ML20104A839

Calculation Fc 05428, Safety Injection Valves SI-207/SI-208 Full Open Stroke Data Analysis for SP-SI-7 Apr 1990 Performance

ML20104A839
Person / Time
Site:	Fort Calhoun
Issue date:	05/31/1992
From:	OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20104A825	List: ML20104A822 ML20104A829 ML20104A839
References
FC-05428, FC-5428, NUDOCS 9209140178
Download: ML20104A839 (97)

Text

Attachment LIC-92-278R 4

e ATTACHMENT 3 Calculation to Analyze the Test _ Methodology and Determine f

Acceptance Criteria for Flow Testing of Safety Injection Tank Check Valves (Calculation FC 05428, Revision 1) t

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9209140178 920903

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Safety injection Valves SI-207/SI-208 O MR No.

NA Full Open Stroke Data Analysis for 0

A SP-SI-7 April 1990 Performance O ECN NO.

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SUMMARY

SHEET Rev.No.

d OBJECTIVE The purpose of this calculation is to determine if the April 2,1990 performance of Special Procedure SP-SI-7, Safety Injection TmA SI-6C Dump Test, successfully accomplished simulated full open stroke in accordance with the Generic Letter 89 04 definition (see page 7) of Safety Injection check valves SI-207 and SI-208.

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SUMMARY

SHEET Rev No.- 6 MEBODS The data used in this calculation was produced by the April 2,1990 performance of Special Procedure SP-SI-7, Safety injection Tank SI 6C Dump Test. The data are two strip chsrt recuidings, in voltage cales, of the Safety Injection tank levels and pressures during the test. The level voltages are converted to the form of tank levels in feet and gallons and the pressure voltages as tank pressure in pounds per square inch gage (psig). The main equation this calculation uses is an equation of flow:

Q = C v N A p ( 62.4 / p ) '

where Q = flow This equation can Cv = flow coefficient be found in Crane A p = change in pressure Flow of Fluids, p = fluid density 1985, page 2-10.

This equation will allow us to calculate a C v using the test data. This C v will then be compared to the C v produced from the values used in tLe LOCA analysis.

If the test produced C v is equal to or greater then the LOCA Analysis C v, then valves SI 207 and SI 208 were full open stroked.

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SHEET Rev.No.

d ASSUMPTIONS The major assumptions of this calculation are the following:

1.

The Gow coefficient, C v, for the same system boundaries and components is constant under varying operational conditions. ( The Gow coefficient is a factor of system geometry including diameter, friction factor and equivalent lengths of piping, not operational parameters.)

2.

The back pressure induced from the 20 feet of water above the reactor vessel flange is assumed to be a constant because the level change of g

about 4 inches in the refueling cavity resulting from the S I T dump is negligible.

3.

Although the C v values may vary due to changing system configuration (ie. variations of the open / closed position of the motor operated valve HCV-2954) the C v value determined when HCV-2954 is fully open is an acceptable standard because it is representative of the flow configuration during an accident.

4.

It is reasonable to expect the Dow to increase / decrease in a steady fashion, not as a step function. The selection of data at one second intervals only produces this illusion. Therefore, the optimum best fit curve will be one based on interpolated or " rounded" flow values which use actual flows as a basis. Rounded flow values are the approximate average of any given consecutive calculated flows.

5.

The density of the SIT water is essentially the same in the test condition as in the accident condition. As such, the density value cancels out.

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SUMMARY

SHEET Rev No.-

d INPUTS / REFERENCES REF.'

t NO.

i l

SP-SI 7, Safety Injection Tank SI 6C Dump Test of Ap-a 2,1990, l

for the conversion factors of( 3.6 feet in tank / volt ) and ( 531.15 gallons in tank / foot) and data.

Flow of Fluids, Crane,1985 edition.

2.

Fort Calhoun Station U S A R, section 14.15.

3 Safety Injection Tank drawing D-7495 for tank dimensions.

q l

RCS elevations vs. LI 106 from page TDB-III-20 of the Technical l

Data Book for the reactor vessel flange elevation.

5 Design Basis Document SOBO-SI-LP-133, Rev. 0 6

l FC-05280, Dept 353, Determination of Safety Injection Tank St.6C I

\\

Pressure For Performance of Special Pmcedure SP-SI 7.

b Generic Letter 89-04, Attachment 1, Item 1, Full Flow Testing of g

Check Valves for definition of Full Open Stroke:

I

• A check valve's full stroke to the open position may be verified by passing the maximum required accident condition flow through the valve. This is considered by the staff as an l

acceptable full stroke."

Experimental Methods for Engineers. J. P. Holman, Fourth l

Edition,1984, McGraw-Hill, Inc.

Record of Conversation, dated 27 April 1990, between Bill Weber, t

l OPPD, and Al Newcomer, ABB Impell Corporation. PED-5$E*-io-0435 5.

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SUMMARY

SHEET Rev.No.

d CONCLUSIONS This calculation determines if the Safety Injection check valves SI-207 and SI-208 perform their design basis function by full-open stroking under the design basis conditions of a single intact loop L0 DECLG break.

Data analysis from SP-SI-7, April 2,1990, produces a C v value of 1258 i 3.4% for the period of full open valve position. The comparable Cv produced from valuea within the LOCA analysis is 1132; a minimum safety margin of 7.4 % (see page 14 for calculation).

Therefore, SI-207 and SI-208 will full-open stroke under design basis accident condition flow. This analysis has also shown that Special Procedure SP-SI-7, Safety injection Tank St.6C Du:np Test is capable of i

proving the full flow capacity of the Safety Injection tank discharge check valves. Based on the above safety margin, all subsequent Safety Injection tank dump tests should be able to prove tank discharge check valve full flow capacity.

This calculation format may be used for subsequent dumps of the remaining SI tanks; providing test-specific numbers are substituted.

Thus allowing for variations in system geometry, starting and ending pressures / levels, recorder settings, etc.

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Symbol Definitions

'n:

time @ n seconds T n+1:

time @ n+1 seconds Lv:

tank levelin volts : as recorded

t. __

L f:

tank levelin feet t_-

Lg:

tank levelin gallons Qc:

calculated flow in gpm Q r:

rounded flow in gpm (for graph smoothing) 222 P ny :

nitrogen pressure in volts l

P np :

nitrogen pressure in psig

~

Ph:

tank variable head pressure 22 1

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total tank pressure in psig Pb:

back pressure from 20' water head Cv:

flow coefficient -

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Level Coaversion Factor

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The level chart recorder was calibrated to a span of 0 - 173 inches corresponding to a voltage range of 1 - 5 volts. Therefore, the level conversion factor = ( 173 " - 0 " ) / [( 5 volts - 1 volt )( 12"/ft ) ]

= 3.60 feet in tank / volt

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And, from Reference 1, Gallons in tank = ( feet in tank )( 531.15 gals /ft )

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Pressure Conversion Factor

~--

The pressure chart recorder was calibrated to a span of 0 - 150.psig 2 2:

corresponding to a voltage range of 1 - 3 volts. Therefore, the pressure conversion factor = ( 150 psig - O psig) / ( 3 volts - 1 volt )

75 psig / volt

=

Samnie Calculation

_~22:

For example purposes, use data when HCV-2954 is fully open at T=52 2

and 53 seconds.

Lv33 = 2.50 volts

~~"

Lf33 = (2.50 volts-1 volt ) ( 3.60 ft in tank / volt ) = 5.40 feet 2

2:

L g 33 = ( 5.40 feet ) ( 531.15 gal / ft ) = 2868.21 gal 22 Lv 52 = 2.54 volts Lfs2 = (2.54 volts - 1 volt ) ( 3.60 ft in tank / volt ) = 5.54 feet

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L gs2 =( 5.54 feet ) ( 531.15 gal / ft ) = 2942.57 gal

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=[ ( 2942.57 - 2868.21 gal ) / ( 53 52 sec ) ] ( 60 sec / min )

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= 4461.60 Pm E

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= 16.50 psig + 2.34 psig +2.42 psig elev dirrrmm me, g

= 21.26 psig flange

~

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P b =( 20 feet ) (.434 psig / ft ) = 8.68 psig 2:

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AP sa = P T 33 - P b = 21.26 psig - 8.68 = 12.58 psig Q 33 = C v Y A P(62.4 )/ p where p = 62.4 for water 2:

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Cy=Q

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D C v = 1258 1

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Uncertaintv Analvsis Based on the last performed calibration procedure for LT 2944X ( 12/26/88 ), the 2

maximum % uncertainty from the level transmitter is:

22

~

~

2.4 % = [ ( 10.00 9.76 )/10.00 )

• 100 where 10.00 is the desired accuracy

~

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and 9.76 was the As Left accuracy.

Based on the last performed calibration procedure for FT-2941 ( 12/12/88 ), the maximum % uncertainty from the pressure transmitter is:

Z:

2:2 0.5 % = [ ( 10.00 - 9.95 ) /10.00 ]

• 100 where 10.00 is the desired accuraey 2:2 and 9.95 was the As Left accuracy.

The overall uncertainty in Cv is a function of the level and pressure transmitter 22:

uncertainty percentages, the recorded values for the times ofinterest, and the Cy equation's partial derivative coefficients with respect to each of the variables.

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[Ilau.rramTp d'tY+h*'twb"I,'t

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t

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i where A, B and C are the partial derivative coefficients.

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Cv Il%'L%f750%+gg+E-iS>)-

h j

would produce coefficients of 1 or less because we do not have any terms wit'.

7 I

l powers greater than one. So conservatively, we will assume all three coefficients E

l equal to one (1).

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LOCA A n a l va i n Recuinment

==-

f The effective flow area ( A ) and representative resistance coefficient ( K ) in a

~~

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LOCA condition as used in the accident analysis are 0.5592 sq. ft.and 7.34 f

i respectively ( see ref.10 ). Equation 2 6, t eference 2, gives us:

~'~~~

Ov wr= 29.9

• d 2 / Q K= 29.9 f 05592 ft2 M 144 in2]_{t21f4U g 1 f 222.~

b

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• ~

[

I Cy tocA = 1131.5

~

Conservatively rounding up.

~

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222.'

CVIDCA = 1132 l

Minimum Rafetv Manrin

[

i Minimum Safety Margin =

(( ( C yi

) 3.4%( C v

) ) / ( Cv s

ux:A

• 1

)

f 1258. 034 (1258 ))/ (1132 h

.1.

i

=-

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=7.4 %

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Calc Preparation, Review and Approval PED-QP 3.5 Page 1 of 2 CALCULATION NUMBER Reviewer's Checklist-Calculations Fc c54 LV IfJi.

11 2 fil&

1.

Is Calculation Cover Sheet attached and l

completed, as required,to the calculation?

K 2.

Is the calculation objective stated? Was this achievedt X

3.

Are inputs correctly selected and incor-porated into the-analysis?

X 4.

Have inputs and/or assumption: t.hich require confirmation at a later data, been identified on the Calculation Cover Sheet and in the calculation body?

X 5.

Are the applicable codes, standards, regulatory requirements, and other raferences including issue and addenda identified such that they are traceable to source document?

