ML20136H213

Intervenor Exhibit I-TMIA-35,consisting of Revised Set of Annotated Reactor Bldg Ambient Temp Recorder Charts from 790328 Event.Log of 790328 TMI-2 Event Sequences Re Reactor Bldg Temp Pressure Encl

ML20136H213
Person / Time
Site:	Three Mile Island
Issue date:	12/13/1984
From:	Crandall W GENERAL PUBLIC UTILITIES CORP.
To:
References
SP-I-TMIA-035, SP-I-TMIA-35, NUDOCS 8508200229
Download: ML20136H213 (16)

Text

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l TMI-2 REACTOR BUILDING AMBIENT TEMPERATURES TEMPERATURE RECORDER CHART l .

March 28, 1979 - Time 0400 thru 1815 a

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j Temperature Sensors l Point 10 (RCDT area) .....&.....-

Point 12 (Elev. '353') y

Point 13 (Elev. 330') g i

Point 14 (Elev. 330') .

Point 15 (Elev. 310') -

Note: Due to chart slippage, all times are. approximate.

I Willard A. Crandall GPU SERVICE CORP.

July 6, 1979 i ,

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LOG OF SEQUENCE OF EVENTS PERTAINING TO REACTOR BUILDING TEM"ERATURE AND PRESSURE March 28, 1979 - Time 0400 thru 1715 The following data is abstracted from:

" Review of Preliminary Annotated Sequence of Events, March 28, 1979, Revision 1" by Robert L. Long, dated June 28, 1979 Willard A. Crandall GPU SERVICE CORP.

July 9, 1979 e

9

1. ;

. s-i t Tise Event

. e a.

- 00:00:03 The Electroestic Rettet V"alve (RC-R2) opened at the setpoint i (0400:40)

Approaimate of 2233 peig 00:00:13 De nectroostic Relief Valve (RC-R2) should have shut at about (0400:50)

Appreminate this time (closure setpoint of 2205 peig). The Electroestic Relief Valve position indication in the Control Room is a red laap which 111minates when the Elsetromatic Relief Valve solenoid is energised. them the lamp is illuminated i.e. solenoid energised, under merual circumstances the valve should be open. Een the lamp is estinguished i.e. solenoid de-energized, under normal circusersaces the valve should be closed; however. it could be in any position as the lany only indicates the solenoid is de-energized and not valve position. The solenoid on the Electrosatic Relief valve (RC42) de-energised at approsisately 00:00:13 (0400:30) resulting in sa implied " shut" indication la the Control Room.

Although the plant operatore did not know at the time subsequent events showed that the valve had failed to shut. The loss of reacter coolant through RC-R2 was not stopped suitil the Electro-natic Relief Block Velve (RC-V2) was shut, approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

- and 19 minutes af ter the start of the transient.

00:00:30 Pressurtser Safety valve (1C-RIB) and Electrosatic Relief Valve (0401:07)

(RC-R2) discharge line temperature alarma were received and

- values of 203 3 F and 239 2 T. respectively priated out. The high temperatures in the discharge lines wir e a result of the

^

high temperature stese flow through the Electroestic Relief valve (RC42) during the reactor pressure transient. The Pressuriser Safety valve (RC-R13) did not openg the RC-RIE temperature alaru

~

received was due to the back flow of steen la the common discharge header shared with the Electroostic RQief Yalve (RC-R2). Thes's alaras were espected by the operator.

00:01:00 Fressuriser level started increasing (Tigure 28). Reac tor 1

(0401:37)

Approminate Cool' ant System hot leg and cold le; temperatures reachcJ i

. approat=ately $75F (Tigure 6). The Reactor Coolant Crain Tank

^

pressure was 12 psig ar.d increasing (Tigure 41).

00:01:00 The Pressuriser safety Valve (I.C-RIA) high discharge line temper.

(0401:37) ature alors was received. This alarm was espected and resulted free back flow in the cosmos discharge heade,r shared with the Electrocatic Relief valve (1C-E2). ,

2.

Time tveet )

)

. e .

00:01:26 A Reactor Coolant Drain Tank temperstare normal alars was *

(0402:03) received and printed out a tersperature of 83.5T. Die indicated

• t the Reacter Coolant Drain Tank tesperature was increasing and 4

had reached the normal range. .

00:03:12 The Reactor Coolant Drain Tank Relief valve (L'DL-ill) lifted (0403:49)

Appromisste at 120 peig temporarily halting the Reactor Coolant Drain Tank

~

pressure increase '(Tigure A1). D e pressure increase was cauaed by the flow of reactor coolant from the Electrocatic Relief Valve (RC-R2). The RCDT Relief Valve (k'DL-R1) discharges to the Reactor Building susp.

