ML20216F222
| ML20216F222 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe, Maine Yankee |
| Issue date: | 12/01/1997 |
| From: | Paul Bergeron, Palmer S, Michael Scott DUKE ENGINEERING & SERVICES |
| To: | |
| Shared Package | |
| ML20216F193 | List: |
| References | |
| MYC-2005, MYC-2005-R00, NUDOCS 9909210216 | |
| Download: ML20216F222 (119) | |
Text
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ORIGINAL: PAGE 1 of NPAGES Rev,1: PAGE 1 of PAGES Rev. 2: PAGE 1 of PAGES Rev.3: PAGE 1 of PAGES 1
QA RECORD' 3
RECORD TYPE 13.C16.036
.X.YES j\\DN 5fe4[/
V03gyQSog\\'i NO Safety Class /P.O. NO. (if applicable) 5377 YANKEE NUCLEAR SERVICES DIVISION CALCULATION / ANALYSIS FOR TITLE Spent Fuel Pool Passive Cooline PLANT Maine Yankee CYCLE NA CALCULATION NUMBER MYC-2005 PREPARED BY REVIEWED BY APPROVED BY SUPERSEDES
/DATE
/DATE
.m /DATE CALC /REV. NO.
ORIGINAL IhlblMbf/I[47 *YikW Michael W. Scott Suzanne almer A
ron
__ l
,o \\hb tu" gu I
KEYWORDS: Soent Fuel Pool. Decay Heat. Passive Cooline. OuatroPro COMPUTER CODES: NA EQUIP / RAG NOs. :
NA SYSTEMS:
Soent Fuel Pool
REFERENCES:
YRC-99i Revs. 0.1. MYC-1562 Revs. O'- 2. 3. MYC-1755 Rev. O. MYC-2004 Rev. O I
FORM WE-103-1 Revisica 3 f
l 9909210216 990826 PDR REV0P ERONUMtC l
l.
PDR 1
I t
a 4
Spent Fuel Fool Passive Cooling MYC-2005 Rev.0 i
December 1,1997 Prepared by MWS Reviewed by M Page.l.of__
'2a INDEX Eage 3.0 Structure / System / Component Applicability....................... 3 4.0 '
Problem Description............................................ 3 4.1 Background Data......................................... 3 4.2 Objectives
...............................................3 4.3 Intended Solution Method................................. 3 4.4
. Pertinent Literature Review................................ 4 4.5 Acceptance Criteria and Design Criteria Applied............. 4 5.0 Details of Analysis.............................................. 4 5.1 Design Inputs............................................ 4 5.2 Assump tions............................................. 4 53 Calculation / Analysis
.....................................5 53.1 Calculation of Actual Decay Heat Load in the SFP based on Test Data........................ 5 53.2 Passive Cooling.................................... 17 6.0 Results / Conclusions........................................... 30 6.1 VS Objectives
...........................................30 7.0 References.................................................... 31
)
1 8.0 Miscellaneous Information...................................... 32 8.1 Results Transmittal. Memo................................. 33 8.2 Spent Fuel Fool Heat-up Rate Test Procedure................ 40 83 Spent Fuel Pool Heat-up Rate Test Data..................... 67 8.4 Memo, " References for Spent Fuel Fool Heat up Calc"....... 104
' 8.5 Evaluation of Computer Code Use Form................... 107 8.6 Calculation / Analysis Review Form........................ 109 8.7 NED WE-103 Review Checklist........................... 113 8.8 NED Analysis Process Checklist........................... 117 1
i
Q Spent Fuel Pool Passive Cooling MYC-2005 Rev.0 December 1,1997 Prepared by MWS Reviewed by bR Page 3.of_
3.0 Structure / System / Component Applicability This calculation is applicable to the Maine Yankee Spent Fuel Pool (SFP).
4.0 Problem Descrintion This calculation provides a portion of the response to Maine Yankee Service Request M 27 (Reference 1). The fifth TAG item in this service request asks the following:
" Spent Fuel Pool Passive Cooling: Calculate the temperature in the SFP as a function of time with no active cooling,"
This calculation provides the temperature in the SFP as a function of time with no active cooling. The calculation also provides an estimate of the actual decay heat load as a function of time from test data taken at Maine Yankee. The estimated decay heat load is more representative of the actual decay heat load than the BTP 9-2 calculation in MYC-2004 (Reference 2), but still bounding with respect to the actual decay heat load.
4.1 Background Data Maine Yankee is permanently shutdown and has permanently defueled the reactor. This analysis was requested by Maine Yankee (Referer.ce 1) to support the desired operation of I
the spent fuel pool in the post shutdown condition.
I 4.2 Obiectives The objective of this calculation is:
To calculate the temperature in the SFP as a function of time with no aptive
- cooling, 4.3 Intended Solution Method This calculation was done using results from MYC-2004 (Reference 2), QuatroPro i
v o
g.
Spent Fuel Pool Passive Cooling MYC-2005 Rev.0 l
December 1,1997 Prepared by MWS Reviewed by jd_
Page__4.of_
t spreadsheets and hand calculations to perform the other calculations.
4.4 Pertinent Literature Review The following were reviewed before and/or during the analysis presented in this calculation:
1.
MY Service Request M-97-27, " Post Shutdown Safety Analysis," (Reference 1) 2.
MYC 2004, Rev. O, " Spent Fuel Fool Thermal-Hydraulic Calculations," (Reference 2) 3.
MYC 1755, Rev. 0, "End of Cycle 14 Allowable Fuel Removal Rate," (Reference 3) 4.
MYC-1562, Revs. 0,1,2, " Spent Fuel Pool Rerack Analysis," (Reference 4) 5.
YRC-991, Revs. 0,1," Estimation of Spent Fuel Pit Heat up Rate Incorporating Actual Plant Data and Thermal Losses," (Reference 5) 4.5 Acceptance Criteria and Design Criteria Applied Not applicable to this calculation.
5.0 Detmiin of Analysis 5.1 Design Inputs Table I from WE-100 Design Input Considerations was reviewed. It was found that none of the considerations were applicable to this calculation. There are no relevant,SER conditions / restrictions for this calculation.
5.2 Amanmotions Any assumptions made are included in the calculation / analysis writeups.
m Spent Fuel Pool Passive Cooling MYC-2005 Rev.0 December 1,1997 Prepared by MWS Reviewed by N Page._5_of_
l l
53 Calculation / Analysis In order to determine the temperature in the SFP as a function of time with no active cooling, first an estimate of the actual decay heat level in the SFP versus time was needed.
i The decay heat level was determined by running a test in the Maine Yankee spent fuel pool similar to tests run previously at Yankee Rowe and documented in YRC-991, Rev. O and 1 (Reference 5), This calculation will rely on the methods and equations already established in Reference 5. As in Reference 5 heat losses from the SFP due to conduction, convection and evaporation were determined. These losses combined with the pool heat load determined from the pool heat up test were combined to determine the actual decay heat load in the Maine Yankee SFP. This calculation does differ from YRC-991 in that it uses maximum and minimum values from the test data when determining heat losses to maximize the heat losses and thus the decay heat load in the pool. This results in a decay heat load that is more representative of the actual decay heat load than the BTP 9-2
- calculation in MYC-2004, but still bounding with respect to the actual decay heat load.
The actual decay heat is then compared to the decay heat calculated in MYC-2004 to determine the offset. The decay heat versus time calculated in MYC-2004 was then used to project the actual decay heat versus time. With the decay heat versus time and heat losses known for the SFP, the temperature in the SFP as a function of time with no active cooling was determined.
