ML20096D727

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Forwards Revised Gpu Nuclear Analysis Re Subcooling Margin Monitor,Per 840824 Response to Commission 840727 Memorandum Concerning Conclusions Reached in SECY-84-237.Svc List Encl
ML20096D727
Person / Time
Site: Crane Constellation icon.png
Issue date: 09/04/1984
From: Baxter T
MEDINA ELECTRIC COOPERATIVE, INC., SHAW, PITTMAN, POTTS & TROWBRIDGE
To: Chilk S
NRC OFFICE OF THE SECRETARY (SECY)
References
SP, NUDOCS 8409060264
Download: ML20096D727 (38)
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Text

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e. SCOTT CUSTER. JR.

RtCHANO S. SEATTY Cous.SEL weerte S OsmECT Daai., sunset 4 September 4, 1984 (202) 822-1090 Mr. Samuel J.-Chilk Secretary U.S. Nuclear-Regulatory Commission

Washington, D.C.-

20555 In the' Matter of Metropolitan Edison Company. (Three Mile Island Nuclear St ion, Unit No. 1) Docket No.-50-289 Restart)-

Dear Mr.-Chilk:

By your Memorandum for Parties to the TMI-l Restart Proceeding, dated July 27, 1984, and. entitled "NRC Staff's Safety Evaluation of,'Subcooling Criteria for Actuating or Throttling High Pressure Injection (SECY-84-237)," the Com-mission invited the comments:of.the parties on the conclusions reached in the Safety Evaluation. -By letter of August 24, 1984, 7 Tdvised the Comission that Licensee had no comments, but that a revised analysis (which supersedes the GPU Nuclear analysis assessed in'the Staff's Safety. Evaluation) would-be filed with the Staff shortly. i y ~B409060264 840904 PDR ADOCK 05000289 Q PDR ~ m

~- SHAW, PITTMAN, PoTTs & TROWPIRIDGE n.. ..o, . = co no. Mr.LSamuel~J. Chilk September 4,'1994 Page-2 -Enclosed is~ letter 5211-84-22'21 (and-enclosures-I and 2), dated August 31, 1984, from H. D. Hukill (GPU Nuclear) to John F. Stoltz'(NRC), Subcooling Margin Monitor (SMM). This represents the revised GPU Nuclear analysis. TheHanalysis demonstrates that the SMM instrument error is ~ less_than'20*F.at the pressures for which the instrumentation would be used.- Consequently, the analysis shows that the

instrumentation complies
with the conditions imposed by the Appeal' Board in ALAB-729.

Respectfully submitted, hu Thomas A. Baxter Counsel for Licensee . TAB:jah -Enclosures -cc: Septice List l l l' E l l t "a - - - =. - ~..,..-.m.. _,, - - - +.. -,. ..-,-,,~.,----.-,.-..,,,r.,, ---__.4.,.,,,,,v.-,---

INITED STAT 15 OFAERICA NUCIJEAR REGUIATORY CCM(ISSION BEFCEE THE CDMISSICE In the Matter of ) ) MEIBGCLITAN EDISN CCMPANY ) Docket No. 50-289 ) (Restart) -(Three Mile Island Nuclear ) Station, Unit No. 1) ) SERVICE LISP Chairman Nunzio J. Palladino Dr. Reginald L. Gotchy -U.S. Nuclear Regulatory Ccanission Atanic Safety and-Licensing Appeal Washington, D.C. 20555 Board s U.S. Nuclear Regulatory Comnission Ccmnissioner thanas M. Roberts Washington,.D.C. 20555 I U.S. Nuclear Regulatory Ccmnission Washington, D.C. 20555 Ivan W. Smith, Esquire Chaiman, Atanic Safety and Licensing remni mui, n. : James K. Asselstine Board U.S. Nuclear Pegulatory Ccmnission U.S. Nuclear Regulatory Ccenission Washingtoini, D.C. 20555 Washington, D.C. 20555 Ccmnissioner Frederick M. Bernthal Sheldon J. Wolfe, Alternate CPairman U.S. Nuclear Regulatory Ccenission Atanic Safety and Licensing Board Washington, D.C. 20555 . U.S. Nuclear Regulatory Ccanission-I Washington, D.C. '20555-Ccunissioner Lando W. Zech, Jr. U.S. Nuclear Regulatory C ="imaion Mr. Gustave A. Linenberger, Jr. Washington,-D.C. 20555. ' Atanic Safety and Licensing Board U.S. Nuclear Regulatory Ccanission Docketing and Service Section Washington, D.C. 20555 office of the Secretary U.S. Nuclear Regulatory emnianion - RicFard' J. Pawson, Esquire Washington, D.C. 20555 Office of Executive Imgal Director ~ U.S.. Nuclear Regulatory Ccenission. Gary J. Biles, Esquire. Washington, D.C. 20555 Chaiman, Atanic Safety and Licensing Appeal Board John A. Imvin, Esquire . U.S. Nuclear Regulatory c = =4aaion Assistant Counsel Washington, D.C. 20555 Pennsylvania Public Utility Ccanission P. O. Box 3265 D::. John' N.. Buck Harrisburg, PA 17120 Atanic Safety and Licensing Appeal Board Marjorie M. Amadt U.S. Nuclear Regulatory Ccanission R.~ D. 5 Washington, D.C. 20555 Coatesville, PA 19320

