ML20082G063

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Proposed Tech Specs 3/4.2.5 Revising RCS Flow Uncertainty to Replace Phrase Prior to Operation Above 75% Rated Thermal Power W/Phrase within Seven Days After Exceeding 90% Rated Thermal Power (Unit 1) or Prior to Operation Above 75%..
ML20082G063
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 08/08/1991
From:
GEORGIA POWER CO.
To:
Shared Package
ML20082G062 List:
References
NUDOCS 9108160187
Download: ML20082G063 (18)
v • d • e


Text

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i

[

t ENCLOSURE 3 V0GTLE ELECTRIC GENERATING PLANT 1 REVISION TO RCS FLOW UNCERTAINTY TECHNICAL SPECIFICATION 3/4.2.5 [

INSTRUCTIONS FOR INCORPORATING The proposed changes should be incorporated into the changes to be implemented i with the initial use of VANTAGE-5 fuel on each of the Vogtle Electric Generating i Plant units. These pages replace the change pages that were attached to letter ,

ELV-02166 dated November 29, 1990, and revised by letter ELV-02661 dated March  :

29, 1991. The pages are listed below and copies of the pages are attached.  !

This includes marked-up and typed pages to be effective as of Vogtle 1 cycle 4 l and Vogtle 2 cycle 3. ,

t WI  :

i 3/4 2-13 D3/4 2-4  ;

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EFFECTIVE AS Of i I-V0GTLE 1 CYCLE 4 t

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-- ~ . , , , . -, . . . . . . . - . _ - , . . . . . . . . - - - , . - , ..

POWER 015'IRIBUT!0N LIMIT 5 " P5IS bd'T b " M U NudiT*2.

FS 3/4.2.5 DNB PARAMETERS E TING CONDITION FOR OP[ RATION ,_

3.2.5 The following DNB related parameters shall be saintained within the limits: 1

a. Roactor Coolant System T- (TI 0412. T10422. T! 0432. T!-0432),

@T%2.'5'r (v77 P) er EN'F (vg

b. Pressurl er Pressure (PFv43A,GM. H un6 & P! 0456A, PI 0457 &

P! 0457A, P! 0458 & P! 0458A), llT?R pns" k

c. Reactor Coolant S FI 0425, FI 0426.ystem Flow FI-0434, (FI-0414, F1-0435 FI 0435

, F10436. F1 0426, El 0444, F1 0414, F1-0445, FI 0446) Missy y

A. ppt ICAe!LITY: H0DE 1. '

w I "

b'Tb ACTION:

(&an "# ~

'3 ff, 000 With any of the above parameters excteding its limit, restore the parameter to within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POW (R to less than 1% of RATED THERHAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Wo. o y.1 aNer escrebbf 10ll RA SURVE!LLANCE REQUIREMENTS ' ## #4 W O 8.I W 4.2.5.1

'\

Reactor Coolant System T,y and Pressuriser Pressura shall be verified to be within theif limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. RCS flow rate shall be monitored for degradation at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. In the event of flow degradation, RC5 flow rate shall be

, determined by precision heat balance within 7 days of detection of j flow degracation.

4.2.5.2 The RCS flow rate indicators shall be subjected to CHANNEL CALIBRATION at each fuel loading and at least once ;;er 18 months.

4.2.5.3 After each fuel leadinbfhe RCS flow rate shall be determined by precision heat balancorptfor to operation above 75% RATED THERMAL

(#f p/ _

POWER The AC5 flow rate shall also be determined by precision heat balaYee at least oncu per 18 months. Within 7 days prior ,to.let-forming the pre dsit..i heat balance floT eensurement, the instrument-I stion used for performing the precision heat balance shall be calibrated. The provisions of 4.0.4 are not applicable for performing

. the precision heat balance flow measurement.

" Limit not applicable during either 4 THERMAL POWER ramp 'In excess 4f % of RATED THEDyAL POWER per minute or a THERMAL POWER step in excess of 10% of RATED THERKAL POWER.

    • Includes a . flow measurement unce.tainty._._

M7. (odiT 4 3.57 (ooiT 2.) )

3/4 cu V0GTLE UNIT 5 -v., 1&2[

42.?

