ML19338F558

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Draft Special Low Power Testing procedures,TP/1/A/2150/21, Effect of Steam Generator Isolation on Natural Circulation
ML19338F558
Person / Time
Site: McGuire, Mcguire  Duke Energy icon.png
Issue date: 10/10/1980
From:
DUKE POWER CO.
To:
Shared Package
ML19338F555 List:
References
TP-1-A-2150-21, NUDOCS 8010200570
Download: ML19338F558 (16)


Text

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zip /1/A/2150/21-DUKE PONER.COMPANI-McGUIRE NUCLEAR STATION, EFFECT OF S/G ~ ISOLATION c

ON NATURAL CIRCULATION

^

Foil itJCFMATION 1.0L Purpose 11.1 Determine the effect of steam generator (S/G) isolation on

~

' natural' circulation conditions.

1.2-

, Verify that natural circulation can provide sufficient flow-

' to remove. decay heat 'af ter a partial. less of. heat - sink.

e 1.3 ' Veiify that natural' circulation.can be reestablished in a primary loop after steam generators are returned to service.

.2.0, References' 2.1 McGuire Limitations and Precautions, OP/0/A/6100/06 Section 3.2.3.1.

2.2-System Descriptiion, MC-1223-12, NI System, Rev. 3, Section 4.1.1.

Addendum 1, UHI Rev. O, Section 2.2.3.

2;3-System' Description', MC-1223-42, Auxiliary Feedwater S'ystem. F.ev. 4.

2.4! Main Steam System Flow Diagram, MC-1593-1.0, Rev. 7,

~

2.5~. Auxiliary Feedwater System Flow Diagram, MC-1592-1.0, Rev. 8.

2.6

.S/G Blowdown Recycle Flow Diagram, MC-1580-1.0, Rev. 8.

2.7 Feedwater System Flow Diagram, MC-1591-1.1, Rev. 3.

2.8 Nuclear Sampling System Flow Diagram', MC-1572-3.0, Rev. 7.

-3.0 Time. Required-7 hours k 2. engineers J(1 Performance and 1 I&E Engineer)

Initial / Dated

-4.0 IPrerequisite Tests

-/

'4.1 TP/1/A/2100/02, Zero Power Physics Controlling Frocedure.

L/J 4.2 TP/1/A/2150/20,-Natural Circulation Verification.

5.0 Test Equipment'

. 5.1 ;

React 1Yit'y Computer

-52

-Six: IBM Floppy-Disks 6.0 -Limits and Precautions.

(

1;6 ;l;. An operator initiated safety injection should be performed if the h

.NCIsystem subcooling-bi less-than~or' equal to 10 F.

. NOTE:.SI termination should be in accordance with plant procedures.

P l

^

0$00;-pg 4

m.,

+

4 6.2 An operator initiated: reactor trip should be performed for one or

.more~of:the following-conditions:

6. 2 ','1

'If the.NC system subcooling is less than 15 F.

~

- 6.2.2 -

If fone of three 'excore power range detectors indicates

'a reactor power ' greater than or equal to 10% F.F.

NOTE: :The'~ fourth excore channel will'be connected to the react'ivity computer.

6.2.3 If any NC'icoo avera'ge temperature exceeds 588 F.

6.2.4 If'anyINC icop delta te perature exceeds 58 F.

6.2.4 If any NC loop hat leg temperature exceeds 617 V.

<6.3 Do not exceed 5: F.P. at any time during this test.

6.4 Avoid any' rapid changes in feedwater flow, S/G 1evel, or steam pressure to prevent rapid-cooling of the NC system.

6.5 Without forced NC flow, the. narrow range temperature indications

. (T-COLD and T. WG) ray-he unreliable. Iherefore, wide range indications.should be used.

6.6 Whenever possibles maintain NC system co? d leg te=peretures stable.

This will minimi:e errors in NI power determination.

6.7 Ensure that control bank D position remains at greater than'or ' equal to'100 steps withdrawn. If this limit is. reached, boron concentra-tion must be' increased.

6.8 Ensure that. seal flow is maintained to the NC pumps during this test.

6.9 Si.culd a reactor trip take place during the performance of this test, restart at:least one NC pump (A or 3) prior to closing the reactor trip. breakers.