00:03:26 The Reactor Coolant Drain Tank hi;h tasperature alars vaa received *

(0404:03) at 127 2T.

t FLANT STATUS ne Reactor Coolant Systes pressure was 1420 peig and steadily decreasing to the saturation.p' ressure of the Reactor Coolset Systen hot leg tempera-ture (Figure 3). Se continued Reactor Coolant Systes depressurization

. wea due to the failure of the Electrosatic Relief valve (RC-R2) to reseat.

and reduction in Migh Pressure Injection flow rate. Ingineered Safety Features. which actuated nigh Pressure injecties when pressure reached 1640 peig, had been bypassed by the operator to permit manual control of the Makeup Fumps and the M1gh Pressur's Injection Isolation valves. As the Pressuriser level continued to increase, the operator stopped Reactor Coolant

, Makeup Fusp C (MU-F-1C) and throttled the Nigh Pressure Injectica Isolation I Valves (HU-16A and MU-V163) in an attempt to control the Pressuriser level and not take the Pressuriser '*aolid" (Tigures 3 and 29). De Raatter Coolant f Drain Tank Relief Valve (CL-al) had opened at 120 paig and was discharging

, l to the Reactor Building Susp (Tigure 41). A Reactor Coolant Drain Tank high temperature alarm had been seceived.

De temperature and pressure of the tank continued to increase. Se Stres Generators had boiled dry as indicated by a continuously decreasing steam pressure while Reactor Coolant systen hot les and cold-les temperatures incrassed (Figures 19, 24 and 32). Sie wee due to the Emergency Tesdwater i 11ock Valves (ET-V12A) and EF-V123) being closed. De operator did not l

realise EF-v12A and ET-V123 were shut. Se Steas Cenerator's startup level indication remained at approminately 10 to 14 inches. A level of 8 inches or less in a Steam Cenerator to considered indicative of a dry Stese I Cenerator.

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Ttee Event

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'* 00:05:54 Pressuriser level increased beyond the range of the instrument (0406:31) indication.

t 00:07:31 Reactor Building Susp Pump A (kTL-F-2A) started on high Reactor (C408:06)

Bu11dus Sump level. De increased sump level was due to the discharge from the kaactor Coolant train Tent L411af Valve (kVL-11) I

• i

• thich had been open for approats.ataly 6 minutes. The b actor Building Susp Pumpe generally started about esce per shif t. For this reason the pump start would not have been considered estraordinary by the operator.

Wete Each Reactor Building Sump Puer has a capacity of appromisatel) 140 gallons per minute as sensured from the Reacter Building ,

Susp to the Miscellaneous Waste Holdup Tank. hacords indicate the Miscellaneous Wasta Holdup Tank level did not change during the incident and it .ts therefore believed the pump discharge was aligned to the Auxiliary Building Susp Tank.

I The operators however believe the pusp*e discharge was aligned to the Miscellaneous Waste Moldup Taek.

00:08:00 The operator discovered the Energency Teodveter 31ock Valves (ET-V12A (0408:37)

Approziasta and ET-V125) were shut. He opened ET-V12A and ET-V125 admitting emergency feedwater to the Stasa Generators. Indicated Stese Generate i' levels were approminately 10 inches just prior to feeduster addition (Tigure 35). A rapid rise in both Steen Generators' Fressures was observed when feedwater was admitted to the stese Generators (Tigurs 32). Addition of feedwater was also confirmed by a decrease in the i I

Energency Teodwater Pump *e' discharge pressure and by "hassering" and {

l

! " crackling" heard from the loose Part Monitoring Systes which vae I ,

aligned to monitor Steam cenarator A (Tigure 49).

l

.. 00:14:50 The nesctor Coolant Drain Tank Rupture Diaphrega (kVL-U26) burst l (0413: 27) at about 190 pois (Tigure 41). Destga burst pressure se 2001 f

25 pets. The contents of the Reactor Coolant Drain Tank were

! released to the Rascto,r Building stacephere.

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• 00:19:23 The Reactor Buildics Furse Air hhaust Duct A radiation monitor 3 (0420:00) i Approminate (HP-R-225) recorded an increase in radioactivity level. The level 'l increased from 1 x 10 counts per minute to 5 x 102,,,,,,,,,

sinute on the particulate channel. Additionally, there were slight radioactivity level sacreases noted on:

(a) Reactor Building Furge Air EaLaust Duct n (MF-R-226) - parti-culate moattor (b) Reactor Building Furge Air hhaust Dust 3 (HP-R-226) - gas sonitor (c) Auxiliary Building Furge Air hhaust Duct (before filter)

(HP-R-222) - gas monitor *

(d) Ana111ary Building Furse Air hhaust Duct (af ter filter)

(NF-A-222) - particulate monitor .

