ML19309B142

Special Test Procedure 2-ST-8:Natural Circulation Test.

ML19309B142
Person / Time
Site:	North Anna
Issue date:	04/02/1980
From:	VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML19309B136	List: ML19309B135 ML19309B137 ML19309B139 ML19309B142 ML19309B144 ML19309B148 ML19309B150 ML19309B151
References
2-ST-8, NUDOCS 8004030193
Download: ML19309B142 (25)

Text

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Page I cf 2 -ST- 8 'L VIRGINIA ELECTRIC AND POWER COMPANY 3,y;3 gen no,, o Date:

SPECIAL TEST PROCEDURE FOR tiORTH ANNA POWER STAT!CN UNIT / 2 TITLE: NATURAL CIRCULATICH TEST PrecarM Sv: p, a, ETtrNo Date: (3 Encineerinc Recer.: rended Acor: val: Date:

STATICN NUCLEAR SAFETY AND GPERATING CCMMITTEE AFPROVAL CF 3RCCECURE_:

Chairman's Signature: Date:

All persennel conducting actual testing in accordance with this precedurc will verify by their signature that they have read it in its entirety prior to cccuencing any testing:

I$

EST RESULT 3 AEVIEWEJ BY ENGINEERING:

Date:

I TEST RESULT 3 APPROVED BY STATICN NUCLEAR SAFE f AND CPERATING CCMMINEE:

Chairman's Signacure: Data:

Cecuents:

O hp 8004030 1 9  ;

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• TEST RESULTS (Use addi:ional :: ages as needed) Page Z Of OlSCRE?ANCIES (List by numcer): 110

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l R_ESOLUTION OF 315CREPANCIES (List by numcer c=rrescending := accve): I

CRITICUE: 112 t b

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CHRCN0 LOGICAL LOG (Use add'1 pages as needed) Page _ cf i ll' 1

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2-ST-8 Paga 1 of 8 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT NO. 2 NATURAL CIRCULATION VERIFICATION Referescas:

1. Precautions, Limitation and Setpoints for Westinghouse NSSS system

2. Technical Specifications, North Anna Unit r/2

3. WCAP-8747: North Anna Nuclear Design Report

4. North Anna S'.ation Curve Book

5. 2-0P-5.2

6. 2-0P-30

7. 2-0P-31 1.0 Purpose 1.1 To demonstrate the capability to remove decay heat by natural circulation.

1.2 To verify that the pressurizer pressure and level control systems can respond automatically to loss of forced circulation from all three reactor coolant pumps and maintain RCS pressure within limits.

1.3 To verify that steam generator level and feedwater flow can be controlled under conditions of natural circulation to maintain adequate cooling of the reactor coolant system.

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2-ST-8 Pags 2 of 8 Initials 2.0 Initial Conditions 2.1 Low Power Physics Testing has been completed to the extent necessary for conduct of this test.

2.2 Reactor is critical and manually controlled at approximately 3%

4 power with control bank D at U 160 steps or as specified by test engineer. (Power determined as indicated in 6.3).

2.3 All three reactor coolant pumps are in operation.

2.4 Pressurizer pressure control and level control are in automatic, maintaining RCS pressure at approximately 2235 psig and pressu-rizer level at approximately 22%.

2.5 Steam dump valves are in the pressure control mode, maintaining steam generator pressure at approximately 1005 psig.

2.6 Steam generator level is being maintained at approximately 33%

on the narrow range indicators.

2.7 feedwater and condensate systems are in service in accordance with 2-0P-30 and 2-OP-31. If main feedwater pump operation cannot be maintained under these conditions, the auxiliary feedwater system will be used in accordance with 2-0P-32.1.

2.8 RCS temperature (T,y ) is being maintained at approximately 547 F.

2.9 Record the follwoing parameters.

2.9.1 Install brush recorders to record data at the following locations.

Brush Recorder No. 1 Connect To: Monitoring Channel No. 1 FP-414B, C1-432 RCS Flow, Loop 1 Channel No. 2 FP-4248, C1-433 RCS Flow, Loop 2 Channel No. 3 FP-434B, C1-434 RCS Flow, Loop 3 Channel No. 4 PP-455B, C1-427 Pressurizer Pressure Channel No. 5 FP-459B, C1-442 Pressurizer Level

2-ST-8 Pago 3 of 8 Initials 2.0 Initial Conditions (cont.)