53.1 Calculation of Actual Decay Heat Based on Test Data The procedure used to perform the test at the Maine Yankee SFP is provided in Section 8.1 and the test data is provided in Section 8.2. He test began on October 221997 at about 11 AM and was completed at 11 AM on November 3,1997. There were two purposes to the test:
1.
The initial stage of the test was performed with the SFP cooling pumps shut off. his portion of the test was used to determine SFP heat-up.
2.
The second stage of the test was performed with the SFP cooling pumps throttled at various flow rates to maintain the SFP temperature at a set
c o,
7 Spent Fuel Pool Passive Cooling MYC-2005 Rev.0 December 1,1997 Prepared by MWS Reviewed byM Page _fi. of __
temperature so evaporation rates could be studied. The holds were at approximately 140*F,130*F,120*F,110 F, and 100"F.
As discussed earlier, the heat load attributable to the heat-up of the SFP plus the losses due to conduction, convection and evaporation equal the actual decay heat load in the SFP.
Each of these pieces were determined below.
Heat Load Attributable to the heat-up of the SFP The heat load attributable to the heat-up of the SFP is given by:
One eup
- Me where:
I m = the SFP liquid mass at = elapsed time for increase in temperature c, = specific heat
+T = change in Temperature Qum, will be determined early in the test data.
SFP liquid mass, m, will be determined first. Since all the items in the pool have volumetric heat capacities equal to or less than water, the entire volume of the pool was assumed to be filled with water to maximize Qump.
From the (Reference 7), the elevation of the SFP liquid can be determined from the SFP level recorded on the test data sheets as follows:
Elevation SFP liquid level = [(46ft x 12in/ft) - Recorded SFP level (in)]/12in/ft l
8p.
U l
L Spent Fuel Pool Passive Cooling MYC-2005 Rev.0 December 1,1997 Prepared by MWS Reviewed by M._.
Page _7_ of _
I (Reference 7, contains the ruler measurement reference, item 2) from the test data between 12:50 PM and 13:50 PM on October 22,1997 the SFP level is 21.25 inches. Thus, i
l Elevation SFP liquid level = [(46ft x 12in/ft) - 21.25in]/12in/ft = 44.23ft j
From MYC-1562 (p 150), the pool bottom elevation is 7.5ft. The liquid level in the SFP is then:
SFP liquid level ='44.23ft - 7.5ft = 36.73ft /
Given the other pool dimensions from MYC-1562 of 41.36ft in length by 36.89ft in width the liquid volume in the SFP is then:
SFP liquid volume = 36.73ft x 41.36ft x 36.89ft = 5.60 x 104 ft' /
Average temperature of the SFP liquid at 12:50 PM and 13:50 PM on October 22,1997 is 81.85'F and 82.89 F respectively. From the ASME Steam Tables the specific volume at the lower of the two temperatures is 0.01608 ft'/lb, and thus the liquid mass, m, is:
i m = 5.60 x 104 ft' x (1/0.01608 ft /lb ) = 3.48 x 10'lb, 3
and At = 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and c = 1.00 BTU /lb,*F p
and AT = 82.89*F - 81.85*F = 1.04*F s l
L
)
p Spent Fuel Pool Passive Cooling MYC-2005 Rev.0 December 1,1997 J
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and thus, Qu,,,, = (3.48 x 10' lb ) x (1.00 BTU /lb,*F) x (1.04*F/1hr)
Qu e, = 3.62 x 10' BTU /hr /
Conduction Losses From YRC-991 the conduction losses are given by:
2 (1.05
,, ) ( 37 92 f e ) ( T,7, - T,,g, )
cond abon "
g gg and (1.05
_,) ( 3482 ft3 ) ( T,7, - S OF )
cond below g gg
- Where, 1.05 BTU /hr-ft *F = thermalconductivity of concrete * /
2 3792 ft = SFP surface area above ground level"* <
3482 ft = SFP surface area below ground level"* /
2 6 ft = thickness of SFP concrete (Reference 7)
/
Ts,r = Max Average SFP water temperature (*F)"
Tm = Min outside air temperature ("F)"
50 *F = assumed ground temperature ( F)""
l
'YRC-991 used 0.85 BTU /hr-ft *F, a more conservative value of 1.05 BTU /hr-ft *F (Reference 7) was used here to maximize the conduction losses. s "The temperatures are chosen to maximize the conduction losses and therefore decay heat.
1
- " Calculated below:
o m
Spent Fuel Fool Passive Cooling MYC-2005 Rev.0 l
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Prepared by MWS Reviewed by $
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From Reference 7 grade is at either the 20 or 21 ft elevation for this calculation 20 ft was used, it maximizes conduction in this calculation and later minimizes conduction in the Section 5.3.2 calculation. Knowing from above that the pool bottom is at elevation 7.5 ft yields that grade elevation is at a pool level of 20 ft - 7.5 ft = 12.5 ft /
As stated and determined earlier SFP dimensions are 41.36 ft x 36.89 ft and the water level is 36.73 ft. So SFP surface area above ground level is:
(36.73 ft - 12.5 ft) x (41.36 ft x2) + (36.73 ft - 12.5 ft) x (36.89 ft x 2) = 3792 ft,
2 and the SFP surface area below ground is:
(12.5 ft) x (41.36 ft x2) + (12.5 ft) x (36.89 ft x 2) + (41.36 ft x 36.89 ft) = 3482 ft j 2
- 50 "F was the assumed ground temperature in YRC-991 and it is a reasonable value to assume for this calculation.
- Thus, 8, "_, ) ( 3792 fe ) ( 141r-26F) 2 1.05 0 a a=v.
- c s fe which yields:
4 Q
o.3,,, = 7.63 x 10 BTU /hr s and 8"
(1.05
,) (3482 ft2 ) ( 1417-sor) b s w o.
- ean s ge which yields:
i Spent Fuel Fool Passive Cooling MYC-2005 Rev.0 i
December 1,1997 Prepared by MWS Reviewed by M Page _.10. of __
Qm = 5.55 x 104 BTU /hr and 8
Q,,4,,,,3 = 1.32 x 10 BTU /hr Convection Losses From YRC-991 the ccavection losses are given by:
- (1 y _ g 2 _ y ) { SA,y ) ( T,, - T,g,,, )
conv 3
- Where, 1 BTU /hr-ft *F = convective heat transfer coefficient SAs, = Pool surface area Fool dimensions from MYC-1562 are 41.36ft in length by 36.89ft in width and SAs, = 41.36ft x 36.89ft = 1.53 x 10' ft2 Tsy = Max Average SFP water temperature (*F)*
Tse.a = Min ambient air temperature inside the SFP building from the test data sheets, Fluke 2, Channel 3 ( F)*
'The temperatures are chosen to maximize the convection losses and therefore decay heat
- Thus,
)
8" d,, = ( 1
) ( 1.53 x10 fC2 ) ( 141F - 57. 4F )
3 o
hr ~ fC3-F which yields:
8 Q., = 1.28 x 10 BTU /hr
7..
- u-Spent Fuel Fool Passive Cooling MYC-2005 Rev.0 J
December 1,1997 Prepared by MWS Reviewed by d Page _.11. of __.
