Text

Reduction Info of All Plant Data Re Incident from 790328-0427
	ML19221A099
Person / Time
Site:	Crane
Issue date:	04/27/1979
From:	; METROPOLITAN EDISON CO.
To:	;
References
	NUDOCS 7905190122
	Download: ML19221A099 (97)
	v • d • e

t'ET/GPU DATA REDUCTI0fl IfiF0 3/28

/27/79 (I&E) popwM 7905190tp...4 ] 28 2 58 0

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$ETROPOLITAN EDISON C O M P A N Y senmo.2,v o, c.. reti.c u,. +,, ce,

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Subject Data Reduction and P.2nage=ent Group Location TMI Date April 9, 1979 To TMI Recovery Task Force A Data Reduction and Manage =ent Group has been established. The objectives of the Group are:

1.

To collect and file in a single location all plant data, docu=ents, procedures, analyses, etc. relative to the TMI #2 incident.

2.

To provide reduction of this data into convenient siery for=ats for use in plant analyses, procedure preparation, design of plant modifications, etc.

3.

To distribute periodic reports listing the information available and updating plant para =eter histories.

4.

To serve as a distribution center to all on-site and off-site users of infor=ation fro = the TMI #2 incident.

Effective imediately it vill be the responsibility of the docu=ent originator to provide a copy of each docu=ent generated, along with the following infor=ation for each docu=ent, to the Data Reduction &

s Manage =ent Group (DRMG):

- Originator's name or Group identification.

- Docu=ent type.

- Date of document.

- 1 or 2 keywords identifying the docu=ent.

This infor=ation should be annotated on the docu=ent or on an attached cover sheet, as appropriate.

A preliminary list of the types of infor=ation to be collected is included as Attachment A.

Initially, copies of all docu=ents and infor=ation generated since the incident should be sub=itted.

Then sub=ittals should continue on a daily basis.

Docu=ent collection baskets will be located in each trailer.

A

=essenger will pick up docu=ents fro = the collection points 4 times a day for delivery to the DRMG.

Af ter reduction of the data has been cc=pleted,1 copy of the documenta-tion will be filed in the DRMG, Trailer #26.

Anyone requiring infor=ation fro = these files =ay visit the trailer or call 233-9045, ext. 170 or 171 t

259

{~'i 7905190 INTER-0FFICE MEMORANDUM

t 2k-TMI Recovery Task Force April 9, 1979 A report of file contents will be published on a regular basis. A copy of the report will be distributed and vill be available in Trailer #2G.

If you have questions or need assistance, please call R. Long or J. Weiser on 233-9045, ext. 170 or 171 or on 367-3676.

8 O

~

Robert L. Lo /

Manager, D W

Approved By:

A R. C. Arnold GPU Operations Manager Distribution:

B. Cobean J. Herbein M. Levenson R. Mctson F. Palmer R. Paulick V. Stello F. Stern R. Wilson

=

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At tachment 91 Trailer City - T'!I

..,T GPU Service Ccrporation

. [h h@@Ch April 16, 1979 260 CNrry H n Rcra M

Pars orany New Jersey 07C54 201 263 4900 TELEX 136-492 TO:

R. C. Arnold FROM:

R. L. Long PRELIMINARY SEQUENCE OF EVENTS IMI 2 ACCIDENT OF MARCH 28, 1979 Attached is a Preli:dnary Sequence of Events spanning the first app ro xima tely twenty hours following the D11-2 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 tice of the turbine trip, 0400:37, defined as time 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 time using a 24-hour clock.

For exa=ple, 1:52:43 p.m. cn 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 f rom various infor=ation anu data sources, including control room logs, strip chart recorders, alar = printouts and

/

reactime ter 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 infor=ation will be provided as soon a.

it is available and we will keep you inforned of our progress.

M R. L. Lo GPU CC: H. Diecka=p J. Herbein R. 'Jilson Industrial Advisory Group Data Redec tion and Management M. Eczilla L. Farding G. Kunder J. Logan G. Miller 128 313 GPU Servce Co porai.on.s a sac:ary ct Ger.eral Puchc Uhht.es Corporabon e+

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TMI 2 ACCIDENT OF MARCH 28, 1979 Issued April 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 total flow was approximately 107.5% of design flow ar.d th'e Reactor Coolant System pressure was 2155 psig. Reactor Coolant Makeup Pump B (MU-P-1B) was in service supplying makeup and Reactor Coolant Puup Seal injection flow.

The Reactor Coolant System soluble baron concentration was approximately 1030 parts per million.