Brush Recorder No. 2 Connect To: Monitoring Channel No. I PP-474B, C2-433 Steam Gen. #1 Pressure Channel No. 2 LP-474B, C1-429 Steam Gen. #1 Level Channel No. 3 FP-474B, C3-741 Steam Gen. #1 Steam Flow Channel No. 4 PP-484B, C2-444 Steam Gen. #2 Pressure Channel No. 5 CP-489B, C1-430 Steam Gen. #2 Level Channel No. 6 FP-484B, C3-746 Steam Gen. #2 Steam Flow Brush Recorder No. 3 Connect To: Monitoring Channel No. 1 PP-494B, C2-445 Steam Gen. #3 Pressure Channel No. 2 LP-494B, C1-431 Steam Gen. #3 Level Channel No. 3 FP-494B, C3-748 Steam Gen. #3 Steam Flow Channel No. 4 S/6A Aux Feed Flow Channel No. 5 S/6B Aux Feed Flow Channel No. 6 S/6C Aux Feed Flow 2.9.2 Record the following on eact strip chart:

a) Test Number b) Recorder QA Number c) Time and Date d) Cahrt Speed  ;

e) Scale Used '

f) Test Point g) Parameters 2.9.3 Record on reactivity-computer recorder

a. Flux

b. Average wide range T

c. eo .s Average wide range Ts ,ld

d. Average Steam generaEor pressure 2.10 Four incore T/C may be trended on the analog trend recorder on the main control board. (Suggest trending the four hottest i thermocouples , one f rom each quadrant.)

2.11 A steady feed to the steam generators should be set up to minimize temperature variation in the RCS.

2.12 "otify the Shift Supervisor e duty of the impending :.ast and -

co-ordinates its performance through him.

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2-ST-8

Page 4 of 8 Initials 3.0 Precautions 3.1 Do not exceed 5% nuclear power.

3.2 Do not exceed any of the following temperature limits.

3.2.1 610*F for anycore outlet thermocouple.

3.2.2 65 F for any loop Delta-T.

3.2.3 580, 3*F for any loop T,y .

3.3 Do not exceed primary to secondary differential pressure of 1600 psi.

3.4 Avoid rapid changes in steam pressure, steam generator level, and feedwater flow to prevent rapid cooling of the reactor coolant.

3.5 Do not exceed 100 psi differential pressure between any two l

steam lines. This will result in a safety injection signal.

Refer to AOI-19 should this occur.

3.6 Maintain reactor coolant pump seal and thermal barrier differen-1 tial requirements as given in SOI 68.2.

3.7 After the reactor coolant pumps are tripped, the normal T avg and aT indications will become unreliable. AT and T avg should be calculated by taking the difference and'the average of the hot and cold leg termperatures indications respectively.

NOTE: Observe the TSAT meter.

3.8 Maintain T cold at the pretrip temperatures by adjusting the 4

steam dump setpoint.

I 3.9 Note possible effects of a positive moderator temperature i

coefficient.  !

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2-ST-8 Page 5 cf 8 fnitials 4.0 Instructions 4.1 Prepare the plant computer to record data as specified in i

Attachment 6.4. Record the initial steady state values for these points on Data Sheet 6.1.

4.2 Start the brush recorders at 125 mm/ min and start monitoring of data points on the computer trend typewriter at a one minute interval.

CAUTION: Continuously monitor main-steam line pressures and care-fully control feedwater addition during the transient to ensure that differential pressure between any two steam lines does att exceed 100 psid.

NOTE: 100 psid will initi. ate safety injection. Feedwater addition to each steam generator should be equal before tripping the pumps.

NOTE: Steam generator pressure, level, and flow conditions should be held as close as possible to stable condi-tions through the duration of the transient. Reactor coolant system cold leg temperatures should be main-tained within i 5*F of the initial values.

NOTE: At the initiation of natural circulation (RCP trip) the following temperature response is expected.

a) Wide range T , increase b) WiderangeT[fd, slight decrease or constant c) Core exit thermocouple, increase d) T indication, unreliable e) DelEa-T 'i'ndications , unreliable f) Pressurizer level and pressure, increase 4.3 Simultaneously trip all three reactor coolant pumps in accor-dance with 2-OP-5.2.

4.4 Maintain RCP seal flow at a minumum of 6 gpm to each pump.

4.5 Maintain pressurizer pressure control in automatic and manually adjust charging flow to match letdown and maintain a constant 003 water volume.

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e-2-ST-R Page 6 of 8 Initials 4.0 Instructions (cont.)