X 6.

Was an a)propriate calculation method used?

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7.

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Is the calculation legible and suitable for microfilming?

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PED-QP-3.36 Rev. 1

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Cal: Preparation, Review and Approval PED-QP-3.5 Page 2 of 2 CALCULATION NLH8ER i

Reviewer's Checklist-Calculations Fe o64 ET

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WA 12.

Are all blocks on the Calculation Cover Sheet addressed correctly?

X 13.

Have Forms PED-QP-3.2, 3, 4 and 5 been used and correctly completsd7 X

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If the calculation has_been pre >ared to l

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new calculation?.

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REVIEWEk C0!NENTS:

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l-lWviewer f~

Date gigg 4.jo.go l

PED-QP-3.37l^

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1.

Does the com) uter run have title, date, and page numaer and alphanumeric program number on every sheet?

Y 2.

Is the listing of computer input provided?

X 3.

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X 4.

Is the computer software validated and ver1fied?

X If not 4a.

Is the computer code developed for one-time-use on a programable calculator or micro-computer?

X 4b.

If yes, has a functional description of the program, identification of the equations, identificationofthecode(title,--revision, manufacturer),identificationofthesoftware and brief user's instructions been provided in the calculation?

X 5.

If the computer software has been loaded on an in-house computer, have the changes made by OPPDbeenproperlyreviewed(verifiedand-validated)fortheirimpactontheaccuracyof the code and have been found satisfactory, or t

is the in-house computer software validated?

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Is the computer program appropriate to do the intended calculation?

X l

. PED-QP-3.38.

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Fc o G 4 2 5(

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Was an alternate calculation or model utilized to verify results? If so, is it attached to this calculation?

Y j

8.

Is the modelino correct in terms of geometry input and initial conditions?

X 9.

Are the results reasonable when compared to the inputs?

-N i

REVIEWER COMMENTS:

l-(

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RWfewer

/

Datecyr)4-3.g c

k PED-QP-3.39:

Ran't

Te. v 2,5 [r G b i

Calc Preparation, Review and Approval 4

PED-QP-3.7 Page 1 of 1 CALCULATION NUMBER Independent Reviewer's Checklist - Calculations F~C 09-l 2N El E0.

Ifa 1.

Are the calculation methods accurate-and appropriate?

y2.

Are input data sufficiently detailed?

3.

Are the calculation assumptions rennnable?

/

4.

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/

used?

I 5.

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6.

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been satisfied?

i 7.

Are the results reasonable and do they resolve the calculation objective?

y 8.

If an alternata calculation was used to verif the adequac of the analysis, is it y

attet ed to the ca culation?

9.

If qualification testing was used to verify the adequacy of the analysis, has it been docu:nented using a retrievable source, or

/

attached to the calculation?

V 10.

Are calculations involving Technical Specification values and associated margins of safety identified?

V INDEPENDENT REVIEWER C ENTS:

b{ snct re cedi Lvcth en k hg,Me.g[4Dcow A occm cr

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FED-QP-3.40

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f) 25A dl' Calc Preparation Review and Approval PED-QP-3.5 Page 1 of 2 CALCULATION NUMBER Reviewer's Checklist-Calculations f,

FC 05429 RevI El 11 9.

Ii/A 1.

Is Calculation Cover Sheet attached and completed, as required,to the calculation?

Y 2.

Is the calculation objective stated? Was this achieved?

N 3.

Are inputs correctly selected and incor-porated into the analysis?

Y 4.

Have inputs and/or assumptions which require confirmation at a later data, been identified on the Calculation Cov6e Sheet and in the calculation body?

Y 5.

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Y 6.

Was an a)

Was the )propriate calculation method used?

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X 7.

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Y 0.

Are the calculations free of arithmetic errors?

X 9.

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X 10.

Is the conclusion stated?

X 11.

Is the calculation legible and suitable for microfilming?

/

PED-QP-3.36'

P 256 ML i

Calc Preparation, Review and Approval PED-QN3.5 Page 2 of 2 CALCULATIM WUMBER Reviewer's Checklist-Calculations FC 05421 Rev I Xfl 52 Elh 12.

Are all blocks on the Calculation Cover Sheet addressed correctly?

N 13.

Have Forms PED-QP-3.2, 3, 4 and 5 been used and correctly completed?

N 14.

If the calculation has been prepared to supersede another calculation, has all the valid information been transferred in the new calculation?

X l

REVIEWER COMMENTS:

j 90 i3E i

/2//3/92

. r721 r

Reviewer

//

}

Dat4 PED-QP-3.37' rm~A

p sc. of O Calc Preparation, Review and Approval PED-QP-3.7 Page 1 of 1 CALCULATION NUMBER Independent Reviewer's Checklist - Calculations FC oS429 %I m

n Ela 1.

Are the calculation methods accurate

/

and appropriate?

l/

2.

Are input data sufficiently detailed?

t/

3.

Are the calculation assumptions reasonable?

/

4.

Has the basis for engineering judgement been included in the calculation, when used?

5.

Is the calculation documented t.ufficiently such that the analysis is understandable te

/

someone competent in the discipline

/

without recourse to the Preparer?

6.

Have the design interface requirements

/

been satisfied?

v 7.

t.re the results reasonable and do they

/

resolve the calculation objective?

V __

8.

If an alternate calculation was used to verify the adequacy of the analysis, is it l

attached to the calculation?

/

9.

If qualification testing was used to verify the adequacy of the analysis, has it been documented using a retrievable source, or attached to the calculation?

y 10.

Are calculations involving Technical Specification values and associated margins of safety identified?

L7 INDEPENDENT REVIEWER C0!HENTS:

"n h/

/

1

'Ipdependent Reviewer Date PED-QP-3.40 w

l Fc w %, ev

e. u l

EXPERIMENTAL 1

METHODS FOR i

ENGINEERS i

l Fourth Edition i

i 6

l' l

J. P. Iloimau Profenor of.\\lecharucal Engrnecting Southern Aleshodist l'ntrersitr In collaboration with W. J. Gajda, Jr.

Anxnare Proh utw of Elecirwal Entwrong lan.ersus of Ao:rr Darne l

l McGraw liill Book Company New York St. Loua San Franciwo Auckland Bogote liarnburg Johannesburg London M adnd Mexico Montreal New Delhi Panarna Parn Slo Paulo Smgapnie Sydney TsLyo Toronto

nn.s "N4I ssis & MPik!WNT4t_ t>4 ra $3

.d sanatisms 1. subsequent vttions we shat!

g experimental uncertainties in a more precise If this relatum a apphed to the eledne power relation of the pressous capected uncertainty is 2.83 percent instead of 4fM percent.

Esample 3-1 The resistance of a certain size of copper wire is given as 3-4 UNCERTAINTY ANALYSIS R = R,[I + 2F - 200 A more precise method of estimating uncertainty in experimental results has been where R = 6 O i 0.3 percent is the resistance at 20'C. e = 00(M"C-percent ts the temperature coefracient of resistance, and the temperature of presented by Kline and McClintock [IJ. The method is based on a careful wire ts T = 30 specification of the uncertainties in the various primary experimental measure-1"C. Calculate the resistance of :he wire and its uncertainty.

ments. For example, a certain pressure reading r.iight be expressed as Sotinm The nommal resistance is 2

p = 100 kN/m i I kN/m2 R = (6)[f + 10004)i30 - 2th] = 6.24 o When the plus or minus notation is used to designate the uncertainty, the person Ihe "ncertainty in :his salue is calculated by applying Eq (3-2). The s making this designation is stating the degree of accuracy with which he or she terms are:

behetes the measurement has been made. We may note that this specification is in itself uncertain became the experimenter is naturally uncertain about the gg accuracy of these measurements.

7* = 1 + a(7 - 20l = 1 + (OMM(30 - 20). Im If a very careful calibration of an instrument has been performed recently.

PR with standards of very high precision, then the experimentalist will be justified in g = Rd T - 20) = 161(30 - 20) - 60 assigning a much fower uncertainty to measurements than if they were performed with a gage or instrument of unknown cabbration history.

UN To add a further specifreation of the uncertainty of a particular measurement.

2T = R.a = (6)to.0(M) = 0 024 Kime and McClintock propose that the experimenter specify certain odds for the.

uncertainty. The aoove equation for pressure might thus be written a = (640.003) 0.018 O w

2 2

p = 100 kN/m 1 I kN/m (20 to I)

01) = 4 x 10 - C ~ '

=

in other words, the experimeter is wi!!ing to bet with 20 to I odds that the

• ' ~

pressure measurement is within 11 kN/m. It is important to note that the Thus the uncertainty in the resistance ss 2

ipecification of such odd-can onIr be made bs the experimenter based on the total laboratory experience.

a"

+

4 x 10 *

'0 024PO f]"2 Suppose a set of.menurements is made and the uncertainty in each measure.

- 0.0305 0 or 0.49%

ment may be expressed with the same odds. These measurements are then used to calculate some desired result of the experiments. We wish to estimate the uncer-Particular notice should be given to the fact that the uncertainty fro tainty in the calculated result on the basis of the uncertainties in the primary m the result w, predicted t y Eq. (3-2) depends on the squares of the un measurements. The result R is a gisen function of the independent variables in the mdependent vanables w.. Th:s means that if the uncertainty in one x.x2.x... x.. Thus, ab!c is sigmficantly larger than the uncertainties in the other vanab i

3 nactor of 5 or 10. then it is the largest uncertainty that predominates and the

=

42223

+ X.

others may probab y be neglected.

~

1 et w, be the uncertainty in the result and w. w3.. w, be the uncertainties ir, To illustrate, suppose there are three variables with a product of s the independent variables. If the uncertainties in the independent varisbles are all 4

and uncertainty [(PR/ds)w,] of magnitude 1. and one variable with a mag given with the same odds, then the uncertainty in the result having these odds is of s.The uncertainty in the result would be gisen in Ref. [1] as gr, g 2, g 2, g jii' = [ = 5.29 The importance of this brief remark concernir g the relatise magmtude of u w, = _ dx,.w, dx dx.

/_

+

w

+- +

w (3-2) tamtrs is evident when one considers the design of an expenment procuremen

[aA$} N [ M */ C >

F I

$2 exrtanwNtas m n*cs psa asusuas mnus m o m anwmr a pa s a 53 of instrumentation, etc. Very httle is gair.ed by trying to reduce the "sma l" r

and me apply Eg (3-21 to give uncertamties. Because 4 the square propagation it is the "large" ones that predominate, and any improvement in the oserall experimental resuit mu;t be

[2E 3hEf,(2 g

achieved by improving the instrumentation or experimental technique connected 3R, 2

\\ R/

with these relathcly large uncertamties. In the examples and problems that follow, both in this chapter and throughout the book. the reader should always Dniding by P = E*/R pres note the relative effect of uncertainties in primary measurements on the final 2

4 - + -gr i,z result.