Pressurizer Sptay Valve (RC-V1) and the pressurizer heaters were in manual coatrol 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*

Operating Level 56%

57.4%

Startup Level 158.8 inches 163.4 inches Steam Pressure 910 psig 889.6 psig Feedwater Temperature 462.7F 462.7F

MPPH is Million Founds Per Hour 128 3i4 a.

Steam Generator Feedwater Pumps ( FW-P-1 A and FW-P-1 B) we re in service, Condensate Looster Pumps (CO-P-2A, CO-P-2B and CO-P-2C) were in service, and Condensate Pumps (CO-P-1A and CO-P-1B) ware in service.

An at tempt was being made to clear a clogged resin transfer line in the standby demineralizer.

-00:00:01 Condensate Pump A (CO-P-1 A) stopped.

(0400:36)

-00:00:01 Feedwa ter Pumps (FW-P-1A and FW-P-13) stopped at essentially the (0400:36) same time resulting in a loss of feedwater flow to both steam generators.

00:00:00 Main Generator was tripped followed by a turbine trip.

(0400:37) 00:00:00

hree Emergency Feedwater Pumps (EF-P-1, 2A, 2B) started.

(0400:37) 00:00:03 The Electromatic Relief Valve (RC-RV2) opened at the setpoint (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 The operator placed the Pressurized Spray Valve (RC-VI) and pres-(0400:45)

Approximate suriser herters under automatic control.

00:00:13 The operator started the Rcactor Coolant Makeup Pump A (MU-P-1 A),

opened High Pressure Injection Isolation Valve A (MU-V16A) and isolated letdow. flow in anticipation of the expected pressurizer level decrease.

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00:00:13 The Elect romat ic F.alie f ( RC-RV2) solenoid de-energized giving (0400:50)

Approx ~ mate a non-open indication to the control rcom operators.

The Elec-tromatic Relief Valve (RC-RV2) should have receated at about this time (closure s e t ro in t of 2205 psig).

00:00:14 The Emergency Feed Pumps (EF-P1,

_A and 2B) achieved no rmal d i s-(0400: 51) charge pressure.

00:00:15 Water hammer in the condensate piping occurred.

(0400:52)

Approxicate 00:00:30 Pressurizer Safety Valve (RC-RVIB) and Electrcoatic Relief Valve (0401:07)

(RC-RV?) discharge line temperature alarms printed out.

00:00:38 Steam Cenerator A 'evel reached the 30-inch setpoint here the (0401:15)

Approximate Feergency Feedwater Valves (EF-VilA and EF-V11B) open.

Fe ed wa t e r was not admitted because Emergency Feedwater Block Valves (EF-V11A and SF-V125) were shut.

00:00:39 Reactor Coolant Maieup Pump A (MU-P-1A) was stopped.

(0401:16) 00:00:40 Steam Cenerator 3 '_evel reached the 30-inch setpoint where the (0401:17)

Approximate Emergency Feedvater Valves (EF-VilA and EF-VilB) open.

Feedwater was not admitted be:suse Emergency Feedwater Block Valves (EF-V11A and EF-V12B) were shut.

00:00:41 Reactor Coolant Ma keup Pump A (MU-P-1 A) was res tar ted.

With (0401:18)

Reactor Coolant Makeup Pu=ps A and B (MU-P-1 A and MU-P-13) oper-ating, pressurizer level rate of decrease slowed.

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00:01:00 Pressurizer level started increasing.

Peactor Coolant System hot (0401:37)

Approximate leg and cold leg terperatures reached 575F.

Reactor Coolant Drain 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 alar = printed out.

(0402:03) 00:01:45 Steam Generators A and B have boiled dry at this time.

(0402:22)

Approximate 00:02:01 Reactor Coolant Makeup Pump B (MU-P-1B) was stopped due to (0402:38)

Engineered Safeguards actuation.

00:02:04 High Pressure Inject ion Pump C (:!U-P-lC) started autcmatically.

(0402:41) 00:03:12 Reactor Coolant Drain Tank Relief Valve (WDL-RI) lifted at 120 psig.

(0403:49)

Approximate 03:03:14 High Pressure Inj ec t ion portion of Engineered Sa feguards was manually (0403:51) bypassed.

Both Reactor Coolant Makeup Pumps A and C (MU-lP-1A and MU-P-IC) were operating.

00:03:26 Reactor Coolant Drain Tank high temperature alar = received at 127.2F.

(0404:03) 00:04:38 Reactor Coolant Makeup Pump C (MU-P-1C) 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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00:04:52 Intermediate Closed Cooling Pump (IC-P-1 A) started.

(0405:29) 00:04:58 First alarm indication received that letdown had been secured.

(0405:35) 00:05:06 Presurizer level s*,pped 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, 21 seconds into the transient.