4.6 Carefully control additions of feedwater to the steam generators to maintain levels at approximately 33%.

NOTE: Natural circulation flow will be stable when:

I a) AT between wide range T ot and T e is costant.

b) AT between wide range T old ^^d *old

1. • **i' I average temperature is constant.

c) Wide range T c re exit T/C average temperature.

hot 4.7 After natural circulation steady state conditions have reached mark each recorder chart to indicate equilibrium has been reached and continue recording data for a minimum of 30 minutes.

4.8 Insert control bank D as specified by test engineer until the hot zero power test range is reached.

CAUTION: Ensure pressurizer spray controller outputs are approxi-mately zero before starting RCP's A of C.

4.9 After stable natural circulation flow has occured for at least 30 minutes, restart RCP A in accordance with 2-0P-5.2. Continue to collect data through the restart.

4.10 After steady state conditions have been reached, restart reactor coolant pump B in accordance with 'c Continue to collect data through the restart.

4.11 After steady state conditions have 4, restart reactor coolant pump C in accrodance wtih 2 s 4. Continue to collect data through the restart.

4.12 Stop the brush recorders and terminate trend recording on the

! plant computer.

2-ST-8 i Pagn 7 of 8 i

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Initials i

4.0 Instructions (cont.)

4.13 Ar. tach the brush recorder charts and computer printouts to this procedure. '

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2-ST-8 Psgm 8 of 8 Initials 5.0 Acceptance Criteria 5.1 Core exit T/C temperature does not exceed 610*F.

5.2 Delta-T for any loop does not exceed 65 F.

5.3 T,y for any loop does not exceed 580.3*F.

5.4 Delta-T established between wide T hot and T is stable and eold less than 65*F.

5.5 Delta-T established between wide range T eold and core exit T/C average temperature is stable and less than 65*F.

6.0 Attachments 6.1 Test Equipment Data Sheet 6.2 Initial conditions 6.3 Primary Caloremetire (Appendix A) 6.4 Process Computer Trend Block Data

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2-ST-8 Attachm2nt 6.1 Page 1 of 1 TEST EQUIPMENT DATA SHEET TEST EQUIPMENT DESCRIPTION

• MODEL NUMBER VEPCO QA NUMBER L

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• NOTE: This applies only to temporarily installed test equipment or instrumentation Permanent instrumentatien which is part of the system and shown on drawings should not be included.

Completed By:

Date:

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2-ST-8 Attachment 6.2 Page 1 of 3 a d CO:CI ICN3

?;assurima ?;assura psig FE-2444 Red Pen

?;assurima Lavel  %

L2-2459 Red Pen ECS Lccp L Ecc Lag Ta:::pers:::a

~i.-2413 Red Pen

103 Ocp 1 Cold Lag Ta=;:erans D 3-2410 Red Pen ICS Lccp 1 Ect Lag Tac:pera ::a 3 - 2423 Green-Pen i 3C3 kcp 2 Cold Lag Tan:pers =ra D 3-2420' Green Pen I 1

1 3CS Mcp 3 Ecc Lag Ta=pers==ra D 3- 2433 Blue Pen l

ECS Mcp 3 Cold Lag Ta==e 2 ::a D 3-2430- Blue Pen Scsas Gana:2::: 1 Laval CII)  %

(L*-2474 )

Scsa:s Ganars::: 2 Laval Cil)  :

(L -2484)

Scaa= Gasa:2::: 3 Laval CE)  :

C.~-2494 )

5cazm Canara: r 1 Laval C42)  % .

L1-2477 Pen 1 Red Pen 5:aam Gaeara::: 2 Laval Cil) .

L1-2477 Pas 2 Green Pen Scana Cana:2::: 3 Laval C42) ~

• 1-2477 ?en 1 Blue Pen

2-ST-8 Attachment 6.2 Paga 2 of 3

I C I.1L CO Q C ' 0:IS Scaan Canara:ce 1 ?:assura psig

?!-2474 S:aan G4: ara:c: 2 ?:assura psig

?I-2484 S:sa: Genera::: 3 ?:assura psig

?!-2494.

S:aa= Ga:arat:: 1 Temisa:a E:w X10' #/hr

(? -2476)

S:aa Ganara:c: 2 Feedsa:a: new x10' #/hr (I'-2486)

Staa= G4: ara:c: 3 Feedia a: ? low 5 xio 4/hr

(?~-2496)

Staas G4: ara:c: 1 S:aam ?lew x10' lbs/h

(?~-2474)

Scans G4: ara::: 2 Staa= ?iew x10' lbs/h

(?~-2484) 5: ass Genera::: 3 Staas n ew X10' ths/h

( E -2494)

Lacy 1 Tav; protection C 7

(!! 2412D) 0

• cp 2 74 73

. protection 7 i (C-2422D) , I

. cop 3 Tavg protection 7

(!!-2432D) l l

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- 2-ST-8 Attachment 6.2 Page 3 of 3 C ~ .. v..