IN

-=#

In Sec. 2-11 (Tabic 2-7) the reader was cautioned to examine possible experi-mental errors before the experiment is conducted. Equation (3-21 may be used Insertmg the numencal v.stees for uncertainty.

very efTectively for such analysis, as me shall see in the sections and chapters that follow. A further word of caution may be added here_ lt is c:iually as utifortunate w,

,3,.2

• 3,

to overestimate uncertainty as to underestim-ate it. An underestimate geses fahe 7*

secunty, while an overestimate may make one discard important re*uits, miss a real effect, or buy much too expenshe instruments. The purpose tithis chapter is For the scend case me have to indicate some of the methods for obtaining reasonable estimates of e*rerimen-a, cP tal uncertainty.

_P, f

_-E EE Il in the previous discussion of experimental plannmg we noted that an uncer-tainty analysis may aid the investigator in selecting alternative methods to g9 measure a particular experimental vanable. It may also mdicate how one may j

improve the overall accuracy of a measurement by attacking certain critica!

2 r

irr variables in the measurement process. The next three examples illustrate these P

_\\ E,

\\l/ ;

points.

l Inserting the numeri-;al values of uncertainty, Example 3-2 A resistor has a norninal stated value of 10 D i i percent. A voltage is impressed on the resistor, and the power dissipataon is to be 3 = [(0'0ll + t001)2]2 = 1.4!4%

2 calculated in two different ways:(11 from P = E2/R and (2) from P = El. In P

(1) only a voltage measurement will be made, while both current and so!tage will be measured in (2). Calculate the uncertainty in the poner determination Thus the second method of power determination proudes comiderably less in each case when the measured values of E and I are:

uncertainty than the first method. esen though the pnmary uncertainties ia cach quantity are the same. In this example the utihty of the uncertainty E = 100 V i 1%

(for both casesl analysis is that is alTovos the individual a basis for sefar}orr <f a encusurement i = 10 A i 1 %

meriwd to produce a result with less uncertainty.

Example 3-3 The power measurement in Example 3-2 is to be conducted by

~.

c V

measuring voltage arai current across the resistor with the circuit shown in the accompanying figure. The voltmeter has an internal resistance R,.,. and the value of R is known only approximately. Calculate the nomina! salue of Or H8" E**"rie 3-2 Power mesurerpent acon the power dissipated in R and the uncertainty for the folionmg conditions:

a remeer.

R = 100 O (net known exactly)

Sot.imos The schematic is shown in the accompanying figure. For the 6rst R.-IM n15%

case we have BP 2E 2P E'

f

• S A L I%

2 DE R

2R R

E. $og y n%

jeO5VMfp22 4 n

54 s utasserstat sema nn eon s wisu ms

,w w m, w,,_,,,,,,.,, 33 R

I

.v.

"f

.+

~

3 3h

=

a R i

p

," v.% p l

~'

s l _ ___Y' Vegwe Eusmple 3-3 t Sed of meter tepedance E

in order of mfluerwe <m the imal untertaenty in the pimer we have en me.s.rement Sol.tmoN A current balance on the circuit yields I. Urncrtainty of current determmati.m

1. +#2"'.

2. Unccrtainty of suitage measurement 1 Uncertamty of knowiedge ofinternal resistance of voltmeter 8

E E

-+-=1 R

R.,

T here are other mncludons we can draw from this exampic. The relatise influence i4 the ciperimental quantities on the oserall pimer deterraination is and noW shive. Itut this hsting tuay be a Nt musicadmg in that it imphes that E

the imcertamty of the meter impedance does not have a larFe efTect on the l

• I- {

M fina! uncertainty in t'ie power determination. This results fr: m the fact that i

R. > R (R. = 10R). If the meter impedance were lower. say 200 0. we The power diwipated in the resistor is would find : hat it was a domirant factor in the overall ur; certainty. For a E

sery luds meter ungwstanv: there would be little influence oen with a very 2

P=Et,=EI (b) inaccurate L rm!cdge of the exact value (4 R.,. Thus, we are led to the simple coru:luwon that we oced not worry too much about the predse salue of the The nominal value of the power is thus calculated as internal impedance of the meter as long as it is very large cornpared with the rewstance we arc measuring the voltage acrost This fact shouId in8uence P = (500x5) 1000 = 2250 W mssrument sclerreme for a particular appiscathm.

In terms of known quantities the power has the functional form P =

Esample 3-4 A sxrtam obstruction-type tiowmeter (erihce. venturi nonicL f(f, I, R.), and so we form the derivatives shown in the accompanying figure,is used to measure the flow of air at low "E

2P 2E 2P

-=1-

- = E, DE R.

?!

p p,(p. - p2)

~'1 m=(4 PP E

R T, bal 2

I where C is en empirical-discharge coefficient. A is the flow area,p, and p, are L

The uncertainty for the power is now written as the upstream and downstream pressures. T, is the upstream temperatum and

,g 2 (gays

- uz wi + E'wl +

1) wi (c) w, =

I-e (v,.r.,)

R-Insertmg the appropriate numerical values gives w, =

5-Sr + (25 x 10*X25 x 10 ~') + 25 x (2500)

\\

n,,,

= [16 + 25 + 615]2(5)

M OA, (r)

= 34.4 W r.e tse iw

.,. u. e,er g

O

O I

.c.

,g 56 txrtasmstat wtruuos son awa%ffs:s

^ N ^ L W5 8

• 8 * " N' M

• 8 *** *

• 51 R is the gas constant for air. Calculate the percent uncertainty in the mass The mam contribution to uncertainty is the p, measurement with its basic flow rate for the following conditions; uncertainty of 2 percent. Thut, to improse the overa!! situ.ition the acturacy C - 0.92 + 0.005 (from cahbration data)

'neasurement should be attacked hnt. In order of influence on the tiow-rate oncertamty, we hase p, = 25 psia i 0.5 psia 7, = 70 F 12'F T, = $30 R I. Uncertamty in p. measurement (i 2 percent)

2. Uncertainty in value of C Ap = p, - p, = 1.4 psia 10 005 psia imeasured directh)

3. Uncertainty in determinatum of r, 2

2 4 Uncertainty in determination of Ap A = 1.0 in 10001 in

5. Uncertainty in determination of A Sotintos In this example the flow rate is a function of several variables, each subject to an uncertainty.

By inspecting Eq. (e) we see th.st the hrst two a. ems make practica!!y the 4: =f(C. A. pp Ap. T,)

(b) whole contribution to uncertainty The value of the uncertas.ity analysis in this example is that it shows the investigator how to imfrove t;*e overa!!

Thus, we form the derivatises:

measurement accuracy of this technique First. obtava a mo.c p ec se meas-urement of p,. Then try to obtain a better calibration of the device. ie., a is L" = A I' Ap better salue of C. In Chag 7 we shall see h<>w salues of the discharge PC

\\ RT

/

e coefficient C are obtair ed.

(Er 24< P 3p))"*

,c DA R T,

= 0.5CA AP Pi (c) 3-5 EVALUATION OF UNCERTAINTIES FOR COMPLICATED DATA REDUCTION PS' A'"*

= 0.5CA P

dAP

\\ RT /

We ha.e een in the preceding discussion. and examples how uncertainty analysis can be a useful tool lo examine experimental data. In many cases data reduction i

2

=-0.5CA{

' Ap T,- *

• is a rzther complicated atfair and is often performed with a computer routine written specifically for the tasL A small adaptation of the toutme can provide for The uncertainty ire the mass flow rate may now be calculated by assemblinF direct calculation of uncertainties without resorting to an analytical determi-thes derivatives in accordance with Eq. (3-25. Designat4g this assembly as nation of the partial derivatives in Eq.13-2). We still assume that this equation Eq.(c) and then dividing by E (4 ghes applies, although it could insolve several computational steps. We aho assume 4

that we are able to obtain estimates by some means of the uncertamties in the r ha "f =

+ 1 ["r2

• 2 2

g2 ;7(h + g 6f) primary measurements i.e w. w,,etc.

+

+

- C A

4\\Ps AP

• n y

a g g g,u g gg w y ggy g,g We r nay now insert the numerical values for the quantities to obtain the cateuiated At :he same time one may perturb the variables by As,. As,. and so percent uncertainty in the mass flow rate.

on and calculate new results. We would have

• ~"2 j* (O H ) * [0001)2\\ 1.0 )

• i [0_5}2G)

• i[\\ 1.4

+ E [\\$5}) _

-[0.005):

1 I 0005'2 1

2 w

Ri s, + A s,) = Ri s, + A sn q.

. %)

= [29.5 x 10 - * + 1.0 x 10-* + 1.0 x 10- * + 3.19 x 10- *

+ 3.57 x 10-*]h2 R( q) = R( t,. x,...s.)

= [1.373 x 10-*]"2 = 1.172%

(c)

R(9 i ^ 4) - Rt t. x 2 + Ax 2

.. x )

i f$b G

IIII i

~

I f

k c>912:1 i

V f 5! h&

\\

f FLOW OF FLUIDS f

THROUGH F

ad VALVES, FITTINGS, AND PIPE F,

F

...s...........m.,,,..

g c

CRANE

.c

\\

m g.

. tees-cra* Ce r:

All rights resersed This pubbc aten in fully pet *c6ted h mpyright ano nothing that appar,in it mas be reprinted, either

• holly or in part, withiwi *Pcial permisen.

I:

Crane D, specifwally eutudes a arranties.expreu or impbed, ai to

[

the accuracy d the data and other mfermation set fath in this pubhcation and dus not assume habibry for any kmes or Jamage esaitmg ham the use of the materials or appination d the data dmuned in this publication.

ll IRAINING llBRARY CRANE CO.

A New York N E3 3+*

After Mar I.1985 E"

757 TNed Avenue New York, NY 10017 w

M 1.canic.irop.,n 4to

=

g j

,, i,.1, o i m u s a.

....,__....si D

i

2 10 cuerte z. now o# ewies soovcs vmn wo onmos CRANI CRANE-i tt]

l Resistance Coefficient K, Equivalent Length L/0, l

And flow Coefficient Cy - continued E23 in the u i

ED from lat The friction factors for clean commercial steel ppe When a pipmg sptem contams rnore than one si:e of numben w it h flow in the :one of complete turbulence (fr), for prpe, s alves. or fittings. Equation 2-5 may be used

$ Q A 25 as t i

nominal stres from it: to 24 inch are tabulated at the to espress all resistances in terms of one si:e For number l

beginmne of the "K" Factor Table trage A 2n) for this case. subsenpt "a" telates to the si:e with ref.

g Q hmit for convenience in conserting the algebraic expressans of erence to which all resistances are to be expreswJ, flow in s {

1 arithmetic quantities and subsenpt "b" r 'ates to tiny other si:e in the g Q system i or sample problem. see E,xample 414 h,,

t There are some resstances to flow in pinng, such as l

suddcn and gradual contractions anJ enlargements.

It has been found convenient in some branches of the w.hich iw.

and pre entrances and cuts that have geometne s ahe industry, particularly in connection u ith con-similanty betsun si:es l he resntance coctficients trol sahes, to express the valve capacity and the g

the frict 4

~

tored ir (K) for these items are therefore independent of size vahc tiow charactenstics in tenns of the flow coct6-above 2 as indicatcJ by the absence of a friction factor in their cient L.

