ML20011D777

10CFR50.59 Evaluation of Reactor Coolant Pump Seal Retrofit at San Onofre Nuclear Generating Station 2 & 3

ML20011D777
Person / Time
Site:	San Onofre
Issue date:	01/21/1986
From:	AEA O'DONNELL, INC. (FORMERLY SMC O'DONNELL, INC.
To:
Shared Package
ML19310C572	List: ML19310C571 ML20011D748 ML20011D777 ML20011D778
References
NUDOCS 8912280414
Download: ML20011D777 (15)

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SOUTHERN CAllFORNI A EDISON COMPANY REACTOR COOLANT PUMP 10CFR50.59 EVALUATION OF REACTOR COOLANT PUMP SEAL RETROFIT AT SONGS 82 AND 83 l

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ENGINEERING DLflGN Cr ANALYSIS SERVICES 241 CURRY HOLLOW ROAD PITTSBURGH, PENNSYLVANIA tStae (412) 655 1200 (412) 6534110 Twx 7to.cer.4eev 8912280414 891227 DR ADOCK 05000, 1

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SOUTHERN CALIFORNIA EDISON COMPANY REACTOR COOLANT PUNP 10CFRSO.59 EVALUATION OF REACTOR COOLANT PUNP SEAL RETROFIT AT SONGS #2 AND #3 l

The reactor coolant pumps at Songe #2 and #3 have been refitted with Singhen W111aaette (B.V.).seele drawing, Reference 5, replacing seale initially furnished by Byrom Jackson (8.J.), Referemos 6.

l The design philosophy and general configuration of the original B.J.

and retrofit 8.W. seals are very stallar.

Significaat design differences j

and characteristice that affect the perioreasse of the osale and that relate to the comettaente in the Sea Daofre 2 and 3 PEAR (updated) 2/45 are described and evaluated hereia.

Both Byron Jackson and Singhes Willamette esploy three breakdown seale in series followed by a vapor seal.

Each breakdova seal is bypassed by a i

pressure breakdova soil which permits controlled leakage blood off to I

maintain an approminately-equal pressure drop acrose each seal and to previde for seal cocling water.- Pertinent design details of the two seale are compared in Table I.

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e 1729-400-003-00 PAGE 2 0F 14

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Reference 1.

Specification 41-9312 (S023-922-196), ' Technical Requiremente Reactor Coolant Pump Seal Replacemente, San Onofre Nuclear Generating Station Unite 2 & 3,* Table I and Table II.

Reference 2.

San Onofre 2 and 3 FSAR (Updated) 2/85, Revision 1,

[

Component and Subsystem Design.

i-1 I-Reference 3.

Parte List for Mechanical Shaft Seal Type RCR-9508-3V.

Ref.

dvg. R-7305 i

Reference 4.

Byron Jackson Report TCF-1025-STR-Vol. 3, Rev. O. Heat i

Exchanger Analyses for SCE.

Reference S.

Binghan Willamette Drawing R-7305-C 950 5-3 Seal Retrofit.

l Reference 6.

Byron Jackson Drawing 1P7530-1, (SCE Drawing 23-922-$0-05?.

'36 x 36 s 38 DPSS Reactor Coolant Pump.*

Reference 7.

SCE Test Data 2PE-211-02, Rev. O, Retest No.

1,.' Loos of I

Cooling Water to a Singhas Boiler Circulation Pump Rochaatcal Shaft Seal Demonstration Test at Alamitee Unit 3 (Pump Opersting),* November 1, 1945.

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Reference 8.

Singbas Willamette Report E 12.S.146,.' Post Test Inspection for Loss of Cooling Test,* performed on November 1, 1945.

Reference 9.

O'Donnell Report ODAI-1729-400-001, 'RCP Pump Neat Eschenger Performance During Loos of Cooling Incident for Southern California Edison Company Reactor Coolant Pump Seal Replacement, San Onofre Euclear Generating Station Unite 2 and 3.*

1729-400-003-00 PAGE 3 0F 14

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l Reference 10.

