Information Notice 1993-84, Determination of Westinghouse Reactor Coolant Pump Seal Failure

Determination of Westinghouse Reactor Coolant Pump Seal Failure

ML031070307
Person / Time
Site:	Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant
Issue date:	10/20/1993
From:	Grimes B K Office of Nuclear Reactor Regulation
To:
References
IN-93-084, NUDOCS 9310140192
Download: ML031070307 (16)

UNITED STATESNUCLEAR'REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555October 20, 1993NRC INFORMATION NOTICE 93-84: DETERMINATION OF WESTINGHOUSE REACTOR COOLANTPUMP SEAL FAILURE

Addressees

All holders of operating licenses or construction permits for pressurizedwater reactors (PWRs).PurDoseThe U.S. Nuclear Regulatory Commission (NRC) is'issuing this informationnotice to alert addressees to a potential problem that could result from theuse of Westinghouse-designed reactor coolant pump (RCP) shutdown proceduresfor pumps whose No. 1 seals have failed. It is expected that recipients willreview the information for applicability to their facilities and consideractions, as appropriate, to avoid similar problems. However, suggestionscontained in this information notice are not NRC requirements; therefore, nospecific action or written response is required.BackgroundWestinghouse supplied the Braidwood Station RCPs, incorporating a three-stageseal series arrangement to limit coolant flow up the pump shaft. The No. 1seal, the main seal of the pump, is a controlled-leakage, film riding faceseal. The No. 2 and No. 3 seals are rubbing face seals. During normaloperation, an injection flow of nominally 30.3 liters [8 gallons] per minuteenters the pump below the No. 1 seal (see Attachment 1). Here the flowsplits. A portion (approximately 18.9 liters [5 gallons] per minute) flowsdown through the thermal barrier heat exchanger and enters the reactor coolantsystem. In this manner, the primary coolant is prevented from entering theradial bearing and seal section of the pump unit. The remainder (11.4 liters[3 gallons] per minute) (controlled leakage) passes through the pump radialbearing and enters the No. 1 seal. Above the No. 1 seal, most of the flowleaves the pump through the No. 1 seal leakoff line and returns to thechemical and volume control system. Minor flow passes through the No. 2 sealand its leakoff line to the reactor coolant drain tank. A back flushinjection of 0.8 liters [0.21 gallons] per hour from a head tank flows intothe No. 3 seal between its "double dam" seal area. At this point, half of theflow passes through one side of the seal and out the No. 2 seal leakoff linewhile the remaining flow passes through the other side and out the No. 3 sealleakoff line. This arrangement ensures essentially zero leakage of reactorcoolant from the pump.9310140192 o W q 3.O3;Afe4% ;IivftC IN 93-84Octoer 20, 1993 During normal operation, the No. 1 seal is subject to full reactor coolantsystem pressure. When the injection flow passes through the No. 1 seal, itproduces a pressure drop of approximately 15.41 MPa [2235 psi]. The No. 2seal has the capability to withstand full operating pressure, and its majorfunction is to act as a backup in case the No. 1 seal fails. If the No. 1seal fails, leakage through the No. 2 seal increases. The No. 2 seal highleak flow alarm actuates at 3.8 liters [1 gallon] per minute.