! 00:24:33 The operator requested the computer to print the Electromatic l l (0423:35) l Relief Valve (RC-R2) and the Pressurizar Safety Valves (RC-RIA and l RC-RIB) outlet tenperatures. Respective values of 283 4F, 263.9F and 273 1T were indicated. The operator attributed the temperature i

level to the normal cooldown of the discharge header following the initial opening and closing of the Electromatic Relief Valve (RC-R2) and believed the Electrosatic Relief Valve (RC-12) to be shut.

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1- 00:25:C0 High radiation alarms were received at the Radiation Monitor Fanel (0423:37)

Approminate froe Intermediate Cooling 14tdown Coolers A and S Radistica Nonitors (IC-R-1091 and IC-R-1092). This alarm is periodically received i because of its low slara setpoint and sensitivity to background t

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radiation. The Interned 13te Cooling 14tdown Cooler Radiation i

Monitors are physically located next to the Reactor Building Su::p.

The alares were believed to be the result of increased background radiation levels caused by the Beactor Coolant Drain Tank discharge of reactor coolant to the Reactor Building susp.

.. 00:29:23 The Beacter Bu11 Jing Air Sample Line monitor (HP-R-227) gas channel (0430:00)

Approsisate count rate increased from 1 s 103 counta per minute to 5 x 10' counts per nimute and then decreased to 1 x 103 counts per minute.

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' 00:32:23 i

The following radiation monitor readings increased and leveled off.

(0433:00)

l. Approximate (a) Cas channel of the Station Vent (EF-R-219) sonitor

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' (b) Iodine channel of the Fuel Handling Building Exhaust Duct (before filter) . (hP-R-221A) sonitor I  !~

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S. .e

. t l Tiee T"'

. 4 .  ! (c) Particulate channel cf th3 Tuel Randling Suilding Enhavet Dust I

' (before filter) (HF-R-221A) monitor (d) Iodine channel o/ the ruel Handling Su11 ding Exhauet Duct (af ter filter) (RF-R-2213) monitor (e) Particulate channel of the Tual Handling Building Exhaust Duct

'(after filter) (HF-R-2218) sonitor (f) cas chaarel of the Tuel Handling Building Exhaua't Duct (after s

filter) (EF-R-2211) monitor (3) Particulate Channel of the Hydrogen Purge Duct (HF-R-229) sonitos j (h) Iodine Channel of the Hydroges Furse Duct (RF-R-229) sonitor 00:32:36 Incore thermocouple R-10 indicated signal was out-of-range (0433:13)

(Bange = 0 to 700 T). It is believed that the Incore hermo-e couple failed.

! 03:38:10 The aus111 sty operator stopped tasetor Building susp Fusp A (WD:,-F-2A; (0438:47)

The operator believed the pucy discharge was aligned to the Waste ,

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Holdup Tank and therefore, stopped the pump to prevent the overflow

• of the Waste Holdup Tank.

. l 00:38:11 The sua111ary optrator stopped Reactor Building Susp Fusp' 3  ;

(0438:43) g (VDL-F-28). The operator believed the pump discharge was aligned t to the Vasta Holdup Tank and therefore, stopped the pump to pre' vent a

. I the overflow of the Waste Holdup Tank.

I i NOTE: n e two Reactor Building Suap Fumps had operated for 31 and 28 minutes, respectively. Based on the seasured capacity of each pump, approximately 8260 gallone of water vos trans-ferred to the Auxiliary Building.

3 j 00:40:00 The operecor monitored the Reactor Coolant Drain Tank parameters.

(0440:37)

Approsisate The Reactor Coolant Drain Tank rupture disc had burst, therefore.

. the indicated temperature and pressure had reduced substantially l

and the plant operator did not associate the indication with leakage

. i past the Electrocatic Relief Valve (RC-R2), but rather with the initial opening of the relief valve.

01

20:31 De operator requestro tLe cosp ter print the Electrosatic Ralief (0521:08)

Valve (RC-R2) outlet camparature. A value of 283.Gr was indicated.

Based on this tecperature the operator continued to believe that the l l

Electrosatic Relief Valve (RC-R2) was shut.

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1- 6. .'

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i Tiec Evert 02:14:23 The Reactor Building Air Saaple (BF-R-227) particulate chamael

,' (0613:00) i increased witti it eventually went off scale.

j Approximate t

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02:17:33 The operator requested the computer print the Electromati,e l

(0418:30)

Relief Valve (RC-R2) outlet temperature. A value of 228 7F was indicated.

