ML19290A087
| ML19290A087 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/16/1979 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | GENERAL PUBLIC UTILITIES CORP. |
| References | |
| TM-0944, TM-944, NUDOCS 7910010477 | |
| Download: ML19290A087 (21) | |
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TMI DOCUMENTS DOCU1ENY NO:
b" COPY IMDE ON CF DOCUMF.Nr PROVIDED BY METROPCLI, TAN. EDISCN COMPANY.s Supervisor, Docu=ent Control, NRC 2221 168-00 10 Vy y
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Inter-Office Memorandum.
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Date:
M.pril 16,1979 Time: 13302 :1 ['- O ISerVICO A
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. Attache,d fo(you,r information.is the TMI/GPU. Data Reduction Management Group > Status Report #2.
The following information is included:
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CjRAPH #2).TMI Unit #2 Reactor Pressure and A Loop Temperature - Cold (April 1 thru April 15)..
.u.c GRAPH #3) TMI Unit 02 Letdown Temperature and Flow (April 1 thru April 15)
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GRAPH #4).TMI Unit #2 Six Highest T/C Readings (April 8 @l800 Hrs to April 15)
A ttachment 1 f
Preliminary sequence of events TMI Unit #2 Accident of March 28, 1979
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Distributiom Traile e City Trailer #7 NRC (NRR) 8 NRC (I&E) 11 GPU - Admin. Support 14 GPU - Management 23 GPU - Management 26 B&W, Met-Ed Licensing 27 NRC (NRR)
Operations Center Building 26 - Saul Levy (thru Trailer #23) 4 Island Locations GPU Support G. Miller Trailer DRMG (GPU Trailer #8)
Radwaste Management Q/C (T. A. Mackey)
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Trailer City - TMI GPU Service Corporaten
- b. @lj SerViCO April 16, 1979 260 Cherry HQ Road Parsiopany NewJersey 07054 201 263-4900 TELEX 136-482 To:
R. C. Arnold r
FROM:
R. L. Long PRELIMINARY SEQUENCE OF EVENTS TMI 2 ACCIDENT OF MARCH 28, 1979 Attached is a Preliminary Sequence of Events spanning the first approximately twenty hours following the TMI-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 time of the turbine trip, 0400:37, defined as time zero. The time of each event in the sequence is given as the number of hours, minutes and seconds relative to 0400:37, followed in parenthesis by the real time using a 24-hour clock. For example,1:52:43 p.m. on March 28 would be written "9:52:06 (1352:43)."
Depending upon the accuracy of the source of data for each event, the times appear alone or with the notation " approximate."
The sequence has been reconstructed from various information and data sources,
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including control room logs, strip chart recorders, alarm printouts and reactimeter printouts. Please note, however, that the alarm printer was out of service from 01:13:27 (0513:59) to 02:47:31 (0648:08) and during the course of the accident was running well behind the actual ti=e of events. Efforts to annotate this chronology and to develop graphs of various plant parameters as a function of time are underway. This additional information will be provided '
as soon as it is available and we will keep you informed.of our progress.
R. L. Im GPU CC: H. Dieckamp J. Herbein R. Wilson '
Industrial Advisory Group Data Reduction and Manage =ent.
M. Bed ll a L.' Harding
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G. Kunder J. Iogan G. Miller 2221 174 GPU Servce Corporaron s a sutscary of General PutWc UtMes Corporaton
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PRELMINARY SEQUENGE~ UY ' EVENTS
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l, TMI 2 ACCIDENT OF MARCH 28, 1979 Issued Apr'il 16, 1979
-00:05:00 Three Mile Island Unit Two was at 97% power with the Integrated (0355:36)
Control System in full automatic. Rod groups one thru five were fully withdrawn, rod groups six and seven were 95% withdrawn and rod group eight was 27% withdrawn. Reactor Coolant System t' cal flow was approximately 107.5% of design flow and the Reactor o
Coolant System pressure was 2155 psig. Reactor Coolant Makeup Pump B (MU-P-1B) was in service supplying, makeup and Reactor Coolant Pump Seal injection flow. The Reactor Coolant System soluble boron concentr'ation was approximately 1030 parts per million. Pressurizer Spray Valve (RC-V1) and the pressurizer heaters were in manual control while spraying the pressurizer to equalize boron concen-trations between the pressurizer and the remainder,of the Reactor Coolant System. Normal Reactor Coolant System letdown flow was established.