Description of Circumstances

In the middle of 1992, while developing shutdown procedures for the RCPs atthe Braidwood Station, Commonwealth Edison Company (the licensee) found thatits abnormal operating procedure contained inadequate instructions forresponding to a failure of the RCP No. 1 seal. On a high RCP No. 1 sealleakoff condition, the abnormal operating procedure directed the operatingpersonnel to check the condition of the No. 2 seal. If the No. 2 seal wasacting as the primary pressure boundary on the basis of leakage of at least3.8 liters [1 gallon] per minute from the No. 2 seal, the procedure requiredthat the RCP be shut down. If the condition of the No. 2 seal was normal, theprocedure required no further action and gave no further guidance.Discussions with Westinghouse indicated that the condition of the No. 2 sealmight not be a sufficient indication of the operability of the No. 1 seal.DiscussionThe inadequacies in the operating procedure stem from the limitations of theinstrumentation used to monitor the leakage. The relevant No. 1 sealinstrumentation limits maximum readings to 22.7 liters [6 gallons] per minute.Although the No. 2 seal high leak flow alarm was set at 3.8 liters [1 gallon]per minute, very high No. 1 seal leak rates, more than 113.6 liters(30 gallons] per minute, are needed for the No. 2 seal to reach this flowrate. Thus, the No. 1 seal could have substantial leakage (e.g., 22.7-113.6liters (6-30 gallons] per minute) even though the No. 2 seal high leak flowalarm was not actuated. In the mean time, the RCP seal system might beseverely damaged if loss of injection were to occur or the No. 1 seal leakrates were more than 30.3 liters [8 gallons] per minute. Therefore,monitoring for high No. 2 seal leakage is not a reliable method of determiningwhether the No. 1 seal has failed.After finding that the condition of the No. 2 seal might not indicate theoperability of the No. 1 seal, Westinghouse provided guidance for theBraidwood Station that significantly enhances operator ability to determine ifimmediate shutdown of an RCP is required or if a more orderly shutdown can beconducted. Westinghouse completed a safety evaluation and issued TechnicalBulletin, NSD-TB-93-01-RO, "Revised Procedures for RCP Shutdown with No. 1Seal Leakage Outside Operating Limits," dated March 30, 1993, to other PWRsthat might be affected. An excerpt from this document is attached to thisinformation notice (see Attachment 2).

IN 93-84October 14, 1993 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactone of the technical contacts listed below or the appropriate Office ofNuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts: Steve DuPont, RIII(815) 458-2852Martin Farber, RIII(708) 790-5774Chu-Yu Liang, NRR(301) 504-2878

Attachments:

1. Simplified Braidwood Seal Water Injectionand Leakoff Flow Diagram2. Excerpt from Westinghouse TechnicalBulletin, NSD-TB-93-01-RO, "RevisedProcedures for RCP Shutdown with No. 1Seal Leakage Outside Operating Limits"3. List of Recently Issued NRC Information Notices 2=."I 'I'TO SEAL WATER HAT EXCHANGERCO IrRo.D myLEVEL IN STAOPIPETOREGENERATIWE1HEATEXCHANGERDR DRAIN IIMPgo 0 Zrtaq ct(D j xD Om 00 MS0 tI-'.II-h' LAl -NIN sAN ThERLARRHER HEAT EXCHANGERF"U.t,&IDwSIMPLIFIED BRAIDWOOD SEAL WATER INJECTION AND LEAKOFF FLOW DIAGRAM I>Attachment 2IN 93-84October 20 1993Page 1 of INuclearServicesDivisionWestinghouseTechnical BulletinAn advisory notice of a recent technical development pertining to th- irts.ation or operation of Wastghous&suppi*d NudrPlant equipment. Recipients shouSd evaluate the Information and recomnM aIRonl, and initite action wh-r aomopriabt.P.O. SOX 35, Pltttxzu PA 15oSubject REVISED PROCEDURES FOR ROP SHUTDOWN WITH NO.'.FAl I FAKA(LF OUTSIDE OPERATING UMITS.oNSD-TB- 93-01-ROSystem(s) REACTOR COOLANT SYSTEM Date 03r3/9PLant ALL WESTINGHOUSE REACTOR COOLANT PUMPS WITH lr SO(s) 125CONTROLLED LEAKAGE SEALS (See Aftacivelt B)References _- -- C , .nA~. cten Is Safety Related Yes 0 Page 1 Of 8h M L) rilv Vl..I Vr-ij' 1 Q %- W I E2o m e t adgqNo O1

