ML20085A480

Nuclear Svc Site Ofc Rept 59 for 770916-1009

ML20085A480
Person / Time
Site:	Davis Besse, Three Mile Island
Issue date:	10/10/1977
From:	Faist F BABCOCK & WILCOX CO.
To:
References
TASK-05, TASK-06, TASK-07, TASK-11, TASK-5, TASK-6, TASK-7, TASK-GB GPU-0487, GPU-487, NUDOCS 8307060524
Download: ML20085A480 (5)

Text

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.3 &tl. A. C' DDL"J' J SITE OFFICE REPORT- T3.3.1

. pg g P2 PORT NUISER j59 . DATE 10/10/TT U.R -M Edisen Cencany LOCATION / UNIT Davis-3 esse Unit I  : , _. /) , p OP EATIC55191*ACER Y Fred R. Faist Fred R. Faist u I *:GP SCFIDULE RCS HYDRO S C g let MHFT g hg FUELLOADg%%7 100% FP gags.te4 i SII".;TE 1 Sta* T Fi .ish lRCS HYDRO 9/UT6 HFI 3.inish

/10/77 FUEI. I,0ADg737777 ,100% FP y773

.T I::CLUSIVE DATES 9/16/77 - 10/9/77 -

. TNMEr, 15 TO INCLLJE THE FOLLOUING INFORMATION: MAJOR EVENTS, ACTIVITIES, PROBLEMS, SCHEDULE,

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1 Plant at 532*F 2155 psig on 9/16/77, all (18) Main Steam'SafetIy Valves (Dresser) reset. ~~~

) 2. CRDM stator in location N-8 determined to have failed. Stator changed out with spare on 9/16/77 - 9/19/77.

3. ~.eactor critical on 9/19/TT. Turbine on line with 2x power apprcxi=ately 155 entire  ;

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Tests completed at 15%, Unit Load Steady State, TP 800.12; Core Pcver Dist:ibution, TP 800.11; Incore Detector Test, TP 800.24

5. 9/2h/77 - Plant experienced an uncontrolled rapid depressurization due to PZR electrenatic relief valve sticking open. See' details below. Plant in r.aintenance j outa$e through 10/10/7T.

l ACTIVITIES:

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1 On 9/16/77 all 18 Main Steam Safety Valves (Dresser) were reset. Valves were fcund to be set lov (as =uch as 50 psig) pr* =-117 due to high room temperature and an error in the hydroset curves supplied by Dressen. SPR 363.

2. Failed Stator - S?R 365 - On 9/16/77, the CROM stator in location N-8 was dete s ~e to have an internal short between 3 is C phases. Atte= pts to d y out stater failed end on 9/17/77 preparations were in progress to change the stater cut with a spare in the CTIC b1dg.

i RCS vas at 532*F, 2155 psig, as:1 a decision to ecolde ~ to 360 -

380*F was made to reduce heatup rate on the CRDM stators with cooling v=cer secured.

Prchlens with seating the new stater, ?I tube adjustment, fining COJ 1eaks end in-l experienced, unfa=iliar =aintenance personnel extended the jcb until 9/19/77. During the PI tube adjustnent, =sintenance d'.= aged the threads and helicoil on the PI tube and hc.i to send a =echenie into the service structure to re=cve the helicoil frc=

the PI positiening stud en the stacor. SPR #36h. Scb $nith of DP3Co on si:e to 0' assis t.

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- Site Office Report #59 620-0014

- October 10, 1977 Page 2 0 .

3. Plant Testing -

a. Reactor achieved criticality on 9/19/7T. Core Pcver at 15% on 9/20/T7, 0600.

Generator output approxi=ately 100 W. Only 1/2 the cire water syste= vas operable (only 1/2 the condensor available). ,,

b. Turbine Overspeed Trip on '9/20/T7 vith the reactor at 75 FP. Three atte= pts were =ade, all unsuccessfcily. Adjustments vill be =ade and further atte= pts vill be cade after physics testing at 15%.

c. Reactor returned to 15% FF on 9/21/TT, 0330, 'avaiting equilibriu= Xenen for core power distribution. During this time period, perfor=ed the fol. lowing:

1. NSS Heat Balance , TP 800.22, results acceptable. ,

2. NI Calibration, TP 800.02, results acceptable. -

3. Unit Load Steady State, TP 800.12 (data being reviewed).

h. Core Power Distribution, TP 800.11, results- acceptable.