I I
Evaporation Losses Frcm YRC-991 the evaporation losses are given by:
( Evap Rate ) (SA,, ) ( h,,)
g
( v, ) ( 12 nch ) ( 24 day )
fC where:
v, = the specific. volume of the SFP water 1
1
. h = the evaporation specific enthalpy of the SFP water g
The evaporation rate is calculated using equation 18 below from YRC-991, Appendix A, assuming atmospheric pressure is 14.21 psia (28.93 in Hg, same as used in YRC-991) and the wind speed is 10ft/sec or 6.8 MPH (0 MPH was used in YRC-991, the 6.8 MPH used for this calculation more than compensates for any actual wind speed over the pool surface and results in increased evaporation heat loss and thus increased calculated decay heat load):
4 Evaporaclon Rate = 0.771 { 1. 465 - 0. 0186 P
)( 0. 44 +0.118 W) { VP,,, - VP
)
where:
Evaporation Rate is in units of inches / day P. =
Atmospheric Pressure (inches Hg) #
W=
Wind Velocity (MPH) inside the SFP building = 6.8 MPH for this calculation VPs,, =
Water Vapor Pressure at SFP Water Temperature (inches Hg) l
j Spent Fuel Pool Passive Cooling MYC-2005 Rev.0 l
December 1,1997 Prepared by MWS Reviewed by.d_.
Page _.12. of _
l VP
=
Water Vapor Pressure at SFP Air Temperature and Humidity (inches Hg)
' Relative Humidity '
y
, y,ser air nem znn
(
i i
where:
VPsrr.9 = Water Vapor Pressure at SFP Air Temperature (inches Hg)
Thus, to determine Q,,,, first VP,. must be determined. First VPsyp i, is determined for the test air temperature on October 22,1997 at 12:00 PM = 62.34"F. From the ASME Steam i
Tables at 62.34*F:
VPspp i, = 0.57 in Hg /
The relative humidity was determined at 12:00 PM on October 22,1997 from the recorded test data. The SFP building air temperature taken with a wet bulb thermometer was 52"F and the SFP building air temperature taken with a dry bulb thermocouple was 62.34*F.
From the Psychrometric Chart in Reference 6 the relative humidity is then approximately 50%.
and VP, = 0.57 in Hg (50/100) = 0.29 in Hg j j
the average water temperature recorded by the instrumentation at 12:50 PM on October 22,1997 is 82.89'F and at this temperature VPs,p = 1.13 in Hg /
l 1
and Evaporation rate in inches / day is given by:
j
l Spent Fuel Pool Passive Cooling MYC-2005 Rev.0 l
December 1,1997 l
Prepared by MWS Reviewed by _d_
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l Evaporation Rate = 0.771(1.4 65 - 0. 018 6 P
)
Evaporation Rate is then:
= 0.771(1. 4 65 - 0. 018 6 ( 28. 931nHg))(0. 44 + 0,118 ( 6. 8 MPH))(1.131nHg - 0. 2 9 fnHg)
= 0.75 in/ day and finally as discussed earlier From YRC-991 the evaporation losses are given by:
?
( Evap Rate ) (SA,,, ) ( h, )
g
{ v,) ( 12 f.nch ) 24 hr day)
Et where:
2 1.53 x 10' ft as calculated earlier SAser =
3 L
v, =
the specific volume of the SFP water at 82.89"F = 0.01608 ft /lb, h,, =
the evaporation specific enthalpy of the SFP water at 82.89*F h,, =
1046.8 BTU /lb, j
and l
l l
i
Spent Fuel Pool Passive Cooling MYC-2005 Rev.0 December 1,1997 Prepared by MWS Reviewed by _4f Page _.14. of _
3 2
(. 0.75 in/ day ) (1. 53x10 fc ) ( 1046. 8 sTU/lb,, )
( 0.01608 fc3/lb,, ) ( 12
) ( 24
)
which yields:
s Q,,,=
2.59 xlo BTU /hr Totaldecay heat load is then:
Q4.c.,=
Q u,+ Qcooaio + Ocoo,+ Q.g 6
5 5
Q3,c,y=
3.62 x 10 BTU /hr + 1.32 x 10 BTU /hr + 1.28 x 10 BTU /hr +
5 2.59 x 10 BTU /hr Q4,,,7=
4.14 x 10' BTU /hr This is the decay heat load estimate for October 22,1997, using the test results. From MYC-2004, the calculated decay heat load using Branch Technical Position ASB 9-2 with 6
an uncertainty factor of 0.1 for October 30,1997 was 5.84 x 10 BTU /hr. The ratio of the value predicted by BTP ASB 9-2 to the value predicted by the test is:
Ratiom x3,,.2mst = (5.84 x 10' BTU /hr)/(4.14 x 10' BTU /hr)
Ratiom 33,,.umr = l 41
- Branch Technical Position ASB 9-2 is a good predictor of the shape of decay heat decrbase
- with time, but, as can be seen from the experimental prediction, overly conservative in the prediction of actual decay heat levels, especially with a 10% uncertainty applied, as was in MYC-2004. As a result, the QuatroPro spreadsheet created in MYC-2004 to show decay heat levels versus time after shutdown was incorporated in this calculation and an i
9 Spent Fuel Pool Passive Cooling MYC-2005 Rev.0 December 1,1997 Prepared by MWS Reviewed byN Page _15_ of _
{
}
additional column was added to the decay heat versus time after shutdown table that incorporates the ratio calculated above to provide an estimate, based on the test, of the decay heat load versus time after shutdown. Table 5.3.1-1 on the next page shows the modified spreadsheet.
..../..&. I A U+ * ?
.*54 g ; _.,,
...,_.e i*
Spent Fuel Pool Passive Cooling MYC-2005 Rev.0 December 1,1997 Prepared by MWS Reviewed by.yf_.
Page _.16. of _
'l TABLE 5.3.1-1 Decay Heat Load Versus Time QuatroPro for Windows Version 6.0 Date Days-After Total Powerin SFP Total Power in SFP Total Power in SFP Based j
Shutdown Based on BTP Based on BTP ASB on Heat up Test (BTU /hr)
ASB 9-2(MW) 9-2 (BTU /hr) 10/15/97 313 1.74773 5.96E+06 4.23E+06 10/30/97 328 1.71064 5.84E+06 4.14E+06 11/29/97 358 1.64511 5.61 E+06 3.98E+06 12/29/97 388 1.58915 5.42E+06 3.85E+06 01/28/98 418 1.5409 5.26E+06 3.73E+06 02/27/98 448 1.49892 5.11 E+06 3.63E+06 03/29/98 478 1.46207 4.99E+06 3.54E+06 04/28/98 508 1.42946 4.88E+06 3.46E+06 05/28/98 538 1.40037 4.78E+06 3.39E+06 06/27/98 568 1.37425 4.69E+06 3.33E+06 07/27/98 598 1.35065 4.61E+06 3.27E+06 08/26/98 028 1.32921 4.54E+06 3.22E+06 09/25/98 658 1.30962 4.47E+06 3.17E+06 10/25/98 688 1.29166 4.41 E+06 3.13E+06 11/24/98 718 1.27513 4.35E+06 3.09E+06 12/24/98 748 1.25985 4.30E+06 3.05E+06 06/22/99 928 1.18815 4.05E+06 2.88E+06 12/19/99 1108 1.13931 3.89E+06 2.76E+06 06/16/00 1288 1.10412 3.77E+06 2.67E+06 12/13/00 1488 1.07743 3.68E+06 2.61 E+06 1
12/13/01 1833 1.03783 3.54E+06 2.51 E+06 12/13/02 2198 1.00773 3.44E+06 2.44E+06 12/13/07 4024 0.89079 3.04E+06 2.16E+06
Spent Fuel Pool Passive Cooling MYC-2005 Rev.0 December 1,1997 Prepared by MWS Reviewed by Ik Page_1Z.of_
j 5.3.2 Spent Fuel Pool Passive Cooling Calculation of the temperature in the SFP as a function of time with no active cooling is performed in this section.