BACKGROUND

Years of Westinghouse RCP operating experience has demonstrated that complete failure of the No. 1seal is a rare occurrence. A complete failure is defined as excessive No. 1 seal leakage in conjunctionwith pump bearing/seal inlet and/or No. 1 leakoff temperatures approaching or exceeding the maximumlimits. Current operating procedures for failed No. 1 seals direct that the No. I seal leakoff be isolatedwithin 5 minutes and RCP shutdown witlin 30 minutes. These procedures are specified in the RCPinstruction books or addenda to the books.After a review of current operating procedures and actual operating experiences with high and low leakingNo. 1 seals, it was concluded ftht distinct procedures could specify steps for both emergency and orderlyRCP shutdowns. The two iems that follow have been incorporated into the revised procedures in thistechnical bulletin. As used within this bulletin, the term 'emergeflym refers to a condition that is relatedonly to RCP operation and in no way pertains to emergency conditions for plant operation as defined ina plant hnal Safety Analysis Report (FSAR).I) A damaged No. 1 seal may produce debris or leak at a high enough rate to exceed theinjection rate and introduce unfiltered, high temperature reactor coolant into the seals. In thepresence of debris. the ability of the No. 2 seal to survive and function as a backup for theNo. 1 seal is more favorable under static conditions. Thus, it is preferred to have pumpshutdown precede No. 1 seal leakoff isolation.AJol" W omutfi. Flequd. may be Obhuned fron @fe 0rawc Teb hoffl 412- 963-5634 or (W) 29-5634Appmvi.T. W. Dunn, Manager, Fied Service & RCP EngineerngL J. HaperEner Systes Saes Suport'q7- -t-. NR. F pleiter. mwnA~e CR 4 -& Seal Engineainat tr* gwonmul)Of corame in W"t "Pon or -an wy reqpo-"kdy 1b "ik&ym dafiQ$ ~iC flf umastamtom am of mooh irdofflo Attachment 2IN 93-84October 20, 1993 NSD-TB-93-01-RO ) High No. 1 seal leakage (> 6.0 9pm) or low No. 1 seal leakage (< 0.8 gpen) can occurwhile no other RCP parameter limits are approached or violated. In these cases. pumpshutdowns within several hours are within the capabilities of the RCPs and are moreconducive to orderly plant shutdowns.The following new procedures are provided to address each of four conditions that irncate No. 1seal flow outside of the operating limits (0.8-6.0 gpm). The first three conditiors address highNo. I seal leakage and the fourth condition addresses low leakage. Each condition with itsrespective procedure is specified below and is summarized in Attachment A.PROCEDURESThe following procedures supersede those in the RCP instruction books or addenda to the booksrelative to:1) RCP emergency operation and shutdown procedures for high or low No. 1 sealleakage. Apply the Conditions 1 through 4 procedures that follow.2) RCP emergency operation and shutdown procedure for No. 2 and No. 3 seals. Applythe procedure for shutdown specified under Condition 1 below. The No. 2 and No. 3seal parameters tat indicate emergency operation remain the same as specified inthe RCP instruction books.Definitions:No. 1 seal leakoff indication: Flowmeter readout of No. 1 seal leak rateNo. 2 seal leakoff indication: Flowmeter readout or estimate of No. 2 seal leak rateTotal No. 1 Seal Flow: Sum of No. 1 and No. 2 seal leakoff indicationsImmediate Shutdown: RCP shutdown and isolation of No. 1 seal leakoff within5 minutesOrderly Shutdown: RCP shutdown within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of higtow No. 1 seal leakoffflow indicationNOTE; A manual plant trip must precede an "Emergency or 'Ordery RCP shutdown. This willprevent an automatic plant tip on a low flows signal which represents an unnecessarychallenge to installed safety system Attachment 2IN 93-84October 20, 1993 NSD-TB-93-011-RO If no alternative Westinghouse direction has been provided to address a specfic RCP sealperformance condition at a plant, the following are the recommended shutdown procedures forNo. 1 seal leak rates outside the operating limits (08-6.0 gpm).Condition 1:a) No. 1 sea leakoff indication > 6.0 gpcn.b) Increasing pump beanngfseal inlet temnperature.and/orincreasing No. I seal leakoff temperature.Procedure:1)Shut down the RCP immediately.2) Isolate the No. 1 seal leakoff after the RCP has come to a complete stop.3) Monitor component cooling water (CCW) to ensure adequate flow andmanually override automatic isotation as required. (Local boiling in thethermal barrier of the affected pump may cause isolation of the CCWsystem.)4) Do not restart the pump until the cause of the seal malfunction has beendetermined and corrected.Condition 2;a)No. I seal leakoff indication > 6.0 gpm.andforTotal No. 1 seal flow > 6.0 gpm and < 8.0 gpm.b) Ppump bearing/seal inlet temperature is not increasing.c) No. 1 seal leakoff temPerature (if equipped) is not increasing.Procedure: 1)Prepare for an orderly pump shutdown to take effect within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ofexceeding 