ML19246A357
| ML19246A357 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/16/1979 |
| From: | Long R GENERAL PUBLIC UTILITIES CORP. |
| To: | Arnold R GENERAL PUBLIC UTILITIES CORP. |
| Shared Package | |
| ML19246A356 | List: |
| References | |
| ACRS-SM-0098, ACRS-SM-98, NUDOCS 7906180608 | |
| Download: ML19246A357 (15) | |
Text
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frailer City - IMI GPU Scrvice Cor poration F7
%M d: bOTV!CO April 16, 1979 260 Cherry H,ll Road Pars:Opany New Jersey 07054 W M.s i
201 263 4900 TELEX 136 482 To:
R. C. Arnold FEC.u.:
R. L. Long.-.
.r '
PRELIMINARY SEQUENCE OF EVENTS TMI 2 ACCIDOiT OF M.GCH 28, 1979 Attached is a Preliminary Sequence of Events spanning the first approxica t ely twenty hours following the 'IMI-2 accident which was initiated at 4:00 a.m. on March 28, 1979.
For this chronology of events, a reference clock was established with the tire of the turbine trip, 0400:37, defined as tine zero.
The time of each event in the sequence is given as the nu=ber of hours, minutes and seconds relative to 0400:37, followed in parenthesis by the real ti=e using a 24-hour clock.
For exacple, 1:52:43 p.
. on March 28 would be written "9:52:06 (1352:43)."
Depending upon the accuracy of the source of da ta for each event, the tices appear alone or with the notation " approximate."
Tne sequence has been reconstructed f rc various information and data sources, including control room logs, s trip chart recorders, alar = printautz and reacticeter printouts. Please note, however, that the alarm printer was out of service fro = 01:13:27 (0513:59) to 02:47:31 (0648:08) and during the course of the accident was running well 'echind the actual tice of events.
Efforts to annotate this chronology and to develop graphs of various plant para eters as a function of ti=e are unden ay.
This additional infor ation vill be provided as soon as it is availabic and we will keep you infor:ed.cf our progress.
ja R. L. lo GPU CC: E. Diecka=p J. Herbein R. Wilson Industrial Advisory Group Data Reduction and Management M. Bezilla
- 1. Harding G. Kunder J. logan G. Miller 7906.18oco8 228 18(J e
i a'on 6 a sub.d.ary Cenaaf ubic Uti!61.e. Qtgr,3 ton
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PFcLLMINARY EEQUENCE OF EVthid
,,TML 2 ACCIDENT OF MARCH 78, 1970
(!
Issued April 16, 1979
~
-00:05'00 Three Mite Island Unit Two was at 97: power vitb the Integrated (0355:36)
Control System in full automatic.
Rod groups one thru five were fully withdrawn, rod groups six and seven were 95% vithdrawn and rod group eight was 27% vithdrawn.
Reactor Coolant System total flow was apprcxi=ately 107.5 cf design flow and the Reactor Coolant System pressure was 2155 psig. Reactor Coolant Makeup Pump B (HU-P-1B) vss in service supplying makeup and Reactor Coolant Pu=p Seal injection f1.v.
Th e Reactor Coolant System soluble boron concentration was approximately 1030 parts per million.
Pressurizer Spray Valve (RC-V1) and the pressurizer heaters were in canual centrol while spraying the pressurizer to equalize boron concen-trations between the pressurizer and the remainder _of the Reactor Coolant Syste=. Normal Reactor Coolant System letdown flow was established.
Steam Generator para =eters were as shown in th'e following table:
Steam Generator A Steam Generator B Loop Feedwater 5.7459 MPPH+
5.7003 MPPH*
Operating Level 56%
57.4%
Startup Level 155.8 inches 163.4 inches Stea= Pressure 910 psig 889.6 rsic Feedwa ter Temperature 462.7F 462.'"