Steam Generator parameters were as shown in the following table:
Steam Generator A Steam Generator B Loop Feedwater 5.7459 MPPH*
5.7003 MPPH*
A Operating Level 56%
57.4%
Startup Level 158.8 inches 163.4 inches
' Steam Pressure 910 psig 889.6 psig F
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- , Fee'dwater Temperature 462.7F 462.7F
- MPPH is Million Pounds Per Hour 2221 175 M
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Steam Generator Feedwater Pumps ( W-P-1A and W-P-1B) were in service, Con'densate Booster Pumps (CD-P-2A, CO-P-2B and CO-P-2C) were in service, and Condensate Pumps (CO-P-1A and CO-P-1B) were in service. An attempt was being made to clear a clogged resin transfer line in the standby demineralizer.
-00:00:01 Condensate Pump A (CO-P-1A) stopped.
(0400:36)
-00:00:01-Feedwater Pumps (W-P-1A and W-P-1B) stopped at essentially the (0400:36) same time resulting in a loss of feedwater flow to both steam generato,rs.
00:00:00 Main Generator was tripped followed by a turnine trip.
(0400:37) 00:00:00 Dree Emergency Feedwater Pumps (EF-P-1, 2A, 23) started.
(0400:37) 00:00:03 he Electromatic Relief Valve (RC-RV2) opened at the setpoin_t (0400:40)
Approximate of 2255 psig.
00:00:08 Reactor tripped on high pressure at 2345 psi. Setpoint is 2355 psi.
(0400:45) 00:00:08 ne operator placed the Pressurized Spray Valve (RC-V1) and pres-(0400:45)
Approximate surizer heaters under automatic control.
00:00:13 he operator started the Reactor Coolant Makeup Pump A (MU-P-1A),
opened High Pressure Injection Isolation Valve A (MU-V16A) and isolated letdo'wn flow in anticipation of the expected pressurizer level decrease.
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00:00:13 The Electromatic Ralief (RC-RV2) solenoid de-energized giving (0400:50)
Approximate a non-open indication to the control room operators. The Elec-tromatic Relief Valve (RC-RV2) should have rescated at about t1
- s time (c13sure,setpoint of 2205 psig).
00:00:14 The Emergency Feed Pumps (EF-P1, 2A and 2B) achieved normal dis-(0400:51) charge pressure.
00:00:15 Water hammer in the condensate piping occurred.
(0400:52)
Approximate 00:00:30 Pressurizer Safety Valvy (RC-RVlB) and Electromatic Relief Valve (0401:07)
(RC-RV2) discharge line temperature alarms printed out.
00:00:38
' Steam Generator A level reached the 30-inch setpoint where the (0401:15)
Approximate Emergency Feedvater Vv.tves (EF-VilA and EF-VilB) open. Feedvater was not admitted because Emergency Feedvater ' Block Valves (EF-V12.1 and EF-V12B) were shut.
00:00:39 Reactor Coolant Maieup Pump A (MU-P-1A) was stopped.
(0401:16) 00:00:40 Steam Generator B *evel reached the 30-inch setpoint where the (0401:17)
Approximate Emergency Feedvater valves (EF-VilA and EF-V11B) open. Feedvater vas not admitted because Emergency Feedvater Block Valves (EF-V12A and EF-V12B) were shut.
00:00:41 Reactor Coolant Makeup Pump A (MU-P-1A) was restarted. With (0401:18)
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Reactor Coolant Miceup Pumps A and B (MU-P-lA and MU-P-1B) oper-ating, pressurizer level rate of decrease slowed.