QS Pang ApNcA6LE 'TD vent n owl.Q fglR_,0!$TRIBt/T!0N LIMITS (O ctT]

p5E5 3/4.2.5 DNB PAR W FTER$ (Continued)

The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> periodic surve111ance of these parameters through instrueent readout is sufficient to ensure that the parameters are restored within their limits fo11owing load changes and other expected transient operation. The la month periodic measurement of the RC5 total flow rate is adeausto to detect flow degradation and ensure correlation of the flow indicatfor, channels with sessured flow such that the indicated percent flow will provide sufficient verification of the flow rate degradation on a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> basis. A change in indicated p'ercent flow which is greater than the instnnent channel inaccuracies and parallax errors is an apprcpriate indication of ACS flow degradation.

)

w k, & RC5 +.h! ,L . !: l, ,,,~....

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) >,.,

~ .u. . .A, u ., i

=!!:a:;.:.n u,, s g:;.;;;,. p .* . L., ,r]. u ,,,,n l_ _ vf y/ 7_ t

-lihll: '  :

Sp lf,l d,' ., z-:, ;, , yi .mu. ; e ./  ;

m. 4 ,',d, , . . !w ha  ;  :.W s a  :. ,m r .a . ,,4 i

A. 4~o4.*6:  :: 4 ;l f:.Z, , -

The measurement uncertainty for the RCS total flow is based upor, perforwing a  ;

precision heat balance flow wasurement above 90% MTED THERML POWER and using .

the results to correlate the flow indication channels with the measured flow.

If a precision heat balance flow measurement is perfomed below 90% RATED THERML POWER, the effect on the measurement uncertainty shall be taken into account. Potential fouling of the feedwater venturis which might not be  ;

detected could bias the results from the precision heat balance in a -

non-conservative manner. Therefore, a penalty of 0.1% for undetected feedwater venturi fouling is ine)uded in the measurement uncertainty. Any fouling which might bias the RCS flow rate measurement by more than 0.1% may be detected by

! monitoring and trending various plant perforsance parameters. If detected, '

action shall be taken before performing subsequent precision heat balance flow f

measurements, i.e., either the effect of the fouling shall be quantified and accounted for in the RCS flow rate measurement or, the affected venturis shall be cleaned to eliminate the fouling. The indicated RCS flow value of 393.000 gpm corresponds to an analyttr.a1 value of 382,800 gpa with allowance for measurement nd indication uncertainties. , l l

vD m E UNITS - 1 2 8 3/4 S*W l

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EFFECTIVE AS OF V0GTLE 1 CYCLE 4 l

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[pVER DISTRIBUTION L1MITS 3/4 f.5 DNB PARAMETERS 4

(lH1TINGCONDITIONFOROPERATION 3.2.5 The following DN8-related parametus shall be maintained within the limits:  :

a. Reactor Coolant System T ,' (T! ,1412, TI-0422. TI-0432. TI-0442), i s 592.5'F (Unit 1) or 591*F (Unit 2).  !
b. Pressuriter Pressure (PI-0455A,B&C, Pl.0456 & PI-0456A, ?!-0457 &

PI-0457A, PI 0458 & P!-045BA), 2 2199 psig* (Unit 1) or 2224 psig*

(Unit 2). .

c. Reactor Coolant System F19.: LF1-0414, F1-0415, F1-0416, F1-0424 F1-0425, F1 0426 F1-0434, F > 0435, Fl.0436, FI-0444, F1-0445,  !

FI-0446) 2393,000 gpm" (Unit 1) or 396,198 gpm** (Unit 2). ,

APkt!CABILIT1: H0DE 1.

ACTION:

With any of the above parameters exceeding its limit, restore the parameter to ,

within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than 5% of ,

RATED THERMAL F0WER within the next 4 h9urs.

SURVE1LLANCE pE001REMENTS 4.2.5.1 Reactor Coolant System i and Pressurizer Pressure shall be verified to be within thNr limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. RCS flow rate shall be monitored for degradation at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. In the event of flow degradation, RCS flow rate shall be determined by precision heat balance within ? days of dettetion of flow degradation.

