ML18026A848

Bottled-up Operation of Bwr

ML18026A848
Person / Time
Site:	Browns Ferry
Issue date:	11/30/1974
From:	Carroll D, Eckert E, Holland L GENERAL ELECTRIC CO.
To:
Shared Package
ML18026A847	List: ML18026A846 ML18026A848 ML18026A849 ML18026A850 ML20079N595
References
74NEO69, NEDO-20697, NUDOCS 8401300285
Download: ML18026A848 (62)

Text

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NEDO-20697 74NEO69 Class I November 1974 BOTTLED-UP OPERATtON OF A BWR D. G. Carroll E. C. Eckert, Manager

~tern Oynamics and Control L K. Holland, Manager System Control and

.Transient Analysis N

WA R R A TOR SYST MS 0 PARTM NT'u N RALcL G RIG COMPANY SAN JOSE, CALIFORNIA95125 GENERAL ';g ELECTRIC 8401300285 840i23 PDR ADOCK 05000296 1'

PDR

DISCLAIi~IER OF RESPONSIBILITY 7M report was prepared as an account of research and development sees%

performed by General Electric Comoany. lt is being made available by General Electric Comoany without consideration in the intetest of promoting the spread of technical knowledge.

Neither Genera/ Electric Company nor theindividual author:

A. Nakes any warranty or representaaon, expressed or implied, with ttsspa:t to the accuracy.

comoleteness, or usefulness of the information contained in this r;oort, or that the use of any information disclosed in this report may not infringe privately ownedfightsl or

8. Assumes any responsibili ty for liabilityor damage which may result from the use ofanyinformation disclosedin this report.

~ 1 NED0.20697 ABSTRACT TABLE OF CONTENTS C

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Page

.vll INTRODUCTION....,...

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Hit BOTTLED-UP OPERATION SPECIAL TEST......,..

CONCLUSIONS....-.. ~

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APPENDIX BROWNS FERRY UNIT 1 BOTTLED-UP STABILITYTEST PROCEDURE

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ol NEDO 20697

'IST OF ILLUSTRATIONS Page BoNedoUp Pressure Maneuver Using Control Rods.............................,...,...

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IRM Traces ot a BottledoUp Control Rod Maneuver (Insert)....................,..

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IRM Traces of a BoNed.Up Control Rod Maneuver (Withdraw).

Parameter Behavior Oudng Heatup Ramp.

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Co trol Rod Withdrawal..

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Control Rod 34-27 Scrammed....

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One Bypass Valve, Fast Open-Fast Close..

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12 11 IRM Respon "to.-"- re Oisturbances..............................,..,...,......

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NEDO.20697 ABSTRACT "8ottledwp" operation of a 8NR refers to that condition where the main steam isolation valves (MSIVs) are closed. thus prevenong any significant steam liow.

Histoncally, there has been a reactor scram conditionif vessel pressure nses aoove 500 psig withthe MSIVsclosed and withthe mode swnchin "stanup." This document

. describes the results ol a soecral test conceived and performed on a typical BIVR/4 design to determine the necessity ofthis plant scram function. Itis concluded that the pressure scram function can oe raised. so that bottled-up hot standby operationis permitted up to!ullpressure and temperature conditions.

~ 4 NEDO-20697 1.

INTRODUCTION Bottfed-vp operation became an identified topic at an early dual-cycle reactor startub. During hoatvp, with the main eteamlsalation valves (MSlvsi closed and oressure at about 600 psi, the operator experienced aifficvltvin controlling power.

The phenomenon was observed as follows: After natctting a control rad out, pressure would begin to increase, as wouid power. There appeared to be no teveiingwut tendency, so tho rad (or rods) was partially inserted to stop the rise. Pressure and power would then level off and start to tall, as if overcorrected. Rods were then partially withdrawn to stop the fall of pressure and power. Again. as if overcorrectod. pressure and power would rise. showing no sign of leveling off. This contin'ueduntilit was suggestio that bypassing steam to gain pressure control (and thus hold void reactivity constant) might trtablllze the plant. This method proved to be effective, pressure control was subsequently recommended for use dunng otartup. In addition, scram logic was added to prohibit operation above 600 psi with tho MSlVs closed.

