERNMENT PRINTING OFFICE: 1978-253 818 8 0 09uo 7 E-
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION III June 27, 1978 IE Bulletin No. 78-10 BERGEN-PATERSON HYDRAULIC SHOCK SUPPRESSOR ACCUMULATOR SPRING COILS Description of Circu= stances:
During the conduct of hydraulic shock suppressor (snubber) functional testing and seal replacerent progra=s at several licensed facilities, a nu=ber of broken accumulator spring coils have been found in early model Bergen-Paterson hydraulic snubbers. The attached extract fro = a Bergen-Paterson advisory letter, dated April 6, 1978, states that a broken accu =ulator spring alone would not render the snubber incapable of i
performing its design function; however, the broken spring could i
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 through 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 broker 1 hibited advanced stages of corrosion. The factors which caused the tpring corrosion are undetermined.
l Bergen-Paterson has recommended that corrosion susceptible accumulator spring coils be replaced with teflon cot;td or stair.iess steel coils during the next refueling shutdown.
Action to be Taken by Licensees:
For all power reactor facilities with an operating license or a construction permit:
1.
If you have received the enclosed Bergs.n-Pater.on letter addressing the accumulator spring problem, and if you have these units installen 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 relate.d systems is not impaired. It is also requested I
that you describe the condition of any springs that were observed during the performance of the corrective action.
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IE Bulletin No. 78-10 June 27, 1978 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 syste=s is not impaired.
3.
If the snubbers are currently installed in safety related systems, it is requested that you identify their location in your 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 forwarded to the
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NRC Office of Inspection and Enforce =ent, 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 prob le=s.
Attachment:
Extract fro: Bers.n-Paterson
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letter dated April 6,~ 1978
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'l Attachment Extract from Bergen-Paterson Advisory Letter
SUBJECT:
B/P Hydraulic Snubbers' HSSA Accumulator-Spring Advisory Letter.'.
Gentlemen:
Bergen-Paterson advises'thit broken accumulator spring coils have been found in a number of early model hydraulic snubbers at the time when -
units were being dissembled for seal replacement purposes. The early models noted are identified as being the external pipe design having serial nu=bers 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 co_ated with a rust preventative. All later external
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pipe design units were initially furnished with springs having the.sa=e j
caterial as noted; abovei.however, all coils were teflon coated..Our*
current model units are furnished with stainless steel'ecils. Both the teflon coated 'and stainless coils have been found to give satisfactory service.
It.i_ ssp.cificallypointhdoutthataunitremainsfunctionalevenwith e
a broken spring; however, the possibility does exist that the debris fro = a broken spring coil could in f act cause da= age to the Accumula. tor Piston U-Cup Seal resulting. in possible leakage of fluid. The remote possibility for the ' Accumulator Piston to become ja=med in the tube
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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.
i Attachmett 1 Page 1 of 1
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b-a IE Bulletin No. 78-10 June 27,1978 LISTING OF IE BULLETINS ISSUED IN 1978 Bulletin Subject Date Issued Issued To No.
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78-01 Ffa==able Contact -
1/16/78 All Power Reactor Arm Retainers in G.E.
Facilities with au CR120A Relays OL or CP 78-02 Terminal Block 1/30/78 All Power Reactor Qualification Facilities with 'an-
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OL or CP 78-03 Potential' Explosive ~
2/8/78 All BWR' Power' Gas Mixture Accumula-Reactor Facilities tions Associated with with an'OL or CP BWR Offgas System Operations,
78-04 Environmentsl Quali-2/21/78
'All Power Reactor fication of-Certain Facilities with an Stem Mounted Limit OL or CP Switches Inside Reactor Containment 78-05 Malfunctioning of 4/14/78 All Power Reactor Circuit Breaker Facilities with an Auxiliary Contact OL or CP Mechanism-General Model CR105X 78-06 Defective Cutler-5/31/78 All Power Reactor Hammer, Type M Relays Facilities with an With DC Coils OL or CP Page 1 of 2
5 bc;.
June 27, 1978 LISTING OF BULLETINS ISSUED IN 1978 Bulletin Subject Date Issued Issued To
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No.
78-07 Protection afforded 6/12/78 All Power Reactor Res~earch Reactors with an OL, all Fuel Cycle Facilities with an OL, and~all Priority 1 Mat.erial Licensees 78-08 Radiation Levels from 6/12/78 All Power and Fuel Ele =ent Transfer Research Reactor Tubes Facilities with a Fuel Element transfer tube and an OL. ~
78-09 BWR Drywell Leakage 6/14/78 All BWR Power Paths Associated with Reactor Facilities Inadequate Drywell with an OL or CP Closures Page 2 of 2
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