The C, coci6cient of a valve is defined as E 3 i

i values gnen n the "K" Factor Table _

the now of water at 60 In m gaHons pn ntnme, at i

a pressure drop of one pound per square inch across E,,3 i

the valve.

As previously stated, the resistance coeffwient K is always associateJ with the diameter in which the g

1 The res vekicity in the term t /2g occurs The values in the By the substitution of apprornate eluivalent units may bc 2

l "K" Factor Table are aswiated with the intemal :n the Darcy equation, it can be shown that, E.I diameter of the foHowind pre schedule numbers for i

K,.

l the vanous ANSI Classes of valves and httincs Cr -

twm. s4 E3 l

O 3

j and the Class 100 and loser.

.&hedule 40 l

Class 400 and t@.

.&hedule 80 w3 i

Class 400

.&hedule 120 Cuas 2500 (mes b io to....

.&hedule Ito g'*

CNs 1 $00.....

Aho, the quantity in gallons per minute of liquids of g,- g

........ XXS Class 2500 (mes e and upt

& heduie mo low viscosity

• that will flow through the s sh e can be Subsc determmed from:

RC3 the s When the resistance coet6cient K is used in flow equa-tion 2-2 or any of its equa alent forms given in Chap-Q. Cr ([AP

• • • a37 Rb3 It is con ter 3 as Equations 314,3-Itt 3-19 and 3 20. the veloci.

8 the sma ty and internal diameter dimensions used m the gg Using t.

Q-7oCrg'[y equation must be based on the dimensions of these Sudd schedule numbers regardless of the ppe with which 6

the t alve may be installed gs. g b,'

• and the pressure drop can be computed from the same formula arranged as follows-An alternate procedure w hich yields iJentical results Ed Sudc i

l for Equation 2-2 is to adjust K in proportion to the K t+

l fourth power of the diameter rano, and to base values 3p. _.a_

Rb3 g o,ti, of vekety or diameter on the mternal diameter of the c2 4 Cr q

connectmg pipe Rt2

'j"O us 2

Since Equations 2-2 and 2J are simply other forms the con

. - K+ g/dy Is.

fe=6 2 8 of the Darcy equation, the hmitations regarding M, 3 the coi their use for compressible flow (explained on page IJ)

I Weisbai i Subsenpt "a" Je6nes K and d with reference to apply. Other convenient forms of Equations 2 2 and 83 the internal diameter of the connectmg pipe 2J in terms of commonly used units are presented on larger r e u, page 3-4.

Subsenpt "b" dehnes K and d w ith reference to the and 2-1 mternal diameter of the pipe for u hich the values of *When handhng highlyviscous liquids determine flow 3

K were estabbshed, as given in the foregomg hst of rate or required valve C, as desenbed in the ISA g8 "

ppe scheJule numbers.

Handbook of Control Valves.

g3 The los 6

kd as a c mate a i M

include, equatio

^

Fc. os4 L9 RECORD OF TELEPHONE COMMUNICATION h

• 33 o PED-SSE.90-04355 DATE:

27 April 1990 TIME:

1430 HRS M

PARTY CALLING:

Al Newcomer IMPELL/0 PPD Special Services (Name)

(Company)

PARTY ANSWERING:

Bill Weber OPPD. Supv. of Reactor Perf. Analysis (Name)

(Company)

SUBJECT:

Values of Physical Constants Used in the Ft. Calhoun LOCA Analysis TELECON

SUMMARY

(Including Decisions and Connitments)

IcalledBillWebertogetaflowcoefficient(C)valueasusedinthe y

plant LOCA analysis for the safety injection system. Bill informed me that aC value would not be possible, but that other parameters might be y

available. After Bill Called Mr. John Jung, Combustion Engineering, he informed me that the effective flow area and representative resistance coefficient (K)were0.5592ft2 and 7.34 respectively, as used in the C.E.

performed LOCA analysis.

From these values, he continued, the C can be i

y calculated.

Bill also added that he would once again contact Mr. Jung for formal documentation of the two constants.

t l

l ACTION RE0VIRED l

Weber contacted Jung for formal documentation of numbers.

DISTRIBUTION:

Chuck Bloyd, FCS Special Services Pon Lip)y, FCS Special Services Bill We)er, OPPD Reactor Perf. Analysis

FEB 3 '92 16: 41 FROM MPS PLT STRUCT COMPT PAGE,002 P 33 A M ABB ASCA DRQWN BoVERI rebruary 3, 1992 0-MECH-92-015 Mr.

C. N. Bloyd Ft. Calhoun Station Omaha Public Power District P. O. Box 399 Ft. Calhoun, NE 68023 subject SIT Injection Line Resistance Factor for Eccs Analysis.

Reference:

CE Lotter 0-PD-113, Omaha and Palisados ECCS Data, dated March 15, 1974.

(Enclosed)

Dear Chuck; This lotter transmits en edited copy of the referenced internal letter.

It in understood that the information contained in this letter regarding the SIT injection line resistance is needed to support the basis for acceptance criteria in the Ft. Calbraun Station SIT check valve operability test procedure.

The enclosed copy of the letter has been edited since it contained design data on both the Ft, Calhoun Station and the CPCo Palisadea Plant.

Only that data which relatos to the Palisades contract has been edited out.

Additionally, in reviewing the OPPD calculation file, we were able to determine that tho source of the data for the line resintance values is based upon a calculation which was produce in late 1971 and that Gibbs fr Hill line isometric drawings were used to establish the unique values for each of the four lines.

ABB CENS is pleased to provide this information and support to you at this time.

Should you have any additional questions, please feel free to contact me at 203-285-3893.

Sincerely, ABB COMBUSTION ENGINEERING NUCLEAR SERVICES e = =_ - l - -

F. P. Ferraraccio bI Supervisor, Plant Engineering Services (g/y 1 12 %

xc:

C. Boughter G. Anglehart (ABB-CE RSSM)

D. Sente11 (ABB-CE) l ABB Combustion Engineering Nuclear Power c====e w m a g g mas rym g m memm 1.Jfhgesum

-- ---^ ~'-~~ ~ ~~~~ ~ ""~

~ ~ ~~

^

i FEB 3 '92 16: 42 FROM f1PS CLT STRUCT COMPT q

PAGE.003 Kev i 1.

P H B J CR

_.1..-.,

lia

! C DiD D U B L Jid C M U3 O b

~

4

,,,A. Good'.in[

Omahn and Talistdss B. M. Pokors l

0; ECCS Data March 15, 1974 T. i.. Carpentino 2

i F. D. !{cun..//

0-PD-113 h

V. !!. Calla 6 an l

E. M. E:*ith 4

c. 1:. thertz G. Sala:en t

• . L'ilhelm v/o t.ttach.

00:

'a'.

D.

. Streint v/o attach.

j A.

'J. Schoenbrunn v/c at. tach.

4 f

?D-7L-100 dated February 15, 197h Eeforences l

In:letures

?!I ?cep, HFSI Fury, and Ssfe y Injcetion

. ank Date Ter Kev ECC5 Evalur.tien 14odel

?

Inclosed are L?SI P.: p,"P.?SI Pc.p. :.nd 3-de:y Inje::tien Tenh ds,tc f:r :ahs and Falisat.es, as requested frca *.he PCS-Scre::uards Sys e.s Orcup by Safety and Licenair.3 in SA-7b-30.

J.

6*11N 00er No 2.It 1L D.11. ?chors 4

g

.b

+

G 4

~

--w

,-,,--m-

,,--,e n-nn.- m - -,,, - -,,.-

a.vnw 7---<a-g

---v-a

-p-

.--..-.__e

. -.... -. ~. -....

FEB 3 '92 16: 42 FROM MPS PLT STRUCT COMPT-ed I PME. 004 P n e n il

~

2-March 15, 197h i

o*-PD-113 1

I.

PAT.TSADES ECCS DATA 1

1-

. 1 This knun gus riauras 1 And,il hAEs

~

kgga edited from thLa cony.

'-~

+

4 a

i i

3 e

i 4

II. OMAMA ECCS DATA i

L.

(a) Humber SI' Tanks: Four

?

(b). SI Ter.k Teeperaturei. 1200F

-(c) SI Tank neessures:255 psia min,- 270 psia nom. 28h psia max.

(d) - SI Tank tuguid Volt::est 825 7t3 min. 856 9 Ft3 noa. 895 8 Tt3 max 3

(e) SI Tau'. Total Volu::es: -1306 Ft /Ta" 2

-- area' =. 5592' Ft )

(f)- SI Tank Discharge Line K Tactors '

Tank 6t K=6.69 Tank 63, K=6.9h 4 6C,2-K=T.3h? Tank 60 K=T.0-g, ;,

' (g)' SI Tank ',tinimum Dischargo Area = 04 492 Ft (h). Elevation of SI Tank Dischar6e Nossles abovo bot' leg [6D,;Ha5'hkh '

Tanh'6A, H=8.1' Tank 6B H=5' Tank; 60, E=6.63' - - Tanx i

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• N'N '

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?

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(a)' LPEI Pump 1C luid Enthalpy:

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Q OT4LT fi FORT CALHOUA STATION SP-SI-7 SPECIAL PROCEDURE i

PAGE 1 OF 12 SAFETY INJECTION TANK SI-6C DUMP TEST 1.0 PURPOSE 1.1 The purpose of this test is to determine if dumping Safety Injection Tank SI-6C to the Reactor Coolant T.ystem will result in an adequate method of verifying the operability of Safety Injection Tank discharge check valves SI-207 and SI-208.

1.2 This test will be performed during refueling with the Reactor Head off, the Reactor Core off-loaded, and the Reactor Vessel Refueling Cavity partially filled.

2.0 REFERENCES

2.1 Technical Specifications 2.1.1, 2.3, 2.8 and 3.6.4.b 2.2 ASME Boiler and Pressure Vessel Code,Section XI, 1980 Edition, Winter 1980 Addenda 2.3 USAR Section 6.2 s4 Piping and Instrumentation Drawings

. 4.1 E-23866-210-130 (sheet 2 of 2) File No. 10480 2.4.2 E-23866-210-110 File No. 10475 2.4.3 11405-M-42 File No. 10450 2.4.4 11405-A-13 File No. 12170 2.5 Instrumentation and Control = Interconnection Diagrama 2.5.1 161F561 SHT. 85 File No. 9583 2.5.2 16F561 SHT. 101 File No. 9599 2.6 Instrument Loop Drawings e

2.6.1 EM-2941 File No. 20576 2.6.2 EM-2944 File No. 20594 2.7 Mission valve Manufacturing Drawings 2.7.1 16259 SHT. 1 File No. 16714 2.7.2 16259 SdT. lA File No. 16716 2.8 Standir.g Order G-19, " Test' Control" 2.9 Standing Order M-28, " Calibration of Test Equipment and Plant Process Instrumentation" FC/SP/05 R2

~.

i Q oSy 2.<f p. 35 0 W FORT CALHOUN STATION

.SP-SI-7 i

SPECIAL PROCEDURE PAGE 2 OF 12 2.10 Calculation FC-05280 2.11 Operating _ Instructions 2.11.1 OI-SI-1,. Safety Injection System-Normal Operation t

2.11.2 OI-NG-1, Nitrogen System-Nor:nal Operation

3. 0-PREREQUISITES INITIALS /DATE NOTE:

Prerequisites 3.2 through 3.11 may be accomplished in any order.