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00:01:00 Pressurizer level started increasing.
Reactor Coolant System hot (0401:37)
Approximate leg and cold leg temperatures reached 575F. Reactor Coolant Drain Tank pressure was increasing.
00:01:00 2he Pressurizer Safety Valve (RC-RVIA) high discharge line temper-(0401:37) ature alarm was received.
00:01:26 Reactor Coolant Drain Tank temperature normal alarn printed out.
(0402:03) 00:01:45 Steam Generators A and B have boiled dry at this time.
(0402:22)
Approximate OG:02:01 Reactor Coolant Makeup Pump B (MU-P-1B) was stopped due to (0402:38)
Engineered Safeguards actuation.
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00:02:04 High Pressure Injection Pump C (MU-P-lC) started adcomatically.
(0402:41) 00:03:12 Reactor Coolant Drain Tank Relief Valve (WDL-R1) lifted at 120 psig.
(0403:49)
Approximate High Pressure Injection portion of Engineered Safeguards was manually 00:03:14 (0403:51) byparsed. Both Reactor Coolant Makeup Pumps A and C (MU-lP-1A and MU-P-lC) were operating.
00:03:26 Reactor Coolant Drain Tank high temperature alarm received at 127.2F.
(0404:03)
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~00:04:38 Rea_ctor Coolant Makeup Pump C (MU-P-lC) was stopped.
(0405:15) 00:04:38 The operator throttled the High Pressure Injection Isolation Valves (0405:15)
Approximate (MU-V16's).
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5 do:04:52 Intermediate Closed Cooling Pump (IC-P-1A) started.
(0405:29) 00:04:58 First alarm indication received that letdown had been secured.
(0405:35) 00:05:06 Presurizer level stopped its sharp increase at 376 inches and (0405:43) began to turn down. It reached a' minimum of 372 inches and then
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started back up at 5 minutes, 21 seconds 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.
Minimum value reached was approximately 1350 psig.
00:05:54 Pressurizer level inc? teased beyond the range of the instrument (0406:31) indication.
00:06:58 Letdown flow of 71.4 gallons per minute was re-established.
(0407:35) 00:07:31 Reactor Building Sump Pump A (WDL-P-2A) started.
(0408:06) 00:08:00 Emergency Feedwater Block Valves (EF-V12A and EF-V12B) were opened.
(0408:37)
Approximate 00:08:15 Reactor Coolant System hot. leg and cold leg temperatures began to (0408:52) decrease.
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' Reactor Coolant System pressure began to decrease.
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(0409:07) 00:10:00 Pressurizer level came on scale.
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00:10:19 Reactor Building Sump Pump B (WDL-P-2B) s;arted.
(0410:56) 00:10:24 Reactor Coolant Makeup Pump 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-1A) tripped.
(0411:05) 00:10:40 Reactor Building Sump high level alarm received. Setpoint is (0411:25) 4.650 feet.
00:11:40 Reactor Coolant Makeup Pump A UU-P-1A) was started.
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(0412:17) 00:14:50 The Reactor Coolant Drain Tank rupture diaphragm (WDL-U26) failed.
(0415:27) 00:24:58 The operator requested computer printout of the Electromatic (0425:35 Relief Valve (RC-RV2) outlet temperature. The reading was 285.4F.
00:25:00 Intermediate Cooling System high radiation alarm annunci" >r (0425:37)
Approximate received at the Radiation Monitor Panel.
00:36:08 Emergency Feedwater Pump 2B (EF-P-2S) was stopped.
(0436:45) 00:38:10
' Reactor Building Sump Pu:no A (WDL-P-2A) was stopped.
(0438:47)
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-00:38:11 Reactor Building Sump Pump B (WDL-P-2B) was stopped.
(0438:48) 01:10:54 Reactor Building air cooling coils emergency discharge alarm (0511:31) printed out.