4.2.5.2 The RCS flow rate indicators shall be subjected to CHANNEL CALIBRATION at each fuel loading and at least once per 18 months.

4.2.5.3 After each fuel loading, the RCS flow rate shall be determined by precision heat balance within 7 days after exceeding 90% RATED THERMAL ,

POWER (Unit 1) or prior to operation above 751 RATED THERMAL POWER ,

(Unit 2). The RCS flow rate shall also be determined by precision heat balance at-least once per 18 months. Within 7 days prior to per-forming the precision heat balance flow measurement, the instrument-

! ation used for performing the precision heat balance shall be calibrated. The provisions of 4.0.4 are not applicable for performing .

the precision heat balance flow measurement.

  • Limit not applicable during either a THERMAL POWER ramp in excess of 5% of RATED THERMAL POWrR per minute or a THERMAL POWER step in excess of 10% of RATED THERMAL POWER.

l

    • Includes a 2.7% (Unit 1) or 3.5% (Unit 2) flow measurement uncertainty, V0GTLE UNITS - 1 & 2 3/4 2-13

t I

THIS PAGE APPLICASLE TO UNIT 1 ONLY POWER DISTRIBUTION tlHITS - UNIT I i

BASES 3/4.2.5 DNB PARAMETERS (Continued)

The measurement uncertainty for the RCS total flow is based upon performing a precision heat balance flow measurement above 90% RATED THERMAL POWER and i using the results to correlate the flow indication channels with the measured flow. If a precision heat balance flow measurement is performed below 90% RATED THERMAL POWER, the effect on the measurement uncertainty shall be taken into account. Potential fouling of the feedwater venturis which might not be detected could bias the results from the precision heat balance in a non- i conservative manner. Therefore, a penalty of 0.1% for undetected feedwater venturi fouling is included in the measurement uncertainty. Any fouling which might bias the RCS flow rate measurement greater than 0.1% may be detected by monitoring and trending various plant performance parameters. If detected, action shall be taken before performing subsequent precision heat balance flow measurements, i.e., either the effect of the fouling shall be quantified and accounted for in the RCS flow rate measurement or the affected venturis shall be cleaned to eliminate the fouling. The indicated RCS flow value of 393,000 gpm corresponds to an analytical value of 382,800 gpm with allowance for measurement and indication uncertainties. ,

The 12-hour periodic surveillance of these parameters through instrument readout is sufficient to ensure that the parameters are restored within their limits following load changes and other expected transient operation. The 18 month periodic measurement of the RCS total flow rate is adequate to detect  ;

flow degradation and ensure correlation of the flow indication channels with measured flow such that the indicated percent flow will provide sufficient verification of the flow rate degradation on a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> basis. A change in indicated percent flow which is greater than the instrument channel inaccuracies and parallax errors is an appropriate indication of RCS flow degradation.  !

v i

I V0GTLE UNITS - 1 & 2 B 3/4 2-4

4 0

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I MARKED-UP PAGES EFFECTIVE AS OF V0GTLE 2 CYCLE 3 i

I

(

POWER DISTRIBUT10N L1 HITS

, 3 /4.2. 5 DNB PARAMETERS L1H1 TING CONDITION FOR OPERATION 3.2.5 The following DNB-related parameters shall be maintained within the limits:

a. Reactor Coolant System T._ (11-0412. T1-0422.110432. TI-0442),

s 592.5'F [i"a" U F-59W-(Why l

b. Pressurizer Pressure PI-0455A,BLC,P!-0456&P1-0456A,PI-045g fig 4gPI-0458 & P 045BA),12199 psig*[(U.,E IT W22Wp;.y ,

t u- . , j

c. Reactor Coolant System Flow fFt-0414, F1-0415 F1-0416 F1-0424 F1-0425. F1-0426, F1-0446) 1393,000 gpm** n F1-043M....._M3L_U-Q{te3L
) vi m ,. we (Unii 2 ; f1-0444 Il q).l APPLICAB1t1TY: MODE 1.