3.1 A Test Director (TD) has been designated and a Chronological Test Log

,,jf (Attachment 1) initiated-'per Reference W

hl/-90 2.8.

The Test-LogLshall be initiated

-Sy-/3.p.,y, at the-first protest-briefing and--

appended to this test'when completed.

M2 / 3-3/-90 TD 3.2-A protest briefing'of all personnel involved in this test has been-conducted (briefings'may 9 conoucted

-in segswats for ease of accomplishment).. Ifl shift ~~ turnover-occurs during the test, a briefing of the on-coming shift shall'.be conducted prior to continuing with the test.

Attach-a list of attendees to the d24.

/3-W d Chronological Test Log.

TD 3.3 All temporary or. portable test:-

equipment-used in-the conduct of this test is: logged.in the appropriate Test.

Eqvipment Log per

Reference:

2.9 and calibration duardates recorded in-Attachment.2 of this test.

JN 8

/ -3 /- To TD l

3.4 Valve HCV-2954.-(SI-6C outlet valve) is closed and is able to be. controlled-from-the Control" Room.

/ 3&M OPS.

3.5 The' Reactor Core is off-loaded.

M 1/30-$

OPS-3.6 Makeup water to: Safety Injection Tank SI-6C is available.

M

/1'N C.

OPS--

FC/SP/05 R2.

n

-c,

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w m.

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.,--,,,,r,r-,

-c<,.-

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-+a-ce-s

.kMQ&y&0 i:

FORT CALL <.N STATION SP-SI-7

!. t SPECIAL Pio*.EDURE

=PAGE 3 OF-12 INITIALS /DATE'

)

3.7 Safety Injection Tank SI-6C level transmitter loop LT-2944X is.in-

/s

/

/

/0/1lff()

service..

h) j/ OPS i

3.8 Safety Injection Tank SI-6C pressure M

f_((///

transmitter loop PT-2941 is in service. (/

/

i

[PS 3.9 A calibrated is available for recording l

l the performance of this test and is loaded with strip chart paper graduated in square centimeters.

(fgtpf 6~M~40 l

Recorder No. / Te2.--Cal Due Dato 8 "3 "J -96 Il6 ~5-Ff-fc l'

l 3.10 Shutdown cooling'is not in service.:

M

-/3-3/D

-OPS 3.11 An appropriate Radiation Work Permit has been obtained.

RWP - No.90-19L k

/3 -3/~t0 RP 3.12 Notify Quality Control prior to the

/)/

J

/_

start of-this test.

67

/

Vfd W

l

-Notify Radiation Protection prior to 3.13 l

i the start of this test.-

/3 -3/~f0 RP 3.14 The Shift Supervisor has-reviewed ther Technicalf Specifications regarding: the--

requirements relating to.the-.RCS,LECCS(

and Refueling Operations.(Sections 2.1.1,-2.3 and 2.8) Land.has granted

/b.3%

. permission to perform-this test.-

-\\

-Shift.Supv.

4.0 PRECAUTIONS AND LIMITATIONS 4.1 Observe the-precautions'and limitations.

L specifled--by the RadiationiWork Permit.

4.2 Ensure that no other. Engineered.

Safequards Testsithat could--affect or-could-.be'affacted by?this test, are being conducted during-the performance:

'of this test.

. 1

'1 FC/SP/05 R2J r

.2.m.

-,,-,.s,;.

m,.

Fe c> s42% e 37 h a FORT CALHOUN STATION SP-SI-7 i

SPECIAL PROCEDURE PAGE 4 OF 12 INITIALS /DATE 4.3 Reactor Vessel Refueling Cavity Level for the performance of this test is between 40% and 50% as indicated by LI-106.

This level will provide adequate Radiological Shielding in the event of a crud burst.

5.0 PROCEDURE NOTE:

Steps 5.1 through 5.4 can be performed in any sequence, but prior to continuing with Step 5.5.

5.1 Close or verify closed valves HCV-331, HCV-317 and HCV-318.

[f b / Y-470 OPS 5.2 Fill Safety Injection Tank SI-6C to a level as close to 90% as possible.

/ @SdC OPS 5.3 Verify or adjust the refueling cavity level to between 40% and 50% as indicated on LI-106.

s!<

/ kid 2" s

OPS 5.4 Connect the strip chart recorder to the Safety Injection Tank SI-6C instruments l

such that:

5.4.1 Safety Injection Tank SI-6C level la recorded over a range of 0 to 100% (LT-2944X).

//0 / 3-T(-96 IsC i

5.4.2 Safety Injection Tank-SI-6C pressure is recorded over e range of 0 psig to 150 psig (PT-2941).

AO / 7*$/-90 IEC 5.4.3 Select and record strip chart recorder speed tomuhrc.

/)tc / 3-3 / 46 j I&C 5.5 Record SI-6C Level.

9O

'd823

/ 9"2-2O LI-2944X OPS N

N l

l l

l

~

FC/SP/05 R2

f (_. O S Y 2-Y P Y 0 W FORT CALHOUN STATION sp.sI.7

- SPECIAL PROCEDURE PAGE 5 OF 12 d

INITIALS /DATE CAUTION 1

Exceeding 65% on LI-106 will-cause Reactor Vessel Refueling Cavity overflow.

t 4

a 5.6 Record the current Reactor-Vessel Refueling Cavity Level from LI-106:

Yb N$

O-A-VQ

/

OPS NOTE:

The Safety Injection Tank pressure setting to be used in'the performance of this test-is e, function e-i of the current Reactor Vessel Refueling Cavity Level.

Typically, the Safety Injection Tank pressure should-be set to 120 -psig when the Reactor. Vessel-Refueling Cavity is 50% as indicated by LI-106:with SI-6C 90% full.

When the Reactor Vessel Refueling Cavity-is-less than'50%, then a lower Safety Injoction Tank pressure will be used.

Also, when the Safety Injection Tank Level'is~less-i than 90%, then a lower Safety Injection Tank Pressure will be used.

See Calculation FC-05280 for the determination of initial Safety Injection Tank Prissure.

5.6.1 Obtain the Safety Injection-L

-Tank pressure to be used to--

perform this test from the Test Director (Safety Injection Tank pressure will be based on current reactor vessel:

refueling cavity level;see

-Calculation-'FC-05280):

l65 osig

$Y / 4ltho.

TO-gp

TVggjf, 5.7 Set Safety Injection Tank SI-6C'to the pressure required to perform this test-using OI-NG-1.

[k ' / #1do.

• • 5x-V(1/10 l

l FC/SP/05 R2

j_,__._.__._-._

I

. f6 C5$ $ pbf h f j.

FORT CALHOUN STATION j

SPECIAL-PROCEDURE SP-SI-7 PAGE 6 OF'12-IMITIALS/DATE.

i 5.8 EHER Safety Injection-Tank SI-6C 1

- pressttre. has been adjusted to the pressure required to-perform this test, IEEE:

f' 5.8.1 Monitor Reactor VesselE Refueling. Cavity level-.using-LI-106 to prevent exceeding 65%

2 in'the Reactor Vessel Refueling

[

Cavity.

Pi '/ s-a-90 OPS FO 4,2.%

i 5.8.2

' Start the strip chart recorder.

/3 ' /'/

• A-f6. l IEC, /J - y -a -po 5.8.3-Open' valve HCV-2954.

1. 6

/s-s -90, OPS $b

1. -R 90 <-

5.8.4 3Digg lic-2954 indicates open, i

IEER close HCV-2954.

. _ P&s -/N-S 1 OPS M.

y - p _. 90

-5.8.5 l

)Q[gg HCV-2954 indicates ' closed, Iggg stop_the brush recorder.

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CALCULATION PREPARATION. REVIEW AND APPROVAL CALCul.ATION NO.

FORM PED-OP-3.4 Form Page No.1 cf 1 I

FC '- C N PRODUCTION ENGINEERING DIVISION CALCULATION SHEET Rev.No.

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Calc Preparat1on, Review ano Approvaj fc C5V23 p. doCD 41 PED-QP-3.5 Page 1 CALCULATI0l.' NUMBER Reviewer's Checklist-Calculations l

p p, g,.,

gg YES NQ N/A 1.

Is Calculation Cover Sheet attached and completed, as required,to the calculation?

2.

Is the calculation objective stated? Was this

\\

achieved?

3.

Are inputs correctly selected and incorporated into the analysis?

4.

Have inputs and/or assumptions which require confirmation at a later data, been identified on the Calculation Cover Sheet and in the calculation body?

5.

Are the applicable codes, standards, v

regulatory requirements, and other references including issue and addenda identified such that they are traceable to source document?

6.

Was an appropriate calculatie method used? Was the basic theory appropriate?

7.

Have assumptions been noted and justified?

8.

Are the calculations free of arithmetic errors?

9.

Is the cciculation consistent with the design

/

basis requirements?

V_

10.

Is the conclusion stated?

/

11.

Is the calculation legible and suitable for t/

microfilming?

12. Are all blocks on the Calculation Cover Sheet s/

addressed correctly?

i i

13.

Have Forms PED-QP-3.2, 3, 4 and 5 been used and s'

correctly completed?

14.

If the calculation has been prepared to supersede d

another calculation, has all the valid inform-ation been transferred in the new calculation?

REVIEWER COMMENTS:

yodE PED-QP-3.33 Rev. 0 7/89

~

j_._______.__.__-...._

e m._ t y i

l Calc Preparation, Review ano Approval FC c'5Y F if e- (o f of a I

PED-CP 3.6 Page 1 CALCULATION NUMBER j

Reviewer',, Checklist Computer Calculations l

R.- Cd Q C Pu. O i

YES N/A 1.

Does the computer run have title, date, and j

page number ditd alphanumeric program j

number on t:yery then?

j 2.

Is the listing of cot.puter input provided?

/

3.

Is the machine generated program name and 1

version on each run or is indicated in the

]

caleration?

I

]

4.

.!s the computer so;tuare validated and verified?

If not

/

4a. Is the. computer code developed for one-time-use v

on a programmable calculator or microcomputer?

/

4b. If yes, has a functional description of the-1 identification of the equations, program identificationofthecode(title, revision, i

manufacturer), identification of the software andsbrief user's instructions besa provided-in i

l the calculation?

If the computee software has been-loaded'on an J

l in-house computer, have the changes made by OPPD beenaroperlyreviewed(verifiedandvalidated) 4 for.tiair impact on the accuracy of the code and have been found satisfactory, or is the in-house computer software validated?

[

6.

Is the computer program appropriate to do the intended calculation?

i 7.

Was an alternate calculation or model utilized

/

i to verify results?

If so, is it attached to this calculation?-

l 8.

!s the modeling correct in terms of'geomatry input und init al conditions?.

c u

V

.9.