'Ihcznas Y. ' Au, Esquire - Steven C. Sholly Office of Chief Counsel'- Union of Concerned Scientists Department of Envirornnental 1346 ConrAx?icut Avenue, N.W., #1101 Resources Washington, D.C. 20036 505 Executive House P.O. Box 2357 ANGRY /'IMI PIRC Harrisburg, PA 17120 1037 Maclay Street Harrisburg, PA 17103 Ms. Imise Bradford 'IMI ALERP Chauncey Kepford 1011 Green Street Judith H. Johnsrud Harrisburg, PA 17102 Environmental Coalition on Nuclear Power 433 Orlando Avenue Ellyn R. Weiss, Esquire State College, PA 16801 Harmon, Weiss & Jordan 2001 S Street, N.W., Suite 430 Washington, D.C. '20009 i - 1 4-l 4 0

I', GPU Nucleer Corporation UC Mr Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057 o191 717 944-7621 TELEX 84 2386 s Writer's Direct Dial Number: 00CKETED cna: August 31, 1984 nj cm tS21-1-84?2221 H Office of Nuclear Reactor Regulation Attn: John F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing U.S. Nuclear Regulatory Comission Washington, D. C. 20555

Dear Sir:

Three Mile Island Nuclear Stetion, Unit 1 (TMI-1) Operating License No. DPR-50 Docket No. 50-289 Subcooling Margin Monitor (SM) During recent discussions with Mr. J. Van Vliet (NRC) on July 11, 1984, GPUN became aware of some apparent inconsistencies identified concerning the 25' F subcooling margin monitor and its associated error. The purpose of this -letter is to clarify our position and to describe recent analyses that we have done to verify the validity of the 25'F SMM action point. By letter dated March 31, 1983, GPUN itotified the NRC of the intent to revise l the reactor coolant pump trip criterion during a small break LOCA from 1600 l psig (ESAS setpoint) to 2',* F subcooling margin (reduced from 50' F). In May 1983 the TMI-1 Restart Atomic Safety and Licensing Appeal Board required NRC i staff to verify SMM instrument error to be less than 20' F (plus a 5'F system configuration error). On September 7,1983 GPUN submitted a detailed calculation indicating a subcooling margin instrument error of + 22.1' F and a l systes configuration error of + 1.3*~F which in total is less than 25' F. Then on June 25, 1984 GPUN provided to the ASLB on Steam Generator repair a l ' report entitled "TMI-1 GORB Subcommittee on Steam Generator Repair Report to the TMI-1 GORB" dated June 13, 1984 for their information. This report contained a recommendation that: (1) An independent verification should be made of the error analysis i-which supports selecting the subcooled margin limit applicable to reactor coolant pump trip followirg a steam generator tube break. The verification should be equivalent to that required by ANSI Standards for de31gn verification. The ar11ysis and the verification should be subject to an interdisciplinary technical review by senior engineers who understand error analpis and primary system response to tube breaks and other loss of coolant accidents. GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation

- 2' - ~ ) ~~Additicnally, this G0RB subcosmittaa report contains sevsral apparent inccasistencies with our earlier submittal. In particular pages 9 and 10 item 2 states: i -(2) For tube rupture transients, the Subcosmittee concurs with the i

desirability of reducing indicated subcooling to 25'F (provided this -value is verified as noted above) or to emergency RCP'NPSH limits (whichever is more limiting). However, the possibility exists that an instrument strin'g which measures subcooling margin-could read erroneously high by more than 25'F.