RIl0!i:

With any of the above parameters exceeding its limit, restore the parameter to within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THEPML POWER to less than 5% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVElttANCE REOU1REMENTS 4.2.5.1 Reactor Coolant System T,, and Pressurizer Pressure shall be vertfied to be within their limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. RCS flow rate shall be monitored for degradation at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. In the event of flow degradation, RCS flow rate shall be determined by pecision heat balance within 7 days of detection of flow degradation.

t 4.2.5.2 The RCS flow rate indicators shall be subje:ted to CHANNEL CAllBRATION at each fuel loading and at least once per 18 months.

4.2.5,3 After each fuel loading, the RCS flow rate shall be determined by precision heat balance within 7 days after exceeding 90% RATED THERMAL POWER,(Ur.'t :) :r prbr t: :p:r:ti:r. :b:ve 7W-AATE9-THEWL-80WER-

-(Ur!! 21 The RCS flow rate shall also be determined by precision heat balance at least once per 18 months. Within 7 days prior to per-forming the precision heat balance flow measurement, the instrument-ation used for performing the precision heat balance shall be calibrated. The provisions of 4.0.4 are not applicable for performing l' the precision heat balance flow measurement.

  • Limit not applicable during either a THERMAL POWER ramp ja excess of 5% of RATED THERMAL POWER per minute or a THERMAL POWER step in excess of 10% of RATED THEPML POWER.

l ** Includes a 2.7%((Ucat n er 3.54 iUnit idflowmeasurementuncertainty.

V0GTLE UNITS - 1 & 2 3/4 2-13

  • -T"!! Pf0: ATTLICAGi! TO Wii ! 0"LY-POWER DISTRIBUTION tlMITS - W'T- P ALES.

3/4.f.S DNBPARAMETERS(Continued)

The measurement uncertainty for the RCS total flow is based upon performing a precision heat balance flow measurement above 90% RATED THERMAt. POWER and using the results to correlate the flow indication channels with the measured flow, If a precision heat balance flow measurement is performed below 90% RATED THERMAL POWER, the effect en the measurement uncertainty shall be taken into

-account. Potential fouling of the feedwater venturis which might not be detected could bias the results from the precision heat balance in a non-conservative manner. Therefore, a penalty of 0.1% for-undetected feedwater venturi fouling is included in the measurement uncertainty. Any fouling which might bias the RCS. flow rate measurement greater than 0.1% may be detected by monitoring and trending various plant performance parameters. if detected.-

action shall be taken before performing subsequent precision heat balance flow measurements, i.e., either the effect of the touling shall be quantified and accounted for in the RCS flow rate measurement or the affected venturis shall be cleaned to eliminate the fouling. The indicated RCS flow value of 393,000 gpm corresponds to an analytical value of 382.800 gpm with allowance for measurement and indication uncertainties.

The 12-hour periodic surveillance of these parameters through instrument readout is sufficient to ensure that the parameters are restored within their  :

limits following. load changes and other expected transient operation. The l i

18 month periodic measurement of the RCS total flow rate is adequate to detect flow degradation and ensure correlation of the flow indication channels with  :

measured flow such that the indicated percent flow will provide sufficient  !

verification of the flow rate degradation on a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> b& sis. A change in  !

l

' indicated-percent flow which is greater than the instrument channel inaccuracies and parallax errors is an appropriate indication of RCS flow degradation.  :

)

I l

V0GTLE UNITS - 1 & 2 B3/42-4

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TYPED PAGES EFFECTIVE AS Of V0GTLE 2 CYCLE 3 1

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. POWER DISTRIBUTION LlHITS  :

3/4.2.5 DNB PARAMETERS LIMITING CONDITION FOR OPERATION  !

I 3.2.5 The following DNB-related parameters shall be maintained within the limits: ,

a. Reactor Coolant System T , (11-0412, T1-0422. T1-0432, T1-0442), i s $92.5'F. l ,
b. Pressurizer Pressure (PI-0455A,B&C, PI-0456 & PI-0456A, PI-0457 &

PI-0457A, PI-0458 & PI-0458A), 2 2199 Ps19*.  !

l

c. Reactor Coolant System Flote (f!-0414, F1-0415 FI-0416 F1-0424, r F1-0425. F1-0426 F1 0434, .*l-0435, F1-0436, F1-0444, F1 0445,  ;

FI-0446) 1393,000 9pm".  ;

l APPLICABillTY: MODE 1.