This calculation evaluates evaporation, conduction, and convection losses to determine the date at which passive cooling can be achieved at 190 F and 200*F.
Evaporation Losses The evaporation rate equation used earlier in Section 5.3.1 needs to be evaluated here against the test data before being used to perform passive cooling calculations. It will be evaluated against the data taken at the 140*F hold point.
Repeating the equation here:
Evaporation Rate = 0.771(1. 4 65 - 0. 0186 P
)
where:
Evaporation Rate is in units of inches / day P.=
Atmospheric Pressure (30 inches Hg assumed for this calculation, since higher pressure reduces heat removal rate) <
W=
Wind Velocity (MPH) inside the SFP building, zero MPH assumed for this calculation /
VPsn, =
Water Vapor Pressure at SFP Water Temperature (inches Hg)
VP, =
Water Vapor Pressure at SFP Air Temperature and Humidity (inches Hg)
Relative Humidity' yp
, y,srr air aca too
e, Spent Fuel Fest Passive Ceoling MYC-2005 Rev.0 December 1,1997 Prepared by MWS Reviewed by _lld Page._18.of_
where:
VPsn* = Water Vapor Pressure at SFP Air Temperature (inches Hg)
Thus, to determine evaporation rate, first VP., must be determined. First %
is determined for the lowest test air temperature between October 25,1997 at 11:07 AM and October 26,1997 at 11:07 AM = 76.6*F From the ASME Steam Tables at 76.6*F:
y VPsy, = 0.92 in Hg j
The highest relative humidity between October 25,1997 at 11:07 AM and October 26,1997 at 11:07 AM was determined from the hand input data table in Attachment 8.3, the SFP building air temperature taken with a wet bulb thermometer and the SFP building air temperature (point 13) taken with a dry bulb thermocouple are used along with the Psychrometric Chart in Reference 6 to determine relative humidity. Table 5.3.2-0 on the next page shows the data enveloping this period.
~we,,n
.**"s,
,,8 se
o
,v Spent Fuel Pool Passive Cooling MYC-2005 Rev.0 December 1,1997 Prepared by MWS Reviewed by d__
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TABLE 5.3.2-0 Relative Humidity Determination Date/ Time SFB AmbientTemp SFB AirTemp Approximate Dry Bulb ("F)
Wet Bulb ('F)
Relative Humidity 10/25 0900 EDT 76.04
/
73
/
83 %
10/251200 EDT 79.11
/
74 4
80 %
10/251500 EDT 81.32 y
76 80 %
10/251800 EDT 81.93 s
75 72 %
j 10/25 2100 EDT 80.53
/
75 79 %
10/26 0000 EDT 79.29 s
74
/
80 %
10/26 0200 EST 77.66
/
73 81 %
10/26 0500 EST 76.98
/
73 83 %
.10/26 0800 EST 77.62 s
74 85 %
j 10/261100 EST 77.56
/
73 4
81 %
As can be seen from the table, the highest relative humidity was 85%. j and VP., = 0.92 in Hg (85/100) = 0.78 in Hg /
the average water temperature recorded by the instrumentation between 11:07 AM on
.. October 25,1997 and 11:07 AM on October 26,1997 is 140*F and at this temperature VP, = 5.89 in Hg 4 and Evaporation rate in inches / day is given by:
Spent Fuel Fool Passive Cooling MYC-2005 Rev.0 December 1,1997 Prepared by MWS Reviewed byi Page _20 of __
Evaporation Race = 0.771(1. 465 - 0. 0186 P
)
Evaporation Rate is then:
= 0.771(1.465 - 0.0186 ( 30.inHg))(0.44 + 0.118 (0. 0 MPH))(5.89dnHg - 0.78inHg)
/
= 1.57 in/ day 4 J
s The actual data from this period shows a level change of 19.5 inches to 22.5 inches (interpolated from the two nearest data points) for a level change of 3.0 in/ day. So the evaporation rate equation taken from YRC-991 clearly under predicts the evaporation rate and as a result will under predict the energy loss by evaporation. The difference is likely attributable to some air flow over the pool surface. An air speed of about 3 MPH over the pool surface would increase the evaporation rate to the measured value. Based on these results, evaporation rates for passive cooling calculations were determined at 1,3, and 5 MPH wind speeds.
The evaporation rates determined below assume the following:
Atmospheric Pressure =
30 in Hg SFP building air temperature =
100*F Outside air temperature =
100 F Wind speed over SFP surface =
1,3,5 MPH SFP water temperature =
190*F, and 200 F, also 210*F @ 1 MPH SFP building relative humidity = 80%
These assumptions are reasonable and none of them significantly impact the results, except the wind speed. The calculation below is performed with a wind speed of one MPH and
~
a 190*F SFP water temperature. The results of the other calculations are included in Table 5.3.2-1.
As in previous calculations:
I J
i
i r "
1 Spent Fuel Pool Passive Cooling MYC-2005 Rev.0 j
l December 1,1997 Prepared by MWS Reviewed by N Page _21. of _.
)
l l
Evaporation Rate = 0. 771 { 1. 4 6 5 - 0. 018 6 P,,)( 0. 4 4 +0.118 N) { VP,,, - VP,,)
where:
Evaporation Rate is in units of inches / day P,. =
Atmospheric Pressure (30 inches Hg assumed for this calculation) i W=
Wind Velocity (MPH) inside the SFP building,1 MPH assumed for this calculation VPs,p =
Water Vapor Pressure at SFP Water Temperature (inches Hg)
VP..=.
Water Vapor Pressure at SFP Air Temperature and Humidity (inches Hg)
' Relative aumidity '
yp
, y,srr air ata gg9
(
where:
VPser.a = Water Vapor Pressure at SFP Air Temperature (inches Hg)
Thus, to determine evaporation rate, first VP, must be determined. First V#p.,
is determined at 100*F VPsvr.w = 1.9 in Hg j The relative humidity assumed for this calculation is 80%.
So, VP,. = 1.9 in Hg (80/100) = 1.52 in Hg /
The assumed SFP water temperature is 190*F and at this temperature VPs,p = 19.0 in Hg. j
c, S' pent Fuel Pool Passive Cooling MYC-2005 Rev.0 December 1,1997 Prepared by MWS Reviewed by $
Page _22. of _
and Evaporation rate in inches / day is given by:
Evaporation Rate = 0.771(1.465 - 0. 018 6 P
)( 0. 44 +0.118 W) { VP,,,- VP
)
Evaporation Rate is then:
= 0. 771(1. 465 - 0. 0186 ( 3 0. InHg))(0. 44 + 0.118 (1. 0 MPH))(19. 0inHg - 1. 52inNg)
= 6.8 in/ day /
and, as before:
(Evap Rate) (SA,,,) (h,)
g
( v ) ( 12 nch ) ( 24 day )
l f
fc i
where:
1.53 x 10 ft as calculated earlier 8 2 SA,=
3 v, =
the specific vchtme of the SFP water at 190*F = 0.01657 ft /lb, h=
the evaporation specific enthalpy of the SFP water at 190*F g
h=
984.1 BTU /lb, g
and 3
( 6.81n/ day) (1.53x10 ft2 ) ( 984.1 BTU / lb, )
( 0.01657 ft /lb,) ( 12 inch ) ( 24 day )
3 E
ft
Spent Fuel Pool Passive Cooling MYC-2005 Rev.0 December 1,1997 Prepared by MWS Reviewed byM Page _23_ of _
which yields:
Q,,,, =
2.15 x 10' BTU /hr j Evaporation losses were calculated for the other conditions using the same approach and the results are summarized in Table 5.3.2-1 J
e
f
'o Spent Fuel Fool Passive Cooling MYC-2005 Rev.0 December 1,1997 Prepared by MWS Reviewedby N Page _21 of _
TABLE 5.3.2-1 Heat Loss Due to Evaporation for Various Conditions SFP Temperature SFP Surface Wind Speed Heat Loss Due to Evaporation
( F)
(MPH)
(BTU /hr) 6 190 1
2.15 x 10
/
6 190 3
3.07 x 10
/
6 190 5
3.98 x 10 y
200 1
2.68 x 10'
/
200 3
3.80 x 10'
/
l 6
200 5
4.92 x 10 j
210 1
3.28 x 10' -
i s
Conduction Losses Conduction losses are calculated here for SFP water temperatures of 190*F, 200*F and 210*F.