- MPPH is Million Pounds Per Hour l0l n2n6 u
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I..3 St eam Gener at or Feedwa ter Pu=ps (W-P-1 A and W-P-1B) were in service, Concensate Booster Pumps (CO-P-2A, CO-P-2B and CO-P-2C) were in service, and Condensate Pumps (CO-P-1 A and CO-P-1B) were in service.
An atte=pt Eas being =ade to clear a clogged
~
resin trans fer line in the standby de=ineralizer.
-00:00:01 Condensate Pu=p A (CO-P-1A) stopped.
(0400:36)
--00:00:01 Teedwater Pu=ps (W-P-I A and W-P-1B) st opped at essentially the (04t0:36) a loss of feedwater flow to both stea=
sa=e ti=e resulting in generators.
00:00:00 Main Generator was tripped followed by a turbine trip.
(0400:37) 00:00:00 Three E=ergency Feedwater Pu=ps (EF-P-1, 2A, 2B) started.
(04CC:37) 00:00:03 The Electro =atic Relief Valve (RC-RV2) opened at the setpoint (0400:40)
Ap pr ex i=a t e of 2255 psig.
00:00:08 Reactor tripped on high pressure at 2345 psi. setpoint is 2355 psi.
(0400:45) 00:00:08 Th e operator placed.the Pressurized Spray Valve (RC-V1) and pres-(0400:45)
Appr ox i=a t e surizer heaters under autc. tic control.
00:00:13 Th e operator started the Reactor Coolant Makeup Pump A (MU-P-1A),
opened High Pressure Injection Isolation Valve A (MU-V16A) and isolated letdown flow in anticipation of the expected pressurizer level decrease.
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00:00:13 The Electrocatic Palief (RC-RV2) solenoid de-energized giving (0400:50)
Apprcximate a non-open indication to the control room operators.
The Elec-treratic Relief Valve (RC-RV2) should have reseated at about this
.. time (closure setpoint of 2205 psig).
00:00:14 The Emergency Feed Pumps (EF-P1, 2A and 2B) achieved nor=al dis-(0400:51) charge pressure.
00:00:15 Water ha=mer in the condensate piping occurred.
(0400:52)
Approxicate 00:00:30 Pressurizer Safety Valve (RC-RVlB) and Electre=atic Relief Valve (0401:07)
(RC-RV2) discharge line temperature alar =s printed out.
00:00:38 St eam Generator A level reached the 30-inch setpoint where the (0401:15)
Approxi= ate E=ergency Feedwater Valves '.EF-VilA and EF-VilB) open.
Feedwater was not admitted because Emergency Feedwater Block Valves (EF-V121 and EF-V12B) were hut.
00:00:39 Reactor Coolant Mateup Pump A (MU-P-1A) was stopped.
(0401:16) 00:00:40 Steam Generator B level reached the 30-inch setpoint where the (0601:17)
Apprcximate Emergency Feedwate-Valves (EF-VllA and EF-VllE) open.
was not admitted because E 7gency Feedwater Block Valves (EF-V12A and EF-V123) were shut.
00:00:41 Reactor Coolant Ma keup Pump A (MU-F-1 A) wa s restarted.
With (Ot01:18)
-. Reactor Coolant Maieup Pumps A and B (MU-F-1 A and MU-F-1B) oper-ating, pressuri:cr level rate of decrease slowed.
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l' 00:01.00 Pr e s s u r i e r l ei[1 started increasing.
Reactor Coolant System hot (0401:37)
/.pproxicate leg and cold leg temperatures reached 575F.
Reactor Coolant Dr a in Tank pressure was increasing.
00:01:00 The Pressurizer Safety Valve (RC-RVIA) high discharge line temper-(0401:37) ature alarm was received.
00:01:26 Reactor Coolant Drain Tank temperature normal alarm printed out.
(0402:03) 00:01:45 Steam. Generators A and B hare boiled dry at th i s t i= e.
(0402:22)
Approxi= ate 00:02:01 Rcactor Coolant Makeup Pump B (MU-P-1B) was stopped due to (0402:33)
Engineered Safeguards actuation.
