ML19224A915

Summary of NRC 790517 Meeting Re Preliminary Chronology of TMI Event.Chronology Encl

ML19224A915
Person / Time
Site:	Crane
Issue date:	05/17/1979
From:	Tam P Advisory Committee on Reactor Safeguards
To:	Advisory Committee on Reactor Safeguards
References
ACRS-SM-0120, ACRS-SM-120, NUDOCS 7906130197
Download: ML19224A915 (49)

Text

'

'.INITED ST ATES yQ

^/ q NUCLEAR REGULATORY COr.WISSION

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{

j ADVISORY COMMITTEE ON HE ACTOR SAFEGUARDS

,f 3.,

.j W.

MHNGTON. D C. 20555

.,\\,,, ", +

May 17, 1979 ACRS ** embers

SUBJECT:

CC."MISSI0f; MEETIf;G: BRIEFIf;G CY INSPECTION AND ENFORCEMEriT ON TMI SEQUENCE 07 EVENTS I went to this nv i.ing on May 17, 1979.

In this meeting, I&E presented highlights of tie prelimint ri chrorology which they sent to the Ccemission on May 16, 1979.

A ccpy of the chronology is attached, and ISE will have the final version on August 1,1979.

The chronology of events was developed based on infomation from taped and unta:ed interviews, taped telephone conversations, strip charts, reactimeter data, alarm printaut data, and formal and infomal logs kept by control room personnel.

I&E currently has an inve:tigative team (consisting of ISE inpectors and in'Jestigators) working to obtain and verify information.

Highlights of the briefing are:

TMI operiters suspected FORV or safety valves leak just prior to commencement of the accident. However, since both the PORV and safety valves tail pipes are headered together, and discharge temperature was measured only at the header, there was no way to tell which valve was leaking.

The condensate polishing system developed difficulty just prior to the incident.

Containment sump pumps were not designed to be isolated by SFAS.

At 8+ minutes, the operater heard noise in the steam generators and assumed it was caused by auxiliary feedwater entering. The noise was more likely caused by the steam generators boilir.g dry.

At 11 hr. 32 minutes, the operators noted that the only means of fiSSS ccM ing was one HPI and the core flood tanks.

D\\

d.%

Peter Tam Staff Engineer cc: ACES Technical Staff I cation W. Lipin ni.

174 046 C. ftichel son W. Stratton 7 9 0 613 0 Icn Z. Zudans O

e THJ-2 Ifil[RI'4 OPEPATIONAL SEQUENCE OF [VENIS AS Of itAY U. 1979

[l ?tSE D TI"E EVErlT DESCRIPTION REFEfJfiCES Prior to Turbine Trip Three Mlle Island Unit Two (IMI-2) was operating at 97% power with the Inte rated 1.

Intervicw Control System (ICS) in full autoautic. flarnul Reactor Coolant System (RCS 2.

CPtl Sequence 4/16/19 rukeup and letdown vere established with flakeup Pump (MUP)

"B" in service.

3.

Chemistry Logs 3/2o/79 Pressurizer Spr ay valve control was in nunual-open to equalize Pressurizer and RCS boron concentration. I:CS boron concentration was 1026 ppm and radioactivity concentration was 0.337 uc/ml. Identified RCS leakage, believed to be from the Electronatic Relief or Code Safety valves on the Pressurizer, was approximately 6 yp:n.

Ulf ficulties were being experienced in transferring an isolated Condensate System 1.

Interview Polisher's spent resins to the Regeneration Receiving Tank. Transfer procedure utilizes Station Air to fluff resin and Demineralized Water to transfer resin between tanks. A resin block developed in the transfer line.

At this point plant operators have hypothestred that water pressure may have 1.

Interviews exceeded air pressure forcing water into the air system. Further the water nude its way to the Polisher isolation valve controls causing them tti drif t towird the shut position. Since the Polisher outlet is operated within 50 psig of the Net Positive Suction llead limit for the Condensate Booster Pumps, the Condensate Oooster Pumps nay be the first to trip. (This problem has reportedly occurred before.)

flote : All Polisher inlet and outlet isolation valves were found shut af ter the 1.

Interview Turbine Trip.

flot e : Polisher Dypass Valve on IMI-2 aoes not open autonatically on high differ-1.

Interview ential pressure.

-1 sec.

Condensate Booster Pun;p 1 rip.

1.

Assumption flote: Loss of Suction Pressure will cau?e a Condensate Dooster Punp trip.

1.

Alarm Procedure 17.E9

.C=.

CD

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!' /F5FD T!!T FVff4I DESCRIPIl0N PE ff REfKES

-1 sec.

Cor.densate Pump 1 A Trips (all but one may have tripped). (Actual Time C4:00:36, 1.

Line Frinter 3/20/19) 2.

Interviews flate: Paired Conder. sate Booster Pump trips with the control switch in AUTO will 1.

Alarn Procedure 17.ES cause Condensate Pumps to trip.

O Main fentwater pumps are tripped resulting in an alnost sinultaneous trip of the I.

Line Printer turbine. (Actual ti:ae 04:00:37,3/28/19) flote: feedeater Pu:ap suction pressure low or loss of the Condensate Booster Pumps 1.

Alarm Procedure 17. A15 ar.d will cause the feed Pump Turbines to trip.

flote: Both feed Pumps tr1Pping w1Il cause the Main Turbine in trip.

1.

Abnormal Procedure 2203-2.2 flute : Tripping both feedwater Pump Turbines will start the Energency feedwater 1.

FSAR Section 7.7.1.2.1.3 Pumps.

flote : loss of one or more feedwater Pumps will cause the ICS to runback reactor 1.

fSAR Table 7.7-2 power, causing the control rods to be driven into the core.

Ut Energency feedwater pumps start. Pressurize. level and pressure rising rapidly.

1.

Line Printer 2.

Interviews 1 sec Turbine Stop and Intercept valves closed. 500 KV breakers are tripped.

1.

Intervicw Pressure in Reactor Ccolant Drain Tank (RCDT) begins to rease.

1.

Reactiireter Data J scc.