Experience on later plant startups indicates that the early experience may not be inherent to the BWR design. In tact, it is reported that heatup is commoniy accompiisnea with tho MSIVs open, but with no flowthrough tho turbine bypass valves.

Inthis case, the pressure regulator pressvre setpoint is kept above the operating pressure. Thus. steamilow is limited to seai steam, steam to the steam let air electors pius losses. This is very close to th'e bomea-up condition (Mslvs closed), and leads vs to question the possibility of stable operation with the MSIVs closed.

2.

BOTTLED-VP OPERATION SPECIAL TEST t

To demonstrate whatever capability a contemporary BWR might have to operate in the bottled-vp condi:ion. a special test was added to the startup test program at Browns Ferry Unit t. a plant judged to be a typical BWR/4 design. Acopy of the procedure used at BF-t may be found in Appendix A. Data from the test were taken in two basic blocks: reactivity perturbations and pressure perturbations.

F)guros 1 through 8 show data taken by the Startup Test Design and Analysis Unit during the reactivity perturbation tests. These traces show no signs of possible instability or generally unpreaictable behavior. The maneuvers demonstrated ln the figures were performed with MSIVs closed, reactor power at about 0.3'.o, damO Pressure at about 920 psig, and recirculation pumps at minimum speed.

Figvro 1 shows reactor wide range pressure as tho rods were inserted to drop the pressure to approximately 650 psig, then withdrawn to increase pressure again to approximately 920 psig in about 20 minutes.

Figures 2 and 3 are IRMtraces'which show onlyrelative power changes. Sudden jumps inthe traces an tho order of an Inch are due to changing the instrumont range to keep them on scale.

Flguro 4 was taken during the heatup ramp. and Figures 5 through 8 were taken at 920 psig while Control Rod 34-27 was being inserted, withdrawn and scrammed. Alltraces are broad due to noise, wnich is commoii. Tho APRM and LPRM '

flees show an amplitude modulated charactensoc which is also due to noise.

The pressure perturbation tests were run with the MSIVs oben to allow the use of the bypass valves to disturb pressure. The auxiliary boiler was usea to suocly seal steam and steam to the steam je! air ejectors plus any other losses, In this manner, ves'sel steam flowwas keat at near zero fabout 0.254'). Thus. the only effective difference between MSIVooen and MSIVclased was tt:e added steam line valume between the MSIYs and the bypass valves. The effect of this extra vofume on low power stabiiity is judged to be negligible. other reactor conditions were the same as for the reactivity pertulbadons. The pressure penurbation of onmarv interest is the first oro lFigure 9), where one bypass valve is ooened quickly(about0.1 seel,heldforasnontimefabout15seciandctosedraoialy!aboutO.t sect. The timeofpnmaryimoartance fa tho question addressed by the test is that followingreciosure of the bypass valves ttho bottled-uo conaitian). The traces shaw that, followingthe disturbance caused by opening the bypass valves, all parameters return to steady. state values and are welt-behaved.

es NEDO.20697 Several events occur during the time that the bypass valve is open in tho fast open. fast c,'ose event. As soon as the valve is opened, turbine inlet oressure gces tnrauqn a sma! I osciilation of about 5 osi in macnituce and 1.6 Hza hint of possible steam line resonance. Atter aoout 0.4 seconds detay (propagaoan time forthe pressure wave in the steam line). the dome pressure begins to drop off. which causes a large inventory density chango duo to the near-saturated canaitian af the vessel water at the operaeno point; this results in the!evel sweil shown. About 3 seconds after come oressure begins to tall lit has droppedabout16 osg, coro flowbegins to tall off, suggesting tho start of boiling in the channels. This is followed by an osctttatian of about 0.36 Hz in pressure and core flowwhich suggests a "chugging 'tfect, or thermal hydraulic oscillation.

The two cycles before the bypass valves close decay by a factor ot about 0.7, and are not considered a detnment to stable Control of the plant at this power.

4 Figure 10 is a trace showing the results ofslowiyopening and closing two bypass valves. Once again, pressure drops and level swells as the valves are opened, and return to normal when the valves are closed.