. C . . ... a Ocp ; g- protection g (C- 2412A)

Mc? 2 dT protection  %

(- 2422A)'

2 00 3 4. ~ protection

( .*_*-24 3 2 )

3~5 C:.t=a'. 3-4; 5~5 t~~ .,-- e ' 5-4: =

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3~3 C.2:=a '. N-43  :

.s ,ma . h. . .

- ~.s it u d 1 oc?7 Of de :.--u.ar pf ::cu: cf de '.=cra "ha=ccc*.=21a Ta=e:2- : 2 . ap.

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2-ST-8

' Attachr.ent 6.3 Page 1 of 8 A2?CIDC' A Cu:11:e

~. Cera ?:ver ':aca. -':1:n A.  ? 10 . 7 Sida Cal::1=a::1: (7c::ad Cire=14:1:n Cely)

1. Rafara=ca ( m 530 D) Cal :d=at:1 a) Cu pu: used := adjus: M/J ?:ve: Ment::: ? :g:s='s pcue: conversic COCsCaO2.

3. M/3 ?:va: leni::: ?: g n

1.  ?:ver Conversic Cens m : Adjus :a==.

a) Se cu:pu: Of de IET p:d-e 7 cal =:1=a::1c vill give a  : ;cuer cc:pu:; dis cu:pu: =us: he i=pu: :: de M/D ? ver-M:ci::: ?:= gras s: .

a: de p : gram cu pu: -ill be 1 pertan: pcuer a d aqual ::

de ;;d=a.7 cal ri=arri curput.

2.  ? ver M::1:::1=.g a) Se M/3 ?:verva.d.:::

. Phg:n #4 e*' ula:a da in:ag:s1 ;cuer as sens by ene pass of 4 :: 5 datac:: 3. Af:a: de cu:;u: has been cali' ara .ad :: be acual :: de ?.II pr =a:7 cale:i=e::1: 1: #11 he ra::= up := . ca

. e're:7 2 ...d.

u:ss c as :ecessary := c:::inucusly

1::: cera ;cuer.

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Attachm:nt 6.3 Page 2 of 8 AP?EDIZ A C::RE PC*an 0:..z CLCION PART A: ?:1=ary sida calc:1=at:1 - Data Shee: A.1 (?c::ed Cir nis 1:n)

A.1 Use evo DVMs and ~aasure the voltsge at the tes: points specified for each locp as rapid as pcssible.

A. 2 Cale.: late the A !; =ultiply tha: 4 T by the specific her: a=d

ne 'Jes:1=ghcuse best esti= ate flew rate of the core average ca=pers:::e (Table A-1) . (Special Tes: No. 9 uses vide range A T so a cc::ac:1cs fact:: is required :o c =pe= sate for pu=m heati=g, refer to Appendix s of 2-ST-7).

A. 3 Su:n the loep hea: races and conver: .co a percent reae::: pcwer. Tae cu:put is used in Far: 3.

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2-ST-8 ~-

. Attachment 6.3 Page 3 of 8 A??F'.mII A (Continued)

Ccre Fever Dece.~4 acien PAa* 3: M/D ?:ver M :1::: ? :g:s=

1. Set up de novable de:ector sys:em for a 1 pass partial cere flux rap. Selec: flux 21=bles as per de table belew fer de flu:e =ap.

Drive 10-Path Posi:1on Cere Locatien A

B C

D l

1"hese posi:icus say *:e al:ered by de :es: engineer, based upcn 1:w-pcwer physics :esting resul:s and previcus special :es-dg experience. .

2. Deter .ine de detect:r cer=alizatica c escas:s and enter dem ine:

he F-250 as f=11cvs:

a) Inter a value of 1.0 into de ?-250 f:: de addrasses sheva in he cable belev.

b) 'Ji:h all 5-pa d selec::: sw1:d es se: :: ac:=al run a flu:

ace.

) 'Jith all f-path selec :: svi: hes se to I=argency, run a see: d flux :: ace.

d) Deca.~ne de detect:r ner:alization c :stan:s f:: Da:a Shee: A . 2.

e) Inter these detec: r sc:=alizarice cessan:s ine: .he ?-250 as shev: in -de able,belev.