O'Donnell Report, ODAI-1729-400-002, ' Southern California Edison Company SONGS 2 and 3 Reactor Coolant Pump Seal Retrofit Analysis.'

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Reference 11.

ASME Paper 80-C2/PVP-24, San Francisco California Conference, August 12-15, 1980, ' Loos of Component Cooling Water Capability of a PWR Reactor Coolant Pump.*

Reference 12.

Kalei Engineering, Inc. Report, '0-Ring Static Seal Performance Evaluation under Loss of Component Cooling Water to Reactor Coolant Pump at SONOS Unite 2 and 3* Dated January 9, 1986.

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TABLE I COMPARISON OF SINGHAM WILLAMETTE REPLACEMENT SEAL WITH THE ORIGINAL SYRON JACKSON SEAL PROVIDED FOR SONGS 2 AND 3 BYRON JACKSON 36 X 36 X 38 DFSS REACTOR COOLANT PLMPS (SOUTHERN CALIFORNIA EDISON DRAWING S023 922-50-05)

J SINGMAN WILLANETTE BYRON JACKSON REPLACENENT SEAL ORIGINAL SEAL 1

Seal Type Breakdown Breakdown Seal Construction Cartridge Cartridge Number of Seale 4e 4e (eThree breakdova seale in series with a final vapor seal)

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Nominal Operating Pressure 2250 poil Notmal Delta Pressure Stage 1 to Stage 2 m 733 peit a 750 poi mest Normal Delta Pressure Stage 2 to Stage 3 m 733 poi s 750 poi east Normal Delta Pressure Stage 3 to Vapar Semi a 733 poit a 750 poi seu2 Vapc' Seal Seok Pressure 35-70 poial 25-250 point Decipe Preen. ?e (Each Seal) 2,445 peigt 2,500 pett Controlled Leo p e Sleed off

-(Nominal) 1.5 i.05 spot-1.0 spe9 Seal 7ype Face Face Seal Noterials Notor Kennasetal Sr. K8011 Titanius Carbidet Stator Norganite Grade CNFJ3 Carbon or Graphiteac s

(Note) Kennaaetal Gr E801 is a proprietary grade of Tungsten Carbide and Norganite Grade CNFJ is a proprietary grade of solded oarbon.

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Superscripte 1-4 refer to references on page 3.

1729-400-003-00 PAGE 5 0F 14

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It can be seen from the comparison table and the referenced drawings that the Byron Jackson original seal and the Singhan Willamette retrofit are very similar in design philosophy and eateriale utflized.

The Byron Jackson seal is further defined by Syron Jackson Drawing, Reference 6, showing the original design.

Singhee Willamette Drawing, Reference 5, shove the design of the retrofit seal.

There are differences in detail which impact the relative performance t

of the two seals.

These are treated in the following paragraphs which address the cometteents for SONOB 2 and 3 in the order presented la the FSAR.

The paragraphs addressed are found starting at 5.4-3 of the Component and Subsystes Design section of the Sea Onofre 2 and 3 FSAR -

updated 2/85 (Revision 1), Reference 2.

i I

l It is first noted that the change covered by this docuseet is the direct replacement of the original Byrom Jackson seal cartridge with the 4

j retrofit Binghan Willamette seal cartridge in the esisting Byron Jackson SONGS 2 and 3 Reactor Coolaat Pumps.

All other parts of the Beactor Coolant Pump and Notor assembly reesta the same for purposes of this

+

evaluation.

The following evaluation statessats oseoeratag the retrofit l

Binghas Willamette seal are keyed to the respective FSAR paragraphs addrecoing the Byron Jackson original tastellation.

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The Singhas Willamette seal esploys controlled bleed off around the l

seals both for cooling and to equalise the pressure drop acrose each sesi as in the original Syrom Jackson design.