00:05:15 Condensate Booster Pump B (CO-P-2B) tripped.

(0405:52) 00:05:50 Reactor Coolant System pressure scopped its sharp decrease and began (0406:27)

Approximate to turn up.

Minimum value reached was approxi=ately 1350 psig.

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

00:06:58 Letdown flow of 71.4 gallens 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 tenperatures began to (0403:52) decrease.

00:08:30 Reactor Coolant System pressure began to decrease.

(0409:07) 00:10:00 Pressurizer level came on scale.

(0410:37)

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00:10:19 Reactor Building Sump Pump B (WDL-P-23) started.

(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 Sump high level alarm received.

Sa t po in t is (0411:25) 4.650 feet.

00:11:40 Reactor Coolant Makeup Pump A (MU-P-1 A) was started.

(0412:17) 00:14:50 The Reactor Coolant Drain Tank rupture diaphragm (UDL-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 annunciator (0425:37)

Approximate received at the Radiation Monitor Panel.

00:36:08 Emergency Feedwater Pump 2B (EF-P-2B) 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-2B) was stopped.

(0438:48) 01:10:54 Reactor 3uilding air cooling coils emergency discharge alarm (0511:31) printed out.

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01:13:29 Reactor Coolant Pump 2B (RC-P-2B) 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 anJ remained (0513:59) out of service until 02:47:31 (0648:08).

01:20:31 Operator requested printout of the Electromatic Relief Valve (RC-RV2) outlet temperature.

The reading was 283.0F.

01:40:37 Reactor Coolant Pump 2A (RC-P-2A) was stopped.

(0541:14) 01:40:45 Reactor Coolant Pump 1A (RC-P-1A) was stopped.

(0541:22) 01:42:00 Operator started raising Steam Generator A level from 30 inches (0542:37)

Approximate ca the startup Range to 50% on Operating Range.

Reactor Coolant System Loops A and 3 cold leg temperatures both started decreasing.

Reactor Coolant System pressure started d<2 creasing.

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.

(0600:3')

Approximate 02:00:00 Reactor Coolant System Loop B hot leg temperature began increasing.

( 06 'J0 : 37 )

02:12:00 Reactor Coolant System Loop B hot leg temperature increased to (0612:37) of fscale at 620F.

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02:17:53 operator requested Electromatic Relief Valve ( RC-12 ) cutlet (0618:30) temperature.

The reading was 228.7F.

02:22:00 The Electrocatic Relief Block Valve (RC-V2) was shut.

(0622:37)

Approxi= ate 02:30:00 Operstor started increasing Steam Generator 3 fres 30 inches on (0630:37)

Startup Range to 50% on Operating Range.

02:45:00 Several radiation alarus were received.

(0645:37)

Approxt= ate 02:45:00 Reactor Coolant Makeup Pump C (MU-P-1C) was s t o p ped.

(0645:37)

Approx ima te 02:45:00 Operator opened Main Stema Isolation Valves (MS-V13 and MS-v73).

(0645:37)

Appr ox ica t e 02:50:C0 Site Emergency was declared.

Notifications to offsite authorities (0650:37)

Approx ica t e and organizations were ir. it i a t ed.

02:51:57 Operator atte=pted to start Reactor Coolant Pc: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-1B).

(0653:53)

Pump would not start.

02:54:C9 Operator started Reactor Coolant Punp 23 (RC-P-23).

(0654:-5) 02:54:49 High Pressure Injection Engineered Safeguards actuation logic (0655:25) reset en increasing Reactor Coolant System prest re.

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02:56:19 Steam Generator B was isolated. Ma in 5:eam Isolation valves (0656:56) (MS-V4B and MS-V7B) 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 shif ted from the Turbine Bypass (0704:16) Approximate Valves (MSV-25A and B and MSV-26A and 3) to the Power Operated E=ergency Main Steam Dump Valves (MSV-3A and B). 03:10:27 Emergency Feedwater Pump 2A (EF-P-2A) was stopped. (0711:04) 03:12:28 Electromatic Relief Block valve (RC-V2) was opened. (0713:05) Approxicate 03:12.13 Reactor Coolant Pu=p 2B (RC-P-2B) was 3:cpped (0712:53) 03:20:13 Reactor Coolant Makeup Pu=p C (MU-?-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. Notificztions to offsite (0724:00) Approximate authorities and organizations were initiated. 03:30:00 Electromatic Relief Block Valve (RC-V2) was shut. (0730:37) 6p proxima te 03:35:08 Emergency Feedwater Pump 2A (EF-P-2A) was started. (0735 43) 03:37:00 Reactor. Coolant Makeup Pump C (MU-P-lC) wa s stopped. (0737:37) 03:51:00 Electromatic Relief Block Valve (RC-V2) wa s opened. (0751:37) APProxi-ate }) S ^ ^ - ^ ^ ^ *w ^^ "A. ? whkh g "h= en hw h ene