Rgure 11 ls an IRM trace showing response to the two bypass valve transients.

Figure 12 is a process chart showing narrow range water level response to the transients.

8.

CONCLUSIONS The data taken at the Browns Ferry 1 site indicate that BF-1 can be controlled adequately inthe bottled-uo condition at pressures well in excess of 600 osig. Thus. there is no reason to assume an unacceotaole ooerating region and scram the reactor when vessel pressure exceeds 600 osig with the MSIVs closed. !n tact. on the Browns Ferry 1 plant, the scram set point maybe set to coincide wuh the Technical Specificationhigh vessel pressure scram set point with no apparent BWR tttabitity problem.

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Browns Ferry is a typical BWR/4 design; therefore. the result of the test at BF-1 may be extended to cover all BWR/4 product line projects.

Atest procedure similar to the one foundin the Appendix willbe performed at each future "firstwf-a-product-tine" plant

'urfng startup testing to verify continued capatxtity for bottled-up operation. Because of its desian.uniaue nature. each pre-BWR/4 product must be considered on an individual basis to determine bottled-uo operating capability by a similar test procedure. Thus, no generic BWR/1, 2 or 3 bottled.up operation permission is, or will be. available.

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10 20 30 650 psi 60 SSURE OR PRE REACT 920 psi 6AM 8AM 7AM 8AM Figure 1.

Bottfed-Up Prekkure Maneuver Uklng Controt RoCk

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Figure 2.

lRM Traces ol a Bottled.Up Control Rod Maneuver (insert)

O IBMCHANNELS oIll ERANGING INSTAUMENT RmOO O0 O0 Figure 3.

IRM Tracea ol e Bottled-Up Control Rod Maneuver (Withdraw)

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VIATER LEVEL N. II. (6 in,/in) r TW'I-T T.t-r-t-.~

PRFSSUR E N. R. )40 psi%n.)

mO0 II CAT FLIJX

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Figure.4.

Parameter Behavior Dunng Heatup Ramp

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NAHIIOV4HANDS HEACTOR PAESSUHE I40 pat fl NAHHOIVHANGL'IVA'IEA LEVEL IS In,tel,!-

WIDE RANGE AFACIOH PHESSLIHE j

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LPAMI0.5%/in.l REACTOR PRESSURE {40 psi/in.l

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Control Rod 34-27 Scrammed

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ee N GING RERA PENT INSTRUI I OPV OPEN REHANGING UMENT INSTR Figure 1f.

lRM Response to Pressure 0.'strubances

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Weter Level Response to Pressure Disturbances

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NE DO-20697 I

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APPENDIX A BROWNS FERRY UNIT 1 BOTTLED-UP STABILITYTEST PROCEDURE

NEDO-20697 Plant:

Browns Ferry. Unit 1 Test

Title:

Date:

Bottled-Up Stability (Special Test)

December 12, 1973 PREPARED BY:

Startup Test Design and Analysis Unit Startup and Training Subsection Atomic Power Equipment Department San Jose, California A-2

NE DO 20697 PURPOSE The purpose of this test is to demonstrate that the reactor can safely withstand pressure and reactivity pe'rturbations at fated pressure while in a bottled-up condition without pressure regulation.

DESCRIPTION Standard operating procedure at this plant permits operating up to rated pressure withthe main steamisolation valves (MSIVs) closed. Heatup in this concition and transfer to and from this condition following turbine trips has been satisfactorily accomplished on seuerat occasions. No incipient instabilities were quantativeiy observeo at any time; however, In an earlier plant IKRB),there were some inaications of possibie instaoikty wnenbottteo-up aoove 600 psig.

Design Engineering at San Jose General Electric has therefore requested tnat a formai test be perlormea to venfy bottled-up stability at rated pressure.