3-5 sec.

HCS Reactor Pressare reaches Electromatic Reifef Valve (EMOV) opening setpoint 1.

Plant Strip Charts (2255 psig).

2.

Reactimeter Data t sec.

Peactor trips from reactor high pressare (setputnt = 23f 5 psig). Indicated 1.

Line Printer Peactor pressure on the Wide Range RCS Pressure Strip chart from the control 2.

Plant Strip Charts

~~-*

N room shows an increase '.o approxinately 2435 psig which suggests one or both 3.

Intervi m safety valves may have lifted. Ilowever, this oaximum value is not confirmed by the reactliceter or by the fWrow Range RCS Pressure recorder trace.

O

-t:.

CO 2

-- -. ~...

~

FEFERff1CES

! ! 5t b T 171 LVIfif DESCRIPTION pressurizer heater groups 1-5 tripped and returncB to control MU Pung flow to loop.

1.

Line Printer 2.

Interviews fla t e : This action, according to interviews, is livedtately taken by the operators following a reactor trip for the sane purpose as the securing of letdown which occurred at 12 seconds, t.e. minimizing the large pressurizer level transient which follows a reactor trip.

s 13 setN PCS pressuie reaches setpoint for EMOV closure (2205 psig).

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FEFEPfhCES F Ui E ED T!"E EVfhT OfSCRIPTION hate: then llPI is initiated, any discharge valves which nay Fave been previously throttled are designed to return autbuatically to their fully open position. Based on interviews the valves on the 1 A pump had rot been throttled closed up to this point in the incident.

Steam Generators appear " dry" based on zero Hot to Cold leg RCS temperature 1.

Reactimetcr di f fererice.

s 2 1/2 min.

Pressurizer level at 207.7 inches.

1.

Line Printer 4.

Reactimeter Shif t foreman enters Control Room and obtains the emergency procedures for

i. Interview turbine trip, reactor trip, and safeguards actuation to confirm that all a[propriate aCtlCDs occurred.

3r r.i n.

ECCS Lypassed by operator actions.

1.

Line Printer 2.

Intervitws Control Room Operator throttles MU-VICH in attenpt to controi Pressurizer level 1.

Interview increase and prevent MU punp runout. Dy this time MU-V17, the normal Pressurizer level control valve would be shut since pressurizer level is above control setroint.

s 3 1/2 rer.,

t CDT tea.perature 121 F, tank pressure rapidly increasing and stabilizes at 1.

Line Printer 0

appro<imately 120 psig for 3 minutes. The reactimeter plot of MDI pressure 2.

Reactimeter exhibits an oscillatory behavior at 120 psig similar to what would be expected if 3.

FSAR the MDT safety valve had actuated. The setpoint for the RCDT safety valve is

===4.

System Description===

• listed as 150 psig. The actual safety valve setpoint is not bnown at this time.

5.

Interviews lhe operators did not indicate during interviews that the RCD 1 cooling system (a r.anually initiated system) was started by thera during the transient.

4 r.in. 33 sec.

Md e-up nump IC tripped. Itake-up puup 1A still running in throttled condition.

1.

Line Printer 2.

Interviews

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I PEFEREhCES ftApStu IIP,E LWitT DESCRIPIl0:4 flote: During this period attempts were underway to reestablish nornci condensete 1.

Interviews system. Based on interviews, it appears that shen the flow f ror.i a flake-up 2.

Linc Printer pump operating in the liigh Pressure Injection mde is throttled, the operators do not reduce flow helow appr oximately 100 opm in order to proteci the purp.

This minimum flow is accomplished only 1,, srttting the valve in one of the two injection paths. If toth paths are cpen, the fleid 1; 200 gpm. Therefore, minimum pump flow, when the pump is operating, appears to he at least 100 gpm.

by 5t W n.

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Line Printer tzer level rise. Orlfice and bypass utilized together.

2.

Interview Note: At five minutes af ter the transient, pressurizer level starts dropping at a 1.

[1?/.4 figures rate of approximately L0 inches per minute for 15 seconds. At this sane 2.

Line Printer ttw, an apparent decrease in loop "A" flow and increasin; seactor coolant 3.

Interviews temperatures are observed. tJpon receiving a high letdowri temperature (at s 7 min) the operator throttled letdown to S 70 qpm.

The pressurtzer level rate of thange is not in agreement with the actions, systen teuperature changes, and riake-up pump operation occurring daring this g eriod.

6 min.

Pressurizer huhble lost. RCDT pressure starts rapid use above 120 psig to the 1.

Reactimeter RCDT Safety Valve setpoint of approximately 150 psig, possibly the result of 2.

Plant Charts passing liquid versus steam. RCS pressure now tracks Hot leg saturation pressure.

3.

Interviews Combination of full Pres;urizer indication and increasing 1:CS pressure, the result of rising hot leg temperature while chargleig with the one ftU Pump, convinces operators they have a solid plant.

I nin. 43 sec.

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Line Printer Heactor Building Sump to the miscellaneous waste holdup tank (ULL-T-2) via the 2.

Intervi w nan ully open fleactor Building isolation valves. 16 wever, tank level records show this tank to have not changed level during the incident, and there is reason to 1,elieve the sump pump discharge was aligned to the auxiliary building sun.p tank. (This tank had a blown tupture disc which wis scheduled for later repair.) lhese isolaticn y

valves do not close on the SFAS sig1al which initiates llPI. These close only when D

4 psig in the Reactor Dullding SFAS setpoint is reached.

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RfffRfiKf5 I t f iN I) IINE IVINI M SCRIPTINI Reactor toolant loop flow indication has been steadily decreasing and indicated 1.

B!W figure diur to 74 siin.

flow in loop B 14 min. approximately f,0% of normal value. Operators report 2.

Interviews receiv tr y vibration alastis ori the reactor coolant puntps (RCP). Chart recorders 3.

Plant Strip Charts for source range nuclear instrumentation show increasing counts with increasing astaplitude of osCllldtjon.

1.

Interview Operators reportedly recognized that they were violating 4 RCP pressure-ten:perature limits and the pin compr ession curves.