6.10 -Auxiliary _. spray flow to the pressurizer can be controlled by

'adju' sting. charging ~ flow, closing,the normal charging path, or openingL the normal spray valves-after the NC pumps are tripped.

6.11. Do not exceed the 1600 psid primary to secondary differential

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pressure limit..

6.12 :Use control rods as necessary to maintain core power approximately

^

7 constant.. If boron addition.becomes.necessary to avoid reaching t cheirodJinsertion limits, use sprayL to. keep the ' pressurizer boron

~

concentration within 20. ppm.of the NCS concentration.

(6.13. Maintain T-COLD-for chetunisolated loops,c 515.-5 F..

4 d

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b

/

jg-r s

=

r 5

e

_3

'6.14.. Loop 4T is defined as'the difference between wide range T-HOT

.and. wide range T-COLD.

7.01 Required Unit Status

~ Initial /Date

'/'-

' 7.1 The unit is'in the:Startup Mode (Mode 2).

8.0' Prerequisite System Conditions-

~/'

3.l' The reactor is at approxi=ately 1%' F.P. with control bank 3 in Bank Select and at approximately 160 steps withdrawn or.as

~

specified by the test coordinator.

/.

3.2

All four NC pumps are in operation.

/

3.3-Pressurizer pressure and level controls are in autocatic-and maintaining NC pressure at approximately 2000 psig and level at approxicately 25%.

/-

8.4 Feedwater to.the S/G's is supplied by the auxiliary feedwater system with level being aintained at approximately 25%.

/

3.5 Steam dump valves are in the pressure control : ode saintaining S/G pressurelat approximately 763 psig and NC temperature at approxt=ately 515 F.

NOTE: Since the pressure in an isolated S/G will rise to the saturation pressure for the hot leg temperature existing at that' time, T-AVG is reduced to 515 F.

/

3.6 Stess generator chemistry is in a condition such that bicwdown may be -isolated for the duration of this test.

/-

'8.7 Nor=al charging and letdown are in service under automatic control.

/1

.S.S-Intermediate and power range (low setpoint) high -level reactor trip setpoints have been set to 7% F.P.

This corresponds to 2.8 x 10 '. asps on the IR.

~

NOTE:

.S.9' Soren equilibrium-has been established as follows:

/

S.9.1

- The' difference between loop and p ressuri er ;ron concen-tratica is_less than 20 pps3.

-/

S.9.2 The difference between 3 successive =easurements of loop 1 boron concentration is_less than 10 ppc3.

/

'S.9.3 The data from the above measure =ents has been recorded on nclosure 13.~4.

NOTE: Boron sa:ples are'taken at 30 minute intervals.

1 m

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I2hitial/Date~

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8.10 'OAC Point Accumulation and Cutput (General Program 24) is set up

. to record the points listed on Enclosure 13.1.

/

-8.ll

~.3C' Transient Monitor lis recording data.

'/

8.12~-The' reactivity computer is set up to display flux and reactivity.

/

' 8.13 ? ' The instrumentation listed on Enclosure 13.3 i:s-in -calibrationiand all information-is recorded.per Enclosure 13.3.

/-

8.14-The parameters listed'on Enclosure 13.7 are modified per Enclosure 13.7.

/-

.8.15-Ensure that all T/C ccmputer points are checked out.

/

8.16. Verify' the valve lineup per Enclosure 13.6.

9.0 Test Method With: natural circulation successfully established in all four primary loops, and the NC system cooled down.to provide sufficient =argin to the S/G_ safeties, a S/G will be isolated and natur>l circulation ver$fied in the.remaiding loops. Once stabilication occurs, another S/G will be.

isolated and natural. circulation verified in the remaining' loops. 'The isolated steam-generators will then be sequentially returned to service to verify that natural circulation can be re-established.

10.0 Data Required' 10.1_ Boron concentration data as required by Section 8.9 and recorded on Enclosure 13.4.

10.2 ~All calibration data required by Enclosure.13.3.

10.3 An output of OAC Point Accumulation and Output with the points listed on Enclosure 13.1 (See Sections 12.1 and-12.24).