00:02:04 High Pressure Injection Pump C (MU-P-1C) started autc=atically.
(0402:41) 00:03:12 Reactor Coolant Drain Tank Relief Valve ( k'DL-Rl ) lifted at 120 psig.
(0403:49)
Approximate 00:03:14 High Pressure Injection portion of Engineered Safeguards sas canually (0403:51) bypassed.
Both Reactor Coolant Makeup Pumps A and C (MU-lP-1A and MU-P-1C) were operating.
00:03: 26 Reactor Coolant Drain Tank high te=perature alarm received at 127.2F.'
(0404:03) 00:04: 38 Reactor Coolant Makeup Pump C (MU-P-lC) vas stopped.
(0405:15)
=
00:04:38 The operator throttled the High Pressure Injection Isolation Valves (C 05:15)
Approxi= ate (MU-V16's).
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('2 00:04:52 Intermediate CSosed Cooling Pump (IC-P-1A) started.
(0405:29) 00:04:58 First alace indication received that letdown had been secured.
(0405:35) 00:05:06
'Ftesurizer level stepped its sharp increase at 376 inches and (0405:43) began to turn down.
It reached a minimum of 372 inches and then started back up at 5 minutes, 2.
onds into the transient.
00:05:15 Condensate Booster Pump B (CO-P-23) tripped.
(0405:52) 00:05:50 Reactor Coolant System pressure stopped its sharp decrease and began (0406:27)
Approximate to turn up.
Minicum value reached was approximately 1350 psig.
00:05:54 Pressurizer level increased beyond the range of the ins tr umen t (0406:31) indication.
00:06:58 Le t d own flow of 71.4 gallons per minute was re-established.
(0407:35) 00:07:31 Reactor Building Sump Pu=p A (WDL-P-2A) started.
(0408:06) 00:08:00 Emergency Feedwater block Valves (EF-V12A and EF-V12B) were opened.
(0408:37)
Approximate p
00:08:15 Reactor Coolant System hot leg and cold leg temperatures began to-(0408:52) decrease.
00:08:30 Reactor Coolant System pressure began to decrease.
(0409:07)
=
00:10:00 Pressurizer level came on scale.
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('h 00:10:19 Reactor Luildi6 Su=p Pump B (WDL-P-23) s tar teo.
6 (0410:56) 00:10:24 Reactor Coolant Makeup Pu=p A (MU-P-1A) tripped.
(0411:01) 00:10:27 Reactor Coolant Makeup Pump A (MU-P-1A) was started.
(0411:04) 00:10:28 Reactor Coolant Makeup Pump A (MU-P-1 A) tripped.
(0411:05) 00:10:40 Reactor Building Su=p high level alarm received.
Setpoint is (0411:25) 4.650 feet.
00:11:40 Reactor Coolant Makeup Pump A (MU-P-1A) was started.
(0412:17) 00:14:50 The Reactor Coolant Drain Tank rupture diaphrag= (WDL-U26) f ailed.
(0415:27) 00:24:58 The operator requested cceputer printout of the Electromatic (0425:35 Relief Valve (RC-RV2) outlet temperature.
The reading was 285.4F.
00:25:00 Intermediate cooling syste= high radiation alar = annunciator (0425:37)
Approximate receivec at the Radiation Monitor Panel.
00:36:08 Emergency Fet dwa ter Pump 2B (EF-P-23) was stopped.
(0436:45) 00:38:10 Reactor Building Sump Pump A (WDL-P-2A) was stopped.
(0438:47)
-00:38:11 Reactor Building Sump Pump B (WDL-P-23) was stopped.
(0438:48) 01:10.54 Eeactor Building air cooling coils emeigency discharge alar =
(0511:31) printed out.
228 186 __
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01:13:29 Reactor Coolant Pump 2B (RC-P-2B) was stopped.
(0514:06) 01:13:42 Reactor Coolant Pu=p 1B (RC-P-1B) was stopped.