03:55:39 Engineered Safeguards actuated on low RCS pressure. Setpoint is (0756:16) 1640 psig. 03:55:39 The Reactor Building high pressure i;olation signal actuated (0736:16) and isolated the Reactor Building. The Reactor Building isolation set point is 4 psig. 03:56:04 Reactor Coolant Makeup Pu=p C (MU-P-lC) was started. (0756:41) 03:59:23 Reactor Building Emerge.cy Cooler 3 was s h u t d o wn. (0800:00) 03:59:53 Reactor Building Emergency Cooler B was started. (0800:30) 04:06:00 Electromatic Relief Block Vcive (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 (AC-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 (MU-P-1C) was stopped. No cakeup (0817:59) pumps operating. 04: 18:17 Operator attempted to start Reactor Coolant Makeup Pump A (MU-P-1 A). (0818:54) The pump would not start. 04:18:30 Electromatic Relief Block valve (RC-V2) was opened. (0819:07) Approximate - 10 _ 128 323 e g

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-lC) was startei, 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) Approxicate 04:54:00 The Electromatic Relief Block Valve (RC-V2) was opened. (0854:37) Approximate 05:18:00 The Electromatic 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 instrument;cien. 07:30:00 Electromatic Relief Block Valve (RC-V2) and the Pressurizer Spray (1130:37) Approximate Valve (RC-VI) 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) .4

08:31:06 Decay Heat Removal Pumps I A and 13 ( DH-P-1 A and DH-P-13) were (1231:43) started. 08:54:56 Core Flood Tank A alarm printed out at a level of 13.13 feet. (1255:33) 09:04:18 Reactor Ceolant Makeup Pump C (MU-P-lC) was stopped. (1304:55) 09:49:44 Reactor Building Isolation and Contair. ment 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-13). 09:49:50 Reactor Building Spray Valves (BS-VIA and BS-VilB) opened. (1350:27) 09:49:58 Reactor Coolant Pumps lA and IB (RC-P-1A and RC-P-1B) inlet air (1350:35) temperature high alarms annunciated and Pressurizer Safety Valves (RC-RlA and RC-RIB) discharge line temperature high alarms annun-ciated. 09:50:24 Reactor Coolant Makeup Pump C (MU-P-1C) was stopped. (1351:01) 09:55:30 Reactor Building Spray Pumps A and B (BS-P-1 A and BS-P-1B) were (1356:07) stopped. 09:56:58 Decay Heat Re= oval Pumps A and B (DH-P-1 A and DH-P-13) were (1357:35) stopped. 10:24: 00 Reactor Coolant System hot leg Loop A temperature decreased to (1424:37) Approximate within the instrumentation range.

10:31:25 Reactor Coolant Makeup Pump C (MU-P-1C) was started. Eeactor (1432:02) Coolant pressure was approximately 440 psig. 10:35:55 Reactor Cociant Makeup Pump C (MU-P-1C) was stopped. (1436:32) 11:0G:00 Pressurizer level started decreas ing. (1406:37) Approximate 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 Img Loop A temperature decreased frem above the instrument range to 560F. 11:18:34 Reactor Coolant Makeup Pump C (MU-P-lC) 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) w: stopped. (1528:49) 11:32:37 Reactor Coolant Makeup Pump C (MU-P-lC) wat started. (1533:14) 11:35:48 Reactor Coolant Makeup Pump C (MU-P-1C) was stopped. (1536:25) 11:36:00 Operator com=enced filling Steam Cenerator B to 97% on the operating (1536:37) Approximate Range instrumentation, 12:00:00 Steam Cenerator A level was 97% on the Operating Range. (1600:37) Approximate 12:48:00 Pressurizer level came on scale. (1648:00) jqn 77/ Approximate iL3 JLg :

13:02:23 Condenser Vacuum Pump 1C (VA-P-lC) was started. (1703:00) 13:08:22 tiormal steam generator fe ed wa t e r st; ply was put in service. (1708:59) Approxicate 13:13:10 Cond :nser Vacuum Pump 1A (VA-P-1 A) was started. (1713:47) 13:23:04 Reactor Coolant Makeup Pump C (MU-?-1C) was started. (1723:41) 14:43:15 Reactor Coolant Makeup Pump C (MU-P-lC) was stopped. (1843:52) 14:54:00 RCS pressure reached 235u psig. (.854:37) Approximate 15:24:00 Reactor Coolant Pump 1A (RC-P-1A) v' s started. (1924:37) 15:24:10 Reactor Coolant Pump 1A (RC-P-1A) v2 s stopped. (1924:47) Approximate 16:04:00 Feactor Coolant Pump 1A (RC-P-1A) v2 s started. (2008:37) 22:15:00 Reactor Coolant System and Steam Generator conditions were: (0215:37) Approximate Reactor foolant System pressure = 1065 psig. Pressurizer Temperature = 551F (pressurizer heaters maintaining temperature). Pressurizer Level = 397 inches. Reactor Coolant System cold leg Loc; A temperature = 2SSI Steam Generator A steaming to the M2in Condenser. 128 27