Drive  ?-250 Address constant 3

C D

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2-ST-8 Attachment 6.3 Page 4 of 8 j APPEIDC A (Con:inued)

Cora ?cuer De:a:M na:ica PAP.T 3: (Concinued)

3. 7e:1fy da: de ?-250 pars =ecers listed in -de folleving :able have :he pr:per vahe and da: de ?-250 :1=a and da:a are curren:.

Upda:a as requirad.

Address value Fune:1cn KC901 1 Set the ecue: normalizatice fac ::

6: elects de cdified K5525 1 "?lu: Mae ?-is:" c: zra=s K0900 0 I:1: dated ? ass Nt=ber p Calibrati:n Constan: fc: M/D KC864 7a-table -)  ? ver Meniter

(')7ariable: he va he encared is a ra:10 of de ?:i=a:f Calori=r.::1c Indics:ed ?:ver (I:an 3 cu Data Shes: C.1) to :he S/D calcula:ed pcver (C0906) -1=es de curren: value en:ered 1: (IC864). If so value has been en:ared is:o (KOS64) en:a 0.25.

I:e= 48 Data Shee: C.1 New (K0864) = Carre:: (K0864) x (UO906)

4. Fo: pcuer data =1:a:1:n, cb + a partial cera fle= =ap.

Se M/D's need sc: he vi ddra- between passes, and passes =ay be repeatad as ef:an as a pcvar dete==ina:1:n is required.

NCE: Se calcula:ad pcver (CC9C6) is prin:ad ai a each pass and a7 be ::anded by de ?-250 if desired. ~he individual de:ac:c:

se:- mM ead in:egrals are also prin:ad.

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- 2-ST-8 Attachmant 6.3

. Paga 5 of 8 A2?"QII A (Ccn 1=uad) 7.13LI A-1 a=p Cp (1) e-3 =

7 3TU/lb= 7 lbm/hr 556 1.250 3.6448 x 10 7 534 1. 255 3.6553 x 10 7 552 1. ~.5 0 3.6659 x 10 550 7 1.245 3.6765 x 10 548 1.240 3.6862 x 10 7 546 1.236 3.6959 x 10 544 1.231 3.70.57 x 10 7 542 1.226 3.7135 x 10'

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540 1.221 3.7254 x 10 7 338 1.217 3.7343 x 10 I 536 1.213 3.7443 x 10 I 334 1.209 3.7538 x 10 '

532 1.206 3.7633 x 10 I 530 1.202 3.7729 x 10 (1)'"sesa talcas are f::s the 1967 ASMI Staan 22bles. 7alues are f r a pressure of 2250 psia.

2-ST-8 Attacitment 6.3 Page 6 of 8 APPF.tIDIX A (Contleiued) -

Data Slicet A.1 ,

Date Time linit Power Tavg "F llem i Calculation Procedure lini t s 1.oop 1 f.oop 2 1.oop 3 _

1 f.nop 4_T-leiservice (at test point) Volts 2 -

I.oop A T - (#1) x "F 3 I.oop A II - (#2) x Cp (f rom Talsle A.1) HTil/llem 4 I.oop RCS Flow (from Talste A.1) 10 lbm/lar ,

5 1.oop Reactor Power - (#3) x (#4) 10 BTU /lir Total Reactor Power - (IS) 6 6 I.oop 1 + I._oop 2 + Loop 3 10 nTll/lir 7 Reactor Power - (#6) x 0.29M7 PRif 8  % Reactor Power - (f 7) x 0.02932 ~Z Conversion factor for A T olitained from scaling document.

Remarks:

Data Hy:

Dater .

2-ST-8 Attachm:nt 6.3 Page 7 of 8 AP?C;DII A (Cca:inued)

DAIA SHIZI h.2 A.I = - _A=

A=

.1 -

C.I = - D.I =

L=

.I 3=

e s C=

s -- D_ = I=

s  :

Ng = 1.CO A, NA

.i 3=3 =

A :. =

'l N

NC = A,3 *l 3

' i

=

3E = \

i C,i . C,i

• A, 3C

.I 3 =

C. =

D = D,I . D,I i

N_=^:

=

%% =

i e e J .i Dolini:1=::

A.,,

" 3,g, C,g, D,g, I.;

=

lIc=a11:ad in:egral from su:=ary sap for e ach detac:cr is a sc=al pa:h is :he firs: pass A ,3 ,C.,D.,I_.