As before, from YRC-991 the conduction losses are given by:
, " 7 ) ( 3 7 92 f t ) ( 7,,,. 7
,g
)
8 (1.05 o
- "d *"
6 fe and q
l
,o s
Spent Fuel Pool Passive Cooling MYC-2005 Rev.0 December 1,1997 Prepared by MWS Reviewed by[
Page _25. of __
8 (1.05
,, ) ( 3 4 82 f c 2 ) ( T,,, - 6 0F )
- "d b*
- 6 ft
- Where, 1.05 BTU /hr-ft *F = thermal conductivity of concrete 2
3792 ft = SFP surface area above ground level 3482 ft: = SFP surface area below ground level '
6 ft = thickness of SFP concrete Ts,p = SFP water temperature,190*F,200*F,210"F T
= Outside air temperature 100*F 60 *F = assumed ground temperature (*F)*
- Assumed temperature has been increased to decrease conduction losses.
Thus at 190*F,
_ ",7 ) ( 3792 ft2 ) ( 190F-100F )
8 (1.05 cond above "
g gg which yields:
4 Qw% = 5.97x 10 BTU /hr j and 8"
(1.05
,7 ) ( 3482 ft2 ) ( 190F-60F) 6 Ec which yields:
Qw% = 7.92 x 104 BTU /hr s
Spent Fuel Pool Passive Cooling MYC-2005 Rev.0 December 1,1997 Prepared by MWS Reviewed byh Page _2fi_ of __
and 5
Qana tou = 1.39 x 10 BTU /hr @ 190*F /
l and at 200*F:
bu, = 6.63 x 104 BTU /hr <
Lw, = 8.53 x 104 BTU /hr /
and 5
Q,,,4,,,,i = 1.52 x 10 BTU /hr @ 200"F /
and at 210*F:
b,% = 7.30 x 104 BTU /hr bw = 9.14 x 104 BTU /hr and 5
Q.,4,,,,3 = 1.64 x 10 BTU /hr @ 210*F /
Convection Losses From YRC-991 the convection losses are given by:
~
C00V
I l
l
,a Spent Fuel Fool Passive Cooling MYC-2005 Rev.0 4
December 1,1997 Prepared by MWS Reviewed by d_
Page ZZ.of
- Where, 1 BTU /hr-ft *F = convective heat transfer coefficient 2
sam = Pool surface area Pool dimensions from MYC-1562 are 41.36ft in length by 36.89ft in width and SA, = 41.36ft x 36.89ft = 1.53 x 105 ft2 T, = Average SFP water temperature 190*F,200 F,210 F T, = Ambient air temperature inside the SFP building = 100*F Thus for 190*F, 8"
d =v = (1 5
57 - gc1 - y ) ( 1.53 x10 f t ) ( 1907-100F) c which yields:
5 Q., = 1.38 x 10 BTU /hr /
and for 200*F, s
Q,,,, = 1.53 x lo BTU /hr /
and for 210*F, I
r 5
Qg, = 1.68 x 10 BTU /hr /
4
Spent Fuel Pool Passive Cooling MYC-2005 Rev.0 December 1,1997 Prepared by MWS Reviewedby N Page _28_ of _
Summarv of Enerstv Losses TABLE 5.3.2-2 Summary of Heat Loss for Various Conditions SFP SFP Surface Heat Loss Heat Loss Heat Loss bt Temperature Wind Due to Due to
- Due to Hea Loss
' (*F)
Speed Evaporation Conduction Convection (BTU /hr)
(MPH)
(BTU /hr) 190 1
2.15 x 106 1.39 x 105 1.38 x 10 /
2.43 x 106, 5
s j
190 3
3.07 x 10'. <
1.39 x 105 1.38 x 105 /
3.35 x 10',
j 190 5
3.98 x 10' /
1.39 x 105 1.38 x 105 /
4.26 x 10' /
j 200 1
2.68 x 10' e 1.52 x 10 /
1.53 x 105 2.99 x 106 5
y 200 3
3.80 x 10' /
1.52 x 10 /
1.53 x 10 e 4.11 x 106 s 5
5 200 5
4.92 x 10' s 1.52 x 10 /
1.53 x 10,
5.23 x 10,
5 5
6 210 1
3.28 x 10'.
1.64 x 10 e 1.68 x 105 3.61 x 10',
5 s
Based on the results contained in Table 5.3.1-1 for decay heat load from the heat up test.and
-Table 5.3.2-2 for total heat loss, Table 5.3.2-3 was constructed which shows the date that
. passive cooling can be attained at 190*F, 200*F, and 210*F for the SFP wind speeds
- evaluated. Passive cooling can be attained when the total heat loss matches the decay heat load in the SFP. The nearest date for which the heat load is less than the losses is taken from table entries in Table 5.3.1-1.
I
[
- o
- o Spent Fuel Pool Passive Cooling MYC-2005 Rev.0 December 1,1997 Prepared by MWS Reviewed by %E Page _29_ of _
TABLE 5.3.2-3 Date Passive Cooling is Attainable for Various Conditions SFP SFP Surface Total Days After Date Temperature Wind Speed Heat Loss Shutdown
( F)
(MPH)
(BTU /hr) 190 1
2.43 x 10' s 2198 12/13/02 s 190 3
3.35 x 10' /
568 6/27/98 j
6 190 5
4.26 x 10 already attainable j j
200 1
2.99 x 10' j 928 6/22/99 200 3
4.11 x 10',
already attainable /
200 5
5.23 x 106 s already attainable j 210 1
3.61 x 106/
478 3/29/98
/
- It wasn't necessary to determine these values. They are earlier than the present date.
Spent Fuel Pool Passive Cooling MYC-2005 Rev.0 l
December 1,1997 Prepared by MWS Reviewed by N Page 3.0_ of _
6.0 Results/ Conclusions 6.1 VL Obiectives The objective of this calculation was:
To calculate the temperature in the SFP as a function of time with no active i
cooling.
The objective of this calculation was met as follows:
Dates at which passive cooling was attainable for SFP temperatures of 190 F, 200 F, and 210 F for various SFP surface wind speeds were determined. The results are summarized in Table 5.3.2-3.
i
7 l
t l
Spent Fuel Pool Passive Cooling MYC-2005 Rev.0 December 1,1997 l
Prepared by MWS Reviewe'd by N Page._31, of _
l l
1 7.0 References 1.
MY Service Request M-97-27, " Post - Shutdown Safety Analysis," dated September 4,1997.
2.