[10.4 'An output of 0AC Transient Monitor (Section 5.2) with~the points

-listed on Enclosure 13.2 (See Sections 12.2 and 12.24).

_ NOTE: 'The' data from OAC Transient Monitor will be frozen and output to 2 floppy disks every.30 minutes from the beginning of;the test. -The 'only points required to be printed on 2 hard. copy are the points listed en Enclosure 13.2.

10.5. An output of.the Reactivity cenputer results (See Sections 12.3 and 12.24).

'10'.6 An' output of OAC Thermocouple -Map per Sections 12.'3, 12.7,'12.2,

~

-12.5, 12.19,'and 12.23.

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=

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'=,

s.

i g

11;0 Acceptance Criteria

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'11.1-~ ~ Suf ficient natural ~ circulation can be maintained in the active primary loops to maintain stable temperatures:following a partial loss.of heat' sink.

11'.2 ~ Natural circulation can be restored to. inactive loops when the associated steam generators are returned. co service.

4

-11.3 The following limits are not exceeded:

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E11.3.1' Coreexit-T/Ctemperature$,620F.

.11. 3'. 2?-

i.,op,at ;;65 T.

11.3.3 Lo'op IAVG jL 88 F.

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- -6 :

.Initid1/Date j

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12.0 Procedure

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' NOTE: ' Data-acquisition st'eps need' not be repeated for multiple test-

.i performances.' -N'/A signoffs-for these steps'are adequate.

/

12.15 ' Initiate OAC point Accumulation and Output (General Program 24)

[

Lreco'rding' the: points listed on Enclosure 13.1.every 60 seconds.

L nNOTE: Be surc ito' get an. output of Transient ibnitor (per Sec-L tio'n 10.4) every'30 minutes throughout the measurement J

i sequence of'thie test.

l

/

'12.2 Initiate the Reactivity computer' recording the points listed in l~

Section 3.12; -

./'

12.3 'Obtain an output of CAC Thermocouple Map (Nuclear Program 11).

'/

12.4 Establish' aux 111ary spray flow.to the pressurizer and manually i

j maintain pressure at about 2000 psig using heaters and spray.

/

12.5 Sisultaneously-trip all four NC pumps, h-

' NOTE:.See Sections 6.8 - 6.12.

l:

/

12.6 Maintain S/G 1evels at approximately 252, steam pressure at i

approximately 763'psig, TCOLD.at 515 +5 F, and NC pressure at l

approximately 2000 psig.

l NOTE: -After tripping NC pumps, the S/G 1evels may shrink slightly l

and.then'sve11:as natural circulation develops.

NOTE:- The steam'ducp pressure controller =ay have to be adjusted to =aintain' cold. leg te=peratures at their initial value.

~

NOTE: Natural circulation will be stable when the AT between

_ vide range T-HOT and T-COLD is constant.

p j'

/

12.7 Obtain an output.of OAC Thersoccuple -Mip (Nuclear Program 11).~

l

[

/.

12.3 Adjust.the setpoints on all four atsospheric relief valve pressure Lcontro11ers'to maintain steam pressure below 1025 psig when the l'

steam generator is isolated.

L NOTE: This'should prevent the opening of the =ain steam safety l

valves.

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' Linitial/Date

- /

- 12.9 Establish maximum maintainable flow through the normal letdown path, and manually? increase charging. flow to saintain a-constant NCS; mass.and pressurizar level. Start an additional. centrifugal

-charging.pwap:if necessary.

~

'/'

12.10 Isolate. S/G ~C -by closing'sain staan isolation valves ISM 3A3,

. auxiliary feedwater valves 1CA46B and ICA44, and.S/G blowdown valves 13B142A an'd 1337A.

NOTE': Carefully _ ' control fee'dwater additions to the! remaining

' S/G's to hold the l' vels at =25%.

a NOTE: LDo not exceed the primary to secondary differential

^ pressure limit of 1600 psid.

NOTE: -Allow the pressurizer level to increase when T-AVG is

' increased (=1% level increase per 1 F increase is expected).

NOTE:

It may be necessary to adjust the steam du=p pressure controller setpoint to' reduce T-COLD in the unisolated loops so that S/G pressure in the isolated loop re=ains below the atmospheric relief valve setpoint.