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01:13:29 Reactor Coolant Pump 2B (Rf -P-23) was stopped.
(0514:06) 01:13:42 Reactor Coolant Pump 1B (RC-P-1B) was stopped.
(0514:19) 01:13:27 The alarm printer became unavailable at this time and remained (0513:59) out of service until 02:47:31 (0648:08).
01:20:3'l Operator requested printout of the Electromatic Relief Valve (RC-RV2) outlet temperature. The reading was 283.0F.
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01:40:37 Reactor Coolant Pump 2A (RC-P-2A) was stopped.
(0541:14) 01:40:45 Reactor Coolant Pump 1A (RC-P-1A).'as stopped.
(0541:22) 01:42:00 Operator started raising Steam Generator A level fr'om 30 inches (0542:37)
Approximate on the Startup Range to 50% on Operating Range. Reactor Cool _ ant System 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)
Approximate 02:00:00 '
Reactor Coolant System Loop B hot leg temperature began increasing.
(0600:32),
02:12:00 Reactor Coolant System Loop B hot leg temperature ' increased to (0612:37) offscale at 620F.
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62:17:53 Operator requested Electromatic Relief Valve (RC-R2) outlet (0618:30) temperature. ne reading was 228.7F.
02:22:00 De Electromatic Relief Block Valve (RC-V2) was shut.
(0622:37)
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Approximate 02:30:00 Operator started increasing Steam Generator 3 from 30 inches on (0630:37)
Startup Range to SQ% on Operating Range.
02:45:00 Several radiation alarms were received.
(0645:37)
Approximate 02:45:00 Reactor Coolant Makeup Pump C (MU-P-lC) was stopped.
(0645:37)
Approxisate 02:45:00 Operator opened Main Steam Isolation Valves (MS-V13 and MS-V7B).
(0645:37)
Approxi= ate 02:50:00 Site Emergenc7 was declared. Notifications to offsite authorities (0650:37)
Approxi= ate and organizations were initiated.
02:51:57 Operator attempted to' start Reactor Coolant Pu=p 21 (RC-P-2A).
(0652:34)
Pump would not start.
02:53:19 Operator attempted to start Reactor Coolant Pu=p 13 (RC-P-13),
(0653:53)
.Ptmp would not start.
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Operator started Reactor Coolant Pump 2B (RC-P-23).
(0654:45) 02:54:49 High Pressure Injection Engineered Safeguards actuation logic (0655:25) reset on increasing Reactor Coolant System pressure.
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02:56:19 Steam Generator B was isolated. Main S:eam Isolation valves (0656:56)
(MS-74B and MS-V73) were shut.
Approximate 03:00:00 Reactor Coolant System pressure increased to 2130 psig.
(0700:37)
~
Approximate 03:03:39 Steam Generator A pressure control was shifted from the Turbine Bypass (0704:16)
Approximate Valves (MSV-25A and B and MSV-26A and 3) to the Power Operated Emergency Main Ste Dump Valves (MSV-31 and B).
03:10:27
%ergency Feedvater Pump 2A (EF-P-2A) was stopped.
(0711:04) 03:12:28 Electromatic Relief Block valve (RC-V2) was opened.
(0713:05)
Approximate 03:12:53 Reactor Coolant Pump 2B (RC-P-2B) was stopped.'
(0712:53)
^
03:20:13 Reactor Coolant Makeup Pump C (MU-P-IC) was started. Reactor Coolant (0720:41)
Makeup Pumps C and A (MU-P-C and A) were operating.
03:23:23 Ceneral Emergency was declared. Notifications to offsite (0724:00)
Approximate authorities and organizations were initiated.
03:30:00 Electromatic Relief Block Valve (RC-V2) was shut.
(0730:37)
Approximate 03:35:08
.. Emergency Feedvater Pump 2A (EF-P-2A) was started.
(0735:43) 03:37:00 Reactor. Coolant Makeup Pump C (MU-P-1C) vas stopped.