Ell @

f With any of the above parameters exceeding its limit, restore the Nrameter to within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than 5% of r RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. -

SURVEllLANCE RE0VIREMENT5 i

4.2.5.1 Reactor Coolant System T and Pressurizer Pressure shall be l verifiedtobewithinthUrlimitsatleastonceper12 hours. RCS flow rate shall be monitored for degradation at least once per [.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, in the event of flow degradation, RCS flow rate shall be  !

determined by precision heat balance within 7 days of detection of flow degradation, j 4.2.5.2 The RCS flow rate indicators shall be subjected to CHANNEL f CALIBRATION at each fuel loading and at least once per 18 months.

4.2.5.3 After each fuel loading, the RCS flow rate shall be determined by precision heat balance within 7 days after exceeding 90% RATED THERMAL POWER. The RCS flow rate shall also be determined by precision heat balance at least once per 18 months. Within 7 days prior to per- l '

forming the precision heat balance flow measurement, the instrument-ation used for performing the precision heat balance shall be t l calibrated. The provisions of 4.0.4 are not applicable for performing i the precision heat balance flow measurement. '

i

  • Limit not applicable during either a THERMAL POWER ramp in excess of 5% of [

l RATED THERMAL POWER per minute or t, THERMAL POWER step in excess of 10% of RATED THERMAL POWER.

" Includes a 2.7% flow measurement uncertainty.

I THIS PAGE BECOMES APPLICABLE FOLLOWING SHUT 00WN FROM UNIT 2 CYCLE 2 OPERATION.  !

V0GTLE UNITS - 1 & 2 3/4 2-13

. . , e l

o POWER DISTRIBUTION LIMITS i 4

BASES 3/4.2.5 DNB PARAMETERS (Continued)

The measurement uncertainty for the RCS total flow is based upon performing a precision heat balance flow measurement above 90% RATED THERMAL POWER and using the results to correlate the flow indication channels with the measured i flow. If a precision heat balance flow measurement is performed below 90% RATED t

THERMAL POWER, the effect on the measurement uncertainty shall be taken into account. Potential fouling of the feedwater venturis which might not be detected could bias the results from the precision heat balance in a non-conservative manner. Therefore, a penalty of 0.1% for undetected feedwater venturi fouling is included in the measurement uncertainty. Any fouling which l micht bias the RCS flow rate measurement greater than 0.1% may be detected ty  ;

monitoring and trending various plant performance parameters. If detected,  ;

action shall be taken before performing subsequent precision heat balance flow ,

measurements, i.e., eit6r the effect of the fouling shall be quantified and accounted for in the RCS flow rate measurement or the affected venturis shall be cleaned to climinate the fouling. The indicated RCS flow value of 393,000 gpm corresponds to an analytical value of 382,800 gpm with allowance for measurement and indication uncertainties.

The 12-hour periodic surveillance of these parameters through instrument readout is sufficient to ensure that the parameters are restored within their limits f,11owing load changes and other expected transient operation. The 18 month periodic measurement of the RCS total flow rate is adequate to detect flow degradation and ensure correlation of the flow indication channels with measured flow such that the indicated percent flow will provide sufficient verification of the flow rate degradation on a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> basis. A change in indicated percent flow which is greater than the instrument channel inaccuracies and parallax errors is an appropriate indication of RCS flow degradation.

l l

THIS PAGE BECOMES APPLICABLE FOLLOWING SHUTDOWN FROM UNIT 2 CYCLE 2 OPERATION.

V0GTLE UNITS - 1 & 2 B 3/4 2-4

= ._

n.% ..