1.

Interviews -

RCP's in B loop chosen t'o be tripped to be able to maintain niaxiniuiii pressurizer 14 min.

spray capability which comes frimi A loop. RCP 111 and 20 tripped. (Line Printer 2.

P&ID indicates that RCP 2A also tripped. This inconsistency will f.e reviewed further.)

3.

Line Printer 4.

U ?.',1 f i gu r e 5.

D&W Sequence 1.

Intervieus Operators reported flow oscillations decreased inaedtately following pump trip.

74 nin.

itarcover. Source Range (Sidt) instrumentation count rate osct!!atory behavior 2.

Plant Strip Charts significantly decreased. SRf1 count rate was approxtriately three times the value 3.

C?>d Se w ence that would be expected at this time after reactor trip. RCS pressure indicates 4.

C&W figures upward pressure trend, and "B" steam generator pressure drops from approximately

'.,0 psig to 140 psig over the next 18 minutes.

\\

- 15 nin.

RCS sample yields 700 pim Coron. Sample required within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of trip. Results 1.

Interview questioned by technician and started to get additional stiiple.

Factor of 10 increase in radiation level as shown on letdown line n:onitor.

1.

Plant Strip Charts C0 nin.

1.

Line Printer Ll rain.

Surge line temperature SIL9"f.

The "B" steam generator was isolated at this point (87 min.).

Operators had ob-1.

Control Roca logs 87 ntn.

served increases in Reactor llullding pressure and noted that pressure in generator N

"ll" was 300 psig lower than "A" and believed steani was leaking into the Peactor h

1:ullding. After isolation of steam generator "B", they note 1,ullding pressure leveling of f and *B" generator level is trending upward so they secure the third LIW valve to the gene.ator. LIV-SD.

g L~'

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12 I

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_RF FE RFt;CES

[IiMED II T EVEf4T DFMRIPil6ti Reverse flow should have occurred in the 6 loop as a result of continued tio te: operation of the pumps in the A loop. No substantial changes in steam it appears that generator level or pressure occurred over the next hour, 0

reverse flow of PCS coolant at a temperature of approximately 550 F was not occurring through the "B" generator.

1.

interview liigh Radiation readings in llot 14achine Shop.

s 93 r.d n.

1.

Interview ppm Bor on and 4.0 uc/ml; a further drop in Boron and 90 uln.

RCS Sample yields 400-500 t

a factor of 10 increase tai activity.

1.

Plant Strip Charts Approximately 5-10 minutes af ter the trip of the D loop 14Cp's SRM count rate instability increases again as well as continuing an upward trend. Operators 2.

Inti:rv iews Prior to 100 min.

report loop flow instability increasing again, arid thi indicated loop flow con-tinues to si.ow a d<+cr ease. Operators state they were concerned about a " seal failure LOCA" and decide to go on natural circulation. Operator stated that he started " emergency boration" during tfits period.

1.

fi&W Sojuence 109 min.

" A" loop RCP's tripped. SRM count rate spikes upward to peak at least one decaJe over count rate expe cted f ollowing a nonnal reactor trip. All radiation stonitors 2.

LilW Figures 3.

Plant Strip Charts exhibiting substantial. ramp increase.

1.

Interviews Operators stated they did not tielieve that natural circulation had been established due to the dif ferential temperature across (fie steam generator and the low sten generator pressure.

RCS was at 1020 psig and 5350F; well outside prerequisite pressure / temperature flote : conditions for establishing natural circulation.

100t ialn.

Operators report increasing IfPI flow. RCS Pressure shows increase. SRM 1.

Interviews 2.

Plant Strip Charts counts drop significantly.

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El AFSED Tit'.E EVENT DESCRIPIl0f!

1.

Interview (b!W Representative reports that the fact that EEV-12A & B were shut with no feeding to the S/Gs for 8 rainutes was not discussed the first day.

It was Jiscovered by ESW representatives later while delogging the reactimeter.)

Electromatic relief valve isolated by operator by closing the block valve (RC-V2) 1.

B&W Sequence 2.3 hrs.

2.

Interviews Operators had noted tall pipe teiaperature on relief valve 350f higher than others and t;elieved valve to be leaking. Noted a drop in Reactor Building pressure after closure of the block valve.

1.

Interview The pressure change in the Peactor Building was more marked than when "B" S/G was isolated. The plant operations group decided that the "B" S/G probably did not have a leak from the shell into the Reactor Building. The "B" S/G still had a level.

With clost.re of Et:0V, RCS pressure begins increase from low point of 660 psig and 1.

B&W Figures 2.3t brs.

reaches 1300 psig. During this period (up to 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />), no change in pressurizer 2.

Plant Strip Charts level is observed.

Prior to this point, stanJard post-reactor-trip Boron samples taken from (f.e 1.

Interview Pecctor Coolant System had been analyzed with no problems indicated or detected relative to radiation levels.

1.

Interview Fifteen to twenty people in Control Room at this time.

2 hrs.-2.5 hrs.

Area Padiation tiont tor (Ahrt) alariris at sample station. Letdown sample lineup 1.

Intervies secured.

2 brs. 33 nin.

Radiation rnont tor on Letdown line experiences a further increase of a factor 1.

Plant Strip Charts o f 100.

. Lr s 45 ntn.

t ale-up pump IC tripped by operator action according to GPU sequence. Houever.

1.

GPJ Se vence tl.e GPU sequence does nat indicate a start time. The last identified chai:ge of 2.

Lir.e Printer status ws at 4 min. 33 sec. v. hen the pu:9 was tripped. fio other status change is nated up to I hr. 13 min. 21 sec. When the line printer stopped uorking.

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a flAPSFD TIliF IVINT DESCRIPTION REFERENCES 3 brs. 13 min.

Operator opens EliOV (f<C-Rv2). High temperature noted on tail pipe of relief 1.

Line Printer valve. Not possible to ascertain at this point if Block Valve had been previously 2.

D!.W Sequence opened and if triOV was operating in automatic mode. RCS pressure and pressurizer 3.