Are the results reasonable when compared to i

the inputs?--

' REVIEWER COMENTS

_ y ode 4

PED-QP-3.34 Rev. 0 7/89.

w

er u. n.s Calc Preparation, Reviea and Approvai K C'i'f 2.S

p. G Z a F G T-PED-0P-3.7 Page 1 CALCULATION NtMBER IndependentReviewer'sChecklist-Calculationsj g

^

YES N/A 1.

Are the calculation methods accurate?

/

page rumber and alphanumeric program numoer on every sheet?

2.

Are input data sufficiently detailed?

I 3.

Are the calculation assumptions reasonable 7 1

4.

Has the basis for engineering judgement been U

included in the calculation, when used?

/

5.

Is the calculation documented sufficiently t

such that the analysis is understandable to someone competent in the discipline without recourse to the Preparer?

6.

Have the design interface requirements

./

been satisfied?

7.

Are the results reasonable and do they

/

resolvethecalculationobjective?

8.

Was the design review method used to verify

_c'_.

the calculation?

9.

If an alternate calculation was used to t'

verify the adequacy of the analysis, is it attached to the calculation?

10 If qualification testing was used to verify a'

the adequacy of the analysis, has it been documented using a retrievable' source, or attached to the calculetion?

11. Are calculations involving Technical Specification

/

values and associated margins of safety identified?

REVIEWER COMMENTS:

e. M i

l i

PED-QP-3.3f Rev. 0 7/89

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' FORT.CALHOUN

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Standing Order M-26 has been reviewedh ' y1iT /

1.1 t-and all conditions set down by this

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order have been completed.

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,M / f //'/d 1.2 Shift Suporvisor Equipment Release.

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1.3.4 other (DCR, MR, Etc.)

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REVISION VERIFICATION T*f; l

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This inst rit loop is used in, conjunction with the surveillance test (s) listed below.

If the "As Found" data for this CP is found out;of tolerance, insure that an Incident Report is initiated.

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2.0 REFERENCES

h>

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2.1 161F561, Interconnection Diagram V

2.2 EM-2944, Block Diagram h

3.0. DEVICES TO BE CHECKED

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LT-2944X Foxboro 823DP

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LIA-2944X Simpson 3623XA f'Ao.

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N,Md32b[ $O. l ~ FORT.!'A u y M N IBRATIOR i g,, ,a g 4 pag 3g a 4.0 TEST EQUTPMENT RROUIRED/USED m~ _yv +... 4 ..u, a. -~ ,s 4, c,pO $d" l ,:J'.upV5.lC sac &k . ~s;a%%7;e a 2 i': a. ] EQUIPMENT @A.< l$in EMg/ DDEg CALIBRATION- -Q h .c; -OPPD'Me. "y, C i " 9.e.Q"Y / f /7 @ sMP.., ;. a A .? 7 $fi Pressure Source M* m- - ' ^ ^. a. l 200' HC DOO h?$' 4 Variable - Tt'- Rasintor AdA - / Mk. (DNN1 Digital A i Multh-Matar M/ifE. '/ M'/* 9d ' Zd{Qcp ) (VON) Voltohn t. (h .w/ M 3, ' .-;M l Mater y I -lGijb?& c y.

d.Y$5

. ~. j 5.0 CALIBRATION PROCEDURE

PWh, INITIALS /D&TE *W

% 1,.L,i, 4,' c:74 f, 5.1 calibration of-LQ-2944X1 A.,- 4 m - m m, s } 5.1.1 Using DMN, measure. he output. %.-O o i-DC volta e of LQ-2944K.- Record' ' f?J reading n the 'As: Found" { column on Data sheet' 1. A/A. g. c / MjW$ x ~,,... 5.1.2 Using DWN, measureIthe AC .%D

• ~

ripple voltage of LQ-2944X. s4 4 I Record-readin in the Sdl I 'As Found* co uan on Data A//A /Ift9A I Sheet 1.- I c?t' i ,: g;:7 'd 5.1.3 If-"As Found"'value for i LQ-2944E DC output voltage is= 1 b},g f out-of-tolerance shown on Data Sheet 1 or an laprovement in )f-9 accuracy is warranted, N/A Steps 5.1.4.A and 5.1.4.5 then jM go to Step 5.1.5... _ Ldh Mild @:b -y y ,m n;g-~ 5.1.4 If "As Found"'value for. 8?I +LQ-29441 DC output voltage is' i within required tolerance shown S, on Data Sheet 1,' pidoceed as 3.'2'-6 follows. iE Jgu y %,- n j S n y A. Record "As Found*u.aA e as .s "As Left" value for W-LQ-2944X DC output voltage 7 on Data Sheet 1.- AMt / 8 I @: 4 1 1, B.. Enter N/A for Step 5.1.5 and go to Step 5.1.6. N/A i YV;#;:,f. }pf ' nQQ 2 F 9 %;4 ~' f. . W

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j .s t, "v v 'ci% IMITIALS/DATE j n .i 1 @.[v 'Ii'w thin tolerance > pf4 y pegu g pyg.g-- g.1 310788 E lJ ' Mb"TMt' W cannot be obtained during W iMdM calibration, notify inunediais?? 4.' I ON ,'"~ } supervisor. N 'W a. 5.1.5 Adjust LQ-2944X as required to-obtain DC output voltage within j the required tolerance shown on i Data' Sheet:1. Record final reading in the 'As Left" I*n' , /A /MJd@ column. M 4: I 4;p + l i 5.1.6 If "As Found" value for

M,

.

4/. 1 LQ-2944K Ac-ripple voltage isL' ,i", 7 *( I out-of-tolerance shown on Data. V;Ms "'. ' " ' VO. ' t I shopt 1, notify inusediate s supervisor, otherwise go to r L i Step 5.1.7i I Al/l /MS4 5.1.7 Record,"As.Found* value as i "As Left" value.for LQ-2944X AC' Ripple voltage on Data Shoot-1. M/A / i 5.2 Calibration of LIA-2944I / ( 5.2.1 Connect variable resistor and I D800 to siaralate input values shown on Data Sheet 2 for andI, i L-2944I. Identify any. lifted 3 leads as required. g; Wire #

1. g Terminal #

TB# g Terminal { g Wire # A/I / 5.2.2 Simulate input' values as sh5wn " s. m on-Data. Sheet 2 for LIA-2944E.'5 J,. 1 Record readin e in the' W.. 'As Found"'.co uan on Data. ,Fe%. t Sheet 2. m ~ v' '. M/A /MSJWI-i A. If~an improvement in W. i accuracy is required and ~ adjustment is,to be made,* N/A Step.5.2.3 and go to i Step.5.2.4,..otherwise N/A L this step and go to-Step 5,2.3. Ai/h- /MIMB / < Ee, n :e,

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+nn 3 _ # m;.:, w,4 .g.Yg;.9: 9, rg:. g;u 4 Q4:p a 3 y g, ,, e r c.m -W " ' nWe h&:, 'l} 1 ^- f f"

Ysks.cm- y'f/y$gp,g}%.q ( - Qg jggeid bv .g 1 FORT CALHOUN STATION. CP-2944 -n CALIBRATIONjPROCEDU m u$z;MWard#mwiersapMt2i,c., ~~ PAGE R s Aw + n, 9:, R...? t INITIALS /DATE',e 5.2.3 If "As Founda value is within tolerance as shown on Data Sheet 2 for LIA-2944% record "As Found* values as "As Left" values in Data Sheet 2, N/A // Step 5.2.4 and go to Step 5.3. d7 /5/0// NOTE: If within tolerance cannot be obtained during calibration, notify immediate supervisor. 5.2.4 If "As Found" valbes are out-of-tolerance as shown on Data Sheet 2 for LIA-2944X or an improvoment in accuracy is required then adjust LIA-2944% to within tolerance, and record final readings in *As Left" column of Data Sheet 2. N//t /Mf5/Md / 5.3 Calibration of Computer Point L-2944X 5,iti Ar,%' input values as shown for 'i # T 4 ) v Data Sheet 2. ) w.W .. puter display values h; A Found* column. wat c. (nput in t:1e e ,j tJl# /$0 5996 3. If an improvement in accuracy is required, N/A Step 5.3.2 and go to Step 3 otherwise this step 5.3.2 If "As Found" value is within tolerance record "As Found" value as "As Lu t" value on 1 Data Sheet 2 for L-2944X and N/A Steps 5.3.3 thru 5.3.7 and go to 5.3.8. h// /NGh ~ 5.3.3 If "As Found" values is for out-of-tolerance or an improvement in accuracy is required adjust variable resistor for input equal to 3 l l volts for L-2944%. n/A /U/#@ l t t, w < p*Q y.c. ;wf, av w, ., c 8 4:' g{d%

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L. FC/CP/09 Wb, R' R .1%.. M'Q . g;. jdM ~ . : Qp, .,s y'l . f f.j - sQygg- .s}~) y;; ! * 'q ~.(ph(:}. g x m. -

A Qis.:;h "FORTCALHOUNSTATIONAMID@l@dWE&r,*T ' d 4 M C. % Q '% 4 e i i .w X CALIBRATIouiPROCEDURR E Ntr& MudM88$.. wmf^ u tu 3% .,J.+ 28

• I p.. m.

-: p. i .g, y,-g 6 + T! I IMITIALE i 1 a, a .:q:::"..w#w. i 5.3.4 With DMM measuEd. voltage acro'ss-W,, l dropping resister for L-2944X Q , ; >y*c1,l> l j and record reading. i= L-2944X ))A VDC A>/4 / f/> 1 (.503 tb.616 VDC) / I 5.3.5 If reading in Step 5.3.4 is j out-of-tolerance notify ) immediate supervisor of results for computer point L-29441. Ai/4 /U## I

e' I

,.3, 4. 5.3.6 If rework of L-2944X cannot be performed-in an expeditious c i manner N/A 8tep 5.3.7 and go to l Step 5.3.8. AdA MI#2 e 1 5.3.7 When rework is lompleted apply _ input values as shown for L-2944X on Data Sheet 2. Record computer. display values-for each input in-the "As Left" l column. - n/A /dfle 5.3.8 Disconnect variable resistor-j and DIOt, verify leads-i disconnected during the performance of this procedure as-identified in Step 5.2.1 ar m/4 /MS#9 re-connected-5.4 Calibration of LT-2944X ,,/ \\ (Uf /NM 5.4.1 Isolate LT-2944X. 1_ 5.4.2 Connect pressure source to simulate input values as shown af on Data Sheet 2 for.LT-2944X. /#7 / 4 90 4 s-s 5.4.3 Connect D00t to monitor output values as shown on Data Sheet 3 for LT-2944X. - Identify any lifted leads as required. LHRM Wire # $/ T3 #MTerminalL# / Wire # erminal 9 /f/9 1 e ..) > ~ .L fli q +( .Q,. t4. )dd.S g. fildl3M s.);f g ;j y c ; ;# g K [. AQ., < w A+ py n FC/CP/09 9e M Aj t - w%g+W' M+h$;.; QW 'Ai%,RS A ~ '!,':,f. 49% ~.,.;.a x.,

l-I;W.