~
(0737:37) 03:51:00 Electromatic Relief Block Valve (RC-V2) vas opened.
(0751:37) 9991 107 Approximate LLLi IUJ
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=
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. -. ~ - - -.
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's 03:55:39 Engineered Safeguards actuated on lov RCS pressure. Setpoint is (0756:16) 1640 psig.
03:55:39 he Reactor Building high pressure isolation signal actuated (0756:16) and isolated the Reactor Building. H e Reactor Building isolation set point is 4 psig.
03:56:04 Reactor Coolant Makeup Pump C (MU-P-lC) was started.
(0736:41) 03:59:23 Reactor Building Emergency Cooler 3 was shutdown.
(0800:00) 03:59:53 Reactor Building Emergency Cooler B was started.
(0800:30) 04:06:00 Electromatic Relief Block Valve (RC-V2) was shut.
(0806:37) 04:08:37 Reactor Coolant Pump 1A (RC-P-1A) was started.
(0809:14) 04:09:14 Reactor Coolant Pump 1A (RC-P-1A) was stopped.
(0809:51) 04:17:17 Reactor Coolant Makeup Pump A (MU-P-1A) was stopped.
(0817:54) 04:17:22 Reactor Coolant Makeup Pump C (HU-P-lC) was stopped. No makeup (0817:59) pumps operating.
04:18:17 Operator attempted.to start Reactor Coolant Makeup Pump A (MU-P-1A).
(0818:54) n e pump would not start.
~
04:18:30 Electromatic Relief Block Valve (RC-V2) was opened.
(0819:07)
Approximate -
2221 184
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04:21:53 Reactor Coolant Makeup Pump B (MU-P-1B) was started.
(0818:30) 04:26:59 Reactor Coolant Makeup Pump C (MU-P-1C) was started, tripped, (0827:36)
~
Approximate and was restarted.
04:30:00 The Electromatic Relief Block Valve (RC-V2) was shut.
~
(0830:37)
Approximate 04:30:45 Condenser Vacuum Pumps lA and IC (VA-P-1A and VA-P-lC) were (0831:22) stopped and vacuum was broken.
04:30:45 Power Operated Emergency Main Steam Dump Valve (MS-V3A) was opened.
(0831:22)
Approximate 04:54:00 The Electromatic Relief Block Valve (RC-V2) was opened.
(0854:37)
Approximate 05:18:00 2he Electromatic Relief Block Valve (PC-72) was shut.
(0918:37) 05:54:00 Operator commenced filling Steam Generator A to 99% on the Operating (0954:37)
Approximat.e Range instrumentation.
07:30:00 Electromatic Relief Block Valve (RC-V2) and the Pressurizer Spray (1130:37)
Approximate 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 Dump Valve (MS-V3A) was shut.
~
(1230:37) 22-1 185 2
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08:31:06 Decay Heat Removal Pumps lA and IB (DH-P-1A and DH-P-1B) were (1231:43) started.
08:54:56 Core Flood Tank A alarm printed out at a ievel of 13.13 feet.
(1255:33) 09:04:18 Reactor Coolant Makeup Pump C (MU-P-lC) was stopped.
(1304:55) 09:49:44 Reactor Building Isolation and Containment Spray were actuated by (1350:21)
Engineered Safeguards. Engineered Safeguards actuation started Reactor Coolant Makeup Pump C (MU-P-lC) and Reactor Building Spray Pumps A and B (BS-P-1A and BS-P-1B). ~
09:49:50 Reactor Building Spray Valves (BS-VIA and BS-VilB) opened.
(1350:27) 09:49:58 Reactor Coolant Pumps 1A and IB (RC-P-1A and RC-P-13) inlet air (1350:35) temperature high alarms annunciated and Pressurizer Safety Valves (RC-RIA and RC-RIB) discharge line temperature high alarms annun-ciated.
09:50:24 Reactor Coolant Makeup Pump C (MU-P-lC) was stopped.