. i. , -

ENCLOSUkE 4 V0GTLE ELECTRIC GENERATING PLANT REVISION TO RCS FLOW UNCERTAINTY TECHNICAL SPECIFICATION 3/4.2.S ERRATA SHEETS Attached are errata sheets for page 6 of WCAPs-12460 and 12461 (proprietary and non~;roprietary) entitled " Westinghouse Revised Thermal Design Procedure Ins troaentation Uncertainty Methodolta: for Georgia Power Vogtle 1 and 2 Nuclear Power Station (for RTD Bypass Loops)" and WCAPs-12462 and 12463 (proprietary and non-proprietary) entitled " Westinghouse Revised Thermal Design Procedure Instrumentation Uncertainty Methodology for Georgia Power Vogtle 1 and 2 Nuclear Power Station (for RTD Bypass Loop Elimination)."

It should be noted that page 8 of each of these reports is identical except for the proorietary notice at the top of the page for the pages used in the proprietary WCAPs.

E4-1

WCAP-12460 4 WESTINGHOUSE PROPRIETARY CLASS 2

.. 3. RCS FLOW RTDP and some plant Technical Specifications require an RCS flow measurement with a high degree of accuracy. - It is assumed for this-error analysis that _the flow measurement is performed within thirty days of calibrating the measurement instrumentation. 'Therefore, except where necessary due to sensor location, drift effects are not' included.- It is also assumed that the calorimetric flow measurement ,

is performed at the beginning of a cycle, i.e., no allowances have l

been made for Feedwater venturi fouling, and above 90% RTP. - ;j i

c The flow measurement is performed by determining the Steam Generator  !

L thermal output (corrected for the RCP heat' input and the loop's share -f of primary system heat -losses)_ and the enthalpy rise (Delta-h)'of- the j

primary coolant. Assuming:that~ the primary and secondary sides are l

'in equilibrium, the RCS total vessel flow is the sum of the individual primary loop flows,1.e'.,

p l

]

Eq. 4- i WRCS = N(W L ).-

.t The individual primary loop volumetric ' lows.are determined by f correcting-the thermal output of the-Steam Generator for Steam 1 Generator blowdown (if not secured).--subtracting the RCP. heat addition adding the loop's share of the-primtry side system losses,

' dividing by the primary side enthalpy rise _a'nd multiplying'by the Cold Leg specific volume. The equation for this-calculation is:  ;

-t l

WL = fA)(OSC -h dL/N)H Vg l Eq. 5- ]

(hH-h)- C 3

t where;

= Loop flow (9pm)

WL

= 0.1247 gpm/(ft3 /hr)  !

i A -_

Qg - Steam Generator thermal output (Etu/hr)  !

3 '

Qp

-- RCP heat addition-(Btu /hr) l I - Primary system net. heat losses-(Btu /hr) I Qt 3

= Specific volume of the Cold leg at TC (ft /lb) {

VC-i i

,a-;i._,,,-.----_=m-_--- . . - - - , , . . . - . . - ~ , , - _ . -

,,_~._~.m.., ._..__..,,m,. - _ - , - - - . , , . . _ , - - . . - -

, p ' ,:- . ' s

3. RCS FLOW .

RTDP_ and some p'. ant Technical Specifications require an RCS flow measurement with a high degree of accuracy. It is assumed for this error analysis that the flow measurement is performed within thirty

' days of calibrating the measurement instrumentation. Therefore, except where necessary due to sensor location, drift effects are not included. -It is also assumed tha.-the calorimetric flow measurement is performed at the beginning of a cycle, i.e., no allowances have been made for Feedwater venturi fouling, and above 90% RTP.

The flow. measurement is performed by determining the Steam Generator thermal output (correctedifor the RCP heat input and the loop's share of--primary system heat losses) and-the enthalpy rise (Delta-h) of the primary coolant. Assuming that the primary and secondary _ sides are in equilibrium, the RCS total vessel flow is_ the sum of the indivikal primary loop flows, i.e.,

Eq._4 WRCS - N(W L ).