If that were to happen, it is important that the operator recognize that the instrument is in error, since once actual saturation has been reached the instrument reading will " hang)up" at the value of error (higher than 25'F in this postulated case while the operator continues._to reduce pressure. The instrument will not indicate -lower saturation margin until superheating from uncovered fuel commecces. Since there are several independent instrument strings which can be used to measure subcooling, the Subconnittee does not . consider it credible - that they would all read erroneously high by ^ more than 25'F at-the same. time, provided calibration procedures and equipment preclude a cosmon error in all the instrument strings. Therefore, the operator should be able to avoid reaching saturation conditions without knowing it. However, it is important that all operators understand the symptom (described above) which would be observed in this case and that-they understand which other plant symptoms would indicate saturation had occurred (i.e., changes in pressurizer level, pump current, etc.). The Subcommittee recommends these matters be addressed in the training discussed in Section II (2). This concern on operability, namely instrument failure, is independent of the 1 error analysis. GPUN had previously recognized the need for training in this area and this training has been accomplished. Failures in one of the instruments can be checked against the other redur. dant instrument and through the plant computer. As a result of tiie GORB-recommended independent verification, several factors - have been identified which affect.the calculation provided earlier to you and to the G0R8. 1) The propagation cf the pressure transmitter string error through the function generator was not adequstely modeled. 2) The pressure transmitter manufacturer's equation for error due to high ambient temperature over predicts the error when the measured pressure is less than the upper limit of the calibrated span. l e ,,m..,--.--,__--.-w+,- w-e=w,.-*e ene w=e-*r e~*

w 3-l '3) The manufacturer's publiehtd valu2s for accuracy include linearity, hysteresis, dead band and repeatability. 4) The difference in ranges among the instruments in the string were not accounted for in some instances. 5) The effect of RB pressure tes not considered. 6) _ Recent changes (improvements in the instrument string) had not been included. GPU's assessmeni of the effects of these items on the earlier conclusion is ~ summarized in Enclosure 1. The complete recalculation is provided in i. The re-evaluation includes consideration of abnormal transients-for which the instrument is used. including steam generator tube rupture, main steam line break,-and small break LOCA under worst-case containment conditions. Results available to date support the following conclusions: 1) The instrument.is ' acceptable for tube rupture and any other event which does not result 1n degraded containment conditions. ~ 2) The instrument is acceptable for main steam line break and any other overcooling event inove 200 psig actual RCS pressure under worst case containment etiditions. Even worst case steam line rupture accidents remain above an actual RCS pressure of 400 psig (450'psig indicated with a 50 psi error) since core flood tanks ~ hold up RCS pressure. The plant will be stabilized above this pressure for some time, and the cooldown below 400 psig actual pressure will continue under. more favorable containment conditions. I 3) The instrument is acceptable above 200 psig actual pressure (250 psig indicated with 50 psi error) for small break LOCA. Below this pressure the RC pumps are tripped and the SMM is not used. Based on the above, the SMM is acceptable for all conditions for which it is used.- The means to determir.e subcooling margin for SB LOCA below 250 psig indicated pressure with the RC pumps off is being evaluated to determine if changes are needed. Sincerely. m u -_ s M Huki 1 Director TMI-l HDH:LWH: dis:0079A cc:' R. Conte J. Van Vliet i ~ * - - -

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i Instrumentation Error Basis Change The function generator converts the pressure signal to a saturation temperature signal. It is essentially an 8-stage amplifier where each stage covers a segment of the total presswe range. A particular stage has a gain which approximates the slope of the Saturation Temperature / Pressure curve for its segment of the pressure range. Therefore, for a given pressure, the pressure errors are amplified by a factor equal to the dT/dP cf the applicable pressure range. The values of dT/dP vary from 0.064 in the 1900-2500 psig. range to 0.496 in the 100-200 psig range, and 1.264 in the 0-100 psig range. The omission of this factor was equivalent to using dT/dP=1 throughout the 0-2500 psig range. This resulted in calculated error values which were non-conservative by a factor of 1.264 in the 0-100 psig range. However, the values in the 100-2500 psig range were conservative by a factor ranging from 2 to 15.6. Tne pressure transmitter mareufacturer's published equations for error due to high ambient teroperature are of the form: Error =+(axURL+bxSpan) Where: a and b are constants URL = Upper Range Limit The highest value that the transmitter can be adjusted to measure. Span = ~The algebraic difference between the highest and lowest values that the transmitter is calibrated to measure. The manufacturer confirmed the following:

1) The equation is for the error when actual pressure is at'the upper limit of the calibrated span.