Stezs Generator 3 isolated. Reactor Coolant Makeup Pump B (MU-P-1B) operating to supply Reactor Coolant Pump seal injection flow. Reactor Coolant System cold leg Loop A temperature = 256.4F. Reae:or 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 = of f scale low, i.e.,less than 520.0F. i \\ - 170 77 \\0 JL . - -....., ~ -.-. - -.w ,5

O TN b ~O 50 rte x/ / Lf l F "~ N '\\l /~ h d 2 ), ) 128 329 i

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Page 1 of 3 TABLE 1A nil-2 Radiation Survey / Aux. & Fuel Handling Building El. 281' DWG #2065 LATEST DATE READING READING GRID (R/hr) OBTAINED* TIME

aA/a 61 0.1 4/14/79 1530 63.5 0.5 - 0.7 4/06 174) aB/a 60.2 0.5 - 0.7 4/14 1530 60.5 0.2 - 0.35 4/14 1530 60.7 0.1 4/14 1530 61 0.1 - 0.25 4/14 1530 61.4 0.1 - 0.25 4/14 1530 61.6 0.5 4/08 1800 62 0.1 4/14 1530 62 1-3 4/14 1530 62.5 C.0%

4/14 1530 63.2 0.3 4/14 1530 63.5 > 1000 4/14 1530 63.5 75 - 125 4/14 1530 63.5 175 4/14 1530 64 400 - 500 4/14 1530 65.2 450 4/14 1530 aBa/a 64.5 1.75 4/04 1800 aC/a 63.5 > 1000 4/14 1530 66 60 4/14 1530 66.5 1-5 4/14 1530 67 0.19 4/07 1800 aD/a 60 10 4/14 1530 60.8 1.5 4/14 1530 61 0.25 4/08 1800 62 25 - 65 4/14 1530 62.8 3-5-7 4/14 1530 63 2-4 4/14 1530 64 50 4/14 1530 67.5 1 4/14 1530 aD-aE/a 60 0.7 - 1.0 4/14 1530 66.8 0.7 - 1.0 4/14 1530 aD-aJ/a 65.8 20 5 4/14 1530 aE/a 62.8 50 4/08 1800 63 50 4/08 1800 63.2 0.1 4/14 1530 66.5 1-3 4/14 1530 Note:

La t e s t Posted HP Data.

Actual dates and times of readings are not available. 128 T3i

Page 2 of 3 TABLE 1A TMI-2 Radiation Survey / Aux. & Fuel Hand 1ing Building El. 281' D'a'G # 206 5 LATEST DATE READING RE ADI!'G GRID (R/hr) OBTAINED* TIME

aE-aG/a 66.5 1-3 4/14/79 1530 67.2 7 - 10 4/14 1530 aF/n 67.8 0.5 4/14 1530 aG/a 60.5

> 1000 4/14 1530 61.5 2-5

/14 1530 62 b 0.28 4/14 1530 62.2 0.025 4/14 1530 63 0.4 4/14 1530 63.6 3-2 4/14 1530 64.5 10 4/14 1530 66 04 4/14 1530 67.5 2

4/14 1530 aH/a' 66.5 0. 3 - v. ", 4/14 1530 67 2 4/14 1530 aJ/a 60.5 10 3/31 1800 52 b 0.4 4/14 1530 63.3 0.4 4/14 1530 64.5 7 4/14 1530 65.8 0.5 /14 1530 66.7 0.5 4/14 1530 67.5 0.15 - 0.20 4/1'4 1530 aK/a 62.b 0.05 4/14 1530 67.4 0.7 4/^ 0930 at/a 61.2 0.15 3/31 1800 62 b 0.05 4/14 1530 65.5 0.05 4/06 1745 66.5 0.3 4/06 1745 aM/a 66.5 0.35 4/14 1530 66.8 0.1 - 0.2 4/14 1530 aN/a 62 b 0.25 4/14 1530 63.5 0.2 4/09 0930 64.5 1.5 4/09 0930-66 0.2 4/06 1745 67.5 0.1 4/14 1530 Note:

La t e s t Posted HP Data.