(0514:19) 01:13:27
-The alar = printer beca=e unavailable at this time and remained (0513:59) out of service until 02:47:31 (0648:08).
01:20:31 Operator requested printout of the Elce.t r ozat ic Relief Valve (RC-RV2) outlet temperature. The reading was ?S3.0F.
01:40:37 Reactor Coolant Pump 2A (RC-P-2A) was stopped.
(0541:14) 01:40:45 Reactor Coolant Pu=p 1 A ( RC-P-1 A) wa s stopped.
(0541:22) 01:42:00 Operator started raising Steam Generator A level from 30 inches (0542:37)
Approxicate on the Startup Range to 50% on Operating Range.
Reactor Coolant Sys t er Loops A and B cold leg temperatures both started decreasing.
Reactor Coolant System pressure started decreasing.
01:54:00 Reactor Coolant System Loop A hot leg temperature began increasing.
(0554:37)
Approximate 02:00:00 Steam Generator A level reached 50% on Operating Range.
(0600:37)
Approxicate 02:00:00 Reactor Coolant System Loop B hot leg te=perature began increasing.
(0600:37) 02:12:00 Reactor Coolant System Loop B hot Icg te=perature increased to (0612:37) offscale at 620T.
228 187
- 02:17:53 operator recue'. Ad Electromatic Relief Valve (_.-12) outlet (0618:30) te=perature.
The reading was 228.7F.
02:22:00 The Electromatic Relief Block Valve (RC-V2) was shut.
(0622:37)
Appr ox ima te 02:30:00 Operator star :ed increasing Steam Generator 3 fres 30 inches on (0630:37)
Startup Rangt to 502 on Operating Range.
02:45:00 Several radiation alarms were received.
(0645:37)
Appr ox ima t e 02:45:00 Reactor Coolant Mckeup Pump C (MU-P-1C) was stopped.
(0645:37)
Appr ox ira t e 02:45:L, Operator opened Main Steam Isolation valves (MS-V13 and MS-V73).
(0645:37)
Appr ox ica te 02:50:00 Site Emergency was declared.
Notifications to offsite authorities (0650:37)
Appr ox ica t e and organizations were initiated.
02:51:57 Operator atte=pted to start Reactor Coolant Pump 21 ( RC-P-2A).
(0652:34)
Famp would not start.
02:53:19 Operator atte=pted to start Reactor Coolant Pu=p 13 (RC-P-1B).
(0653:53)
Pump would not start.
02:54:09 Operator started Reactor Coolant Pump 2B (RC-P-23).
(0654:16) 02:54:47 High Pressure Injection Engineered Sa feguard s a c t u2 t i on logic (0655:26) reset on increasing Reactor Coolant System pressure.
228 188 228
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i 02:56:19 Steam Generator B was isolated.
Ma in St e am Isolation valves (0656:56)
(KS-V4B and MS-V7B) were shut.
Appr.exicate 03:00:00 Reactor Coolant System pressure increased to 2130 psig.
(0700:37)
Approxicate 03:03:39 Steam Generator A pressure control was shifted from the Turbine Bypass (0704:16)
Approxicate Valves (MSV-25A and B and MSV-26A and 3) to the Power Operated Emergency Main Stea= Du=p Valves (MSV-31 and B).
03:10:27 Emergency Teedwater Pu=p 2A (ET-P-2A) was. stopped.
(0711:04) 03:12:2S Electromatic Relief Block valve (RC-V2) was opentd.
(0713:05)
Approximate 03:12:53 Reactor Coolant Pump 2B (RC-P-2B) was stopped.
(0712: 53) 03:20:13 Reactor Coolant Makeup Pu=p C (MU-P-IC) wa s s tart ed.
Reactor Coolant (0720:41)
Makeup Pu=ps C and A (MU-P-C and A) were operating.
03:23:23 General Emergency was declared. Notifications to of fsite (0724:00)
Appr ox ica t e authorities and organizations were initiated.