Singhee villamette, as spea from Table I employs 1.5 1.05 spe blood-off flow compared to 1.0 spe for the I

Byron Jackson seal.

This differosos provides more effective cooling of the replacement sosis during normal operation.. Novever, during a thirty staute lose of cooling water incident or a two hour statica lose of off-site power, the higher blood-off flow will result la a more rapid tosperature i

I 1729-400-003-00 PAGE 6 0F 14

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rise through the replacement seal.

This change has been addressed by both analyses and by test and is treated below.

FSAR ooeniteents and rtatements that are modified by the application of the Singhee Willamette retrofit seal are addressed below in sequence as i

they appear in the San Onofre 2 and 3 FSAR, updated ' Component and Subsystem Design

• esction.

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5.4-3 Paragraph 3.

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As in the originally designed B.J. seals, the retrofit Bit.,hae Willamette seal cartridge is cooled by controlled leakage blood off which in turn is cooled by the heat exchanger that is integral with the pump.

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has been shown, however, by the test results (Reference 73 and analyses (Reference 103 that the retrofit seals can operate for thirty stautes without cooling vetor to the heet exchanger with no significant damage or increase in seal leakage.

This was clearly demonstrated by the test run on the Binghen Willamette boiler circulating pump (4 1/2' seal) oceducted at the SCE Co. Alsattes Station on November 1,1985, (Beieronoe 71, and as supported by 00&I Evaluations, (Reference 9 and Referenos 103.

The SCE test results are available as SCE Test Data #2PE-211-02 Ree. O, (Reference 71 and the results of the seal evaluation following the test are published in Singhee Willamette test report, Reference 4.

In summary, eassination of the 4 1/2" seal following a thirty minute loss of oooling test showed that it vae in such good condition that it could have continued to operate without cooling water for an entended period of ties, (Reference 81.

5.4-5 Section 5.4.1.3 Paragraph 4 The tests referred to by this paragraph of the FSAR dated 2/45, as run by Byron Jackson, continue to apply to the pump motor (which has not been changed) since the seal retrofit has essentially no impost on motor load or 1

l 1729-400-G03-00 PAGE 7 OF 14

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i performance over the original Byron Jackson results.

The second test,.

however, which describee the operation of the 36 x 36 x 34 DFSS Reactor Coolant Pusp with the original Byron Jackson cartridge seal is not I

applicable to the Singhes Villamette seal.

In place of that test, a test was run at Southern California Edison Alesitos Station on November 1, 1945.

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This test to described in detail and results are reported by SCE Report, Reference 7, and by Singhaa Willamette poet test evaluation report.

l Reference 4.

The test veo conducted on a boiler circulation pump handling

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630*F veter at 2,300 poi that vee subjected to a loss of oooling veter l

incident.

The test pump employed a cartridge seal utilizing the improved elastomers and the ones design factors as applied to the 50508 2 and 3 reactor coolant pump retrofit.

This ses11er pump seal (4 1/2' seal face diameter vs. a 9 1/2' seal diameter for SOE05 2 and 3) was then subjected to the ease inoostag controlled leakage bleed-off flew temperature ramp a

l that the replacement SONGS 2 and 3 seslo will esperience in a loss of cooling water incident.

The ramp had been calculated using data from the

5. J. heet exchanger analysis report, Reference 4.

A further verification of the analysis to provided by ASME Paper, Referense 11. -The calculation

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I of the temperature rase of the primary water estertag the SOSIN 2 and 3 RCPe and used for this test is documented in O'Donnell and Associates report, Reference 9.

The results of the 4 1/2' boiler circulating pump seal test are contained in SCE Report, Reference 7, and the results of essataatica of the seal following the test are contained la Singham Willamette Report,-

Reference 8.

The test clearly demonstrates that the 4 1/2' diameter seal operated without definable performance degradation or increase la leakage for a full thirty minutes.