NOTE:.During this transient' the following responses can be expected:

'a)

Wide range T-80T will increase.

~

b)'

'41de range' T-COLD for loop C will increase to approxisately T-HOT.

c)

Core exit T/C readings will increase, d)

Wide range T-COLD for the unisolated loops will remain constant via steam dumps, e) 1ressurizer pressure and level will-increase.

12.11 Allow'n'tural circulation conditions to stabill:e.

- /

a NOTE: Natural circulation will be stable when loop C ST is stabis at approximately zero and when iT for the renaining loops

.are constant.-

50TE:- If T-AVG continues co increase and cannot be stabilized..the test :ccordinator should determine if further testing can be continued,'

/1 12.12.Cbtain an' output.of-0AC Thermoccup1A Map (Nuclear program 11).

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, Initial /Date 12.13 ' Isolate S/G D by closing main steam isolation valve 1SM1A3, 1

/ -

auxiliary'feedwater valves 1CA40 and 1CA423, and S/G blowdown valves 1BB143A.and'1338A.

NOTE: Carefully control feedwater additione to the remaining S/G's>to hold the levels at =25%.

See Section 6.4.

NOTtt. It may_beinecessary to' adjust the steam dump pressure controller setpoint to reduce T-COLD in the unisolated loops so that S/G pressure in the isolated loops remain below the atmosph'eric relief valve setpoin',.

NOTE: Do not exceed the primary to secondary differential pressure limit of 1600 psid.

NOTE: Allow the pressurizer level to increase when T-AVG is in' creased (=l: level increase per i F increase is expected).

. NOTE: During this transient the following responses can be expected:

a)-

Wide range T-HOT will increase.

b)

' Wide range T-COLD for loop D will increase to appt a-ximately T-HOT.

c)

Wide range T-COLD for loops A and 3 will remain constant via steam dumps.

id)

Core exit T/C readings will increase.

e)

Pressurizer level and pressure vill increase.

/

12.14 Allow natural circulation conditions to stabilize.

Natural circulation will be sta,ble when loopiD AT'is stable NOTE:

3-at approxi=ately zero and when for the remaining loops are

' cons tant.

NOTE:

If T-AVG continues to increase and cannot be stabilized, the test coordinator should determine if further testing can be continued.

' /.

12.15.0btain' an output of 0AC Ther=occuple Map (Nuclear Program 11).

12.16 When the itest ccordinator is satisfied that sufficient data has J

/

.been, collected, slowly reduce the atsospheric relief valve controller setpoint and allow S/G D pretsure to reach approxi= ate equilibrium

,Jith steam header pressure. Then, slowly restore feedwater to main-tain approxi=ately 252 levels.

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Ini:151/Date-

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'12.17 When S/G D pressure is approximactly equal:to steam header pressure

.open MSIV 1SM1A3 and close the atmospheric' relief valve..Carafully

.3 Scontrol feedwater addition to S/G's A. 3, and,C to maintain I

approximately 25: levels.

' NOTES-During this'cransient,.the'following responses can be expected:

i a)

Wide range T-HOT will-decrease.

Tb)

. Wide range _T-COLD for loop D will decrease.

c)j Wide tange T-COLD for leop C will remain constant.

fd)

Wide range T-COLD for loops A and B will increase via steam dumps.

/

12.13 Allow natural circulation conditions to stabilize.

(:

NOTE:. Natural circulation will be stable when the aT for loops A, d

B, and-C are' constant and spproxi=ately equal.

/-

12.19.0btain an output of OAC Thermocouple Map (Nuclear Program 11).

[

/

12.20 Slowly reduce the atmospheric relief valve cuntroller setpoint and reduce steam. dump to the condenser, allowing S/G C to reach approxi-mate equilibrium with' steam header pressure (=1005.psig). Then, l

slowly restore feedwater-co maintain approximately 252 levels.

/'

1?.21?When S/G C pressure is approximately equal to steam header pressure open MSIV ISM 3A3 and close' the atsospheric relief valve. Carefully control 'feedwat'er addition to 3/G's' A and B to maintain approximately.

25: levels.

. NOTE: During the transient, the-following responses can be expected:

a)

Wide range T-EOT will decrease.