=

Normalized de:ector , 12:eg:21 f = su==ary map for each

Tg . :13 , N ' a an emergency path in the seccnd pass C D' I

=

e ac c nc ra: On fac::: for end detec:::

.h= arks:

Ds:a 37:

Daca

2-ST-8 .

Attach = ant 6.3 Page 8 of,.8 AP?PiDII A (Concinued)

Par: C: Using "he=cc uples na incere der =ccouples can be used as an indica:1cs of both ecre flew dia::1bu:10: and power shif s duri=g =atural circula 1cs.

?:1o to :-"' s a cer=cccuple =ap or trending de eigh: quadran: til:s (fcur cancer 11:e and f:ur d1agenal til:s) the fc11cving shculd be verified:

10701-K0765 = 1, For de flew du g fac: ors K5501 = 0 Indica:as de sensured core 4 U is unreliable K0791 = 0.075, Core bypass ficw frac:ics

.0010 = 8, Uells derseccuple p cgra= hev =a=7 read 1=gs of .her= occupies are required for averag1=g before calcula:10: is done, nis in ::: sees de == ing fraquency of de ne=ccuple Averaging

? cgram a: 1, 2 , . . . . I 8 secends er 64 secceds for us.

ne de. ccuple proges=s breaks the core deva in:o eigh: quadrants-feur ce carli=e and four 11 age al quadran:s (see Figure C-1) . Quadran:s 1-4 can be direc:17 cc=ela:ad wi h the execte detac:crs bu: quadran:s 5-8 ca= c:.

ne quadran: :11 s are indicative of pcver shifts a:d should be : ended at appr zina:aly a 2- . d:u:a frequency. n e folicwing addressable valuas are de quadran: :11:s:

Cuad:ss: Addrassah1a *.'alue 1 U1159

U1160 3 U1161 4 U1162 5 U1151 6 U1152 7 U1153 3 U1154 .

A Shc:: Ic= Man shculd be == periedically c: upc request fr = de :as:

engineer as an indica: ice of core flew dis:-ibutics.  :: shculd be pu: ce de U:111:71Tpev:1:e if possible. ne P-250 Cpera:c:'s Ccusole Referesca M2:nal p;cvides 1:strue:1ces fc cb:-d g de cc uple =aps.

ne ::and cu:put and Sher: Fors Maps should be a:: ached to dis procedura .

at de end of de :es:.

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2-ST-8 Attachment 6.4 Page 1 of 2 PROCESS COMPUTER TREND BLOCK A COLUMNS ADDRESS PARAMETER UNITS 1 T0406A RCL A T COLD 2 T0426A RCL B T COLD 3 T0446A RCL C T COLD 4 T0419A RCL A T HOT 5 T0939A RCL B T F HM 6 T0959A RCL C T HOT 7 T0400A T LOOP A *F AVG 8 T0420A Tgyg LOOP B *F 9 T0440A T OOP C *F AVG 10 T0403A AT LOOP A  %

11 T0423A AT LOOP B  %

12 T0443A AT LOOP C  %

13 F0128A CHARGING FLOW GPM 14 F0143A LETDOWN FLOW GPM 15 U1250 HIGHEST REL FUEL ASSY PWR 16 LO480A PRESSURIZER LEVEL  % l 17 LO112A VCT LEVEL  %

18 U1251 HIGHEST REL ASSY PWR INDENT J

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2-ST-8 Attacha nt 6.4 ,

Page 2 of 2 PROCESS C0riPUTER TREND BLOCK B COLUMNS ADDRESS PARAMETER UNITS l 1 LO400A S/G A LEVEL  %

2 LO420A S/G B LEVEL  %

3 LO440A S/G C LEVEL  %

4 PO400A S/G A PRESS PSIG 5 PO420A S/G B PRESS PSIG 6 PO440A S/G C PRESS PSIG 7 PO480A PRESSURIZER P PSIG 8 PO498A RCL SYSTEM P PSIG 2 P0142A CHARGING PRESS PSIG 10 UO482 AVG PZR PRESS PSIG 11 UO483 AVG PZR LEVEL  %

12 U1118 RX THERMAL POWER MW 13 U1170 AVG T/C TEMP F 14 AS REQUIRED HOTTEST T/C (QUADRMT 1) *F 15 AS REQUIRED HOTTEST T/C (QUADRMT 2) F 16 AS REQdIRED HOTTEST T/C (QUADRANT 3) *F 17 AS REQUIRED HOTTEST T/C (QUADRMT 4) *F i

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