ML18347A814

From kanterella
Jump to navigation Jump to search
LER 1980-037-00 for Palisades Nuclear Plant, Pipe Support Sway Struts Identified to Have the Potential of the Bushing Becoming Loose And/Or Disengaged from the Clamp End of the Sway Strut
ML18347A814
Person / Time
Site: Palisades Entergy icon.png
Issue date: 10/10/1980
From:
Consumers Power Co
To:
Office of Nuclear Reactor Regulation
References
LER 1980-037-00
Download: ML18347A814 (2)


Text

  • ...

Attachment to LER 80-03'7/0l-X-O Consumers Power Company Palisades Plant Docket 50-255 - License DPR-20 Description Pipe support sway struts furnished by Corner and Lada, Inc have been found to contain some deficiencies. The specific deficiencies identified involve the potential of the bushd.ng becoming loose and/or disengaged from the clamp end of the sway strut. Under seismic conditions, disengagement of the clamp end from the bushing could overstress the piping system. This problem has been identified at a few nuclear plants already.

By letter dated October 8, 1980, Consumers Power Company was notified by Bechtel Engineering Corporation (Ann Arbor, Michigan) that the sway braces, furnished by Corner and Lada, Inc are potentially deficient.

1. GCl-H-142 LPSI Pump discharge area 2/w engineering safeguards rooms
2. DC2-H-6 SI Recirc to SIRW tank
3. HB-35-H-932 Aux feed pump suction area 6/aux feed pump room
4. GC-ll-H-862 Pressurized safety and relief valve piping to quench tank The sway struts identified were recently installed as part of plant modifications related to IE Bulletin No '79-14 activities and were obtained from Midland Plant stock. Other struts out of the Midland stock have been found to be defective.

Bechtel has also indicated that support devices provided by other manufacturers may have a similar defect.

Cause of Deviation There appears to be a generic deficiency in the pipe support sway struts furnished by Corner and Lada, Inc. The specific deficiencies identified involved the bushing becoming loose and/or disengaged from the clamp end of the sway strut.

Corrective Action Since this is a potential problem, and we have not experienced an actual failure to date, immediate action is not required. However, Bechtel Engineering Corpora-tion will proceed in resolving this issue as follows:

1. Review hanger drawings to identify any "potential" sway strut defect condition,
2. Establish criteria and schedule for inspection of these sway struts,
3. Provide a fix, if required.

PALISADES PLANT*

NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION C7*771 LICENSEE EVENT REPORT CONTROL BLOCK:  !-I 1

_..._......___..___.__..-...ii 6

CD (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

~IMIIIPIAILlll@IOIOl-IOIOIOIOIOl-IOIOIG)l411111i11101 I 10 7 8 9 LICENSEE CODE 14 ,5 LICENSE NUMBER , 25 26 LICENSE TYPE 30 57 CAT 58 CON'T

[ill] ~~~~~ UJ©I o I 51 o I o Io I 2 15 15 1011 I o I o I9 I 8 I o l@I 11 o I 1 I o I 8 I o 10 7 8 60 61 DOCKET NUMBER 6B 69 EVENT CATE 74 75 REPORT CATE 80 EVENT DESCRIPTION ANO PROBABLE CONSEQUENCES@ .

((I1J !Pipe support sway struts furnished by Corner and Lada, Inc have been

())!] I identified to have the potential of the bushing becoming loose and/or

~ t disengaged from the clamp end of the sway strut. This is reportable

(([TI 1under Palisades Plant Technical Specifications 6.9.2.a.(5).

[QI[].__~~~~~~~~--~~~~~~~~~~~~~~~~~~~~~~~~~~~~--'

rr:m

[))))

7 8 9 so SYSTEM . CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUSCODE SUBCOOE .

ITIII 1s IAI@ ~@ l!J@) 1s 1u1 PIO IRIT 1@ ~@ G@

7 8 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION r.::... LERIRO LVENTYEAR REPORT NO. CODE TYPE NO.

~ REPORT NUMBER I 8 I 01 I I I OI 3 17 I I /I *I O 11 J UJ l.=J l2J 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN t.:::\ ATTACHMENT NPR0-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS ~ SUBMITTED FORM sue, SUPPLIER MANUFACTURER Lz.J@LA.J@

33 34 W@

35.

LzJ 36 Io lo Io I ol 37 40 LxJ@

41 W@

42 .

ILJ@

43 Ix I 2 19 I 2 X@>

44 47 CAUSE DESCRIPTION ANO CORRECTIVE ACTIONS @

I This problem seems to be a manufacturing defect. See attachment for

[JJJJ 1additional details.

lI.IIla 1 g so FACILITY /'jQI METHOD OF . (.;':;\

STATUS  % POWER OTHER STATUS \.::::,1 DISCOVERY DISCOVERY DESCRIPTION ~

ITIIl IE.J@ I 0 I 9 I 7 l@l....__.N......l....,A.____ ____ Ll2.J~I AE Evaluation a s 10 12 13 44 45 46 80 ACTIVITY CONTENT r::;;-,.

RELEASED OF RELEASE AMOUNT OF ACTIVITY ~ LOCATION OF RELEASE @

[2:EJ ILJ@ ~@I N/A I N/A 1 a s 10 11 44 45 so PERSONNEL EXPOSURES Q.,

.NUMBER ~TYPE t::;;.. DESCRIPTION

[!]2] a s lo lo I ol~l.]J~..._~N~A------------------------------------------------ .....

1 11 12 13 so PERSONNEL INJURIES (.';\

IIII] lo NUMBER lo I ol@> ................

DESCRIPTION6 7 8 9 11 12 so LOSS O" OR DAMAGE TO FACILITY f.i3' TYPE DESCRIPTION '.:::.::;

~ ~@)~N ..........A,,____________________________________________________________.

7 8 9 10 so PUBLICITY Q..

ISSUE DC,;\ DESCRIPTION~ . NRC USE. ON Ly

[ilIJ llLJ~~--N~A--.________________________________________...... I II I I II II I II I 7 8 9 10 68 69 so 5010150501