3:,. A% " 1 -y IlT E- %h{ $ b[ 4M%h%)t ME'Mj'.h[{[,4 ~

i FORT CALHOUN STATI ~ .Mh f 23 f _. CALIBRATION:F @ EDU.REa o

e. wMeenJ%.

VP

2..p p,ep p., AGE 54'Of)119E'A=I

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• * * " IMITIALS/DATE

~ 5.4.4 Simulate input values ts W.4 LT-2944X as shown on Data-w i Sheet 3. Record DNN readings ul ~ ~ ~l in "As Found" column of Data llM - /fMf5 i Sheet 3. i A. If an improvement in i accuracy is re adjustment is quired and i to be made, i N/A Step 5.4.5 and go to Step 5.4.6, otherwise N/A this step and go to Step 5.4.5. AJ/A / hAS. I 5.4.5 If "As Found" values are within Tc!%j; a tolerance as shown on Data C?. Sheet 3 for LT-29442 record "As found* values "As=Left" ^ values in Data-. sheet 3, N/A y /fJ46 Step 5.4.6 and go to 5.4.7.

1. U 5.4.6 If."As Found" value is out-of-tolerance as'shown on Data sheet 3 for LT-2944X or an improvement in accuracy is required, adjust LT-2944X to within1 tolerance and record fina1 readings in "As Left" column of Data-Sheet 3 for--

LT-2944X. A)/4 /8IfJ.90 e 5075s If within tolerances - cannot be obtained during' calibration, notify immediate supervisor. .s ^ 5.4.7 Disconnect (201 frost LT-2944X -[ and verify leads.-disconnected. 3x during the performance of this procedures as identified in: i r. m/ Step 5.4.3. Irl /J W D verdec.' n D n.\\i;90 V 1.,. 4 . c- + ~ X ~.% ,...a;3j g. \\ ?} jf l-yhkgtf-FC/CP/09 J-W inC- ... bas y en ..rQ, R$

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.e*' d< 'JW%ed; i t,*[- FORT CALHOUN STATION th CALIBRATION PROCEDURU - 4]QPW 8'.? W'" 1f'p"$ 3 '..a INITiq.S/DATE 5.5 Loop Chock 5.5.1 Simulate an input value of 43.25"H 0 to LT-2944X and verify that LIA-2944X and L-2944X roads within tolerance as shown below. Record m/ reading. /N@ LI-2944X 7H t 75t(75% to 77%)' M7ff /S/Ad L-2944X 7f'f/ _t 75t(73% to 774) 5.5.2 Disconnect pressure source from LT-2k44X, re-install testing fitting plugs or instrument tubing as required, fill and vent transmitter, ensure equalizer valve is closed and 3f/ isolation valve is open. //# /,G O 5.5.3 If S.I. Tank 6C is in service verify that LI-2944X and L-2944X read within 12% of each other. If S.I. Tank 6C is not in service, N/A this step. Record readings. LI-2944X a JA t J/4 - 1 4;/4 /N L-2944X i ( v y;. 2 %*i j,v${.Q;{- lR97 FC/CP/09 _ a q,, %@gci&, ' Q h ifi'i}3 l sY & # ' ~

,ffk I'S CP N FORT CALHOUN STATION' I +' CALIBRATION _ PROCEDURE. - a,,ccA gl.l t, v,. f1';pAgg:,g nygg{Ms' ., cw , r.s % ..,,y,. INITIAr.c/DATE 6.0 PROCEDURE COMPLETION 6.1 Notify Shif t Supervisor Loop returned to normal, eL46 /An/p/ Shitt Supv 6.2 Lead Craftsman assure that all witness ,/ blanks are initialed or N/A and dated. //N /S4.6 v s // //d}ib' ~ b LAllM J//.9b ns Omplis s yI'&Cfecy (Signature) iDate i M orbr/po Reviewdd by Supervisor I & C/ Date System Engineer / Coordinator (Signature) REMARKS: LA1/9Y *T4TMSRUPi' 5W7PM Ek/OfAlFR h) REC 7Eb Tn nMLY j ho CALIAFAT7m) DP 72htSMIwtR AGTL1/MfK OQ SML (OMPLWb 1 i 1 FC/CP/09 .,s.- RB _ - ;[ A17 m A . g g e

/y!j.CN[AilA/Wic.xlfl"4'*J'.%,'jff,'g". L-@' :p[- b{st 'g ;j. k CALIBRATION' PROCED,URE6*'M#M.,..; %% FORT CALHOUN-STATION '" C T' ' v g * (, 7 DATA SNEET 1 CP-2944K ^~ Step 5.1.1, 5.1.4.A. 5.1.5 S.)ff) LQ-2944K M TOLERANCE (VDC) AS LEFT (VDC) 52. .II.L m-g4-M5WW -Step 1 1.2, 5.1.7 AS FOUND (mVAC) TOLERANCE.(mVAC) (mVAC) Less than 38 mVAC x f h i i s l l l l k

,, s

. {s;. -n' { g '. a 1;.. it ,e.,v 1 , t'.Ik4"ifld TC/CP/09 ~ '[l';. l ' 3,+ R }?l 9 'u g

1 ' 'd;lig,' CP-2944(? ~f:' & y.. -J ;& FORT CALHOUN STATION -edI J M l CALIBRATION PROCEDURE ^.it?rn "W' C.%#WPAGE!10 CF '11'l# i DATA SHEET 2 CP 2944K l Step 5.2.2, 5.2.3, 5.2.4 1 Sy4j LI-2944X mA) AS FOUND (%) TOLERANCE (%) AS LEFT(%) i 10 \\ \\ 0 (-2 to +2) \\ 25 (23 to 27) 20 \\ 50 (40.to 52) i 30 40 5 (73 to 77) 50 100 o 102) 40 75 (73 to 1 30 50 (48 to 52) \\ 20 25 (23 to 27) \\ 10 0 (-2 to +2) \\ Step 5.3.1, 5.3.2, 5.3.7 l k A $fMD L-2944X I mA) AS FOUND (%) TOLERANCE ( % ). AS LEFT(%) 10 N O'(-2 to +2) 20 25 (23 to 27) 30 h 50 (48 to 52). 40 73 to 77) 100-(9 k l02) 50 75 (73 to k 40 30 50 (48'to. '52) \\ 20 25 (23 to 27) \\ 10 0 (-2-to +2) FC/CP/09-a. IR8

1 FORT CALHOUN STATION CALIBRATION PROCEDURE CP-2944X PAGE 11 OF 11 DATA SHEET 3 CP-2944X Step 5.4.4, 5.4.5, 5.4.6 4 4 LT-2924X INPUT ("H2O) AS FOUND (mA) TOLERANCE ( mA) AS LEFT=(mA) 168.4 gp 10 ( 9.2 to 10.8) gpp 126.3 gg 20 (19.2 to 20.8) gg 84.2 jp g 30 (29.2 to 30.8) ((g 42.1 gjpg 40 (39.2 to 40.8) // g O.0 50 (49.2 to 50.8)_ gg,gy-ggy 42.1 40 (39.2'to-_40.8) g p pg 84.2 g,9j 30 (29.2 to 30.8) g py 126.3 f9,pg 20 (19.2 to 20.8) jg 168.4 p pg 10 ( 9.2 to 10.8) ,pg 9 i t l e i (~ t l l FC/CP/09 R8

i l (t eft Blank intentionally). i

I Attachment LIC-92-278R ATTACHMENT 4 Fort Calhoun Station Inservice Testing Philosophy

LIC-92 278R Page 1 ATTACHMENT 4 FORT CALHOUN STATION INSERVICE TESTING (IST) PHILOSOPHY This document describes the philosophy Fort Calhoun Station used to develop and implement the IST Program. This is a guideline used by OPPD in determining components to be tested tests to be performed, test frequencies, acceptance pertaining to fort Calhoun Station's IST Program. The Fort criteria, etc.,151 Program Plan does in some cases deviate from this philosophy. Calhoun Station In general, this philosophy is adhered to whenever practical.

1.0 REFERENCES

A. ASME Boiler and Pressure Vessel Code Section XI 1980 Edition, Subsections IWA, IWV and IWP, Winter 1980 Addenda B. ASME Boiler and Pressure Vessel Code Section XI 1989 Edition C. NRC Generic Letter (GL) 89 04, dated April 3, 1989 D. ASME Operation and Maintenance of Nuclear Power Plants Manual 1987 Edition, 1988 Addenda E. Fort Calhoun Station ISI Program Plan F. Fort Calhoun Station ISI Basis Documents G. Station Engineering Instructions: SEl-ll, SEI-13 H. Quality Procedure: QP-33 1. Fort Calhoun Station Standing Orders 1. G-21 Modification Control ISI Coordinator reviews all modification packages prior to final acceptance, for compliance with the ISI Program Plan. 2. G-23 Surveillance Test Program ISI Coordinator reviews all ISI related surveillance tests for compliance with the ISI Program Plan. 3. G-30 Setpoint/ Procedure Changes and Generation 151 Coordinator reviews all ISI related surveillance test procedure changes for compliance with the ISI Program Plan.

LIC 92 278R Page 2 1. Various meetings / correspondence with NRC J. Various industry /NRC meetings / symposiums K. Previous inspections / experience 2.0 DEFINITIONS A. Active Valves Valves which are required to change obturator position to accomplish a specific function. B. Passive Valves Valves which maintain obturator position and are not required to change obturator position-to accomplish a specific function. C. Valve Categories Category A Valves for which seat leakage is limited to a specific maximum amount in the closed position for fulfillment of their required function. Cetegory B Valves for which seat leakage in the closed position is inconsequential for fulfillment of their required function. Category C Valves which are self-actuating in response to some system characteristics, such. as pressure (relief valves for fulfillmen) or flow direction (check-valves) t of the required function (s). Category D Valves which are actuated by an energy source capable of only one operation su disks or explosive-actuated vaives.ch as rupture D. Exencising The demonstration based on direct or indirect visual or other positive indication that the moving parts of a valve function satisfactorily. E. Operational Readiness The capability of a valve to fulfill its funcMon. F. Pressure Isolation Valves (P!Vs) 1. Two normally closed valves in socies that isolate the RCS from an attached low pressure system. PlVs are within the Reactor Coolant Pressure Boundary (RCPB).

LIC-92-278R Page 3 2. Event V PlVs Two check valves in series at a low 3ressure/RCS interface whose failure may result in a LOCA that )ypasses containment. G. Check Valve full-Stroke A check valve's full-stroke to open position is verified by passing the maximum r%uired accident condition flow through the valve. This is the maximum flow rate for which credit is taken for this component in a safety analyses in any flow condition. The safety analyses are those contained in the plant's Final Safety Analysis Report (FSAR), or equivalent, but are not limited to the accident and transient analyses. H. Check Valve Partial-Stroke Any flow rate less than " full-stroke" is a partial stroke. 1. Cold Shutdown Justification When it is not practical to perform a test at the Code required frequency of quarterly, acceptable technical justification shall be given in the ISI Program Plan and the test will then be performed at a frequency of Cold Shutdown in accordance with the requirements of the ASME Section XI/0&M Codes. J. Refueling Outage Justification When it is not practical to perform a test at the Code required frequency of quarterly, acceptable technical justification shall be given in the ISI Program Plan and the test will then be performed at a frequency of refueling outage in accordance with the requirements of the ASME Section XI/0&M Manual. K. Relief Request When a Code requirement cannot be met or a deviation from the criteria of the Code is necessary, a Relief Request shall be submitted to the NRC prior to implementation of the deviation. L. IST Program 1. Interval - Fort Calhoun Station 151 Program Plan complies with the-requirements of Inspection Program B es defined in IWA-2420 of Section XI. The ISI Program Plan is divided into four intervals consisting of ten years each. Prior to the beginning of each interval, a revised ISI-Program Plan shall be submitted to the NRC -for review and approval. The requirements of the latest approved Section XI Code that is accepted by the NRC within 12 months of the beginnir.g of the upcoming interval shall be incorporated into the ISI Program P1an.