03:30:00 Electro =atic Relief Block valve (RC-V2) was shut.
(0730:37)
Approxicate e
03:35:08 Emergency Feedwater Pump 2A (EF-P-2A) was started.
(0735:43) 03:37:00 Reactor Coolant. Makeup Pump C (MU-P-IC) wa s stopped.
(0737:37) 03:51:00 Electro =atic Relief Block Valve (RC-V2) was opened.
(0751:37)
Approxicate 228 189
- g. t 03:55:39 Engineered Safeguards actuated on lov RCS pressure.
Setpoint is (0736:16) 1640 psig.
03:55:39 The Reactor Building high pressure isolation signal actuated (0756:16) and isolated the Reactor Building.
The Reactor Building isolation set point is 4 ;sig.
03:56:04 Reactor Coolant..akeup Pump C (MU-P-lC) was started.
(0756:41)
I i
l 03:59:23 Reactor Building E=ergency Cooler 3 was shutdown, i
(0800:00) 4 03:59:53 Reactor Building E=ergency Co' sic. O was started.
(0800:30) 04:06:00 Electrocatic Relief Block Valve (RC-V2) was shut.
(0d06:37) 04:08:37 Feactor Coclant Pump 1A (RC-P-1A) was started.
(0809:14) 04:09:14 Reactor Coolant Pump 1A (RC-P-1 A) was stopped.
(0B09:51) 04:17:17 Reactor Coolant Makeup Pu=p A (MU-P-1A) was stopped.
(0817:54) 04:17:22 Reactor Coolant Makeup Pump C (ML-P-1C) was stopped.
No makeup (0817:59) pumps operating.
04:18:17 Operatar attc=pted to start Reactor Coolant Makeup Pump A (MU-P-1 A).
(0818:54)
The pump would not start.
2 04:18:30 Electromatic Relief Block Valve (RC-V2) was opened.
(0819:07)
Appr ox i=a t e 228 190 10 -
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06:21:53 Reactor Coolant Makeup Pump B (MU-P-13) was started.
(CS15:30) 04:25:59 Reactor Coolant Makeup Pu=p C (MU-P-1C) was started, tripped, (0827:36)
Approxi= ate and was restarted.
04:30:00 The Electro =atic Relief Block Valve (RC-V2) was shut.
(0830:37)
Approxi= ate 04:30:45 Condenser Vacuum Pumps 1A and 1C (VA-P-1 A and VA-P-1C) were (0531:22) stopped and vacuum was broken.
04:30:45 Power Operated Ecergency Main Steam De=p Valve (MS-V3A) was opened.
(0831:22)
Approxicate 04:54:00 The Electrecatic Relief Block Valve (RC-V2) was opened.
(0S34:37)
Approx cate 05:18:00 The Electrematic Relief Block Valve (RC-V2) was shut.
(0918:37) 05:54:00 Operator commenced filling Steam Generator A to 99~ on the Operating (0954:37)
Approximate Range instrumentation.
07:30:00 Electromatic Relief Block Valve (RC-V2) and the Pressurizer Spray (1130:37)
Approxi=ste Valve (RC-V1) were opened.
08:11:26 Core Flood Tank A high level alarm was received.
(1212:03) 08:30:00 Power Operated Emergency Main Steam Du=p Valve (MS-V3A) was shut.
2 (1230:37) 228 191 -
m
{3 Decay Heat Removal Pumps l A and IB (DH-P-1 A and DH-P-1B) were 05:31:06 (1231:43) started.
at a level of 13.13 feet.
Core Flood Tank A alarm printed out 08:54: 56 (1255:33)
Reactor Coolant Makeup Pump C (MU-P-1C) was stopped.
09:04:13 (1304: 35)
Reactor Building Isolation and Containment Spray were actuated by 09:49:44 (1350:21)
Engineered Safeguards actuation started Engineered Safeguards.