It overpredicts the error at lower measured pressures. P.) To calculate the error at measured pressures below the upper limit of the calibrated span, span is defined as follows: Span = The algebraic difference between the measured pressure and the lowest value that the transmitter is calibrated to measure. In the case where the lower limit is O psig, Span = Measured Pressure In some instances, error values for linearity, repeatability, and dead band were included in the original calculation in addition to values for accuracy. Since the manufacturer's published accuracy value already includes these errors, they were accounted for twice. 200 sto ott afrcrti nde Er:CI re 'TD EO

The range of the final modules of the instrument string is -100F to 400F Subcooling. The calculated loop error is expressed in percent of this range. However, there are modules in the string with different ranges. Therefore, the percent error for these modules must be multiplied by the ratio of.the module range to the final module range. This error was non-conservative by a factor of 5 for the pressure transmitter and the I/E converter. The calculation has been revised to account for these factors. l ) E00. ST0 *0tl &J3 Int n#3 tr:CT r9/Ti 80

v-TMI-1 SATURATION MARGIN M0 NIT 0R LOOP ERROR ANALSIS l l { ( tOO ST0*Ct1

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Rnv. 3 GPU Nuclear cAi.e.no.c.no.1.-66se.53so-oos SHEET NO.... h.... OF.. 2.S.... eusacT........T.M.I.... AT.U. ATI oy..nn ns.I.n..Mo.y.I.T.@......................... oAre...... : ik.fi s R ..N9-84 cow. swoATs. .M'W .................'..,,00PERRoRANALJ,SI5 cHK o. swoATs OBJECTIVE Determine the expected errors for the alarm, indicator, and calibration instrument loops during normal operations and also for saali break LOCA, and steam line break conditions. This calculation is based on the instrument loop defined by the Reference 1 modification and includes the - 2 verification coments (Reference 2) to the original issue. REFERENCES 1. GPUN 8/A 123072 - Modification of TSAT to replace non-1E temperature inputs with 1E temp. inputs. 2. GPUN verification of Calculation C-1101-665-5350-005 by J. P. Moore dated 7/10/84. 3. USNkC Memo - Peter S. Kapotow 8/23/82 page A6 NUREG-0737 analytical solutions to two problems pertinent to Items II.F.1.4, 5, 6, a statistical treatment of deadband and hysterssis errors. 4. Control valve handbook, Fisher Controls, Properties of Saturated Steam. 5. GPUN memo EP&I/84/1525-047H, Rosemount 1153 accuracy. ~ GPUN Calculation C-1101-665-5300-006,' "TMI-1 Saturation Margin Monitor 6. Error Analysis - Rosemount Pressure Transmitter". ASSUWTIONS 1. Unless otherwise stated, Vendor published accuracy data includes the combined effects of linearity, hysteresis, deadband and repeatability as stated in Standard ISA-551.1,1959. 2. Unless otherwise stated Vendor published accuracy data represents 3 Sigma (3t) values, and can be converted to 24 values by multiplying by 2/3 as stated in Reference 3. 3. Accident conditions are: 7 Steam line break 38 psig, pray),1005 RH, 5x10 R, 2450F.(245'F{ SBLOCA 30 PSIG (no RB s 3900F. 4. Signal conditioning electronics and display devices are located within controlled environments within the control building, i ^ " " * " "'" 0451M E00 STO'Otl dO3 ral na9 5; ::T W TE 60