This test followed an additional period of one and one half hours of operation without cooling vetor during which the pump seal case up on a olover ramp to an operating temperature in the 430' to 300'F l

1729-400-003-00 PAGE 4 0F 14 L...

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b range.

It le noted that the pump was operating during the above tests in a boiler recirculating loop at 650'T and a noainal pressure of 2250 peig.

The temperature ramp of the controlled leakage blood off water following a lose of cooling vetor le shown for the various seal stages of the Boiler Circulation Pump 4 1/2' seal by DDAI Report, Reference 9.

The

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l respe for_each of the successive seal stages are calculated for the full size 9 1/2' diseeter seal used for retrofit in SONOS 2 and 3 in Reference l

10.. The reduced ties at temperature of the full size (9 1/2') seal l

provideo significaat conservatise in applying the 4 1/2' circulating pump i

seal test results to the larger RCP seal.

This is of course clear since seal failure is associated with esposure of the elastomer 0-riage t9 high temperature over a period of time and to increased rubbing e9sagement of the seal faces at the higher temperature as fluid viscosity is reduced.

It is to be noted that there veo no significant change in leakage discernible from the test.

Further, the Boiler Circulation Pump 4 1/2' seal was disassembled and essained following the above test cycles and both the seal faces and the 0-ringe were found to be in good osadition following the lose of cooling vetor test as skova la Referemos 8.

This is a significant improvosest over the Byrom Jackson Seal Test referred to in the FSAR for two reasons: 1) The Singhes Willamette 4 1/2' diameter seal withstood the thirty esaute. loss of cooling test to which the 50008 2 and 3 seals will be sub3ected on a loss of cooling incident.

This seal performed well even after being sub3ected to a prior one and one half hour loss of cooling test on a reduced temperature ramp to 500'F vithout need for seal refurbishment staos both the higher temperature elastomers and the seal faces were in escellent ooedition following the combined test periods.

2)

The Singhan Willamette seal tested was a ses11er soel with significantly less thermal capacity causing the seal cavity temperature to rise more

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rapidly than occurs in the larger actual RCP seal when sub3ected to the same incostag veter toeperature reep. The smaller seal (4 1/2' essi

~1729-400-003-00 PAGE 9 OF 14

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diameter) tested vae therefore subjected to more oevere thereal conditions for the thirty minute period, (Reference 71, than the SONGS 2 and 3 RCP retrofit seal (9 1/2' seal dia.) vill experience in a loss of cooling veter incident.

Further, the elastomers applied to the 9 1/2' 50508 2 and 3 seals, although of the ease composition, are proportionately larger in crose section than those in the 4 1/2' test pump seals, thereby tacreasing their resistance to thereal degradation.

In sueeary, the replacement Biaghan Willamette seals lastelled in the SOROS 2 and 3 RCP's are capable of thirty minutes of operation without damage or significant increase in leakage during a loss of cooling incident.

The 8.W. replacenest seal esploys the same aveber of seals (3) j plus a back up vapor seal as in the original Byrom Jackson osal design.

Each seal of the 8.W. replacement unit is designed to acoopt the full operating pressure of 2250 poi.

However, they mores 11y operate with a pressure differential equal to one third of the operating pressure except for the vapor (#4) seal which normally is esposed to a such lower pressure differential (Table I).

5.5-3 Paragraph 5.

Although a test of the actual seal cartridge to shoe specifically that the B.V. replaceamat-reactor coolant pump' seal assemblies will act lose functica during a two hour station blackout condition has not been performed, teste have been performed with duplicate replaessent seal elastomers which demonstrate that the elastomers applied in the B.W.

1 replacement seal show no loss of function and esosatially no change in characteristics after eight hours of operation under static test at 2250 poi and 550*F.

Further, there vae minimal change in hardases and no leakage following an eight hour static test at 2230 poi and 600*F.