Actual dates and times of readings are not available. 128 332

Page 3 of 3 TABLE 1A TMI-2 Radiation Survey / Aux, & Fuel Handling Building El. 281' DWG #2065 LATEST DATE READING READING GRID (R/hr) OBTAINED* TIME

4P/a 66.5 0.02 4/04/79 1800 66.8 0.7 4/14 1530 aQ/a 61.6 0.25 4/14 1530 62 b 1.2 4/14 1530 62.2 0.25 4/09 09?O 63 1.2 4/14 1530 63.8 0.2 4/14 1530 64.5 1.5 4/14 1530 65 0.8 4/14 1530 65.2 0.2 4/14 1530 66.2 0.3 4/14 1530 aQa/a 65.8 0.01 4/06 1745 67.2 0.06 3/31 1800 aQ-aR/a 61.5 3-2-1 4/1.4 1530 62.2 0.15 4/06 1745 aR/a 63 100 4/14 1530 63 2

4/14 1530 64 3 4/04 1800 64.3 0.5 - 0.6 4/14 1530 64.5 3 4/14 1530 66.3 0.5 4/14 1530 66.5 0.7 4/14 1530 67.2 0.15 4/14 1530 aT/a 66.5 0.15 4/14 1530 Note:

Latest Posted HP Data.

Actual dates and times of readings are not available. 128 333 i

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Page 1 of 1 TABLE IB TMI-2 Radiation Survey / Aux. 6 Fuel Handling Building El. 258' & 281' DWG #2065 LATEST DATE OF TIME OF READING ACTUAL ACTUAL GRID (R/hr) READING READING El. 258' aA/a 60.2 0.010-0.015 4/16/79 2200 61.8 0.04 4/16 61.9 0.07 4/16 aB/a 60.2 0.08 4/16 60.9 0.1 4/16 61.7 0.050-0.300 4/16 62, 0.3 - 0.4 4/16 El. 281' aB/a 63 0.5 4/16 aD/a 62.2 0.2 4/16 aH/a 62.6 0.9 4/18 aK/a 62.4 0.9 4/18 aN/a 64.5 4.0 (shaf t flooded) 4/18 128 335

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Page 1 of 1 TABLE 2B TMI-2 Radiation Survey / Aux. & Fuel Handling Building El. 305' DWG #2066 LATEST DATE OF TIME OF READING ACTUAL ACTUAL GRID (R/hr) READING READING aE/a 62.7 0.04 4/18/79 63.2 100 4/18 1130 aL/a 60.8 0.001 4/14 aQ/a 60.9 0.6 128 339 i

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Page 1 of 3 TABLE 2A TMI-2 Radiation Survey / Aux. & Fuel Handling Building El. 305' DWG #2066 LATEST DATE READING READING GRID (R/hr) OBTAINED* TIME

aA/a 61.5 0.01 - 0.012 4/14/79 1530 62 0.5 4/14 1530 64*

0.09 4/04 1800 65 10 4/06 1745 aBa 60.2 0.006 4/07 18.0 60.5 0.002 4/14 1510 61.5 7-5-2 4/14 1 5'.10 62 10 4/14 1539 63 0.7 4/14 1530 63.5 1.5 4/14 1530 63.8 0.18 - 0.5 4/14 1530 64 0.5 - 1.0 4/6 1745 64 25 (abova HPR-227) 4/14 1530 64.5 5 4/14 1530 65 1.5 4/99 0930 ac/a 61.5 8-6-1 4/14 1530 64 3 4/14 1530 65.5 200 4/14 1530 68 0.04 - 0.06 4/06 1745 68 0.095 - 0.11 4/06 1745 68 0.003 - 0.02 4/06 1745 aD/a 60.8 0.045 4/14 1530 61.5 7 4/14 1530 62.5 0.6 4/14 1530 63 0.03 4/14 1530 63.5 15 4/14 1530 aE/a 60.5 0.002 4/14 1530 61.5 2 4/09 0930 62 2 4/14 1530 63 50 - 100 4/06 1745 63.6 50 4/14 1530 66 0.3 4/14 1530 aG/a 61 30 3/30 7'00 61 0.1 4/14 1530 62.5 C.6 4/14 1530 63 30 4/14 1530 a6 1 4/04 1800 Note:

La t e s t Posted HP Data.