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5. Incore Detector Test, TP 800.24, results acceptable.

6. ICS Tuning, TP 800.08, to be continued on return to power.

L. RCS - rapid depiessurication O o= 9/2'/TT. 1eco, a te - 1e x betwee= *se *==*t=e e-ver='r v 1ve e= a= *==bi=e oce. red, necessitating turbine shutdevn. Reactor power /as being reduced to 6 - 7% power (re=ain in Mode 1) until stea= leaks could be repaired.

APproximately 213k on 9/2h/TT, with reactor 'at 9% FP - the following sequence of events occurred:

a. SFRCS for unkncvn reasons shut the S/U W control valve to #2 0'ISG.

b. #2 OTSG level dropped causing RCS Tave, pressure to incre'ase. SFRCS actuated on lov OTSG level. ,

c. SFRCS actuation bottled up both OTSG's initiating Aux. N to both. '!he Aux.

W pu=p to #2 OTSG failed to ec=e up to speed due to gove=nor prcble=s , thus causing #2 CTSG to go dry.

d. PZR level reached 290 in. and the reactor was tripped =anually.

e. Prior to reactor trip, the RCS pressure had increased to greater than 2255 psis, causing the electrc=stic relief valve to open. A seal-in relay was later deter-r.ined to be missing frc= the relay cabinet, thus causing the valve to cycle cpen and closed abouc 2255 psig. It was deter =ined that the valve cycled 9 times within h5 see. before the pilot valve was da= aged causing the electrc=atic re'.icf to stick open. ,

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Site Office Report #59

, . 620-0014 October 10, 1977 '

Page 3

f. RCS pressure decreased and at 1600 psig, the SFAS actuated. CD2 isolation and h?I. Isolating = cst of the CT:C cut off cooling vater to the Quench Tank.

,; . With the electro =atic relief valve still open, and the Quench Ta=k unable to quench stes=, the quench tank rupture disc blev out da= aging a ventilating duct and blowing approx 1=ately 200 sq. ft. of mirror insulation off the OTSO.

h. An esti=ated 20 =inutes vent by before the electro =atic relief isolation block val.re was closed.

i. During the transient, 2 RCP's were tripped le'aving a 1/1 co=bination, HPI was secured and restated, two =akeup pu=ps were operating si-"Ttaneously t

during par.t of the ti=e, PZR level indication vent greater than 320 in, and as 1cv as 10 in. Approxi=ately 6000 - 8000 gallons du= ped into CDE. .

RCS pressure /te=perature was such, that stea= for=ed in th'e RCS loops , co=-

ponents, etc. -

Da=are:

a., Quench Tank rupture disc.

b Ventilating duct.

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d. PZR heater cables (high hu=idity - lov =eggar readings).

e. Potential danage to EW supplied equipr.ent, such as =ajor co=ponents, RCP, RCPM, RCP seals, etc. , has been evaluated and deter =ined not to be a proble=,

however, =ccitering of RCP perfor=ance during startup vill be required. See SPR's 369 and 372 for details.

Meetings between TICo/3G/NRC vere conducted to revbv th 1 transient. NRC re-stricted DB-I to operatien below 200'F (less than Mode h; until all proble=s could be resolved. On 10/7/77, NRC released DB-I to startup.

5. RCP Initial Runs after transient: .

3-J representatives and John De=psey of BW vere on site 10/5/77 -.10/7/77 to 4

vitness ths initial RCP runs after the transient. RCS pressure approxi=ately 225 pais, te=perature approximately 100'F, a series of short RCP runs were con-ducted on all h RCP's. Data fr== these runs indicated goed RCP seal perfor--ce.

Salance of RCP data to be taken when RCS is greater than 1300 psig.