BMJ Figure level both drop (RCS pressure to 1915 psig; pressurizer level - 300") and Reactor 4.

Plant Strip Charts Building pressure increases. A pressure spike of 5.5 psig also seen in RCDT.

3 brs. 13 min.

Operator stated that coincidant with tripping of FCP further radiation alarms 1.

Interviews received and they started following radiological emergency procecures.

2.

Plant Strip Charts Note: At about 3 hrs., the line printer displayed incore thermocouple data accumulated earlier (approx. 2 hrs. 55 min.):

Thermocoude iocatton Temperature (of)

TC 12-0 623 TC 14-H 653 TC 14-0 687 TC 13-C 577 TC 11-L L34 1C 10-C 599 TC 2-G 623 Marcover, a large number of entries were made for the incore monitoring system. Entries arpear erratic in nature.

3 hes. 13 utn.+

Date accumulated at 3 hrs. show:

Thenrocougle I ocation Temperature OF I C-l %

675.6 TC-if C94.1 IC-50 666.1 In

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Eyltif DESCRIP110il I.

Pegion ! Incident Nstagefum 1 hrs. 59 min.

ItPI flow is 250 9pa/ leg - RCS pressure 1400 psig I.

BW figures 5 hrs.

General parameters at this points:

1.

RCS pressure 1375 psig and generally stable; 2.

Reactor Building pressure approx. 4 psig and stable; 3.

Pressurize:- full; 4.

Steam generator levels 40-50% and steady; 5.

Steam generator pressures "D" decreasing slowir; f rom 325 psig and "A" at 50 psi.) and increasing.

5 trs.

Containment Dome Radiation Monitor reaches 6000 R/hr.

1.

RI Incident ifessagefom s5 brs.

Licensee reported to Region I at 0900 (elapsed time = 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />) that the Aux. Bldg 1.

RI Incident Messagefom.

was isolated at 0800. lleported that "B" Steam Generator leak was noted at 0300 by Vacuum pun:p Monitor.

1.

RI Incident Pes;agefom 5 brs. 10 min.

Region i Inspector at site reports to Region I that based on his discussions, some staf f n: embers belteved code safetles may not be closed. SG Levels A-44%,

B-66%; said S/G's isolated.

Based on first infomation recorded on Region I Incident Response Center (IRC) 1.

Region i IRC Tapes 5 hrs. 15 min.

Tapes.

1.

ItSL Safety Valves said to be shut.

2.

S/G "A" Level reported at 41%.

3.

S/G "B" Level reported at 06%.

4.

S/G are reported to lie isolated.

5.

RB Spray had not actuated yet.

Convinced steam in e x h loop, decided to raise pressure and collapse unwanted 1.

Interylew M hrs 15 mins.

Vertfled again Ett0V block valve was shut. (Recall position stem Lubbles.

"indicattua" shu.is valve position demand rather than actual location.) Increase in Illgh Pressure injection flow is directed.

23

O N

O T

N ElAP'fD TIf:E EVENT OfSCRIPTION REFERENCES 15 f.rs.15 riin. (Continuel)

Concerned if RCS pressure Vent too high, it could cause code safeties to he opened. Decided to control pressure at 2000-2100 psig using ifXW and its block valve.

5 hrs. 17 min.

Reactor Building Air Cooler D started.

1.

Line Printer.

5 trs. 18 min.

Block valve on Ef t0V opened. (When thli valve was previously closed is not known 1.

B&W sequercc at this time.) Building pressure starting to decay and RCS pressure rising.

5 hrs. 19 min.

Decay heat pump 1 A turned of f.

1.

Line Prin.ter 5 brs. 21 min.

LSF Actuation in Red anel Blue Channels due to 4 pst in Reactor Building cleared.

1.

Line Printer 5 trs. 25 min.

ESF Actuation in Yellow Channel due to 4 pst in Reactor Building cleared.

1.

Line printer 5 Frs. 30 min.

ESF Actuation in Green Channel due to 4 pst In Reactor Dullding cleared.

1.

Line Printer 5 brs. 31 nin.

Group 3 of the pressurizer heaters trips and remains inoperable for the re-1.

Line Printer malnder of the period covered by this sequence. No more than 9 heater groups are now operational.

5-6 hrs.

Note:

1. Reactor Building pressure showed a peak of 4.4 psig and trended down-1.

Plant Strip Charts ward to 1.6 psig during this period. SRf1 count rate showed a general decrease with no anom311es. Steam Generator "A" level raised to 95%

f roni 501. (Reached at approximately 6 hrs. 20 mins.)

5 hrs. 35 min.

Region I inspector reports to Region I that:

1.

R:I IRC Tares 1.

Dellef expressed that S/G pressure transient prol; ably lifted S/G Safety iellefs.

2.

No one had been evacuated from site yet.

3.

No conslieration of of f site evacuation yet.

4.

Licensee reported to have stated have no significant leakage.

5.

No significant offsite activity reported yet.

24 (next page is 26)

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t El APSED TlHE IVENT (1ESCRIPTIO!1 RFFERENCES Region I inspector reports:

6 hrs. 14 min.

1.

reported 140 uc/cc gross 8-y activity in RCS 1.

R:1 IRC Tapes 2.

concerned "It" S/G primary + secondary leak may lead to burp of activity 1.

R:f IPC Tapes from safety reliefs. Water level high at 45%.

6 hrs. 15 nin.

"Still injecting" anJ InlST level dropping based on report from Region I inspector.

1.

RI Incident Messageform 2.

R:I IRC Tapes Region I inspector reports:

6 hrs 17 min.

1.

Unit 2 people having to don masks 1.

RI Incident Messagefom 2.

Using "A" S/G for cooling. Delieved natural circulation was working.

1.

R:I IRC Tapes 6 trs. 27 min.

Everyone inoved to Unit 1 CR except essential personnel.

1.

R:I IliC Tapes 6 hrs. 52 min.

Low Vacuum Trip, feedwater Turbine A 1.

Line Printer Note:

Not many lef t Control Room as result of evacuation order.