The test willbe in two parts. The firstwillinvolve making a reactivity perturbation, and the second willbe a pressure perturbation. Both willbe initiated from ooreied up not stanobv conditions, with ihe MSIVs coen and the main turbine stop valves (MTsvs) closed. The feeowa! er turoines willbe snut off. ana the main turoine oiand seal ana the steam let air ejector (sJAE) willbe operating from tne auxuiarv ooiler. The pressure reaulator willbe set aoproximately 20 Dsl above the actual reactor pressure. This willproduce a bonled-uo condition tnat closelv simulates having the MSIVs dosed, but willpermit lowenng of the pressure setpoint to open bypass valves it instability does occur.

Heatup data willbe collected during normal ooeration with MSIVs closed at close to rated pressure. Normal heatup rates and rod insertions and withdrawals are sufficient for reactivity insertiofts.

3.

CRITERIA 3.1

. Level1 The test willbe terminated ifvessel pressure is unstable or if the limitcycje exceeds = 20 psi. or if limitcycles with periods less than 10 seconds exceed = 10 psi. The test will be terminated if the flux osallation is so large that a OuxdnNated scram is likely. In this case. the Technical Specification willbe changed to forbid bonled.up operation above 600 psig, 34 Level 2 Limitcycles greater than = 10 psi will reauire that the data be analyzed by Design Engineering, and consent be received prior to further bottled-up operation above 600 psig.

INSTALLATIONINSTRUCT(ONS None 5.

INITIALCONDITIONS 5,1 52 The reactor pressure will be at 920 5 psig. AII normal plant surveillance procedures shall be satisfied.

The control rod drive and cleanup systems will be operating to the reactor vessel.

I Tfte reactor feed pumps and their turbines will be off and isolated from the reactor vessel.

5A 5.5 The main turbine will be on turning gear with the gland seal and the (SJAE) operating from an auxiliary boiler.

The MSIVs will be open, and the MTSVs will be closed.

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NE00.20697

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p ssurevegulator setooint willbe set 20 = 5 psi above tho actual reactor pressure. Th'llb 5.6 The re re.

is wi e set by reducing

. setpoint until incipient bypass acean is observed and coming up 20 psi from this point.

5.7 The transient recorder will be ready for operation with the following signals connected:

narrow-range reactor pressure, wide.range reactor pressure, narrow-range reactor water level. bypass valve No. 1 position, ApRM,LpRM and core flow.

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5.8 Recirculation M/G sets will be at minimum speed.

8.

PROCEDURE 8.1 Reactivity Perturbation 6.1.1 Withthereactoro eraon stabl tt p

ya hoinitfalconditionssetfonhinSectian5.seioctafuitywithdrawncontrotrodintho

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that ra 'd in central region of the reactor. Take aooroonate data. such as TIP traco. OD-7 d ODN

. an computer printouts. to venfy rapi insertion of this rod will not result iii lne compromise of any fuel warranty limits.

8.14 Take base steady. state data and start the transient recorder.

8.14 CantinuouslyinsertthecontrotrodfromPosition48toPosition00.it' 'l is esira etoobtaindataonanyoscillationsthat

~ might occur. therefore. itany occur and they are not too large. record them forseveral minutes. ar until Level 1 criteria are approached. To end any such osciliations. reduce the oressure reaulat r

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'I th o se ooin unti ebypassvaiveopens.lf cntefla are reached, terminate testing and stop the transient recorder.

t c teria are not reachedin Step 6.1.3. keep the transient recorder running and continuously withdraw the control rod 8.1.4 ll ri tO Position 48. IVhen the reactor is aoain stable. and with the transient record ien recor er running, scram the control rod to Position 00. Continue as in Step 6.1.3.

6.1.5 Withdraw the control rod to its futlwut position and stop the transient recorder. This completes the reactivity before proceeding.

perturbation test. Ifeither Level 1 or Level 2 criteria are reached. concurre co l D rrencoo esign ngineeringistobo obtained l

82 Pressure Perturbation 82.1 After satisfactory completion of Step 6.1. and with the reactor ooerati tabl h

era 'ng s y at t e initial conditions sot forth in Section 5, take base data and start the transient recorder.

644 'apidly open fully.and then dose. one main steam bypass valve No. 1. Ob asi St 6.1..

as n tep 6.1.3.

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serve and accommodate any osciliations 8~

If cnteria are not reached in Slep 6.2.2, repeat the tost for simultaneous full opening of two bypass valves.