See Kalsi Engineering, Inc. Report Beforence 12.

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This static teet significantly exceeds the thereal and pressure coaditions in the various seal cavities during a postulated two hour I

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station blackout incident where the elastomers are only subjected to approximately 730 poi differential pressure and to a toeperature of 350'F or below.

See Reference 10.

Further, the pump is stationary during this loss of cooling incident except for the first three to five minutes so that t

there is no vibratory motion from shaft runout.

Also, er M ; r :t to the first three to five sinutes, the carbide end carbon seal faces remain stationary so that no deterioration of those surfaces would be espected.

Since these carbide to carbon seal faces are less strosood than is normal operation and minoe the elastomers are shova to withstand 530'F to 600*F vetor c:ndition for at least eight houros supported by the excellent performance condition of the Alasites test osal described above and la References e and 10, the S.V. replacement seals installed La ElglN 2 and 3 v111 operate noceptably in oncess of two hours during a station blackout incident.

5.4-6 Paragraph 2 The FS&R stateneet concerning RCF performance during (1) a LOCA or (2) a essor stesa line break La osataineset applies to the 5.W. repleoeeent seal without modification.,This.is certainly shova by the above test at Alamitos, in Referencee 7 and 4, which define the test results and an evaluation of the test seal fo11oving a history of one and one half hours with the lower seal at 400 to 500*F after which the ease seal cartridge was 4

subjected to the thirty minute loss.of cooling veter test duplicattag the toeperature reop which will be experienced by the SOON 2 and 3 BCP's,:

Reference 9.

This test supported by OD&I Analyses showing the reduced toeperature conditione which will attain in the 30 W 2 and 3 seals, Reference 10, and by the Kaisi Engineering Elastomer Tests Referenos 12, clearly demonstrates that no seal deterioration or failure will occur l

1729-400-003-00 PAGE 11 0F 14-l

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l during a thirty minute loss of cooling incident, pump operating; or a 2-hour loss of cooling incident, pump stopped.

It le further noted that each of the four seal stages to designed to operate at 2500 poi differential, so

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that only one stage is required to reesta inteet to assure continuing j

performance during a LOCA.

The seals will therefore continue to operate satisfactorily without failure resulting from lose of cooling water.

The reactor coolant pump seals are designed and the above elastomer tee +,s demonstrate that they can withstand hot standby conditions without component cooling veter flow conditions that would result free a loss of 1

offsite power.

Esposure to these conditions therefore dose not seriously degrade the ECP seals and will not result ta a easil LOC &.

Since it has been demonstrated that the seal vill continue to function satisfactorily during a lose of cooling water incident and since the seal cartridge has the snee series-arranged face seals as the original design, l

the replacement seals are not susoeptible to a LOCA and the current FSAR etateeenta page 5.4-6 paragrsph 2 and paragrsph 5 apply.

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Page 15.3-7, Paragraph 15.3.3.1.1 The aenlaoseent seal design is stataar is its general eschanical configuration to the original S.J.' esel.' Further, it has been demonstrated in the above paragraphs, that no failure or es1functica of the seal vill occur due to a thirty minute loom of cooling water incident with the Binghae Willamette replacement seals installed in the SOE M 2 and 3 BCPe.

I Even continued operation of the pump significantly beyond the thirty minute-I period should not result in significant seal face degradatica.

The materials of the seal sating surfaces are such that should severe rubbing engagement occur, the carbon material would esperience high voar eventually losing engagement with the carbide runner.

Even if subsequent rubbing should occur between the rotating carbide ring and the stataleen steel stationary ring carrier (part 442, Reference 3), seizure would not be E

A 1729-400-003-00 PAGE 12 CF 14

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l anticipated. !1ovever, if for some reason seizure should occur, it would have less severe effect in the replacement 8.W. seal than in the original B. J. seal.