MYC-2004, Rev 0, " Spent Fuel Pool Thermal-Hydraulic Calculations," dated November 1997.
3.
MYC-1755,"End of Cycle 14 Allowable Fuel Removal Rate," dated February 2,1995.
4.
MYC-1562, Revs. O,1,2, " Spent Fuel Pool Rerack Analysis," dated January 1993, June 1993, and February 1995 respectively.
5.
YRC-991, Revs. 0,1, " Estimation of Spent Fuel Pit Heat-up Rate Incorporating Actual Plant Data and Thermal Losses," dated June 1992 and April 1994.
6.
Fundamentals of Classical Thermodynamics G. J. Van Wylen and R. E. Sonntag, John Wiley and Sons, Inc., Second Edition, Copyright 1973.
7.
SFPI 97-020, " References for Spent Fuel Pool Heat up Calc," dated November 25, 1997.
f l
I
Spent Fuel Pool Passive Cooling MYC-2005 Rev.0 December 1,1997 Prepared by MWS Reviewed by Page _22. of __
8.0 Miscellaneous Information The sections contained herein are as follows:
8.1 Results Transmittal Memo 8.2 Spent Fuel Pool Heat-up Rate Test Procedure 83 Spent Fuel PoolHeat up Rate Test Data 8.4 Memo, " References for Spent Fuel Pool Heat up Calc" 8.5 Evaluation of Computer Code Use Form 8.6 Calculation / Analysis Review Form 8.7 NED WE-103 Review Checklist 8.8 NED Analysis Process Checklist i
z--.
,u l
Spent Fuel Pool Passive Cooling MYC-2005 Rev.0 December 1,1997 l
Prepared by MWS Reviewed by Page _33. of _.
j
=__
l 8.1 Results Transmittal Memo i
l I
i i
i i
l i
l i
i l
l I
MEMORANDUM g 2co f b' N j
YANKEE ATOMIC-BOLTON
)
To P. L. Anderson Date December 1.1997 Gmep #
TAG MY 97-052 Fmm M. W. Scott W.O.#
5377 Subject SFP Passive Cooling Calculation Results LM.S.#_
File #
I REFERENCES 1.
Maine Yankee Service Request M-97-27, " Post-Shutdown Safety Analysis," dated September 4,1997.
2.
MYC-2005," Spent Fuel Pool Passive Cooling," dated December 1,1997.
3.
TAG MY 97-050,"SFP Boron Dilution Results," dated September 25,1997.
4.
TAG MY 97-051, "SFP Thermal-Hydraulic Calculation Results," dated December 1, 1997.
DISCUSSION The Transient Analysis Group has performed calculations that provide a portion of the response to Maine Yankee Service Request M-97-27 (Reference 1). The final TAG item in this service request asked the following:
" Spent Fuel Pool Passive Cooling: Calculate the temperature in the SFP as a function of time with no active cooling,"
In order to determine the temperature in the SFP as a function of time with no active cooling, first an estimate of the actual decay heat level in the SFP versus time was needed. The decay heat level was determined by running a test in the Maine Yankee spent fuel pool similar to tests run previously at Yankee Rowe. Heat losses from the SFP due to conduction, convection and evaporation were determined in Reference 2.
These losses along with the pool heat load determined from the pool heat up test were combined to determine an estimate of the actual decay heat load in the Maine Yankee SFP.
The Reference 2 calculation uses maximum and minimum values from the test data when determining heat losses for conduction and convection to maximize their heat losses and provide some conservatism for the estimated decay heat load in the pool.
This results in a decay heat load that is more representative of the actual decay heat load than the BTP 9-2 calculation in MYC-2004, but still bounding with respect to the actual decay heat load.
__j
,o M N(., - 1Q05 s
P. L. Anderson P. 3 h l
December 1,1997 Page 2 f
l The estimated decay heat is then compared to the decay heat calculated in MYC-2004 i
to determine the offset. The decay heat versus time calculated in MYC-2004 was then used to project the actual decay heat versus time. With the decay heat versus time and heat losses known for the.SEP,.the. temperature.irtthelEP.as a function of time with no active cooling was determined.
This memo provides the results of these calculations (Reference 2) as follows:
1.
The estimated decay heat load in the spent fuel pool as a function of time was calculated. The results are presented in Table 1.
2.
Conduction, convection, evaporation, and total heat losses were calculated for various conditions. The results are presented in Table 2.
3.
Based on the results contained in Table 1 for decay heat load from the heat up test and Table 2 for total heat loss, Table 3 was constructed.
It shows the date that passive cooling can be attained at 190*F, 200*F, and 210 F for the SFP wind speeds evaluated. Passive cooling can be attained when the total heat loss matches the decay heat load in the SFP.
The nearest date for which the heat load is less than the losses is taken from table entries in Table 1 as the date at which passive cooling is attainable.
This memo along with References 3 and 4 close out the Transient Analysis Group portion of Maine Yankee service request 97-27.
S AFETY EVALUATION This calculation is safety related. It provides information to be used in the Defueled Safety Analysis Report.
/ /
/
Date: / 2///87 M. W. Scott, S'eitior Nuclear Engineer ' '
Transient Analysis Group Reviewed by-Am 9thtL Date: la h M'1 S. PalnTer, Senior Engineer Transient Analysis Group
h\\jl., ~36I P. L. Anders:n f'3b Dectmber 1,1997 Page 3 M*
2 1 2# #
Date:
~
Approved by:
P. A. Berger Manager Transient ysis Group c:
J. R. Chapman R. P. Jordan (Maine Yankee)
D. B. Boynton (Maine Yankee) i
@(- 2.,@T P. L. Anderson 37 December 1,1997 Page 4 TABLE 1 Decay Heat Load Versus Time Date Days After Total Powerin SFP Total Power in SFP Total Power in SFP Based Shutdown Based on BTP Based on BTP ASB on Heat up Test (BTU /hr)
ASB 9 2(MW) 9 2 (BTU /hr) 10/15/97 313 1.74773 5.96E+06 4.23E+06 10/30/97 328 1.71064 5.84E+06 4.14E+06
)
11/29/97 358 1.64511 5.61E+06 3.98E+06 12/29/97 388 1.58915 5.42E+06 3.85E+06 01/28/98 418 1.5409 5.26E+06 3.73E+06 02/27/98 448 1.49892 5.11E+06 3.63E+06 03/29/98 478 1.46207 4.99E+06 3.54E+06 04/28/98 508 1.42946 4.88E+06 3.46E+06 05/28/98 538 1.40037 4.78E+06 3.39E+06 06/27/98 568 1.37425 4.69E+06 3.33E+06 07/27/98 598 1.35065 4.61E+06 3.27E+06 08/26/98 628 1.32921 4.54E+06 3.22E+06 09/25/98 658 1.30962 4.47E+06 3.17E+06 10/25/98 688 1.29166 4.41E+06 3.13E+06 11/24/98 718 1.27513 4.35E+06 3.09E+06 12/24/98 748 1.25985 4.30E+06 3.05E+06 06/22/99 928 1.18815 4.05E+06 2.88E+06 12/19/99 1108 1.13931 3.89E+06 2.76E+06 06/16/00 1288 1.10412 3.77E+06 2.67E+06 12/13/00 1468 1.07743 3.68E+06 2.61E+06 2.51Et06 1.0. 783 _
3.54E+06 3
12/13/01 1833 12/13/02 2198 1.00773 3.44E+06 2.44E+06 12/13/07 4024 0.89079 3.04E+06 2.16E+06 s
P. L. Anderson kSUO
~
December 1,1997 Page 5 f, 3 g-TABLE 2 Summary of Heat Loss for Various Conditions SFP SFP Heat Loss Heat Loss Heat Loss Total Temperature Surface Due to Due to Due to Heat Loss
(*F)
Wind Evaporation Conduction Convection (BTU /hr)
Speed (BTU /hr)
(BTU /hr)
(BTU /hr)
(MPH) 190 1
2.15 x 10' 139 x 10 1.38 x 10 2.43 x 10' 5
5 190 3
3.07 x 10 1.39 x 105 138 x 10 335 x 10' 6
5 5
138 x 105 4.26 x 10' 190 5
3.98 x 10' 139 x 10 200 1
2.68 x 10 1.52 x 10 1.53 x 10 2.99 x 10' 6
5 5
200 3
3.80 x 10' 1.52 x 10 1.53 x 10 4.11 x 10' 5
5 5
5 5.23 x 10' 200 5
4.92 x 10' 1.52 x 10 1.53 x 10 5
5 3.61 x 10' 210 1
3.28 x 10' 1.64 x 10 1.68 x 10 O
1 i
Y)'C-lpof f.[G P. L. Anderson December 1,1997 Page 6 TABLE 3 Date Passive Cooling is Attainable for Various Conditions SFP SFP Surface Total Days After Date Temperature Wind Speed Heat Loss Shutdown
(*F)
(MPH)
(BTU /hr) 190 1
2.43 x 10' 2198 12/13/02 190 3
3.35 x 10' 568 6/27/98 190 5
4.26 x 10' already attainable 200 1
2.99 x 10' 928 6/22/99 200 3
4.11 x 10 already attainable 6
200 5
5.23 x 10' already attainable 210 1
3.61 x 10' 478 3/29/98
- It wasn't necessary to determine these values. They are earlier than the present date.