. b)

' Wide range T-COLD for loop C will decrease.

c)

Wide range I COLD for loops A, B and D will increase via steam dumps.

/

12.22[A11ow natural circulation conditions to stabilize.

. NOTE: Natural'circulat' ion will be stable when the AT for all loops are constant:and.approximately equal.

/'

12.23 Obtainfan outpuc of OACl!her=occuple Map-(Nuciaer Program 11).

~

i:

/'

12.24.Stop. recording test data (See Sections 12.1, 12.2 and 12.3).

12~.25 Insert contr'o1 bank D.until the reactor is;in the HZ? test range.

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a 8

s i

_ ~; L; d'y i

+

. +.n:

i.

LInitial/Date;

/'

1,12.26'Ensuretthat the pressuri:e spray 1 contro11ers are at :ero output and then restart'all four SC pumps.in accordance'with Section 2.

a.

-Restart in_the following' order:

3, A, C,'D.

/

12.27 Return control of the system' to Operations.

/

-12.23 Unless:the next tert to_be performed requires the same'modifica-

- tions, return the parameters listed on Enclosure 13.7 to their

< _T original state.

12.29 Complete Enclosure 13.5.

E/

/'

12.30'A11 acceptance criteria are met.

'13.0 Enclosures 1

4

' 13.1 Point Accumulation and Output (FAO) Input List 13.2 Transient Monitor Output List

. 13.3 Calibration Verification 13.4 [ Log of Boron Concentrations

- 13.5 Acceptance. Criteria Verification 13.6 Valve Lineup 13.7' Para =eter Modification-l I

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POINT ACCLHUI.ATION AND OUTPUT (PAO).' INPUT LIST -

f2 ENCLOSURE 13.1 TP/1/A/2150/21 EFFECT' 0F S/G ISOLATION ON NATURAL CIRCULATION A1061 NC Loop A.'(kt) T-COLD F

f l

A1067

. NC Loop B (k'R) T-COLD F

LA1073 NC Loop C.(WR) T-COLD.

F.

Al*79

- NC Loop D (WR) T-COLD F-

.A0965 NC Loop A (WR) T-HOT-F

'A0971

- NC Loop 3 (k'R) T-HOT F

A0977-NC Loop C (kt). T-MOT.

F l

- A09A3 NC Loop D.(WR).T-HOT F

. A0626-PP, Average Level, Quad.4 (N4))

A0627 PR Average Level,' Quad 2'(N42)

P. '

A0622 PR Average Level -Quad 1.(N43)

A0629

~PR. Average level,. Quad 3 (N44)

A010U In-Core Temp'C12 (Quad 2)

F

. A0238-In-Core Temp N12 (Quad 3)

F

. A0220:

In-Core Temp 504 (Quad 4)

F

  • A0274' In-Core Temp.C04 (Quad.1)-

F-P1424 NC Loop A Flow, 3est Estimate GPM P1425

. NC Loop B F1'ow, Best Estimate GPM i

, NC Loop C Flow, Best Estimate-GPM P1426 l

71427.-

NC Loop D-Flow, 3est Estimate GPM H

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y F

4 4'

1 sF

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TRANSIENT MONITOR OUTPUT LIST'_

INCLOSURE 13.2 TP/1/A/2130/21 EFFECT 0F S/G' ISOLATION zdN NATURAL CIRCULATION A

)

A1124

'PZR Level:I

'A1118

.PZR Pre's'sure I PSIG

-A1059-

.S/G'A Level (NR) IV

- A1065

.Sid B Level:.(NR) IV i

-A 071 S/G.C Level'(NR)_IV e

~

A1077 S/G'D Level (NR) -IV A11071-S/G A Pressure I PSIG i A1113

.S/G B Pretsure I PSIG A1119 S/G C Pressure I PSIG A1125 S/G D Pressure I PSIG

-A0890 S/G A Aux. Feed Flow GPM

~

A0884.

S/G B Aux. Feed Flow GPM A0878 S/G C Aux. Feed Flow GPM

~

A08'72'.