I, Interview Note:

Door to Unit 2 Control Room without automatic recloser. People failed 1.

Interview to close on their own, possibly compromising recirculating ventilation system).

6 '.rs. % nin.

NRC Inspector reports trying to cooldown using "A" S/G and Atmospheric 1.

RI Incident Onmps, possible Buthie in t oth PC pump legs;31 feet lef t in I"lST.

liessa wform h essurizer Lcvel > 4h0" feeding "A" S/G with (mrgency Iced.

2.

R:1 IEC Tapes l evel in Conta tunent in. fica ting

>6', which is maxtraum possible level ir dication.

1.

R:I IPC iares tloisa level in liait 2 fontrol Doom reported to be high with 20> pe,ple.

1.

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CD T

N El f PSE D TIMI EVIrli DESCRIPTIOil RE FE RE f!CE S 7 brs. 9 min.

EfW Pump 2A on.

1 Line Printer 7 brs. 19 min.

EFW Pump 2A off.

1.

Line Printer s7 hrs. 30 nin.

Reported that Pressurizer lleaters were unavailable. Concerned that [MOV block 1.

Interview valve might fall open. Decided to drop pressure.

Didn't appear to be getting anywhere so group decided to drop pressure to get 1.

Interview Core flood Tants (CFI) float on core.

Were controllinc pressure with the llPI and [f*0V.

Were concerned IIPI might be 1.

Interview bypassing core since Th sf>20. Tc s220 and Pressurizer Water Space RID was rel-atively constant at 35Uof. Wanted to mate sure core was covered so decided to depressurlie, flote:

Steani Tables were referred to several times by Control Room personnel 1.

Interview during sequence.

7 brs. 30 min.

Operator opens electromatic relief valve to depressurize RCS to attempt Initiation 1.

B?.W Sequence of OliR at 400 psi, interlock at 430 psig. DF.W sequence states that IMOV block 2.

Pt.W figures valve was opened at this point. Reactor Building pressure shows rise from low 3.

Plant Strip Cnarts f oint of 0.2 psig tn 2.5 psig during this RCS depressurization.

7 hr s. 40.aln.

"B" S/G ts battled, but appears may have to relieve its pressure.

1.

R:1 IRC Tapes 2)

C N

CD W

N El f 05f D Tit'F IVENT DESCRIPTION REffRENEf5

/ brs. 40 min.

Region 1 inspector reports that licensee thinks they have release under control 1.

RI Incident I:essagefom per superir.tendent.

7 brs. 42 ntn.

f SF MB bypassed. Reactor Pressure at that time is 1650 psl. Believed to be 1.

Line Printer operator action to prevent inadvertant actuation of !!PI during depressurization.

2.

Plant Strip Charts 7 trs.14 min.

Pressurizer heater groups 1 and 2 trip tut are reenergized within 2 seconds.

1.

Line Printer 1 hrs. 50 min.

Pressurizer heater groups 1 and 2 trip and remain in a tripped state for 2 hrs.

1.

Line Printer 16 min. At this time, there are no more than 7 heater groups operable.

Note:

Throuqhout depressurization pressurtzer level did not change from 400 1.

Bt.W Figures Inch Indication. Reactor pressure decrease also shows discontinuity 2.

Plant Strip Charts at 1400 psig at about this time.

7 hrs. SS min. 2 Using atmospheric dumps now. Ilnit I reported to be in llot Standby.

1.

R:1 IRC Tapes 8 hrs. +

As the operators reduced pressure, they had even greater problems maintaining 1.

Interview adequate letdown flow. Personnel hesitated to take corrective action for concer ns relat?ve to NRC tolerance of deliberate over-exposure required to mai.jpulate those valves necessary to regain adequate flow.

8 hrs. 12 ntn.

liigh level (M!cated on core flood tank A (13.3 feet of water). RCS pressure 1.

Line Printer at tha* point was rpproxima*.ely 800 psl.

2.

Plant Strip Charts 8 1.rs. 20 min.

Pressurizer level is off scale high. Delieve bubble exists in S/Gs.

1.

R:1 1RC Tapes B hrs. 33 ntn.

Decay he n cooling pump *, lA and 1G started.

1.

Line Printer 8 brs. 41 min.

PCS pressure reaches 600 psig which is equinient to the nominal gas pressure 1.

B?.W Sequence maintained in the Core Flood Tank (CFT) nitrogen rover gas.

2.

Plc,nt Strip Charts 30

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FI APSED TIMC FVf flT DESCRIPTIOff RffEREllCf5 9 hrs. 15 min.

Region I infonned that Condenser is isolatcd.

1.

RI Incidcnt liessageform 1.

Reported llarrisburg IP Exit at 25 mr/hr using uncalibrated instrtment.

1.

R:I IRC Tapes 2.

Core flood Tanks have partially injected.

3.

BWST now at 31 feet. 600 psig in RCS.

4.

lloping Core flood Injection will drop temerature allowing use of Decay lleat 1.

R:I IlC Tapes Renoval (DHR) system.

19 hrs. 15 min. +

Personnel felt core was demonstrated to he covered when CFI level dropped only 1.

Interview slightly upon dropping itCS pressure below CFT blanket pressure. Attributed in-ability to drop below 450 psig as sign lad reached saturation pressure of loops.

Would he unable to depressurize further without some wchanism for cooling those loops.

9 hrs. 17 min.

Oper ator closes EliOV Block Valve, Core flood Tanks indicate slow discharge, fM 1.

Operatir.g Logs indications of changes seen on RCS pressare or pressurizer level instrumentation.

2.

Plant Strip Charts Pressurizer still at 400 inches. Reactor Huilding at 2.6 psig and decreasirig.

Bf>W Figures O

togs indicate "Stoppel itPI" (Initiation time not known - not confirrned by line printer).

9:15 + 9:13 f;RC inspector reports steam dun:ps closed.

1.

RI Incident !bssagefom imC expresses concern th1t leaving Core Flood Tank isolation valves open tuy 1.

R:I 1RC Tapes lead to injecting fi into vessel.