9
~
0
Spent Fuel Pool Passive Cooling MYC-2005 Rev.0 December 1,1997 Prepargd by MWS Reviewed by,M Page __40_ of ___
8.2 Spent Fuel Pool Heat-up Rate Test Procedure Any information in this section that is not legible is not important and was not used in the calculation.
(hyc-goor 1
Ptoe. No. 0-06-2 p qI Rev.No.18 ATT AIRMENT A Page 33 of.16 TPC= 97'3/3 TE:vf?ORARY PROCEDURE CHANGE REOWST FOPJ.I Total Number of TPC Pages 6
Pace
/
Precedure No.: '.-17-23 Rev. '
0 Subsequent Rev./ Initial:
i Precedute Tit!e: ren, iue: ecci Heat-uo Rate rest 2
- 7 Pmcedure Pares Adectec (Provide numbers):
fniciated Bv: hes G Room Date: _J n 71 o-IdentiF stipporting documentation (i.e.. Tech. E tal. #, Memo =. etc.)
/
-- Non-Intent Change E Intent Change O QC " HOLD POINT" Change Z Justi5catica for Use of a TPC instead of the ocnr.al revision procesr.Pmeedural chances are att non intent Reason and/or Technical Justificatio,r. for Change (s): Changes are oniv minor / editorial in nature and are made _
to orevide consistenev in the erececure.
D7scription of Change (s)/ Steps Affected: (Mark-uo and attach affected casesi
?. 3 5
7 FrFUO30 SCREENING.
Is the existing 10CFR59.59 Determination still valid:
EY ON Initia.
I C - ? / 'I T IfNO:
Oate a)
Complete a new 10CFR50.59 Determination according to Procedure 0 t.
- b)
Chan2e reviewed bv the TPC Subcommitte ( Attachment J, TPC REVIEW SUBCOMMITTEE MCGITES.)
CY ON c)
The change must be approved by the Plant Manager / designee before tmplementation.
New 10CFR50.59 completed?
EY EN Date of NEW 10CFR50.59 Detennination is:
NA n change. THEN, COG NOTE: IE TPC is result of a desig/ Approval is required.
COG Engineer (CRS-4)
Engineer / Designee Review 1
TEMPOR ARY CF ANGE At TFORT7 ATTON TPC#
17'3/3 Date: /#/2///7 Time: /8 ' N M. b % Y gmt. Staff: A'/bd
- Licensed SRO:
QPD (if QC"$1d Point" Change)
Original TPC to ted to the PORC Secretary Asst.: Recommended Disposition:
z O Temporary Termmate (used once d4Wbo Date: /0/1//D OTempo to Remain m Effect til Initiator:
R Changes nly Revision i
PORP RFVTFW/DTSPOSITIO.N (This section is for PORC use only)
O Temporarv Terminate (used once) O Temporary To Remain in Effect Until:
O Changes 6nly Revision PORC Meeting Number-Date:
i i
I
y,,u
- ~ - t i.a Class A SPENT FGL POOL HEAT-UP RATE TEST Rev. No. 0 Issue Date 10-20-97 Review Date Page ! of 13 10/98 7
APPROVED BY PLANT SIANAGER DESIGNEE AT PORC MEETING #
>"7 - N C DATE:. /c// s / ?7 j
PSS F.euew:(ghg die:g/gfyJ me: gjF l Ti Test Engmeer))
Date:
7, - A Test Date: fg/;g g
]
L/
I1-tc-f 7 1.0 OBJECTIVE To perform a heat-up rate test on We spent fuel pool without the spent fuel pool cooling system in operation. This test is pedormed for the pugose of establishing the -actual decay heat rate of the spent fuel and to determine the actual evaporative losses which occur at various spent fuel pool bulk temperatures.
2.0 DISCUSSION Due to de unusual nature of this test, this procedure will be performed in accordance with the requirements of procedure 0-06-9 INFREQUENTLY PERFOR.NED TEST OR EVOLUTION, although it does not strict!y fall within de guidance criteria of dat procedure.
Therefore, this procedure provides for a pre job and shift tumover briefings. Additionally, a Test Director has been named and management oversite will be provided.
This procedure shall be used to measure the heat-up rate of de Spent Fuel Pool when the ecoling system is not in operation. The data will be used to calculate the decay heat load produced by the spent fuel stored in the pool. The results of 6is calculation will be used to decennine future emergency equipment opembility requirements.
The procedure shall also be used to measure the spent fuel pool evaporation rate at pool temperatures between 140*F and 100*F. To perform this measurement, the spent fuel pool cooling system shall be started and the spent fuel pool shall be controlled within various temperature bands to allow measurement of spent fuel pool level over a designated period of time. Sufficient decay heat is judged to exist in the. spent fuel to assure heat up of the pool to 110*F.
During performance of this test, it is anticipated that the heat-up of the spent fuel pool which occurs between 80*F and 100*F will most closely mirror the actual decay heat load of the spent fuel due to the low evaporative losses at these temperatures. At temperatures above 100 *F, evaporative losses are anticipated to become increasingly large owing to the increa' sing
- differential between the vapor pressure of de spent fuel building and that of the spent fuel pool water.
1
m..~
^
TFC * '77-313 g. 2.
of 5 MYC-2M Rev. No. O p, q 3 Page 2 of 13 Data tc be obtained by tis test wi!! Se acquired by te use of RTDs located in te spe.-: iei pooi and in selec:ed areas of te Fuel Bldg... RCA Sidg... and new the! storag: area conne :ed to ovo ?! uke Hydra Cara Recorders :o be located on de t t ft. Elevation of de fue! building.
Additiona! d2:a will be obtained icrn de.' VET Tower, and som a psych oc: ter.
