ML19345D851

LER 80-012/03L-0:on 801202,slippage Found in Shaft Driven Seal Water Pump Impeller Resulting in Overheating of Throttle Bushing.Caused by Reduced Seal Water Flow Due to Loosening of Pumping Ring.Shaft Sleeve & Bushing Replaced

ML19345D851
Person / Time
Site:	Point Beach
Issue date:	12/11/1980
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19345D844	List: ML19345D843 ML19345D851
References
LER-80-012-03L-01, LER-80-12-3L-1, NUDOCS 8012170606
Download: ML19345D851 (2)

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m'NRC F CRM 366 U. S. NUCLEAR REGULATORY COMMISSION (7 776 LICENSEE EVENT REPORT CONTROL BLOCK l l l l l l l (PLE ASE PRINT OR TYPE ALL REOUIREO INFORMATION) 10 l1A 3 l l W LICENSEE l I l P CODEl Bl Hl 142 l@l 15 O l 0 l -l 0LICENSElOl0 ] 0 l O l - l 0 l 240 l@l NUY8ER 26 4 LICENSE l l l 1 lTYPE1l 1l@l JO l

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' 8 NUMBER 14 75 EVENT DESCRIPTION ANO PROBAFLE CONSEQUENCES h 10121 l A routine test of the Unit 2 safety iniection cumo 2P15A at 0448 hours0.00519 days <br />0.124 hours <br />7.407407e-4 weeks <br />1.70464e-4 months <br /> I lol3l lon 12-3-80 revealed a slippage of the shaft driven seal water pump l l o 141 I impeller resulting in the overheating of the throttle bushing. This I lo Isl lresulted in placing one of two safety injection pumps out-of-service. l l o 16 l lThis is a degraded mode of operation reportable under Technical Speci- l J o l 7 l l fication 15. 6.9. 2.B . 2. The safety injection pump was returned to l l a ia i i service upon completion of repairs on 12-03-80. l 7 g g 80 SYSTEV CAUSE CAUSE COMP. VALVE CODE CODE SUSCODE COVPONENT CODE SUSCODE SUSCODE 10191 l S l Fl@ ]@ l B l@ l P l U l Ml P l X l X l@ @@ l Z l @

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33 J4 35 36 J/ c 41 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS l i l o l l Overheating of the throttle bushing was caused by reduced seal water I li l11 I flow due to a loosening of the pumping rina. The shaft sleeve and I iil2; Ithrottle bushing were replaced and a seal replacement kit was installed.l lil3l l After a reduction in power in preparation for shutdown, pump repairs l ii 41l were completed and a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> test run was completed on 12-3-80. l 7 8 9 80 ST S  % POWER OTHER STATUS Di V RY DISCOVERY DESCRIPTION Ii 15 l l E l@ l 0 l 9 l 9l@l N/A l l B l@l Routine inspection l ACTIVITY CO TENT RELEASED OF RELE ASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Ii 168l 9l Z l @ 10l Zl@l N/A l l N/A l 7 11 44 45 80 PERSONNEL EXPOSURES NUM8ER TYPE DESCRIPTION l i l 7 ) l 0 l 0 l 0 l@l Z l@l N/A l

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ATTACHMENT TO LICENSEE EVENT REPORT NO. 80-012/03L-0 Wisconsin Electric Power Company Point Beach Nuclear Plant Unit 2 Docket No. 50-301

, During the inservice test of the Unit 2 safety injection pumps on December 2, 1980, the Auxiliary Operator no* iced the throttle bushing on pump 2P15A was overheating at 0448 hours0.00519 days <br />0.124 hours <br />7.407407e-4 weeks <br />1.70464e-4 months <br />. The pump was secured at 0450 hours0.00521 days <br />0.125 hours <br />7.440476e-4 weeks <br />1.71225e-4 months <br /> and the verification of operability of the remaining safety injection pump 2P15B was completed at 0457 hours0.00529 days <br />0.127 hours <br />7.556217e-4 weeks <br />1.738885e-4 months <br />. This event is reportable under Technical Specification 15.6.9.2.B.2 as a degraded mode of operation. Repairs to the af fected pump were commenced; however, due to the length of time . required, a load reduction to hot shutdown was commenced at 044 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, December 3, 1980, in accordance with the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> requirement of Technical Specification 15.3. 3. A.2. Repairs to the pump were completed at 06'9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> on December 3, 1980, and a one hour test run was began. The load reduction was halted and held at 0633 hours0.00733 days <br />0.176 hours <br />0.00105 weeks <br />2.408565e-4 months <br /> at 260 MWe after 15 minutes of the successful pump test run. At 0718 hours0.00831 days <br />0.199 hours <br />0.00119 weeks <br />2.73199e-4 months <br /> the one hour test run was successfully completed and ascension to full load was commenced at 0729 hours0.00844 days <br />0.203 hours <br />0.00121 weeks <br />2.773845e-4 months <br /> on December 3, 1980, and full power was reached at 0915 hours0.0106 days <br />0.254 hours <br />0.00151 weeks <br />3.481575e-4 months <br /> December 3, 1980.

The cause of the overheating throttle bushing was traced to a decreased seal flow from the shaf t driven seal water pump. This decreased flow was due to a working loose of the pumping ring which is used to drive the seal water pump. Repairs consisted of replacing the shaft sleeve, the throttle bushing and installing a seal replacement kit.

Despite the overheating of the throttle bushing, the pump was evaluated as probably being able to fulfill its safety related function.

Notification to the Nuclear Regulatory Commission was made via the " red phone" when the unit had commenced to be taken off line per the limiting condition for operation.

The resident inspector was notified orally on December 2, 1980.

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