Reactor Coelant Makeup Pump C (MU-P-lC) and Reactor Building Spray Pumps A and B (BS-P-1A and BS-P-1B).
Reactor Building Spray Valves (BS-VlA and BS-V113) opened.
09:49:50 (1350:27) inlet air Coolant Pumps 1A and IB (RC-P-1A and RC-P-13) 09:49:58 Reactor (1350:35) temperature high alares annunciated and Pressurizer Safety Valves (RC-Rla and RC-R13) discharge line te=perature high alares annun-ciated.
Reactor Coolant Make.up Pump C (MU-P-1C) was stopped.
09:50:24 (1351:01)
Reactor Building Spray Pumps A and B (BS-P-1A and BS-P-13) were 09:55:30 (1356:07) stopped.
Removal Pumps A and B (DH-P-1 A and DH-P-1B) were 09:56:53 Decay Heat (1357:35) stopped.
2 Reactor Coolant System hot leg Loop A temperature decreased to 10:24:00
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(1424:27)
Approximate within the instrumentation range.
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Re ac t or 10:31:25 Reactor Coolant Makeup Pump C (MU-P-1C) was start ed.
(1432:02)
Coolant pressure was approxicately 440 psig.
Reactor Coolant Makeup Pump C (MU-P-1C) was stopped.
10:35:55 (1436:32)
Pressurizer level started decreas ing.
11:06:00 (1406:37)
Approximate 11:?9:00 Reactor Coolant System cold leg Loop A temperature started to (15L :37)
Approximate increase from 200F to 400F.
Reactor Coolant System hot leg Loop A temperature decreased frem above the instrument range to 360F.
11:18:34 Reactor Coolant Makeup Pump C (MU-P-1C) was started.
(1519:11)
Pressurizer level stopped decreasing at 180 inches and started 11:24:00 (1524:37) hour.
Approximate increasing, going of f scale during the next 11:28:12 Reactor Coolant Mckeup Fu.,p C '(MU-P-1C) vas st opped.
(1528:49) 11:32:37 Reactor Coolant Makeup Pump C (MU-P-1C) was started.
(1533:14)
Reactor Coolant Makeup Pump C (MU-P-1C) was stopped.
11:35:48 (1536:25)
Operator commenced filling Stea= Generator B to 97% on the Operating 11:36:09 (1536:37)
Approximate Range instrumentation.
the Operating Range.
Steam Generator A Icvel was 97 on 12:00:00
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(1600:37)
Approximate 228 193 12:48:00 Pressurizer level came on scale.
(1648:00)
Approximate WW-O
Condenser vacuu( l ump IC (VA-P-lC) vas started.
13:02:23 (1703:00) 13:08:22 Normal stea generator feedwater s:pply was put in service.
(1708:59)
Approximate Condenser Vacuus Pu=p 1A (VA-P-1A) vas started.
13:13:10 (1713:47) 13:23:04 Reactor Coolant Makeup Pump C (KU-?-1C) was started.
(1723:41) 14:43:15 Reactor Coolant Makeup Punp C (MD-C--1C) wa s stopped.
(1843:52) 14:54:00 RCS pressure reached 2350 psig.
(1854:37)
Approxicate 15:24:00 Reactor Coolant Pu=p 1A (RC-P-1A) 2s started.
(1924:37) 15:24:10 Eeactor cc lant Pu=p 1A (RC-P-1A) vis stopped.
(1924:47)
Approximate 16:04:00 Reactor Coolant Pu=p 1A (RC-P-1A) vis startec.
(200S:37) 22:15:00 Reactor Coolant System and St eam Ge:erstor conditions were:
(0215:37)
Anproxicate Reactor Coolant System pressure = 1:65 psig.
Pressurizer Terperrsture "- 551F (pres surizer heat ers caintaining temperature).
Pressurizer Level = 397 inches.
Reactor Coolant System cold leg Locp A temperature = 28SF 2
Steam Generator A steaming to the M2in Condenser.
228 194.-
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