2

'; hrs 22 nin.

IfDV tailpipe temperatures showing decrease.

1.

t.ine Printer I

W IN CD

-;;t-N d

ElfPiED TIP.E EVf MT DESCRIPTIOil REFEREtlCES 9 hrs. 30 aln.

Reactor Building pressure 1.6 psig. SRM count rate continuing to show slowly in-1.

Plant Strip Charts creas ng level.

2.

Operating Logs i

Pegion I inspector reports from site that State of Pennsylvania was concerned 1.

R:1 1RC Tapes about Steam Dump.

9 hrs. 35 ntn.

Region I inspector, in response to question, states to Region that Pressurizer 1.

RI Incident ficssageform relief valve is closed.

2.

R:I IPC lapes 9 hrs. 45 min.

Pegion I inspector reports to Regional Office that DHR will be initiated when 1.

C-14 cf RI Incident itssagefern RCS pressure gets to about 350 psig.

1.

Rx Press s500 psirj.

1.

R:I IRC Tapes 4

2.

Temperature s250"F.

3.

Pressurizer being vented to Vent lleader.

4.

Norm 1 letdoun in operation.

5.

Pumping Bleed Tank to Core flood Tanks to complete water cycle.

9 hrs. 50 min.

ESF actuation t y high building pressure. Building pressure experienced spike 1.

Line Printer to 20 psig (inificated) af ter reaching low of 1.4,,sig.

Ilullding spray pumps on 2.

Plant Strip Charts within 6 seconds and 30 psig actuation clears within 11 seconds. fot able to confina at this tim if pressure strile of similar magnitude exhibited in RCDf.

!:CS pressur i shows raplil 50 pst decrease and recovery to 500 psig at that sa:ae t irc.a. fM eup pump IC starts (IB already operating). Itikeup pump IC tripped in 40 seconds.

O,arator reports that the alarn occurred simultaneous with his opening of the 1.

Interview I U/

4:ii f t M ervisor I elieved he f ait a " noise" or electrical cross connection

' ',l d y i e ld.1 " i al <. " s i t;r.a l. Supervisor rupsest'd aid frcm instruu ntation people.

D. 3 questlun e.sists as to whether this infoncation was passed to management on site.

31

~

N

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~

RE FI FT flCES Et "I M D flite EVffiI DESCRIPil0N 9 brs 55 min.

Unit i CR still in Respirotors.

1.

R:! 1RC Tapes 9 hrs 55 mln.

Pressurizer heater group 8 trips and remains tripped for the remainder of the in-1.

Line Printer tident. At this time, no more than 6 heater groups are operable, 1.

Line Prjnter 9 hrs. 56 min.

Iteactor Butiding spray was shut down.

2.

O p rator Interviews 9 brs. 53 min.

Core flood tank A level alarms in.!!cate varying levels over the next 1 1/2 hours, 1.

Line Printer tietween a low of 12.3 feet to a high level at or above 14 feet. During this 2.

Plant Strip Charts period RCS pressure slowly increased to Sf>0 psig. These alailris continued inter-Inittently over a period of approximately 1 1/2 hours.

10 hrs. 6 min.

Pressurizer heater groups I and 2 return to normal but trip again within I min.

1.

Line Printer 51 seconds.

10 hrs. IS nin.

RCS Pressure s500 psig.

1.

R:1 IRC Tapes 0

Th 600 F 0

I 230 F c

Suspect Bubble in Loops Reported to t>e Venting Pressurizer 34

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CO CD 4

N fttrith IIPE IVINT DESCRIPTION RLfrornr s 10 hrs. 36 min.

flake-up Pump 10 tripped off.

1.

Line Printer a.10 hrs. 41 min. t 1.

All the Auxiliary Hullding Sumps are full.

1.

R:I IRC Tape 2.

A Region 1 IIP Indicated his tour of Auxiliary. Building identified no visible leans, just water on floor.

10 brs. 45 min.

Operators note that hot leg temperature returning on scale again. Pressurizer 1.

Interviews level starts steady decrease to 100 inches from 400 inches (minimum level 2.

D?.W figures react ed at about 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> 24 miriutes).

sl0 brs. 57 min.

Region I inspector reports current status to be:

1.

R:I IRC Tape T 550"F h1 ?uPF FbSPress450psig Plan to go into UllR via fiWST.

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l EtAPSID IIFE EVifH DESCRIpiluff Rf FE PC t;Cf S 11 hr s. 18 min.

Loop A cold leg temperature star ts rapid increase from 200"f to 400 f.

RCS 1.

DW Sequence 2.

BW figures pressure rapid increa".e of 50 psig.

3.

Plant Strip Charts 11 hrs.19 min.

f!a6eup pump IC started and runs for less than 10 minutes and tripped. Restarted within 5 minutes and runs for 1 minutes until 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> and 36 minutes.

11 l.rs. 24 min.

Pressurizer Icvel begins steady increase to 400 inches from 180 inches, reaches 1.

DAW Figures 400 inches at 12 hcurs, 30 minutes.

sll hrs. 28 min. +

Only one 16 valve open. Pressurlier level 175" (Per Operator in tinit 1 Control 1.

R:I 1RC Tape Room speaking to Region I of fice - potential time lag).

Periodically bumping electronatic. Worried continued burping relief might cause it to fall, failure mode uncertain. tiot using S/G cooling at all at this point.

11 brs. 29 min.

Pressurizer heater groups 1 and 2 trip but are returr.ed to nonnal within 17 mins.

1.

Line printer

' erating Logs 11 brs. 32 min.

Operators indicate method of cooldown at this time is one high pressure injection 1.

pump and the core flood tanks. (Region i Incident liessagefona states pressurizer 2.

Ha incident itessagefom 8

level 166* and periodically cycling Lt:0V).

1.

RI incident Messagefom 11 trs. 34 riin.

North Gate 30 rir/hr.

2.

R:1 IRC Tape I.

Line Printer 11 brs. 36 min.

MW pump 2B turned on and shut down 16 minutes later.

1.

R:I ITC Tape sll br 43 min.