This attains since the replacement sesi provides articulated (sochanically separate) rotating and stationary parts for each stage while the original Byron Jackson seal employs articulation only of the stationary parts.

If seizure occurs in the original S.J. design, it will force rotation of the shaft within the seal cartridge sleeve.

The sleeve is one piece for the full length of the cartridge.

In the replacement Binghee Willamette seal, however, seizure of any seal permits rotation of both the affected local outer stationary seal element gad, rotation of the shaft l

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vithin the inner seal element sleeve sogeent for the seal stage affected.

This increased freedos provides an additional nochanical fuse, (rotation of l

various seal eleasets with respect to each other, of both the stationary l

and rotating elessats of each stage) that is not available in the S.J.

I designs, thereby further reducing the already estremely unlikely possibility of shaft seizure.

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In summary, the results of the November 1 Alamitos test, of the O'Donnell & Assootstes' analyses and of the statto seal tests conducted (References 7, 4, 10 and 123 elearly deseastrate that the B.W. replacement SONGg 2 and 3 seals will periore without loss of fumation dering both a i

thirty einute incident during which no cooling vetor is available for the seal (pump operettag); and for a two hour incident of loss of statica power during which the pump osasts dova and no cooling vetor is supplied to the j

seal.

The refereased tests and analysis show that those incidents will be-

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survived without significant change in seal leakage rates.

Also, analysis and evaluation of the seal design demonstrates that a shaft seizure incident is even less likely than la the original seal design.

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Further, the replacement seals, based on this evaluation and the test results, are not susceptible to a loss of coolant assident (LOCA) or a f

major stese line break in containment. The current stateneet of FSAR 5.4-6 i

1729-400-003-00 PAGE 13 0F 14

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l paragraphs 2 and 3 continues to apply to this replacement seal.

Based on the above analysis and test it is concluded that the replacement SONOS 2 and 3 seale vill perfore within current FSAR conoiteente with a significantly greater margia than was available in the original seal.

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1729-400-003-00 PAGE 14 0F 14

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ENCLOSURE II S

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AUG 31 1989 l

1 Mr. Edward C. Sterling III, Cheirman ti, i l

Combustion Engineering Owners Group I

c/o Arizona Nuclear Power Project

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l 11226 North 23rd Avenue

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Phoenix, AZ 85029

Dear Mr. Sterling:

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Thank you for your letter of July 26, 1989 providing Combustion Engineering Owners Group (CEnG) comments on the information presented in NUREG/CR-4821 and-NUREG/CR-4948 which are some of-the supporting documents for the resolution of Generic Issue 23 (GI-23), Reactor Coolant Pump Seal failure. We have actively.

attempted to obtain, develop and use all information which might be relevant to

.the resolution of GI-23. As a result, the staff is generally familiar with the information provided in your letter.

We do not believe this information conclusively demonstrates that reactor coolant pump (RCP) designs used in CEOG-plants should be exempt from any new requirements.

l We are currently preparing a proposed technical resolution for this issue.

It is our intention to present several resolution alternatives for public comment.

Each alternative will be evaluated on the basis of the estimated cost-benefit.

At present, we are considering two distinct failure scenarios, one involving failure of the RCP seal during nonnal operation and one involving failure of the RCP seal during loss of all seal cooling.'

g Failures of RCP seals during nornial operation are'not typically a function of l

faulty seal design but are more often a result of improper operation, i

maintenance and quality assurance. -Failures during normal operation continue to occur and the enclosed table lists the events that have occurred since May 1988. Although none of these failures have resulted in the large. leakage _'

rates seen in some of the earlier events, the seal failure rate appears to have remained relatively constant.

Further, there appears'to be a disproportionately large number of events involving the types of RCP seals used at CEOG plants.

l Loss of all RCP seal' cooling would occur during a-station blackout or if there were a total loss of the component cooling water system. Also, loss of.all, service water for an extended period would also cause a loss of RCP seal cooling. At present we intend to propose allowing a licensee to address the loss of seal cooling aspect by either including additional seal cooling provisions in the plant or'by demonstrating acceptable performance by a meaningful test.