6. Makeup and Purification Pu=ps:

On 10/8/77 and,10/9/77, atte= pts to run a =akeup pu=p .resulted in va*- 'ad age out the inboard seal. This seal had just been replaced by TECo maintencace the previous veek. The seal was i= properly installed, an "C" ring had be.en rolled -

during installation. P.:=p vas declared operable en 10/10/77, in preparation to h run RCP's for hen up. !.'U ~'u :p proble= vas an offspring of the bearing housing oil lech prcble= reported in SpH 368.

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• Site Office Report #59

. 620-0014 October 10, 1977 Page 4 0 .

7. Feedvater Cleanup started on 10/6/77.

3. Ceeputer Repairs -

During the past several.veeks, the 855 had been stalling and reinitiallising frequently. The outage during the last two weekn pe:mitted I&C and BMCo per-sonnel to take the computer out of service to locate proble=s , replace " marginal" IC chips , r.odules , etc. Troubleshooting vill continue into the week of 10/10/77 On 9/22/77, proble=s with the NSS calculations, PDO, delayed physics testing Approxi=stely 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

PROBI.D'S

1. SPR 372 - for the past two weeks the major problem has been t:-Ag to reconst: tet, evaluate the transient that occurred on 9/2k/77. NRC has per=itted DB-I to start up, however, TECo made several co==itt=ents in order to obtain this pe=ission.

2.  :.7-1 Source Range Instru=entatica - during the past two veeks the source range'has failed icv 3 or k ti=es. The count rate amplifier was changed out , but the results

.ere the sa=e - TECo is setting up monitoring equip =ent to dete=ine cause.*SPR 342.

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v SPR's - Status Since Previous Report - -

a. Eleven (11) new SPR's have been written:

1. 363 - S. G. Code Relief Setpoint Drift '

1. 364 - Da= aged Threads & Helicoil on PI Tube & Stator ~

1. 365 - Short in CRDM Stator at N-8

1. 366 - Errors in CRDM Manual Use of Wrong Lube *

1. 367 - Reactor Trip

1. 368 - 011 Leak en M.U. Pu=p Bearing Rousing

1. 369 - Electrc=atic Relief valve Damage ,

- #370 - Rose =ount k1hE & 414F RTD Bridges

1. 371 - FC #97 Installation

1. 372 - SFRCS Trip / Reactor Trip / Coolant Spill

1. 373 ' Inboard Water Seal Le**g -

b. Seven (T) SPR's have been cleared. *

c. Sixty-five (65) re=ain open.

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' Site Office Report #59 620-001h October 10, 1977

, . Page 5 SGEOULE 1.

Reactor Critical - estimated 10/12/TT 2

Finish 15% power testing, including turbine overspc .d tr'.p te$ ting, unit shutdevn test, - anticipated completion 10/14/77.

3.

PES to h05 pcver to start 10/16/TT. Reach h0% power 10/19/77.

FEFf0ZEL F. R. Fais t , SOM I. D. Green, ROE

2. L. Flood, Sec'y. -

J. E. Anderson .

3. F..Snith ....

C. C. England ,

1 L. Nelson D. L. Allison D. 2. Shaffer, 3MCo PSS

, psTS TOPS bei -

9/16/77 +- Bin Nielsen, 3&W, reactimeter operator 9/1T/TT - Mike Boesch, 3MCo, computer 9/18/TT.- Bob S=ith, DPSCo, service .CarM .

9/21/TT - Garden Markley, B&W, inspection .

9/2k/TT - Mike 3cesch, BMCo, computer 9/27/TT - Norm Infott, 3&W, audit for Isley-9/27/77 - W. R. Conroy, Crosby Valve, service 9/27 & 28/TT - J. J. Keny, 3&W, data evaluation .

9/29/77 & Joe Lauer, George Meyer, John Dempsey, Art McBride, 9/30/77 '

Frank Levendoski - all B&W - meeting with. TICo on SFRCS 10/3/TT - W. D. Ssith, 3MCo - computer service 10/3/77 - Roger Kunes, EMCo - co=puter service (still on site).

i 10/k/TT - Tis Grubaugh, 3MCo - service (meeting with PSS).

10/5/TT - W. J. Lollis, 3.J. Pu p - service -

10/5/TT - Larry Wong, B.J. P=p - service .

10/7/TT - Carl roledzy, 3&W, = aster services

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