6.0 gpm No. I seal flow. Ensure that seal injection flow rate is9 gpm or greater to the affected RCR Attachment 2IN 93-84October 20, 1993 NSD-TB-93-o -RO ) Continue to monitor the No. 1 seal for further degradation durng the orderlyshutdown. If the total No. 1 seal flow exceeds 8.0 gpm or temperaturesbegn to increase, proceed with immediate shutdown in accordance withthe Condition 3 procedure. Otherwise, proceed with the orderly shutdown.3) Secure the pump within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of exceeding a No. 1 seal eamkof indicationor total No. 1 seal flow of 6.0 gpn.4) Moritor component cooing waler (CCOW to ensure adequate flow andmanually override as required. (Local boiling in the thermal banier of theaffected pump may cause isolaton of the CCW system.)5) No. I seal leakoff may be isolated at the discretion of operations to mitigateinventory loss and to assure that seal injection flow exceeds total No. 1 sealflow on the affected pump.6) Do not restart the pump until the cause of the seal malfunction has beendetermined and corrected.Condition 3: a) Total No. 1 seal flow x 8.0 gpm.Procedure: 1) Shut down the RCP immediately.2) Isolate the No. 1 seal leakoff after the RCP has come to a complete stop.3) Monitor component cooling water (CCW) to ensure adequate flow andrnanaly override automatic Isolation as required. (Local boiling in thethermal banier of the affected pump may cause isolation of the CCWsystem.)4) .Do not restart the pump until the cause of the seal malfunction has beendetermined and corected.Condition 4: a) No. I seal leakoff indication c 0.8 gpm.b) Zero (or negligible) No. 2 seal leak rate such that total No. 1 sealflow < 0.8 gprn.c) Pump bearingfseal inlet temperature and No. 1 seal leakoff temperature(if equipped) are stable (i.e.. not coninuously increasing) and within limit Attachient 2IN 93-84October 20, 1993 NSD-TB-93"01-RO Procedure: 1) Prepare for an orderly pump shutdown to take effect within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ofviolating the rninimum 0.8 No. 1 seal leak rate Knit2) Continue to monitor the No. 1 seal for further degradation duing theorderly shutdown. If the bw No. 1 sa lealkge reverses to high leakage(> 6.0 gpim) or temperatures start to increase, proceed with immeciateshutdown in accordance with the Condcion 1 procedure. Otherwise,proceed with the orderly shutdown.3) Secure the pump within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of violasts the rnirnmum 0.8 No. 1 seal leakrate limit.4) Do not restart the pump until the cause of the seal malfunction has beendetermined and correcte ATTACHMENT ANo. 1 Leakotf No. 2 Leakoft Total Pump Bearing/SealCondition Indication Indication No. 1 Seal Flow Inlet and/or RCP ShutdownNo. 1 Leakoff Temp.1 > 6.0 gpm > 6.0 gpm Increasing Immediate(wilhin 5 minutes)2 > 6.0 gpm > 6.0 and < 8.0 gpm Stable Orderly(within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />)3 > 8.0 gpm Stable or Immediateincreasing (within 5 minutes)4 < 0.8 gpm zero < 0.8 gpm Stable Orderly(or negligible) (within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />)Note:Total No. 1 seal flow a No. 1 leakoff plus No. 2 leakoff indications(00q40oz3IFwoI'dPz nMD 0a% ID00'-P-a(J.%Drt*r1-U) 0i2w~,r Attachment 3IN 93-84October 20, 1993 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to93-83Potential Loss of SpentFuel Pool CoolingFollowing A Loss ofCoolant Accident (LOCA)10/07/93All holdersfor boiling(BWRs).of OLs or CPswater reactors93-8293-8193-8093-7993-7893-7793-7693-75Recent Fuel and CorePerformance Problems inOperating ReactorsImplementation ofEngineering Expertiseon ShiftImplementation of theRevised 10 CFR Part 20Core Shroud Cracking atBeltline Region Weldsin Boiling-Water ReactorsInoperable Safety SystemsAt A Non-Power ReactorHuman Errors that Resultin Inadvertent Transfersof Special NuclearMaterial at Fuel CycleFacilitiesInadequate Control ofPaint and Cleaners forSafety-Related EquipmentSpurious Tripping ofLow-Voltage Power CircuitBreakers with GE'RMS-9Digital Trip Units10/12/9310/12/9310/08/9309/30/9310/04/9310/04/9309/21/9309/17/93All holders of OLs or CPsfor nuclear power reactorsand all NRC-approved fuelsuppliers.All holders of OLs or CPsfor nuclear power reactors.All byproduct, source, andand special nuclear materiallicensees.All holders of operatinglicenses or constructionpermits for boiling-waterreactors (BWRs).All holders of OLs or CPsfor test and researchreactors.All nuclear fuel cyclelicensees.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.OL = Operating LicenseCP = Construction Permit IN 93-84October 14, 1993 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactone of the technical contacts listed below or the appropriate Office ofNuclear Reactor Regulation (NRR) project manager.Original signed bYBrian K. GrimefBrian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts:Steve(815)DuPont, RIII458-2852Martin Farber, RIII(708) 790-5774Chu-Yu Liang, NRR(301) 504-2878