8912280415 891227 PDR ADOCK 05000361 p

PDC

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2 AUG 31 1999 Prior to issuing the proposed resolution package, it will be reviewed by NRC staff, the Advisory Comittee for Reactor Safeguards (ACRS) and by the Comittee..

for Review of Generic Requirements (CRGR).

It is scheduled to be issued for public coment in the Spring of 1990.

During the public coment period CE0G will have the opportunity to review the basis for each alternative and provide coments.

Sincerely, e

s./

v R. Wayne Houston, Director Division of Safety Issue Resolution Office of Nuclear Regulatory Research

Enclosure:

Table of Recent Seal Failure Events 4

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JCH C175 BE9 6173 OBA C345 PWH G104 luA 6915 JAL 6144 LGP G163 ner.nu 701?

CTes J 7034 hc s

RWP 7102 DNS 7702 PFC 7434 ACR 7048 OSE 710 5 JEA 7106 DW

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e Enclosure RECENT SEAL FAILURE EYENTS EVENT DATE NUCLEAR PLANT NS$$

SEAL VENDOR DE8CRIPTION OF F A I 'l U R E EVENT $

MAY 23, 1988 NjWE MILE PT 2 GE BJ REC!kC. PtMP SEAL LEAK, 5 GPM. PLANT $NUTDOW, SEAL REPLACED AUG 1, 1988 ANO 2 CE BJ LOWER 8 MIDDLE SEALS FAILED. LEAK 40 GPM -

SEP 15, 1988 TM1 1 4&W W

DAMAGED 0 RING, CAUSING SEAL #1 FAILURE. LEAK 9 GPM

, NOV 4, 1988 SEQUOTAN W

W DESCRIPTION NOT AVAILABLE NOV 9, 1988 WATERFORD CE BJ N9000 SEALS FAILED AFTER START UP. REPULCED PWPS WITN OLD BJ SEAL DEC 5, 1988 PAL!$ADES CE BJ DESCRIPTION NOT AVAILABLE DEC 15, 1988 TMI*1 B&W W

DAMAGED 0 RING, SEALf1 LEAK 8 GPM. WM UNASLE TO ADVISE $0LU110N DEC 21, 1988 MAINE YANKEE CE BJ SU DEGRADED SEAL PERFORMANCE. SEALS REPLACED WITN BJ M9000 SEAL MAR 3, 1989-PALD VERDE 3 CE KSB SEALS DAMAGED

• LEAK 2 GPM MAR 29, 1989 SAN ONOFRE 1 W

W LEAK 33 GPM RCS PRES $URE LOWERED TO ATMOSPN. LEAK 22 GPM I

i MAT 29, 1989 MILLSTONE 1 CE BJ QUTER SEAL ON REclRCULATION PLMP FAILED, LEAK 46 P.PM i

JUN 1, 1989 CLINTON 1 GE BINGHAM SOTH SEALS ON RECIRC. PUMP FAILED AFTER START UP. LEAK 63.GPN l

JUN 16, 1989 KEWAUMEE W

W 0 RING DEGRADED, SEALf1 LEAK INDICATE LEAK BTPASS, REPLACED SEAL

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JUN 19, 1989 INDIAN PolNT 2 W

W SEAL #1 FAILED, LEAK 14 GPM, SEAL REPLACED DURINC QUTAGE JUN 23, 1989 QUAD CITIES 1 GE BJ PRES $URE DIFFERENTIAL ACRoss UOTER SEAL 70 750 PSI CAUSING LEAKAGE -

AUG 8, 1989 RIVER SEND GE SJ RECIRC. PWP SEAL LEAK, 4 GPM. PLANT $NUTDOWW, REPLACING SEAL

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