02:18:02 The operator requested the computer print the Reactor, coolant (0418:39)

Pressure Relief Valve (RC-RIA) outlet tesperature. A,value of ,

189 3'T was indicated.

02:18:12 The operator requested the computer print the Beactor Coolant (0618:49)

Pressure Relief valve (RC-R13) outlet toeperature. A value of 194 2F was indicated.

I l  ! 02:19:00 The oserster shut the tiectroostic Rettet alock valve (RC-V2).

, (0619:37) uhich stopped reactor coolant leenage through the Electroaatic l Approminate I Relief valve (RC-R2). The operator noted that the Raaetor I

Building pressure started to decrease rapidly (Figure 43).

t 02:24:23 The Reactor Building ur sample (dF-P-227) gas channel increased 4 i.' (0623:00) .

Approatmate wit 11 it ever.tually went of f scale.

02:44:23 Incore Instrument Fanel '

Area Panitor (HF-R-213) ' indication in-l (0643 00) l Appromisste creased offscale high. The levels recorded on the following so=1 tors began to increase.

i (a) Reactor Building Furge Air Enhaust Duct A (HF-R-223)-particulate (b) Reactor Building Furge Air Inhaust Ducts n (HF-R-226)-particulate (c) Auxiliary Building Purge Air Exhaust (HP-R-222)-partic41ste, gas.

I and iodine '

(d) Auxiliary Evilding Heating 4 Yeatilation monitor gas channel l

(indication wee off scale within 30 minutes).

The Reactor Building Air sample (HP-R-227) todine channel indication l'

increased off scale. .

03:12:28 The operator opened the Electromatte taltef Stock valve (RC-V2)

(0713:03) .

Apprestaate in an attempt to establish pressuriser level within stie normal operating range. The reactor out-of-core Intermediate Range Channel NI-3 indication decreased sharply indicating flow was established through the reactor core regina (Tigure 46).

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i 03:21:23 The I:11ovi:3 raditti:o solit:rs indic:t:d radicti:2 levels I (0722:C0)

Approniaste exceeding the sonitor range, and remained above range until the stripchart ended at 11C0

C0, 4/2/79 l

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(a) Reactor Building Furge Air Exhaust Duct A (HF-1-225) -

. Farticulate Monitor  ;

(b) Reactor Building Furge Air Exhaust Duct 3 (HP-R-226) -

Farticulate Monitor (c) Aus111ary Building Furge Air E4haust (EF.1-222)

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03:30:00 The operator shut the Electre=stic Rettef Block valve (EC-v2).

(0730:37)

Approximate The pressuriser level was 220 inches and the Raattor Coolant system pressure was 1480 pois (Tigures 4 and 12).

l 03:51:00 The operater opened t'.e t.lectreestic Rettet 31ock valve (RC-v2)

(0731:37)

Approximate in an attempt to decrease pressuriser level, which had increased to 395 inches (Tigure 4).

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. 03:55:38 The operator stopped Intermediate cooling Pump (IC-F-5) i (0736:15)

I t 03:55:39 Engineered Safety Teatures actuated on Reactor Building high

! (0756:16) pressure at the setpoint of 3 58 peig (Tigure 45). As a result actuatico Inter:ediate Cooling Pump B (IC-F-3) tripped.

j 03:55:39 The Reactor Building isolated automatically as part of the Engi-  !

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(0736:16) neared Safety Testures actuation from Keactor Building high pressure.

Reactor Building isolation occurred at the cocinal setpoint of 4  ;

pstg.

05:18:00 The operator closed the tiectrosatic Relief Ele:k valve (RC-v2) i

! (0918:37) '

Approximate in an attempt to compress the reactor coolant and condense the steam in the F.eactor Coolant Systen.

t 5

05:57:C0 The Reactor Coolant system pressure reached a value of 2200 peig.

(0957:37)

The operator over.e4 tt., tieetromatse Relief alon v.1ve (RC-V2) to stop the pressure it.cressa ar.d reduce pressure to abcut 2050 ps13 I

During the period C5:57:CJ (0957:37) thru 07:45:00 (!!45:377, the operator attempted to condense the steam in the Reactor Coolant Systen by a.atntainir.g high pressure injection and controlling the Reactor Coolant system pressure at approntaately 2100 psig bv eveltet PC-V2 (Tigure 4). The Reactor Zwildtr.g pressure and tesperature I

, reflected the cycling of AC-V2 (Fidure 45).