Reported readings from Unit 2.

RB Pressure O psig Pill I evel 1/U" P/R Temp.

4 W"F P/R Pr ess.

450 psig ll trs. 59 ain.

IFC senior raan u;er ad s licensee operator (over telephone) to conmunicate NPC 1.

R:1 IRC Tape concern that Pressuriier level indication d6as not preclude bubble in core, that te.4erature readings indicating superheat may be real and implying core is uncovered. Uuuld then need to put water into core.

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IlfsPSID TIME

[VEN! Of5CRIPfl0N FffEPINCES 5.

fiorinal letdown at 120 gpm.

6.

Makeup Pur..ps feedin<; from OWST.

7.

B?.W Calculations indicate 120 gpci insuf ficient to remove current core d* cay heat.

8.

Operating electromatic reifef and (Pressurtzer Vent Valves) periodically to remove adilitional heat.

9.

Plan is to estabitsh vacuum in condenser, steam "A" S/G and remove core heat through natural circulation.

12 hrs. 30 min. +

flote:

Reported licensee tiel' eves A loop is solid since: Original Th IMC loops) s/000 with Tc *225"; Directed til to A loop to collapse steam l ut ble and its hy dropped quf te rap!dly to s515"F. At the same time PlR level 'frepped considerably and curve back on scale.

12 f.rs. 35 min.

Tallpfre temperatur. alarms received on EMOV and both pressurtzer safety valves.

1.

Line Printer s12 hrs. 45 min.

"A" loop Th reported s580"f.

1.

R:I IRC Tare 12 t r s. 15 n. i n.

Ikylen I insrector reparts conditions are : pressure 450-500, continuing nontal 1.

RI Incident tiessagefem leto wn (120 grm), and !!10V orening intermittently. lowest pressure reacted 2.

R:1 IFC Tape 450 psiq during bio.vdown end it just " hung" there. flothinq tried so far coi;1d drive it 1wer.

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n-fl M 5!0 Tir'E EVENT MSCRipTIcil FE FEFE rice S s13 hrs. 23 ntn.

Reported by Region ! Inspector:

1.

R:I 1RC Tape 1.

15" Vacuum in Condenser.

2.

Just starting to steam now.

3.

s650 psig.

Thb 650-700 F 0

T 570-500 f Tcbha & a 2250F 4.

Electromatic Relief indicates closed.

13 hrs. 23 min.

Makeup pump IC starte.t..

1.

Line Printer 13 hrs. 26 min.

Pressurizer heater groups 1 and 2 trip. At this time there are now no enore than 1.

Line Printer 6 operable pressurizer heater groups.

13 firs. 30 ntn.

Electreratic relief valve closed to: repressurize RCS. collapse volds, and 1.

IE Bulletin 79 05A prepare to start RC purp. Plant charts confirm pressure increase, but unable 2.

Line Printer to confim closure of Ep.0V block valve. flowever, at 13 hrs. 25 minutes.1he printer shows tallpipe temperature returning to normal.

Ncte:

Regarding dacision in repressurlie RCS. Interviews indicate that Control 1.

Interview Poo.1 personnel had desired to reiniin in depressurized statt-since had regnincJ Pressurizer Level, appeared to have collapsed but,ble in "A" loop and were pt ogressing on doing sane to *B" loop.

Af ter decision to pressurize. Control Poon personnel recornend restart of RCP to succp vapor from 1 cop.

13 f.cs. 32 ntn.

RCS Pressure 625 psig.

1.

Operating togs 13 brs. 35 min.

RCS Pressure 645 psig.

1.

Operating togs 42

4 CC CO CD v

+

N It?!MO I!!C FVENT DESCRIPTI0fi Ef f f M lK f 5 13 hrs. 37 min.

RCS Pressure 660 psig.

1.

0;erating Logs 13 hrs. 40 min.

RCS Pressure 675 psig.

1.

Cperatir.g Lcgs 13 hrs. 40 min.

"A" S/G valve not optning - not steaming. D!eed valve for generator to cond(nser.

1.

RI incident Messagefern Start investigating. Indicator must be in error.

2.

R:t RC Tate 13 hrs. 41 min.

RCS Pressure f,90 psig.

1.

Operating Logs 13 hr: 42 r:in.

RCS Pressure 705 psig.

1.

Operattrg Logs sl3 hrs. 45 min.

Reactor Dullding Pressure is -0.2 psig.

1.

R:1 IRC Tare 13 hrs. 50 min.

RCS Pressure 765 psig. (Pressurizer level 285 inches).

1.

Operating Legs 13 hrs. 50 min.

"A" S/G started steaming using turblae bypass valves to condenser. ' Indication 1.

RI incident Fessagfom of level change in steam generator and indication of feedwater flow.

2.

R:1 IPC Tage 13 brs. 50 min. +

Nat now wearing respirators in ll11-2 Control Room.

1.

R:1 IP.C Tape 13 hrs. 55 utn.

RCS Pressure 800 psig.

1.

Operattn] Lcgs 13 brs. 53 min.

RCS Pressure 835 psig.

1.

0;'erating Logs 14 hrs. O Min.

RCS Pressure 860 psig.

1.

Operating Legs it brs.

Legion 1 Inspector reports DWST 23'.

1.

RI incident Messagefcrm 43

CN CO C-N f l 'I" f il II.EE_

[Vf flT liESCRIPil0'l ICEf f rf NCIS 14 hrs. +

1 Region i Inspector reports: Licensee staf f or senior management have concern 1.

R:I 1RC Tape whether core covered or not.

2.

lhe plan has changed now.

Licensee plans to centinue cooldown by steaming.

"A" S/G ih now 5 E01, T now 446"F.

Ihey increased mncup to 480 gpm with c

letdo..n at 40 gpw. letting pressure increase and plan to take plant solid at s2000 psig to collapse all bubbles.

14 hrs. 4 min.

RCS Pressure 900 psig.

1.

Operating Logs 11 trs. 7 min.

RCS Pressure 945 psig. (CWST 24 ft.)

1.

0; erating Lojs 14 f.rs.10 ntn.