Rsv.I GPU Nuclear c,i.e. no g,,1.1,9,1,,4,q s..p g o - o o s si cst no... 2.. or... 2.8.... susaseT........F.I..... 5A.TURA,U,0N,,t@,RE I N,,tt0N,I T 08,,,,,,,,,,,,,,,,,,,,,, oars,,,,,.,,',.,,,s,...$:,1,ty comp. BY/DATE.... i W P ERROR M YS H cHK'D. SY/DATE.. DISCUSSION The saturation margin monitor measures RC temperature and pressure. The pressure signal is used to electronically compute the fluid saturation temperature. This computed saturation temperature is compared to the actual measured temperature and a margin to saturation is detemined and displayed. An alarm is provided. There are two channels. The RTD's and RC pressure transmitters are inside containment and exposed to the SBLOCA/SLB environment. The system is used under normal, SBLOCA/SLB,.nd GTSG tube rupture conditions only. Error calculations are organized in four parts. 13 a) Part 1 derives the random error for non-accident and S3 LOC A/SBL [3 conditions in the alarm instrument loop. The Rosemount RC pressure transmitter latest test results (1153 series B/D) is based on LOCA conditjons with a maximum temperature of 420* and radiation exposure of 5 x 10/ RAD. This is too conservative compared 7 with $8LOCA conditions of 24W and 5 x 10 R. Therefore, original test data was reviewed to calculate the standard deviation of temperature effect error data. It was determined that a conservative estimate of the SBLOCA/SLB 2(temperature error could be obtained by dividing the LOCA W temperature error equation provided by Rosemount by three (Ref. 6). Analysis of the SBLOCA indicates that elevated LOCA temperature and radiation will not ociur concurrently. Therefore, the worst of these two error values (temperature) was used alone in the " Accident" er ror calculations. b) Part 2 derives the random error for non-accident and SBLOCA/SBL 15 conditions, in the Indicator instrument loop. The same pressure transmitter temperature error values described in paragraph a) above are used, c) Part 3 derives the random error for calibration of the alarm instrument loop. d) Part 4 derives the systematic worst case errors due to the (! characterizer RC pressure to saturation temperature conversion error and containment pressure errors during SBLOCA and SLB conditions. In addition to the loop uncertainty errors that are random in nature, there exists systematic errors that are fixed quantities under certain conditions. ^ " ' " ' ' ' ' ' " 045m 900 ST0 *m dO3TO 4 nds 9t : t t-e 12 80

R,v. 2 cAtc. no..c..4&. 6 A s."5 Nuclear swaET NO.. 3,,, , og,,,3,g,,,, I s " suencT......... IMI... SATURAT ID K.MA RGIN..M0tt1 TOR.............. oats.. A/16/SA....... cow. swoATE...()......... l - (.................. l.9.CP,, ERR,0R,,AN A,1:Y S I,S........................................ CHK'O. BY/DAT l The systematic errors cor.sist of: a) Characterizer Curve Error, b) Containment Pressure Error s Characterizer curve error is.a function of reactor coolant pressure conversion to saturation temperature. For each of eight segments of RC pressure, the error varies from slightly positive at the segment end values to negative errors in between. For this application, this would be the maximum negative error (conversion to a saturation temperature value that is lower than the actual saturation value). Therefore, the maximum negative error for each RC pressure segment is presented as a systematic error and the random error should be added to it where applicable. Containment pressure error is a function of ambient pressure in the containment building where the low side of the RC pressure transmitter l Vents. During SBLOCA and steam line break accident conditions when the containment pressure is elevated the RC pressure transmitter will provide l a pressure signal that will be decreased by an amount equal to the l increase of containment pressure over atmospheric. The increase in containment pressure during SELOCA is 30 psig, and for steam line break is i a maximum of 38 psig approximately 80 seconds after the break. The RC pressure is converted.to its equivalent saturation temperature and the erroneous decreased pressure transmitter si nal would result in a lower value of saturation temperature than actual y exists for the true RC pressure. For this application, this would be the maximum negative error value (0F) for each of the eight segments. f-Therefore, the containment pressure error is presented as a systematic error during accident conditions and the random error should be added to it. CONCLUSIONS The calculated errors are the difference between the indicated margin value and the true margin value. A negative error is conservative and denotes that the indicated value is less than the true value. When the error is algebraically subtracted from the indicated value it gives the true value. For example, if the indicated margin and error is 50'F (-10+15'F), the true margin is between 60*F and 35'F. The worst case loop systematic error for eight segments of RC pressure is presented in Table 1 below. a) For non-accident conditions, systematic error ' equals characterizar curve error. j L i b) For SBLOCA, systematic error equals characterizer curve error ] plus containment pressure error at 30 psig. I l i c) For steam line break, systematic error equals characterizer curve error plus containment pressure error at 38 psig. ,ooo oo, n.,,. l m-cm m m nyn w wr m,7 m - - \\

