ML19338F558
| ML19338F558 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire |
| 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
~
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
~
b
/
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=
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
1
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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:
~
E11.3.1' Coreexit-T/Ctemperature$,620F.
.11. 3'. 2?-
i.,op,at ;;65 T.
11.3.3 Lo'op IAVG jL 88 F.
5 2
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- -6 :
.Initid1/Date j
j.
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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, s
' 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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e
8-
~
, 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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gg l
Ini:151/Date-
/
'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.
i
/J J.
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
1 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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k.
Y' s%
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ly,.
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El d
1,
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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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- : z;,
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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.
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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
~
1
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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
-