82.4 The above completes the pressure perturbation test.

63 Reactivity Perturbation viith MSIV Closed (Optional) 62.1 If sufficient reactivity perturbation data have not been obtained du'l nng norm startup proceed to Step 6 3.2 692 With the reactor at about 600 osig and closed MSIVs. increase power to heatup, maintainin a hi h rate of heatup tless than 100'Flhr).

wer o eatup, maintaining a high, but reasonablo, Record rod pattern and the followingdata at 30-minute intervals: vessel prossure v

I temperature.

ossure, vessel level, and recirculation loop

NE00-20697 8.3A Continue the heatup until rated pressure is reached.

8.3.5 As before, ifoscillations are observed. start the transient recorder. Itis desirable to obtain data while the reactor state Is unchanged; however, if osallations become large, rapiaty insert control rods until the reactor is subcntical, and terminate the test.

82.6 tf no instabilities are observed during this heatup, repeat Steps 6.1.1 through 6.1.5.

7, ANALYSIS Ifno oscillations are observed. orifoscllations do not approach the criteria, the system willbe considered stable under.

bottled-up hot stancby conoitions.

If measuraole osciilations are ooserved which approacn the critena, Design Engineering is to eva(uate them and recommena suosequent action. Design Engineenng is to bo supplied with ail data, Irrespective of results ootained.

8.

SUPPORTING INFORMATlON 8.1 The steam volume of the reactor dome and steam lines out to the MSIVs is aoproximately 11,740 ft'. The corresponding volume of the reactor dome and steam lines out to the MTSVs is approximately 14,540 ft'. This difference should not make being bottled-up aganst the MTSVs significantiy different from being bottled.up against the MSIVs, in terms of steam pressure transients.

82 One bypass valve full open passes about 400.000 lb/hr of steam. Wis compares with 800.000 ib/hr for one relief t

valve. Thusopening two bypass valves will approximate the transient associated with opening one relief valve.

8.3 In selecting the control rod to be inserted. the main concern would bo if an adjacent rod were at a high flux peak location. Such a posi~Jon would be Position 08, which also corresponds to the end of a gadolinia zone.

A4/A4

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~I NUCLEAR KNERQY OIVI~'GH ~ GENERAL KLECTlIC COMPANY SAN JOSE. CJL(FCANIA Q5125 GEHERAL -,~ ELF CTA It:

TECHNICAL INFORMATION SERIES TITLK PacK AUTHOR D. G. Carroll SUIUK.CT BWR Operation NO.

74NED69 DATE November 1974 TITLE

~

Bottled Up Operation of a BWR

",EPRODUCI8LE COPY FILED AT TECH~.C-'L PUBLlCATIORS, Rg,UO..A:I AROSE. CAL FCr~IA SUL'QRY GE CLASS 1

GOVT. CLASS IIO. PAGES "BOttfed-up" Operanen Of a BWR raferS tO that COnditiOn WherO the main steam isolation valves IMSIVsl aro closed. thus preventing any significant steam flow. Histoncally. thoro has boon a reactor scram condition if vessel pressure dses above 600 osig with tho MSlvs closod and wsh the mode switch in "startup." This document descnOes tho results ol a special test conceived and performed on a typical BtvR/4 design to determine the neces-sity of this plant scram function. It is concluded that the oreSsuro scram function can bo raised. so that boalod-uo hot standby operation is permitted up to full pressure and tomperaturo oonoibons.

By ctittlng oot this rectangle and folding on the center line, the above information can be fitted into a standard card file.

NEDO-20697 lllFORMATIOHPREPARED FOR General Electric Company TESTS ~DE 8Y D. G. Carroll COUNTERSIGIIEO L. K. Holland SECTION SCROTA 8uf( OfffQAND ROOM IIQ 1850 So. 10th Street LOCATION San Jose 'Ca.

Analog Trip System Information The instrumentation which will be installed as part of the analog trip system at Browns Ferry is the same or better than the instrumentation which is described. in General Electric Company NEDO-21617.

The following information demonstrates applicability of this topical report to the system proposed for Browns Ferry.

The analog tr ip system for unit 1 was approved by amendment No.

