ML18347B207

Licensee Event Report 80-018 Regarding Oil Level in Snubber No. 2 Found to Be Less than Zero During Routine Testing of Hydraulic Snubbers

ML18347B207
Person / Time
Site:	Palisades
Issue date:	06/19/1980
From:	Huston R Consumers Power Co
To:	James Keppler NRC/IE, NRC/RGN-III
References
LER 80-018
Download: ML18347B207 (2)

Text

consumers Power company

• General Offices: 212 West Michigan Ave.nue, Jackson, Michigan 49201

• Area Code 517 788-0550 June 19, 1980 Mr James G Keppler Office of Inspection and Enforcement Region III U S Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255 -LICENSE DPR-20 -PALISADES PLANT -LICENSEEE EVENT REPORT 80-018 -SNUBBER FAILURE On the reverse side is Licensee Event Report 80-018 which is reportable under Technical Specification 6.9.2.B.2.

Rog Senior Licensing Engineer CC Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement NRC Resident Inspector

-Palisades

JUN 2 3 1880 PALISATIES PLANT NRC FORM 366 (7*771 U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT CONTROL BLOCK: I I G) (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6 [£:EJ 7 B I Ml IIPI AIL 111010 I 01-p 10 10 I 010 1-10101014 11111111101 I 10 9 LICENSEE CODE 14 LICENSE NUMBER 25 26 LICENSE TYPE 30. : 57 CAT 58 CON'T ITiiJ 7 B L..!:JG) I o I 5 J o I o Io I 2 I 51 51(?)1 o I 5 12 12 I 8 I o KV I o I 61 1 19 I 8 I o I G) 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE BO EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@

I During routine testing of hydraulic snubbers, the oil level in snubber--... [ill] I No. 2 was found to be less than zero, and the snubber was declared inoperable.

Event reportable per T.S. 6.9.2.B.2 and 3.20. See LER I 80-14 thru 80-16 for similar occurrences.

SYSTEr-...-.

CODE I H1B I@ 9 10 Q LEF.IRO CVENT YEAR v REPORT I 8 I 0 I NUMBER 21 22 CAUSE CAUSE COMP. CODE SUBCODE COMPONENT CODE SUBCDDE L1LJ@ Is I u IP Jo IR I Tl@ QLl@ 11 12 13 16 19 SEQUENTIAL OCCUR REN CE REPORT REPORT NO. CODE TYPE I I 10 111 81 1,..,...1 Io 13 I Li 23 24 26 27 28 29 30 VALVE SUB CODE Ll.J@ 20 l.=l 31 REVISION ND. LQJ 32 80 ACTION FUTURE TAKEN ACTI0'-1 EFFECT SHUTDDWt<

r::;::;., ATTACHMENT NPRD-< ON PLANT METHOD HOURS SUBMITTED FORM ,UB. PRIME COMP. SUPPLIER COMPONENT MANUFACTURER l.IJ@l.2.J@)

W@ W I o I 01 o I o I LIU@ Lll§ 33 3* 35 36 3 7 40 41 42 CAUSE DESCRIPTION AND CORR EC rive ACTIONS @ 43 IB 1211 10 ' 47 [II§] 1The cause of fluid leakage is apparent seal degradation.

The snubber o::ID jwill be disassembled to confirm the cause. ITEl 1 e 80 F,_C1L1-:-Y f:jQ\ STATUS 'i. POWER OTHER STATUS GE l.£l@ I b I 0 I 01@ ..... I _N_A ____ __. B 9 10 12 13 ACTIVITY C:JNTENT (.;.;\ RELEASED OF RELEASE AMONUl'jT OF 8IJ

___ A ____ __, a 9 10 11 METHOD OF r::;::;., DISCOVERY DISCOVERY DESCRIPTION

'2Y 45 46 80 NA LOCATIOt<

OF RELEASE @ 45 BO PERSONNEL EXPOSURES

(.;;;\ NUMBEP. (.;::;\TYPE DESCRIPTION DJ2J I 0 I 01 0

_______________________

__. 7 B 9 11 12 13 80 PERSONNEL INJURIES Q NUMBER

[2JZ] I 01 OIOl@)L-___ N_A ___________

7 B 9 11 12 ao LOSS Q< OR DAMAGE TO FACILITY 0 TYPE DESCRIPTION GTIJ U_j@ NA 7 B 9 10 so PUBLICITY r,;-.. NRC USE ONLY ISSUEDQ LN..16......._

_____

II II I I I I I I I I I 8 9 10 68 65 BO