RCS Pressure 1012 psig (Pressurizer level 370 inches).

1.

Operating Legs 14 hrs. 15 min.

RCS Pressure 1120 ps,g.

1.

Operating Lcgs 14 hrs. 17 ntn.

• Region ! Inspector reports:

1.

R:1 !!C lape 1.

Continuing cootdown of "A" S/G. 1he AT for A" loop is increasing.

Ty 555 Thb (250-700(*)

2.

RI frctdent Massagefom I ca 300 Tcb 200

(*) = Old data from last time ISW manually read back panel Thermcouple or IIID parameters.

2.

Ibkeup at 450 gna. Pressure 1100 psig increasing, Pressurizer full leut pressure increase indicates bubble still exists s<newhere in system.

3.

Using condensate pumps, not emergency feed, for S/G.

14 hrs. 23 aln.

FCS Pressure 1203 psig (Pressurlier level 400 inches and PW5T level 23 ft.).

1.

Operating Lcgs 44

CD ON CD

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I t tyN D TIFT EViNT OfSCRIPTION R E F E P.E f.CE S sl4 hrs. 29 nin.

Region I Inspector reports:

1.

R:I IRC Tape 1.

S/G 1evel s907..

2.

27" Vacuui.i in condenser.

3.

'tialn Steam Bypass valve indicates 30% open.

14 hrs. 26 min.

Pressurtier teater groups I and 2 return to normal. There are now no ra.re than 1.

l.ine Printer 8 operable pressurizer heaters.

14 hrs. 30 min.

RCS Pressure 1520 psig (at approximately this time, the SRf1 count rate showed a 1.

00erating Logs rapid rise and then decayed to a point telow its starting value).

2.

Plant Strip Charts 14 hrs. 33 r11n.

RCS Pressure 1700 psig (Line printer shows 1000 pst interlock cleared at 32 1.

Operating logs minutes).

2.

Line Printer sl4 hrs. 34 min.

Region I Inspector reports:

1.

R:I IRC Tape 1.

Still steaming "A* S/G, tot indications not getting much natural circulation.

2.

T sS700f. T s??cof; one Incore T/C reads 570, Indicating T3 may be accurate; 8

ok,iler T/Cs cb6 not be read.

D&W Site Representative contacts E&W at Lynchburg who indicate that they had also 1.

Interview come to corriusion that licensee should repressurize and start a RCP.

It hrs. 34 rrin.

RCS Pressure 1781 psig.

1.

Line Printer 14 hrs. 35 rtin.

RCS Presswe 1890 psig.

1.

Operatir.] togs T =570. T =220 2.

RI IncWnt Messagefe,m h

c 14 brs. 35 min +

Region I Inspector reports:

1.

R:I IRC Tape 1.

1800 psig increastr.g.

2.

Indication sane bubbles may le collapsing since lieve seen some temperature changes.

45

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EVEtti UESCRIPTIO.'l REFERENCES h4 hrs.52 min.

Region I Inspector reports RCS 2300, Dubble still in "B" loop, "A" loop T = 560, 1.

RI Incident Messagefom h

Tc=320, 100,000 l/hr condensate flow in "B" steam generator, "A" steam generator 50 psi.

15 brs.

1.

Reports Th cropping slowly. Tc rising slowly. Delleve getting some 1.

R:I IRC Tape natural circulation flow, but still very little.

2.

Licensee has considered starting RCP, but unabic to do so since has lost power to RCP oil pumps. Itaving problems restoring power to oil pump bus because of high radiation and contamination levels.

15 brs.

B&W in Lynchburg has been contacted and is doing calculations for 1HI.

1.

R:1 IRC Tape Proceeding to attempt start of a RCP.

Inspector reports T a=560. Tc3=360. Tcn=2200 1.

RI Incident Messa.geforn 15 hrs.

hihb of f scale high 2J00 psig 2.

R:1 IRC Tape 15 hrs. 4 rain.

HQ-f;RC were of opinion might have to bump RCP to clear " candy-cane" of volds 1.

R I 1RC Tape to allow full natural circulation, since trend of parameters strongly suggest little o: no natural circulation is occurring.

15 hrs. 10 min.

Inspector reports Th 557. Tc 380, il 240, 2300 psig.

1.

RI f acident Messagefom Steam Generatar "3" 100 psig 2.

R:1 IRC Tape Steam Generator "A" 20 psig sl5 hrs. 15 nin.

1.

Ileaters now on in an attempt to draw a bubble, but currently level is off 1.

R:1 1RC Tape scale high.

2.

Since no power to.\\.C. RCP oil pump, trylpg to start D.C. RCP oil pumps.

Interview indicates liceisee had to send operators to Auxiliary Building to 1.

Interviews assist in starting RCP ofj pumps.

15 trs. 20 min.

Pegion I Inspector reports that 0WST 22 Ft. St111 steaming; "A" loop af decreased, 1.

RI Incident Massagefcm RCS Pressure 2300. Increasing Temp with heaters. Trying to steam down "A" 2.

R:I IRC Tape S/G 1evel and have secured feeding it.

Th 560 f Tea 3950 Tcb 220 futeup and Letdown 40 gpa Reactor Building Pressure = -0.2 psig Pressurlier Imp inu casing with heaters on

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4 M H!1_IIE EVffiT OFSCRIPTIGR FE rf Fi tC.E5 l!, hrs. 50 min.

Italeup Punp IC started.

1.

Operating Logs 15 brs. 51 min.

Started RCP and let it run. Flow and amps look good. Reactor coolant pressure 1.

Operatioq Logs 1321 psig. (Log did not note if LS' actuation received a Time period Leyend 2.

R:I IRC Tape that covered by line printer data available at this time. gain.

1.

Loop T mperatures:

A.

Loop Cold Leg: 340"F B.

Locp Cold Le,g: 338PF 2.

Steam Generator Pressures:

A.

Gererator increases from 0 to approxtrnately 40 psig.

B.

Ger crator decreases from 140 psig to approximately 50 psig. (Tsat 0

approximately 330 f0.

41