93 dated December 16,

1983, and all information concerning the system for unit 1 is applicable to unit 3.

0

SPECIFIC Ih NT LOOPS E ui ment Bei Installed Vendor Model No.

Variable Name Bein Deleted S stem Involved Transmitter, Model No.

Trip Unit Model No.

TVA Instrument Loop No, and Division Reactor low water level Barton Model No. 278 Reactor Protection Rosemount 1153 Rosemount 710 DU L-3-203A (IA)

L-3-203C (IIA)

L-3-203B (IB)

L-3-203D (IIB)

Reactor high pressure Barksda le Mcdel No. B2T-A12SS R actor Protection Rosemount 1153 Rosemount 710 DU P-3-22AA (IA)

P-3-22C (IIA)

P-3-22BB (IB)

P-3-22D (IIB)

Reactor low low water level Maih steam line low pressure Yarway Model No. 4418C Primary Containment isolation and recirc Rose cunt pump trip 1153 Magn steam line Barton high flow Model No. 278 Primary Containment Rosemount isolation 1153 Barksdale Primary Containment Rosemount Model No. B2T-A12SS isolation 1153 h

Rosemount 710 DU Rosemount 710 DU P-1-72 (IA)

P-1-82 P-1-76 (IB)

P-1-86 dP-1-13A,

-25A> -36A, dP-1-13B>

-25B, -36B>

dp-1-13C>

-25C> -36C) dP-1-13D,

-25D, '6D>

(IIA)

(IIB)

-50A (IA)

-50B (IB) v.:~~.'-i;-.

-50C (IIA) 50D (IIB)

Rose"cunt L-3-56A (IA)

L-3-56C (IIA) 710 DU L-3-56B (IA)

L-3-56D (IIB)

Primary Containment high pressure Static-o-ring Model No.

12N-AA4-X2PP Reactor protection and primary contain-Rosemount ment isolation 1153 Rosemount P-64-56A (IA)

P-64-56C (IIA) 710 DU P-64-56B'(IB)

P-64-56D (IIB)

Turbine first stage pres.

perhissive Reactor high pressure Reactor protection Barksdale and recirc.

pump Model No. B2T-A12SS trip Static-o-ring Model Recirc.

pump No. 9N-AA4-X911 trip Rosemount 1153 Rosemount 1153 Rosemount P-1-91B (IA)

P-1-81B (IIA) 710 DU P-1-91A (IB)

P-1-81A (IIB)

Rosemount P-3-204A (IA)

P-3-204C (IIA) 710 DU P-3-204B (IB)

P-3-204D (IIB)

Variable Name Vendor Model No.

Bei Deleted S stem Involved Transmitter Model No.

Trip Unit Model No.

ontinued)

E ui ment Bein Installed TVA Instrument Loop No.

and Division Reactor low water level Reactor low water level Reactor low water level Yarway 4418 Yarway 4418 Ear way 4418 Core spray RHR (LPCI)

Containment spray (RHR)

Rosemount 1153 Rosemount 1153 Rosemount 1153 Rosemount 710 DU Rosemount 710 DU Rosemount 710 DU L-3-58A(Z)

L-3-58B(I)

L-3-184(I)

L-3-52(I)

L-3-58C(II)

L-3-58D(IZ)

L-3-185(ZI)

L-3-62(IZ)

Reactor pressure Barton 288/

Recirc, core spray, Barksdale B2T-M12SS RHR (LPCZ)

Rosemount-1153 Rosemount 710 DU P-3-74A(I)

P-68-95(I)

P-3-74B(II)

P-68-96(ZI)

HPCI Steam-line HZ Flow RCZC Steam-line HI Flow Primary Containment pressure Barton 288 Barton 288 Static-o-ring Model No.

12N-AA4 HPCZ RCIC Containment spray (RHR)

Rosemount 1153 Rosemount 1153 Rosemount 1153 Rosemount 710 DU Rosemount 710 DU Rosemount 710 DU dp-73-1A(I) dp-73 IB(II)

P-64-58E(I)

P-64-580(Z)

P-64-58F(II)

P-64-58H(II) dP-71-1A(I) dp-71-19(II)

Primary Ccntainment Pr ssure Static-o-ring Model No.