(1351:01) 09:55:30 Reactor Pailding Spray Pumps A and B (BS-P-1A and BS-P-1B) were
. (1356:07) stopped.
09:56:58 Decay Heat Removal Pumps A sud B (DH-P-1A and DH-P-1B) were (1357:35) s stopped.
10:24:00 Rea'ctor Coolant System hot leg Loop A temperature decreased to -
(1424:37)
Approximate within the instrumentation. range.
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10:31:25 Reactor Coolant Makeup Pump C (MU-P-1C) was started. Reactor (1432:02)
Coolant pressure was approximately 440 psig.
10:35:55 Reactor Coolant Makeup Pump C (MU-P-1C) was stopped.
(1436:32) 11:06:00 Pressurizer level started decreasing.
(1406:37)
, Approximatei,,.
~
u.,
11:12:00 Reactor Coolant System cold leg Loop A temperature started to (1512:37)
Approximate increase from 200F to 400F. Reactor Coolant System hot leg Loop A temperat'ure decreased from above the instrument range to 360F.
11:18:34 Jeactor Coolant Makeup Pump C (MU-P-1C) was started.
(1519:11) 11:24:00 Pressurizer level stopped decreasing at 180 inches and started (1524:37)
Approximate increasing, going off scale during the next hour.
11:28:12 Reactor Coolant Makeup Pump C (MU-P-lC) was stopped.
(1528:49) 11:32:37 Reactor Coolant Makeup Pump C (MU-P-lC) was started.
(1533:14) 11:35:48 Reactor Coolant Makeup Pump C (MU-P-1C) was stopped.
(1536:25) 6-11:36:00 Operator com=enced filling Steam Generator B to 97% on the Operating (1536:37)
- Approxiniate Range instrumentation.
12:00:00 Steam Generator A level was 972 on the Operating Range.
-(1600:37)
Arproximate 12:48:00 Pressurizer level came on scale.
2221 187 (1648:00)
, Approximate
- 4...<..-].
f-
F s
13:02:23 Condenser Vacuum Pump 1C (VA-P-1C) vas started.
(1703:00) 13:08:22 Normal steam generator feedwater srpply was put in service.
(1708:59)
Approximate 13:13:10 Condenser vacuum Pump 1A (VA-P-1A) vas started.
(1713:47)
.,s 13:23:04 Reactor Coolant Makeup Pump C (MD-7-1C) was started.
(1723:41) 14:43:15 Reactor Coolant. Makeup Pump C (MU-P-1C) was stopped.
(1843:52) 14:54:00 RCS pressure reached 2350 psig.
(1854:37)
Approximate 15:24:00 Reactor Coolant Pump 1A (RC-P-1A) vas started.
(1924:37) 15:24:10 Reactor Coolant Pump 1A (RC-P-1A) uss stopped.
(1924:47)
Approximate 16:04:00 Reactor Coolant Pump 1A (RC-P-1A) was started.
(2008:37) 22:15:00 Reactor Coolant System and Steam Ge:erator conditions were:
(0215:37)
Approximate Reactor Coolant System pressure = 1065 psig.
Pressurizer Temperature = 5517 (pressurizer heaters maintaining temperatu.re).
Pressurizer Level = 397 inches.
Reactor Coolant System cold leg Loop A temperature = 288F Steam Generator A steaming to the P.zin Condenser.
2221 188
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Steza Generator B isolated.
~
Reactor Coolant F.>r,up Pump B (MU-P-1B) operating to supply Reactor Coolant Pump seal injection flow.
Reactor Coolant. System cold, leg Loop A temperature = 256.4F.
Reaccor Coolant System cold leg Loop B temperature = 252.4F.
Reactor Coolant System hot leg Loop A temperature = off scale low, i.e..less than 520.0F.
Reactor Coolant System hot leg Loop B temperature = off scale low, i.e.,less than 520.0F.
I I
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2221 189 15 -
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