Actual dates and times of readings are not available. I28 34i

Page 2 of 3 TABLE 2A TMI-2 Radiation Survey / Aux. & Fuel Handling Building El. 305' DWG #2006 LATEST DATE READING READING GRID (R/hr) OBTAINED* TIME

aH/a 65.5 0.15 4/14/79 1530 aJ/a 60.3 0.012 4/14 153C 60.75 0.0005 4/14 1530 61.5 2.3 4/06 1745 62 0.7 4/14 1530 b

62 1.0 4/14 1530 62I6 1.5 4/08 1800 63 5 4/14 1530 63.2 0.7 4/14 1530 63.5 400 4/14 1530 63.9 1 4/14 1530 65.4 0.15 4/14 1530 aK/a 64.5 0.1 4/06 1745 aL/a 61.5 1.25 4/06 1745 62 1.5 4/14 1530 62I5 0.5 4/14 1530 65.5 0.2 4/14 1530 aN/a 60.3 0.012 4/14 1530 60.75 0.0005 4/14 1530 62 0.4 4/14 1530 62.6 0.15 4/14 1530 62.8 0.075 4/14 1530 64 0.002 4/14 1530 64.5 0.02 4/14 1530 aQ/a 60.2 0.012 4/14 1530 61.8 3 4/14 1530 62 0.15 4/14 1530 63 0.1 - 0.2 4/09 0930 63.8 0.15 4/14 1530 65.5 0.3 - 0.4 4/14 1530 aQ-aP/a 64.5 0.15 4/14 1530 m Note:

Latest Posted HP Data.

Actual dates and times of readings are not available. 128 342 i

Page 3 of 3 TABLE 2A TMI-2 Radiation Survey / Aux. & Fuel Handling Building El. 305' DWG #2066 LATEST DATE READING READING CRID (R/hr) OBTAINED* TIME

aR/a 60.2 0.012 4/14/79 1530 60.5 0.002 - 0.001 4/14 1530 60.5 0.0005 4/14 1530 61 0.05 4/08 1800 61.5 0.2 4/14 1530 62.5 0.005 4/14 1530 63.5 0.05 4/14 1530 65 0.4 4/14 1530 66.5 0.1 - 0.2 4/14 1530 aT/a 62.5 0.005 4/14 1530 63.2 0.1 - 0.2 4/14 1530 64.8 0.5 4/14 1530 65.2 0.5 4/06 1745 66 3

3/30 2100 Note.

La t e s t Posted HP Data.

Actual dates and times of readings are not available. 128 343

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Page 1 of 1 TABLE 3B 'IMI-2 Radiat ion Survey / Aux. & Fuel Handling Building El. 328' DWG #2067 LATEST DATE OF ~.1ME OF READING ACTUAL ACTUAL GRID (R/hr) READING READING aB/a 62.9 0.04 4/18/79 aD/a 62.4 0.005 62.8 0.02 64.5 0.15 64.6 0.1 aE/a 65.5 3-7 65.7 250 aG/a 63.8 0.1 65.4 0.45 65.6 1 a.Y/ a 63.4 0.05 aK/a 63 0.12 ('- 63.2 0.9 at/a 62 0.15 63.8 0.3 aQ/a 63.6 0.002 128 347

Page 1 of 2 TABLE 3A TMI-2 Radiation Survey / Aux. 6 Fuel Handling Building E1. 328' DWG #2067 LATEST DATE READING READING CRID (R/hr) OBTAINED* TIME

aB/a 60.5 0.15 4/14/79 1530 60.7 0.15 4/14 1530 60.8 0.03 4/14 1530 63.5 0.15 4/14 1530 64.2 1.0 4/14 1530 64.3 3.0 4/14 1530 64.5 0.2 4/14 1530 aC/a 65.5 3.0 4/14 1530 65.5 2.0 4/04 1800 aD/a 62.4 0.05 4/14 1530 62.8 0.05 - 0.075 4/14

';30 64 0.05 4/09 0930 64.3 1.0 4/14 1530 64.7 0.3 4/14 1530 aE/a 60.5 0.05 4/14 1530 60.8 0.20 4/14 1530 ( 62 0.30 4/14 1530 64 5 1.0 4/04 1800 64.9 0.1 4/09 0930 65.3 0.45 4/14 1530 66 40 4/18 aG/a 64 0.3 4/14 1530 64.4 0.3 4/14 1530 65.4 5.0 4/14 1530 aJ/a 60.8 0.05 4/14 1530 62 0.05 4/14 1530 62.2 0.025 4/14 1530 62 0.04 - 0.05 4/14 1530 b 63 0.17 4/09 0930 63.6 0.2 4/18 64.2 3.0 4/14 153C 64.3 0.15 4/14 1530 64.5 1-3 4/14 1530 64.8 3.0 4/04 1800 aJ-aL/a 63.9 0.075 - 0.05 4/14 1530 Note:

La t es t Postc? HP Data.