12N-AA4 Core spray RHR (LPCI) HPCI Rosemount 1153 Rosemount 710 DU P-64-58B(I)

P-64-58D(I)

P-64-58A(IZ)

P-64-58C(IZ)

Primary Containment Pressure Static-o-ring Model No.

12N-AA4 Rosemount 1153 Rosemount 710 DU P-64-57B(Z)

P-64-57A(ZI)

P-64-57D(I)

P-64-57C(ZI)

TEB:VD 1/03/84 B4262D.VD

1 ll!P IIIIlT CA!I1 I:I'.7

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./I' dnDRIJ(r/NcirRII

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ENVIRONMENTAL INTERFACE TEMPERATURE AND HUMIDITY Transmitter Normal Normal Accident Accident Qualified Qualified-No.

Tem.( 1)

Humidit (1 Tem.

1)

Humidit 1

Tem 1

Humidit 1) 3-LT-3-203 A, B, C,

D 3-P T-3-22 A, B, C)

D 3-LT-3-56 A, B, C,

D 3-PDT>>1-13 A, B, C,

D 3-PDT-1-25 A, B, C,

D 3-P DT-1-36 A, B, C,

D 3-PDT-1-50 A, B, C,

D 3-PT-64-'56 A, B, C,

D 3-PT-3-204 A, B, C,

D 3-PT-1-72, 76, 82, 86 90oF gOOF 90oF g5oF 95 oF 95oF 950F gOOF 90 oF gooF 98$

98%

98%

98$

98$

98$

98'8$

98$

98$

180OF 180OF 180OF 117OF 117OF 117oF 117OF 110oF 100oF N/A(2) 100$

100$

100$

100$

100$

100$

100$

1004 100$

N/A(2) 303OF 303oF 350oF 350oF 3500F 3500F 350OF 303oF 303OF 303oF 100$

100$

100$

100$

100$

100$

100$

100$

100'$

100$

3-PT-1-81 A) B) 91A)

B 90OF 98$

N/A(2)

W/A(2) 303OF 1004 (1) Maximum (2) Equipment located where it will not be subjected to environmental conditions produced by LOCAs and HELBs.

Continued Transmitter Normal Normal Accident Accident Qualified Qualified No.

Tem.(1)

Humidit 1

Tem 1

Humidit 1

Tem 1

Humidit (1) 3-LT-3-58 A, B, C, D

3-LT-3-184

-185 3-LT-3-52

-62 3-PT-3-74 A,

B 3-PT-68-95

-g6 90oF g0oF 90OF gooF gooF 98$

98$

98$

98$

98$

183oF 135oF 117oF 183oF 163oF 100K 100$

100$

100$

100$

303oF 303oF 350oF 303oF 303 F 100$

100$

100$

100$

100$

3-PdT-73-1A

-1B 95oF t

3-PdT-71-1A

-1B 95oF 98$

98$

123oF 118oF 100$

100$

350oF 350oF 100$

100$

3-PT-64-58 E, F, G,

H 3-PT-64-58 il, B, C,

D 3-PT-64-57 A, B, C,

D 90 OF gPOF g0oF 98$

98'8$

122oF 122oF 110oF 100$

100$

1004 303oF 303oF 303oF 100%

100$

100$

T""B:VD 1/03/84 B4262D.VD

ENVIROX~IENTAL INTERI'ACE SEISHIC

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Environmental Intel face All equipment except the transmitters are located in the preferred location in accordance with paragraph

5. 1.4.

PL!Q4T IHTERCOANFCTIOY, EXISTING JUNCTION BCx RACEWAY TO EXISTING LOG IC TO BE REMOVED CUT WIRES NEV TWISTED SX<FLDED PAIR WIIIF MASTER TR IP UN IT l

OLD PRESSURE SN ITCII NEW PRESSUR'E TRANSMITTER TRIP SIGNAI. RELAY L

LOCAL INSTRUMENTCABINETOR LOCALLY MOUNTED INSTRUMENT TRIP UNIT CABINET IN CONTROL ROOM