. s . U Time tvcet I

07:30:00 De Statten Hauter dir+eted th* roerster t*2 rpee ths Etaetros-tte e . w e 1 (1130:37)

Appreminate Relief Block Valve (kC-v2) and the Pressuriser Spray Valva (EC-V1) to rapidly depressurtse the Reacter Coolant Systes and actuate the Core Fleed Systes d.11e utgh Pressure Injection was maintained (Figure 12). This was done after the operator observed no evidence '

of natural circulation while the Reacter coolant Systes presourc l

• was above 2000 pois. De reducties in Raseter Coelaat Systes l pressure was aise done t3 approach condittens e1ch would allow the De' cay Heat Reseval Pumps 1A and 13 (DE-F-1A and Cu-F-18) to be put inte service. ,

09:13:00 ne operator shut the Electromette Relief slock valve (RC-v2).

(1314:37) .

Apprestaate y

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7-09:49:43 The operator opened the Electrosatic Relief valve (RC-22) and a l (1350:20) hydrogen deter.ation occurred la the Beacter teildir.g. Hyd roges

! gas froi. the reacter caelant aircociu-vater reactica tud collected I . .

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in the Pressuriser and had been vented throu6h the Electromatic Relief Valve (RC-R2) to the Raatter Coolant Drain Tank ar.d released e

t to the Reactor Building through the Drata Tank Rupture Ciaphraga l

, (CL-U26) dich had been breached. De hydre,;en concentration I

, eveetually reached an empleelve sisture. It is believed the deton-atism was a result of a set of RC-R1 costects arcing. N"N

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, 09:49:46 Iagineered Safety Teatures actuation occurred es high-high reactor f building pressure (Figure 43). De setpoint is 28 pois. This is I*

the result of a 28 psig building pressure tapulse from the hydrogea detonattee. Raattor Building !seletion and Containment Spray v e actuated. (Reacter Coolant Mahaup Puep C (MU-F-1C)), Makeup pump i

i started at 13:30:23; and Reacter Building Spray Pumps A and B i

(SS-F-I A and 35-F-13) started autosatically.

l 09:49:38 Reactor coolant Pu ps IA and 18 (RC-F-IA and RC-F-13) high inlet

.e (1350:33) air teeperature alaras annunciated and Pressuriser Safety valves (RC-R!A and RC-R13) discharge line toeperature high alarse

, annunciated.

[p i .

? 10 CO*C0 ne operator opened the Electrocatic Relief Block valve (RC-V2).

(1400:37)

Appreatmete i

.No!r: O!!42 s43 anef I 0100:00 en/ro'es arr eenforsfy. JhnloIn'/ 09:421.43 refry be fee Yaler (WC-V2) vire Meloof Yah'e (MC IU) ? If J*,

. J%)ve (MC=V2) on.rrf bove de sl oar.l [*r ** fa /0:04:4 0 enlty

Yle Time Fyent t

• L 11:1* 00 Tht eperre r shut ths tiectreestic Relief Block Velve (ac-V2)e

• • * (1312:37)

Appresisate 12:36:00 The operator opened the nectrocatie Estief Block valve (RC-V2).

(1634:37) 1 Appresiaste 6 .

FLANT STAT;;S All reacter coolant pumpe (RC-r-1A, RC-r-2A, RC-F-18 and RC-F-23) were stepped. Steam / gas existed la the vessel head and 14ep 3 het leg. De Loo; A het les stees wee collapsed and natural circulaties flow established la this

, loop. Condenser vacue was re-established af ter the ausiliary steam boiler was returned to service. Steas Generator A was steasing to the condenser and stese Generator 3 was isolated. De Ucetronatic Relief Block Valve (RC-V2) was open, keeptag the Reactor Coolant syntes depressuria.d to 450 peig (Tigure

• 12). . Vesting through the Castrosatic Islief Valve (RC-22) to the reacter t'

l building resulted in a hydrogen concentration increase and subsequent denota-ties which caused 'a 28 pelg Reactor Building pressure pulse. Attespes to use the Care fleed systes to coe'. the core ever the last ein hours had resulted la limited success. De reactor core was betes cooled by (1) steas Coastster A i

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steestag, (2) utgh Pressure Injection flow into the Reactor Coolant Systes and I

thee to the Reacter Building floor via the coctroostic Relief Valve (RC-R2) i 3 and (3) Core Fleed Tank A partial discharge.

The operater shut the ceetonatic Rettet stock Velve (RC-v2) in 13:13:00

- (1713:37)

Apprestaate an atteept to condense the resatains stese in the Reactor Coolant

! Systes by increasing esctor Coelaat Systes pressure (Tigure 12).

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