The individual primary loop volumetric flows are determined by correcting the thermal output of the Steam Generator for Steam Generator blowdown (if not secured), subtracting the RCP heat additien, adding the loop's share of the primary side system losses, dividing by the primary side enthalpy rise and multiplying by the

- Cold Leg specific volume. The equation for this calcula. tion is:

WL - ( AMO SC -OP d /N)H L Vcl (hg-h) Eq. 5 C

where; Wt

- Loop f 5 (gpm)

A - 0.1247 gpm/(ft3 /hr)

Qg - Steam Generator thermal output (Btu /hr)

S Qp

- RCP heat addition (Btu /hr)

- Primary system net heat losses (Btu /hr) l Qt VC

= Specific volume of the Cold Leg at TC (ft3 /lb) 1 L

L - -

~, , - . - - - - -

.p (: . o WCAP-12462

. WESTINGHOUSE PROPRIETARY CLASS 2 3.- RCS FLOW RTDP and some-plant Technical Specifications require an RCS flow measurement with a high degree of accuracy. It is assumed for this error analysis that the flow measurement is performed within thirty days of calibrating the measurement instrumentation. Therefore, except where necessary due to sensor location drift effects are not included. It is also assumed that the calorimetric flow measurement is performed at the beginning of a cycle, i.e., no allowances have been made for Feedwater venturi fouling, and above 90% RTP.

The flow measurement is performed by determin'ing the Steam Generator thermal . output _ (corrected for the RCP heat input and the loop's share of primary system heat losses) and the enthalpy rise-(Delta-h) of the primary coolant. Assuming that the primary and secondary sides are in equilibrium, the RCS total vessel flow is the sum of the individual- primary loop flows, i.e.,

Eq. 4 WRCS - N(W L ).

The individual primary loop volumetric flows are determined by correcting the thermal output of the Steam Generator for Steam Generator-blowdown (if not secured),-subtracting the RCP heat addition, adding the loop's share of the primary side system. losses, E dividing by the primary side enthalpy rise and multiplying by the Cold Leg specific volume. The equation for this calculation is:

L L

WL -- 1&)lDSC - Op M t/N)HVcl Eq. 5-(hH-h) C l where; Loop flow (gpm)

~

WL A - 0.1247 gpm/(ft3 /hr)

Q3g- -- Steam Generator _ thermal output (Btu /hr)

Qp - RCPheataddition(Btu /hr)

Qt

- Primarysystemnetheatlosses(Btu /hr)

VC

- Specific volume of the Cold Leg at TC (ft3 /lb)

O l' * -  ;

WCAP-12863 s,

3;; RCS FLOW .

RTDP and some plant Technical-Specifications require an RCS flow . _

measurement with'a'high degree of accuracy. It~is assumed for this error analysis _that the flow measurement is performed within thirty days of calibrating the measurement instrumentation. Therefore,

'except where necessary-due to sensor location, drift effects are not included. lit is also assumed that the calorimetric. flow measurement is performed at the beginning of_ a cycle, i.e., no allowances have been made for-Feedwater-venturi fouling, and above 90% RTP.

The flow measurement is performed by determining the Steam Generator

- thermal output'(corrected for the RCP heat input and the loop's share -;

of primary system he'at. losses) and the enthalpy rise (Delta-h) of the-

. primary coolant. Assuming that the primary and secondary sides _are in equilibrium, the RCS total- vessel- flow is the sum of the individual primary loop flows, i.e., j Eq. 4~

WRCS - N(W L ).

The individual primary loop volumetr_ic flows .are determined by I correcting the thermal output of the Steam Generator for Steam Generator blowdown ~(if- not- secure'), subtracting the RCP heat addition, adding the loop's: share of the primary side: system losses,  ;

' dividing by the-primary side enthalpy. rise and _ multiplying by the- ,

Cold Leg specific volume. - Theiequation for-this calculation is:-

Wt-(AMOSC--Op_fjl/N W Vgl L Eq. 5 (hH_-h)=

C where;-

W- - - Loop flow (gpm)

L 3

0.1247gpm/(ft/hr)

A .-

Qg_ = Steam Generator thermal output (Btu /hr) 3 Qp:

- RCP heat addition (Btu /hr)

-Q- -- -Primary system net heat losses (8tu/hr) t 3

V_ C

= Specific volume of the Cold Leg at TC (ft /lb) 8-t

.a---me#..-.i

- _-, ...,,,,,,,,m.,_, _ , . . , . , , _ , , , , , , ,

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