S/G D Aux. Feed Flow GPM' 1

..S/G A Main' Steam Flow.I

-ML3/HR A1060 s

A1066

- S/G 3 Main. Steam Flow I ML3/HR

~

A1072 S/G C Main Steam Flow I ML3/HR r

S/G D Main Steam Flow I ML3/HR A1078 4

I L

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CALIBRATION VERIFICATICN ENCLOSURE.13.3

~ TP/1/A/2150/21 EFFECT OF.S/G-ISOLATION g

ON NATURAL. CIRCULATION Instrument (s) Name,L Medel.and Serial or Calibration

~ -

Parameter.

Manufacturer, if' Applicable Loop No(s).

Due Date(s)

NC Loop-INCLP5423 TAVG INCLP5463 4

1NCLP5503 1NCLP5543 Cold Leg 1NC7.P5860

~ Wide

~1NCLPSS80 Range INCLP5910 Temp.

1NCLP5930 Hot Leg 1NCLP5850 Wide:

INCLP5870

~

~

Range INCLP5900 T'mp.

1NCLP5920 a

_r 2 l s

4

-Racorded ihr Date 4

k

['

i s

s a

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2 e

4 w

=

3 f

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= ?:

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LCC 0F BORON CONCENTRATIONS.

~

ENCLOSURE 13.4 TP/1/A/2150/21

-EFFECT OF S/G ISOLATION I

CN NATURAL CIRCULATION.

/

5

?

V NCS Boron Concentration-Date

. Time

- Recorded By NCS PZR Comments l

l '.

7.

t

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s 4,

h f N 6

N

. x J.

q

.~

ACCEPTANCE' CRITERIA ~ VERIFICATION

~

- ENCLOSURE ~ l3 ' 5

-TP/1/A/2150/21

'EFFECT OF.S/G ISCLATION ON NATURAL CIRCL*LATION

- Place an "X" on the' appropriate spaces.

True False A.

Sufficient natural' circulation has'been =aintained'in 11 oops A, 3,' and D to maintain stable temperatures when

-S/G C was~ isolated.

B.

-Sufficient naturc ocirculation has been maintained in

~

loops A and 3 to.=aintain stable. temperatures when S/G C and D was isolated.

.C..

Natural ' circulation has been restored ta) loop D when S/G D-was returned to service.

~

LD.

Natural circulation has bece restored to' loop C when S/G-C was returned toiservice.

.E.

Core exit T/C temperatures were $620 F.

F.

Loop AT"s were <65 F.

G.

Loop TAVG's were <338 F.

t-

.l 1:

rRecorded 3y

-Date 1

1 r

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VALVE LINEUP

. ENCLOSURE 13.6

.TP/1/A/2150/21' EFFECT OF S/G ISOLATION ON NATURAL CIRCULATION'

' Valve Name.

Position Initial

S/G'C Upper _Shell Sample Cont. Isol. Inside-

. CLOSED

- S/G C'3 lowdown Line Sample Cont. Isol. Inside CLOSED S/G C Sample-Hdr. Cont. Isol. Outside-CLOSED S/G D Upper Shell Sample Cont. Isol. Inside CLOSED S/G D Blowdown Line Sample Cont. Isol. Inside CLOSED S/G D Sample.Edr. Cont. Isol. Outside CLOSED S/G D FDW Control' CLOSED

'S/G C FDW Control CLOSED S/G.3 FDW Control CLOSED S/G A FDW Control--

CLOSED S/G'D FDW Cont. Isol.

CLOSED S/G C FDW Cont..Isol.

CLOSED S/G 3 FDW Cont. Isol.

CLOSED S/G A FDW Cont. Isol.

CLOSID Aux. FDWP No. L'Disch. to S/G'D Control CLOSED Aux. FDb7 No.1 Disch. to S/G D Control Outlet Isol.

CLOSED Aux.;FDWP No.'1 Disch. to S/G A Control CLOSED Aux. FDWP No.1 Disch. to S/G A Control Outlet

~

Isol..

CLOSED Aux. FDWP No.1 Disch. to S/G C Control CLOSED Aux. FD%T No.1 Disch. to S/G 3 Control CLOSED

Aux. FDWP No.- lLDisch.~ to S/G C Control Outlet Isol.

CLOSED

' Aux. FDWP. No.11 Disch. to: S/G 3 Control Outlet.

.Isol.

CLOSED 1

e e

4

-