Attachments:

1. Simplified Braidwood Seal Water Injectionand Leakoff Flow Diagram2. Excerpt from Westinghouse TechnicalBulletin, NSD-TB-93-01-RO, "RevisedProcedures for RCP Shutdown with No. ISeal Leakage Outside Operating Limits"3. List of Recently Issued NRC Information Notices*SEE PREVIOUS CONCURRENCEOFFNAMEDATE*OGCB:DORSPCWen07/26/93*SRXB:DSSACYLiang07/26/93*SRI:DRP:RIIISGDuPont07/26/93*TECH EDMMejac07/27/93*SC/DRP:RIIIMJFarber07/29/93*D/DSSAACThadani09/23/93*C/DRP:RIIIBClayton07/29/93*C/OGCB:DORSGHMarcus09/28/93*SC/SRXB:DSSAMACaruso08/05-93.4:;tes10// r 93*C/SRXB:DSSARCJones08/09/93DOCUMENT NAME: 93-84.IN IN 93-xxOctober xx, 1993 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactone of the technical contacts listed below or the appropriate Office ofNuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts:Steve DuPont, RIII(815) 458-2852Martin Farber, RIII(708) 790-5774Chu-Yu Liang, NRR(301) 504-2878

Attachments:

1. Simplified Braidwood Seal Water Injection and Leakoff Flow Diagram2. Excerpt from Westinghouse Technical Bulletin, NSD-TB-93-01-RO, "RevisedProcedures for RCP Shutdown with No. 1 Seal Leakage Outside OperatingLimits"3. List of Recently Issued NRC Information Notices*SEE PREVIOUS CONCURRENCEOFFNAMEDATE*OGCB:DORSPCWen07/26/93*SRXB:DSSACYLiang07/26/93*SRI:DRP:RIIISGDuPont07/26/93*TECH EDMMejac07/27/93*SC/DRP:RIIIMJFarber07/29/93*C/DRP:RIIIBClayton07/29/93*SC/SRXB:DSSAMACaruso08/05/93*C/SRXB:DSSARCJones08/09/93*D/DSSAACThadani09/23/93DOCUMENT NAME:C/OGCB:DOi,_ D/DORS PcEYGHMarcu$s& !:' BKGrimesng P4it P (so-.-qI),MAMWRCPSEAL.We 0fFnfS T HE 049 /9o o3eevat lro1hE NftC 41TA03rA* THS g*Sr*qWSC _ %,A _ } U. .O ' 0a* W S~--.W""i r. MOFbV4' ( H& S5ef ) vvia %;nfgnri& dr i tw LWI44n44t et-K'%$ U -te pnvi.d %e ,W Tec6-,.p^ MoTtwcdL. ?et hk~