car.c.wO..c.u0.1.-4AE.b -oo5 E N~: clear SHEET NO.... $.... OF.... 2M.. h,3,$;M suaaacv.........TMI,,,SA,Tp,RA,J,,gN,M,h,RG,I,N,, MON,IT,gR,,,,,,,,,,,,,,,, ,,5 I ,,,,,, g37,,,,,,,,.,,,,,,, " ' " ^ ' " " t L008 ERROR ANALYSIS csico. emira.".utt.t.".."..".. __5T51EMATIC ERROR ('P ) RC Pressure ACCIDENT (PSIG) NON-ACCIDENT CHAR. CURVE ERROR SBLOC SLB I -6z 3 -7z.4 0-100 -z4.4 100-200 -2.7 -17.6 -21.5 200-400 -3.8 -12.8 -15.2 400-600 4.6 - 7.7 - 9.4 600-900 -1.5 - 6.1 - 7.3 900-1300 -1.1 - 4.5 - 5.4 1300-1900 - 1.3 - 3.9 - 4.5 1900-2500 -0.8 - 2.7 - 3.2 TAR.E 1 SYSTEleTIC ERROR Table 2 contains the random loop error uncertainty at a 2( 1evel for eight segments of RC pressure from 0-2500 psig for both non-accident and worst case temperature and pressure SBLOCA/SLB conditions. LOOP UNCERTAINTY - RANDOM NON ACCIDENT ACCIDENT SBLOCA/SLD l RC PRESSURE (PSIG) ALARM INCICATOR . CALIBRATION ALARM INDICATOR ('F) (*P ) (*F) (*F) ('F) 0-100 +23.0 +22.7 +15.6 +60.3 +60.2 100-200 T11.5 711.0 7 9.4 725.4 T25.2 t 200-400 7 9.0 7 8.4 78.1 T17.0 716.6 400-600 T 8.0 7 7.2 T 7.6 712.8 T12.4 600-900 T 7.6 7 6.7 7 7.3 T11.1 710.5 900-1300 7 7.2 7 6.4 7 7.1 7 9.7 7 9.1 1300-1900 77.1 76.1 7 7.0 T 8.8 T 8.1 1900-2500 T 6.9 7 6.0 I6.9 I8.7 T 8.0 I TAR.E 2 RAND 0M LOCP ERROR 4000 ooie i s... 0451M EW STO M M m Od9 eg.:;7 pg,TE EO a

GPU Nucleaf CALC. NO...C..110.1.-N3 5 0 -00 SHEET NO....$..... OF....... 2 DM Y'YY sumanci.........i.g..SATURAT10R MARGIN HOMTOR cow. swcars.... ..................LQQP..EMQB. AMLYSI S........................................... cm o. swom Table 3 presents the total alarm loop error for eight ranges of RC pressure. During normal operating conditions, the negative error is the sum of the ~ negative random error and ther worst negative characterizer curve error, and the total petitive error is the sum of the positive random error and the best (zoro) charac!*rizer curve error. For the accident conditions, the total negative error is the sum of the negative random error and the applicable accident systematic error, and the total positive error is the positive random error alone RC PRESSURE TOTAL ALARM LOOP UNCERTAINTY Normal $8LOCA SLB (OF) ('F) (CF) 0-100 -47.4 +23.0 -122.6 +60.3 -189.7 +60.3 100-200 -14.2 +11.5 -43.0 + 25.4 -69.8 + 25.4 200-400 -12.8 + 9.0 -2 9.8 + 17.0 -46.1 + 17.0 400-600 - 9.6 + 8.0 -20.5 + 12.8 -31.5 + 12.8 600-900 - 9.1 + 7.6 -17.2 + 11.1 -25.5 + 11.1 900-1300 - 8.3 + 7.2 -14.2 + 9.7 -20.4 + 9.7 1300-1900 - 8.2 + 7.1 -12.7 + 8.8 -17.3 + 8.8 j .T900-2500 -7.7 + 6.9 -11.4 + 8.7 -15.7 +.8.7 TAR.E 3 TOTAL ALARM LOOP ERROR l t A000 0016 e s. e 0451H 600 ST0 *0N 603 Crei nd9 6t :2T tS TE 50 ~ _ __

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