Actual dates and times of r < dings are not available. 128 348

Page 2 of 2 TABLE 3A TMI-2 Radiation Survey / Aux. & Fuel Handling Building El. 328' DWG #2067 LATEST DATE READING READING GRID ( R/hr) OBTAINEJ* TIME

aK/a 64.5 45 4/14/79 1530 65.2 0.05 4/14 1530 aL/a 61.5 0.015 4/14 1530 61.8 0.015 4/14 1530 62.8 0.7 4/14 1530 64 0.2 4/18 aL-aN/a 65.3 0.06 - 0.05 - 0.04 4/14 1530 aM-aP/a 65.5 0.03 4/18 aN/a 61.8 0.01 4/14 1530 62.6 0.001 4/07 1810 63.2 0.03 4/07 1810 64 0.005 4/07 1810 64.2 0.025 4/14 1530 64.6 1.0 4/14 1530 aQ/a 61.8 0.002 4/14 1530 63.4 0.15 4/04 1800 63.8 0.015 4/14 1530 64.8 0.05 4/14 1530 aR/a 61 0.025 4/14 1530 61.8 0.001 4/14 1530 62.2 0.02 4/09 0930 62.5 0.002 4/07 1810 63.4 0.01 4/09 0930 aT/a 60.5 0.001 4/14 1530 62.8 0.001 4/14 1530 63 0.001 4/14 1530 Note:
Latest Posted HP Data.

Actual dates and times of readings are not available. 128 34?

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Page 1 of 2 TABLE 3 TMI-2 Radiation Survey / Aux. & F2e1 Handling Building El. 328' DWG #2067 LATEST DATE READING READING GRID ( R/hr) OBTAINED* pit aB/a 60.5 0.15 4/14/79 1530 60.7 0.15 4/14 1530 60.8 0.03 4/14 1530 63.5 0.15 4/14 1530 64.2 1.0 4/14 1530 64.3 3.0 4/14 1530 64.5 0.2 4/14 1530 ac/a 65.5 3.0 4/14 1530 65.5 2.0 4/04 1800 aD/a 62.4 0.05 4/14 1530 62.8 0.05 - 0.075 4/14 1530 64 0.05 4/09 0930 64.3 1.0 4/14 1530 64.7 -0.3 4/14 1530 aE/a o0.5 0.05 4/14 1530 ( i 60.8 0.20 4/14 1530 (. 62 0.30 4/14 1530 64 5 1.0 4/04 1800 64.9 0.1 4/09 0930 65.3 0.45 4/14 1530 66 35 4/14 '530 aG/a 64 0.3 4/14 530 64.4 0.3 4/14 1530 65.4 5.0 4/14 1530 aJ/a 60.8 0.05 4/14 1530 62 0.05 4/14 1530 62.2 0.025 4/14 1530 62 0.04 - 0.05 4/14 1530 b 63 0.17 4/09 0930 63.6 0.22 4/14 1530 64.2 3.0 4/14 1530 64.3 0.15 4/14 1530 64.5 i-3 4/14 1530 64.8 3.0 4/04 1800 aJ-aL/a 63.9 0.075 - 0.05 4/14 1530 I Note:

Latest Posted HP Data.

Actual dates and times of r eadingr are not available. 128 351 c.

Page 2 of 2 TABLE 3 TMI-2 Radiation Survey / Aux. & Fuel Handling Building El. 328' DWG #2067 LATEST DATE READING RE ADING CRID (R/hr) OBTAINED* TIME

aK/a 64.5 45 4/14/79 1530 65.2

,0.05 4/14 1530 aL/a 61.5 0.015 4/14 1530 61.8 0.015 4/14 1530 62.8 0.7 4/14 1530 64 0.22 4/14 1530 aL-aN/a 65.3 0.06 - 0.05 - 0.04 4/14 1530 aM-aP/a 65.5 0.015 - 0.020 4/14 1530 aN/a 61.8 0.01 4/14 1530 62.6 0.001 4/07 1810 63.2 0.03 4/07 1810 64 0.005 4/07 1810 64.2 0.025 4/14 1530 64.6 1.0 4/14 1530 ( 's aQ/a 61.8 0.002 4/14 1530 63.4 0.15 4/04 1800 63.8 0.015 4/14 1530 64.8 0.05 4/14 1530 aR/a 61 0.025 4/14 1530 61.8 0.001 4/14 1530 62.2 0.02 4/09 0930 62.5 0.002 4/07 1810 63.4 0.01 4/09 0930 aT/a 60.5 0.001 4/14 1530 62.8 0.001 4/14 1530 63 0.001 4/14 1530 Note:

Latest Posted HP Data.

Actual dates and times of readings are not available. 128 352 i

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