IN 93-xxSeptember xx, 1993 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactone of the technical contacts listed below or the appropriate Office ofNuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating ReactorSupportOffice of Nuclear Reactor RegulationTechnical contacts:Steve DuPont, RIII(815) 458-2852Martin Farber, RIII(708) 790-5774Chu-Yu Liang, NRR(301) 504-2878

Attachments:

1. Simplified Braidwood Seal Water Injection and Leakoff Flow Diagram2. Excerpt from Westinghouse Technical Bulletin, NSD-TB-93-01-RO, 'RevisedProcedures for RCP Shutdown with No. 1 Seal Leakage Outside OperatingLimits'3. List of Recently Issued NRC Information Notices*SEE PREVIOUS CONCURRENCEOFFNAMEDATE*OGCB:DORSPCWen07/26/93*SRXB:DSSACYLiang07/26/93*SRI:DRP:RIIISGDuPont07/26/93*TECH EDMMejac07/27/93*SC/DRP:RIIIMJFarber07/29/ AFD/DSS ai' _ACThadani09/2_/93DOCUMENT NAME:*C/DRP:RIIIBClayton07/29/93C/OGCB:DORSGHMarcus09/ /93WRCPSEAL.WEN*SC/SRXB:DSSAMACaruso08/05/93*C/SRXB:DSSARCJones08/09/93D/DORSBKGrimes09/ /93 Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts:Steve DuPont, RIII(815) 458-2852Martin Farber, RIII(708) 790-5774Chu-Yu Liang, NRR(301) 504-2878

Attachments:

1. Simplified Braidwood Seal Water Injection and Leakoff Flow Diagram2. Excerpt from Westinghouse Technical Bulletin, NSD-TB-93-01-RO, 'RevisedProcedures for RCP Shutdown with No. 1 Seal Leakage Outside OperatingLimits"3. List of Recently Issued NRC Information Notices*SEE PREVIOUS CONCURRENCEOFF *OGCB:DORS *SRXB:DSSANAME PCWen CYLiangDATE 07/26/93 O7/26/93STW RD I :I I C/R J.:RIIIMJFarber 4 BClayton07ial/93 J 07/< /93we 74FCoo .7,6/93D/DSSA C/OGCB:DORSACThadani GHMarcus07/ /93 07/ /93*SRI:DRP:RIIISGDuPont07/26/93,JSRXB:DSSAC ones?/ /93*TECH EDMMejac07/27/93SC/SRXB:DSSALMACaruso `y rr/4r/93 / rD/DORSBKGrimes07/ /93

\s-/Martin Farber, RIII(708) 790-5774Chu-Yu Liang, NRR(301) 504-2878

Attachments:

1. Braidwood Seal Water Injection and Leakoff Flow Diagram..r-2. Excerpt from Westinghouse Technical Bulletin, NSD-TB-93-01-RO, "RevisedProcedures for RCP Shutdown with No. 1 Seal Leakage Outside OperatingLimits"3. -List-ef Recently IssueFd4RC-4nf-4fmation.-Not-ies-.-OFFNAMEDATEOCB:DORSPCWen07/a6/93SRXB L SA S I RIIICYLiang _ SGDuPont MR-07/;xb/93 V~ 07/Vb/93 T1-e'A.@TECH EDMMejac *Mi 07/1.7/93SC/SRXB:DSSAMACaruso07/ /93SC/DRP:RIIIMJFarber07/ /93C/DRP:RIIIBClayton07/ /93C/SRXB:DSSARCJones07/ /93D/DSSAACThadani07/ /93C/OGCB:DORSGHMarcus07/ /93D/DORSBKGrimes07/ /93! .