3 i LIC 92-278R j Page 4 i l 2. Period - Each interval consists of three periods of 40 months each. M. Rapid Acting Valve 1 Power operated valves with normal stroke times open or closed, of two l seconds or less. j N. Normal Plant Operation The conditions of startup, operation at power, hot standby, and 4 reactor cooldown, as defined by the plant technical specifications. l 0. Reference Values / Baseline Data One or more values of test parameters measured or determined when the equipment is known to be operating acceptably. P. Instrument Accuracy i The allowable inaccuracy of an instrument loop based on the square root of the sum of the squares of the inaccuracies of each instrument 1 or component in the loop. Q. Instrument Loop i Two or more instruments or components working together to provide a 1 single output (e.g., a vibration j conditioning and readout devices). probe and its associated signal l R. Routine Senvicing/H31ntenance The performance of planned, preventive maintenance (e.g., replacing or adjusting valves, adjusting packing, adding packing rings, flushing the cooling system or mechanical seal maintenance or replacement, etc.) which does not require disassembly of the pump or valve or replacement of parts. S. Valve Position Indication (VPI) Verification j Valves with remote position indicators shall be observed locally in order to verify that the valve operation is accurately indicated. Where practical, the local observations should be supplemented by other indications such as use -of flowmeter or other suitable instrumentation to verify obturator position. These observations need not be concurrent.. Where local observation is not possible, other indication shall be used for verification of valve position / operation (e. for solenoid valves use voltage / contact measurements). At Forf.dalhoun Station the VPI verification is performed independent of the valve stroke time measurement and has a "once every two years" performance frequency, ,.-..n. ,... - _,.. ~,,, _ .,y, y

i ) LIC-92-278R l Page 5 3.0 SELECTION CRITERIA FOR COMPONENTS TU BE TESTED A. Valves (including actuating and position indicating systems) l Selected active or passive Class 1, 2 or 3 valves are ones which are required to perform a specific function in: I a. Shutting down reactor to the Cold Shutdown l condition, i i b. Maintaining reactor in a Cold Shutdown condition. c. Hitigating the consequences of an accident. ) i B. Safety / Pressure Relief Devices (as defined by Article 2000 j ASME Section 111 Subarticles NB, NC and ND) 1. Relief valves are tested in accordance with ANSI /ASME PTC 25.3-1976 Setpoint Test portion only. 2. Safety or relief valves that are selected for testing 3 under ASME XI are ones which protect systems or portions j of systems which perform a required function in: j a. Shutting down reactor to the Cold Shutdown condition. b. Maintaining reactor in a Cold Shutdown condition. t c. Mitigating the consequences of an accident. 3. Do-not test relief valves that protect a safety related component or safety related system when not required to operate dur_ing an accident condition. 4. Do not test valves that provide a thermal relief function. i C. Pumps (Positive Displacement and Centrifugal) Selected centrifugal and positive displacement pumps are ones provided with an emergency power source, which are required 4 in: ) a. Shutting down reactor to the Cold Shutdown condition. b. Maintaining reactor in a Cold Shutdown condition, c. Hitigating the' consequences of an accident. N 4 i ..- o v e .r,. e,a-, ..s.,. e, ,..,gn .~p ,.,,v-.

LIC-92-278R Page 6 4.0 EXCLUSIONS (COMPONENT NOT REQUIRING TESTING UNDER ASME XI) A. Excluded Valves are: Valves that do not provide or are not required to perform a s)ecific safety function as described in 3. A.1 and 3.0.2 a3ove, and 1. Are used only for operating convenience such as vent, drain, instrument root and test valves; or, 2. Are used only for systems control, such as pressure regulating valves; or, 3. Are used only for system or component maintenance; or, 4. Are for external control and protection systems responsible for sensing plant conditions and providing signals for valve operation. B. Excluded Pumps /0 rivers are: 1. Drivers except where the tmmp and driver form an integralunitandthepumpbearingsareinthedriver. 2. Class 1, 2 and 3 pumps that are supplied with emergency power solely for operating convenience. 5.0 GENERAL TEST PHILOSOPHY - VALVES A. Manual Valves 1. Do not stroke test. 2. Do not verify position indication. 3. May perform Appendix J testing, if applicable. 4. Do not exercise. B. Dampers 1. Do not stroke test. 2. Do not verify position indication. 3. May perform Apper. dix J testing, if applicable. 4.- Do not exercisee J LIC 92-278R Page 7 C. Power Operated Valves 1. Test in direction that valve goes as a result of a safety signal if different than normal position. 2. Test in " fail" position if different than normal position or safety signal (tested by switch from Control Room). 3. Leak test valves if: a. Category A; or, b. Appendix J; or, b. Pressure Isolation Valve (PIV). 4. Stroke test valves closed, open or both as applicable: a. Time valve stroke from device (actuation to end of valve travel as indicated by lights). b. Only stroke / time valves from Control Room. c. Reference value (last - three performances averaged) for most valves - established in 1990. D. Check Valves 1. Test valve in direction the valve is required to travel in order to perform its safety function. 2. Full-stroke exercise valve in either the open, close or both directions as a nlicable quarterly. If not practical to perform fu' stroke of the valve quarterly, as required, perform a partial stroke quarterly, and full stroke tie valve at the first Cold Shutdown or Refueling Outage as able. If not able to perform either a partial or full stroke of the valve, perform a sample disassembly and inspection of the valve in accordance with GL 89-04. 3. Exercise valve to close position and verify closed by: a. AP. b. Leakage. 4. Perform leak test if required. i l

LIC-92-278R Page 8 E. Safety and Relief Valves 1. Test relief valves that are protecting systems or portions of systems which perform a required function in: a. Shutting down reactor to the Cold Shutdown condition, b. Maintaining reactor in a Cold Shutdown condition. c. Mitigating the consequences of an accident. 2. Perform setpoint pressure or " pop" tests in accordance with ASME PTC 25.3 (setpoint test only) and OH-1. 3. Perform rescat and seat leakage test per ASME OH-1. 4. Class I relief valves shall be tested once every five years: a. 33% of relief valves tested every refueling oMage. b. A minimum of 20% tested every 24 months until 100% of the relief valves have been tested. 5. Class 2 and 3 shall be tested once every ten years after the inisial test: a. 17% of relief valves tested every refueling

outage, b.

A minimum of 20% tested every 48 months until 100% of the relief valves have been tested. 6.0 GENERAL TEST PHILOSOPHY - PUMPS A. Centrifugal 1. Perform operational test (AP vs flow): Fix. flow, AP or speed or flow whichever is (notif required), measure AP a. set, typically Fort Calhoun Station sets flow and measures AP. b,

Evaluate, compare with reference value or reference curve for degradation.

LIC-92-278R Page 9 B. Positive Displacement 1. Perform operational test (discharge pressure vs flow). 2. Heasure flow and discharge 3ressure and compare to reference values for degradat<on. 3. Measure vibration per Section X1/0&M Part 6. 7.0 ACCEPTANCE CRITERIA / CORRECTIVE ACTION A. Valves 1. Power Operated a. Alert Range: (1) 125% of reference value if reference.41ue 210 seconds. (2) 150% of reference value if reference value s10 seconds. (3) No alert range for rapid acting valves. (4) Alert range may be Engineering judgement if safety analysis value is less than calculated required action range. (5) Action taken is (a) Recalibrate instruments and retest valve, or, (b) Repair or replace valve or, (c) Engineering analysis to prove acceptability or, (d) Augment frequency of test, b. Required Action Range: (1) 2.5 times reference value or conservative to safety analysis. J

LIC-92-278R Page 10 (2) Action taken is (a) Valve is immediately declared inoperable, and (b) Repair or replace, or, (c) Recalibrate and retest, or, (d) Engineering analysis to prove operability. 2. Check Valves a. Maximum required accident flow for "open". b. Minimum AP for "close". c. Visual inspection. d. Leakage criteria, if required, e. Sample disassembly: (1) If one valve fails sample disassembly, all other valves in group require sample disassembly. (2) Typicallyi valves in class are disassembled in one valve every other refueling outage (e.g., al six-yearcycle). (3) Partial stroke / leak test upon reassembly if k practical. 3. Relief / Safety Valves a. Class 1 (1) If valve measured relief pressure ex;eeds >103% of stamped set pressure criteria, additional valves of same type and manufacture shall be set pressure tested on the basis of two additional valves for each valve failed up to the total number of valves of the same type and manufacture in the system of concern. If any of the additional valves tested exceed the stamped set pressure criteria by >3%, then all valves of the same type and manufacture shall be tested. i

LIC-92-278R Page 11 B. Pumps 1. Centrifugal a. Alert range: Table IWP-3100-2 of ASME Section XI. Table 3A and 3B of 0&M-6. b. Required ntion range: Table IWP-3100-2 of ASME Section XI. Table 3A and 3B of 0&M-6. 2. Positive Displacement (Reciprocating) a. Alert range: Table IWP-3100-2 of ASME Section XI. Table 3A and 3B of 0&M-6. b. Required action range: Table IWP-3100-2 of ASME Section XI. Table 3A and 3B of 0&M-6.

LIC-92-278R Page 12 1 I i HOTES: 1. Data is evaluated within 96 hours of the completion of the test. 2. Class 1, Class 2, ten-year hydros are not performed (reference ASME Code Case N-498). 3. The Fort Calhoun Station design basis definition of a safe shutdown l condition is " Hot Shutdown". 4. The Fort Calhoun Station only uses the "setpoint testing" section of Code for relief valve testing criteria and does not commit to the requirements for supervising relief valve testing as stated in PTC i 25.3 Code. 5. Components added to the ISI Program Plan as a result of plant / system modifications, engineering changes or re-evaluation of component eligibility requirements are considered operable based on interim acceptance criteria (established by construction, preservice, post maintenance, or preoperational tests), until a trend can be established. 6. Corrective actions as defined in the ISI Program Plan can be one or more of the following: a. Check calibration and/or recalibrate instrument, then perform retest of component. b. Repair or replace component, then perform acceptable retest. c. Engineering analysis to prove that component is capable of performing its design function. 7. In determining selection of components to be include in the ISI Program, Fort Calhoun Station does not consider passive failures of piping seismically qualified per the. USAR and not included specifically in the safety analyses contained in the USAR. l . -}}