ML20084S394

RO 50-254/76-33:on 761029,while Performing RCIC Sys Pump Operability Surveillance,Discovered That Pump Could Not Achieve Flow & Pressure Required.Caused by Two of Five Stages Being Severely Damaged.Pump Being Rebuilt

ML20084S394
Person / Time
Site:	Quad Cities
Issue date:	11/10/1976
From:	Joyce T, Kalivianakis N COMMONWEALTH EDISON CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20084S382	List: ML20084S379 ML20084S394
References
NJK-76-411, RO-50-354-76-33, NUDOCS 8306160713
Download: ML20084S394 (4)

Text

i' Com nwrith Edimn Quad-Cines Nuc! ear Power Station Past Othee Box 216 Cordova, Ithnois 61242 EFILE CON Telephone 309/654-2241 A 6;

'b A RECG;ED 'O' N DEC 7 1976 u.a. = cu n a m ous NJ K-76-411 NQ @!

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November 10, 1976 J. Keppler, Regional Director Office .of Inspection and Enforcement Region lil U. S. Nuclear Regulatory Commission 799 RooseveIt Road Glen Ellyn, Illinois 60137

Reference:

Quad-Cities Nuclear Power Station Docket No. 50-254, OPR-29, Unit 1 Appendix A, Sections 3.5.E.1 and 6.6.B.l.e Enclosed pleas'e find Reportable Occurrence Report.No. RO 50-254/76-33

- for Quad-Cities Nucidar Power Station. This occurrence was.previously reported to Region ill, Office of Inspection and Enfor~ cement by telephone on October 29, 1976 and by telecopy on November 1, 1976.

This report is submitted to you in accordance with the requirements of Technical Specification 6.6.B.I.

Very truly yours, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION i /

/

// wM/I N. J. Kalivianakis Station Superintendent NJK/LFG/lk cc: G. A. Abrell 1

l 83061607g3}gh4 NOV 15 N PDR ADOC PDR S

P. _ . _ _ .

O LICENSEE EVENT REkT I l

CONTROL BLOCK:l l l l l l l (PLEAftE PRINT ALL REGulRED INFORMATION) 1 6 NAME LCENSE NUMBER PE TY oi l i I t. l 01 Al Dl1 l l0l0l-l0 l0l0l0l0l-b l0 25l l4 l} l1 l1 l} l l0l1l 32 7 89 14 15 26 30 31 CATEGORY DOCKET NUMBER EVENT OATE REPORT DATE TYPE O 1 CONT l l l (LJ l 0 l 5 l 0 l-l 0 l 2 l 5 l 4l l1 l0 l 2 l 9 l 7l 6l lIlIl1l0l7l6l 7 8 57 58 59 60 61 68 69 74 75 80 EVENT DESCRIPTION gg l While performing routine Reactor Core isolation Cooling (RClC) System pump operabi1ityl 7 89 80 35 l surveillance, it was discovered that the pump could not achieve the flow and oressure l 7 89 80 EE I as reautred by Technical Soecification 4.5 E 1. Bv surveillance nrocedure. the numn !

7 89 80 HE I should provide a discharge pressure of 1250 psig at a flow of 400 gpm. The 1250 valuel 7 89 80 gg l accounts for a reactor vessel pressure of 1150 psig, plus line pressure losses l 7 89 pnug 80 CE CODE COMPONENT CODE SUFFUER VOLATION gg l Cl El @ l P l U l Ml Pl X l X l QJ ]B l2 l6 l0 l {48 7 89 10 11 12 17 43 44 47 CAUSE DESCRIPTION ME l (Proximate Cause-Equipment Failure) The pump was disassembled and it was found that l 7 89 80 DE l two of the five stages were severely damaged. The procedure for startina the oumo l 7 89 80 DE l states that the test return valve to the contaminated condensate storace 4see attache S Tu  % POWER 0 HER STATUS OISCOVERY OtSCOVERY DESCRIPTON 1 (E_j l0 l9 l4 l l NA l d45 l Routine surveillance testino l 7 8 9 10 12 13 44 46 80 L 0 0F AMOUNT OF ACTMTY LOCATON OF RELEASE gg lZ l {E EASE l NA l l NA l 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTON gg l 0]O l0 l 8y l NA l 7 89 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTON gg l 0l0 l0 l l NA l 7 89 11 12 80 OFF3lTE CONSEQUENCES NA 39 i l 7 89 80 4 1 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTON 03 d 7 89 l 10 NA 80 l PUBUCITY l DE l NA l 7 89 80 ADDITIONAL FACTORS Q@ l (Event Description contd) and head differential between the RCIC pump discharge and l 7 89 80 U@ l the rencene vessel. The pumo actually delivered 400 com at 1200 osia. (contd) l T. P. Joyce

• NAME: PHONE:

sFo ses. set

p-CAUSE DESCRIPTION continued tank be opened prior to rolling the RCIC turbine. This results in a situation where the pump is started with no resistance to flow. It is conceivable that during this situation, the pump could pump itself dry and the resulting water slug filling the void in the pump would have jolted the two impe11ers loose. After the impe11ers came loose, continuous running of the pump resulted in damage to the two impellers. ADDITIONAL FACTORS Event Description continued An investigation as to the nature of the problem was initiated. Pump discharge flow and pressure instrumentation were calibrated, and all valve positions were verified. A subsequent pump flow rate test, hcwever, revealed that the pump performance was worsening. Since turbine speed was normal, and other system and turbine parameters were observed to be satisfactory, an internal pump problem was suspected. The RCIC System was then declared inoperable and work request 4045-76 was issued to inspect the pump. The High Pressure Coolant injection (HPCI) System was then tested in accordance with Technical Specification 4.5.E.2, and was found to be fully operable. The RCIC turbine-driven pump is required to be operable whenever reactor

  .         pressu,re is greater than 150 psig. In accordance with Technical Specification 3.5.E.2, RCIC may be inoperable for seven days in order for reactor operation to ' contin 6e, if HPCJ is tested immediately*and daily thereafter. Repairs to the pump were started immediately, but' Unit One was shutdown on November 2, 1976 due to ele'ctromatic relief valve problems. An agreement was reached with the NRC which allowed the unit to be started up and subsequently operated with RCIC inoperable, under the stipulation that the HPCI system is demonstrated operable daily. This agreement is in effect from November 6 through November 20, 1976. Since the HPCI system has been demonstrated to be fully capable of performing its intended function in the required manner during the repair period, this occurrence has not resulted in any adverse reactor safety implications.      (RO-50-254/76-33)

Corrective Action to Prevent Recurrence The RCIC pump casing was sent out to the Bingham Pump Co. for rebuilding, and a new rotating element has been ordered. This new element will have snap rings on the first four stages for reinforcement, while the fifth

  .          stage will have two set screws, 1800 apart, for reinforcement. The rotating element for Unit Two will also be changed at the earliest opportunity af ter the new parts are received. To aid in preventing recurrence in the future, a procedure change has been initiated to start the pump with the discharge valve to the condensate storage tank closed, and establish initial flow with the minimum flow valve. To date repairs have not been completed. An Update Report will be submitted upon completion of repairs and operability testing.

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9 .m.0.2 - 4 . I Failure Data _ l This is the first occurrence of this type at Quad-Cities Station whereby the RCIC pump has caused the system to be rendered inoperable. Prior RCIC failures have been related to valves and the turbine. The RCIC pump is a 5-stage horizontal centrifugal pump, manufactured by Bingham Pump Company. ! l 1 l l 1

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