- Pdor to penormr.ncr of a heat up mte portion of dis tes:. spen: fuei poei : ciing pum: few
~
l shall be adjusted by throtding FP-15 to ensure tat te individual flow rate for each pump is l
equal te - 750 gpm. TI:is adjusm:en: is intended :o plac: te pt=p openting point sit'-in $e manuf=mrer's operating band and ensure at adequate NPSE is available upca ast n cf de pumps when pcol temperature reaches 1 LO'F.
i 3.0 PRECA* TONS, 2.1 ine punncanon sh.pstrea:. scall ngl be m. cpennon du-ng pecormr.nc: or tus :est to prevent heat amova! by 6is system.
3.2 The spent fuel poci is filled with water bor2ted to de redteling bcron concent aden and shall be maintained g eater dan or equal :o 1720 ppm (7.1.3) 3.3 Prior to performance of tis test, spent fue! pool temperature shall:e matta=en at a ::mpera:ure above 75'F. Minimum Spen: Fue! Pool Tempe=cre is 63 'F. (.'.2) 3.4 PCC flow :o de Spent Fuei Pool Heat Enchanger (E 25) is limited to a maximu= of 1100 gpm. (7.1.1) 3.5 No thel handling operations shall be performed during the performance of 6is :est.
3.6 Do not allow de spent fuel pool temperature to exceed 150*F based on ie highest RTD reading. Maximum allowable the! pool temperare:is li L*F. (7.1.4) 17 During te initial heat up portion of tis tes:, it should act be necessary :o provide makeup to the spent fuel pool, however, if this becomes necessary de test engineer Q
should be contac:ed and de time, quantity of water added (in. of level), and 7
tempemture of the water in de Primary Water Storage Tank (PWST) as read on TI-N 4002 should be recorded. During the balance of testing if makeup is required makeup water shall be added prior :o ie performance of steps f.:, f. ;, 5.12. 5.11. and 5.166 [ "o Makeup shall be added in ac:ordance wid Procedure 1-17-1, FUEL POOL M 2 KZ-R UP, COOLING AND PURIFICATION. Ensure dat pool temperature is cortsistent with the temperature requirements of the applicable step of this procedure.
During pe:#ormance of this test, if any RTD(s) malfunctions de!e ion of that rid (s) 3.3 is at the discretion of the test engineer.
- 5. I8, $'. 2.0
Y /W 3
l' lyt -kd Rev.No.9 9 44 P:ge 3 of i3 3.9 Du:ing pinbn:2nce ofiis test i:1 building ventilation shal! be niain:sined :s limi:
nunucity. S. ou.:c a ::uture or me venutron system oc:ur.
~ i! ding :empenn::: and.
n ou at it disen: ion c(6e test dia::or de es: sh2ii be te=tinated and he! peo! no!!ng
- es:2b!!shed.
m 3.10 During penbr=2ne ofits :est. spent iei;ect ievei enay exc :d se bigh levei 212.
z' due :o iennai enpansion of the water in ie spent ie! pool. No ac:icn. 2s recuired R
by..OP 2 37.RE. RESPONSE TO MCB PANAL>_0.! SECTION R'-i h
A.'t.T.NCLATORS. sir.c suRicient volume in 1e pooi remains :o p= vent ove-flow.
=
^ IS requim Q as.
p 2.11 uunng percen=c: o: iis test, spent ici pool ! eve! !s not annc:pa::: :o cecr:.se below i: low leve! alr= se: pein:. If ie !cw level ala:= se: point is = ached, ieve!
shall be mised as acted in 3.7 above and in ac:Orde.cce with prec:du : 1-17 '
3.13 The spent i ! peol is a Foreign Mate:ial Ene!usion Zone (BEi. Ins:21!ation of $e P' Ds. ienneceugie win, and de ruler :o de:ennine poo; levei sneuid be done careilly to prevent dropping of de inst u=ents into de pcoi..CI items :o be installed in te pcol should be rinsed wii primary g=de water prior :o insulla:ica.
3.14 The li=itations listed in procedure 26-309, FUEL FOREIGN.NL2.TERJ_23 EXCLUSION (BE).NLANDJ., shall be aviewed as pan of de pr: fc5 brie =.ng.
3.15 The :est shall be te inated if: he! pool level is !cwered below icw level ala=n point 2nd cannot be mised using makeup water, fue! pool tempe=rre c any op enile RTD eo,uais or ene eds 150'F; fuel building ventilation is no longer ope =bie as determined by te test direc:ot, one of ie two fue! pool cooling pumps bec =e tnoperacte.
4.0 PREREGOts e INI I215 G/
4.1 The spent fu ! pool shall have been cooled :o be: ween 75'F and 35'F. _ sf L -
v e -,/,
4.2 A psychr =e:::is available to measure re!arive humidity.
C.-
4 j
4.3 The bacr.:p spent ie! ceoling pump has been verided to be ope =tions!
g t
in accorcance w:m procecur: 1-1 < 1.
4.4-Two recorders, calibrated in accordance with procedure 0-12-1,
- ME.ASURLNG AND TEST EQUIP.NENT, records attached. at:
g 1
avatscie.
\\
4.5 Total :e=pe=ture :nessurement loop accuracy including ie RTDs and f..
recorders, shall be verified to be within -/- 2 F.
L v'
1
- a..
f g
,m.
Page 4 of 13 P. yf
~
bility of
[NTTIALS
' A.evei measurement device with a minimum measuring espa ll l
2 ft. is available to measure spent fuel pool level. Spent fuel p 4.6 llif this may be measured by de installed levei indicator on the pool w O 97-03393-y',
measurement is deemed adequate by the test director. (W
.jL
.. ~
00, Rev. 0)
Spent fue! pool level shall be initially at or above the n ll point of 45 ft.
of.14 ft., but should not exceed de high leve a ith fa, 4.7 L-section 3.7. (7.1.5) ih m
The fuel building ventilation is in operation in accordance w p '/
v Procedure 1-12-3, CONTROL AREA VENTILATION.
4.8 L.
l.
The RTD strings are assembled and have been lowered ll be fuel pool and positioned as shown in Attachmen 4.9 l
td Attachment A; I RTD located direedy above de pool; I RT located as follows:
h cask in the fuel bldga general area; I RTD located in the RCA nea de to de recorder.
M,/b wash down area. All RTD connections have been nr.
(WO 97-03393-00, Rev. 0)
Spent fuel pool temperature during the test will be d ion of the highest
'(..
averaging of all termocouple readings with the except
~
4.10
/
and lowest values.
h ent Radiation Protection shall provide a co jh i dic-
/r,
4.11 atmospheric tntium sample.
f lbuilding shouldnot 4.12 - Security shall be notified that the doors t
~
b usedbut
- /
not bicck'ed open.-
PCC atthe An ultrasonic flow measurement device has be spent fuel pool heat exchanger and on the FPC system.
. 4.13 Calibration Date. 3-/ 2 -9 7 Instrument No.G 2 2 '~f.
Calibration Date. / 0 ~/0'I7 Instrument No.//0 / 2.3 ORMP This test will create an orange condition for the SFP jL-i r to conducting 4.14.
Shutdown Safety Assessment.
r, notification of the Operations Depamnent Manager pr o the test.
m a
m m.
(hyC-1608 Page i cf 13 V'W h niimA L5 5.0 PROC:E4 5.1 Before ste-ing iis procedure, ensure a discussion r.d review has be::
h:!d wid the operating crew and test engineer: involved in accord:ncewid procedu c 0-06-9 COEL'CT OF NFR2QLT.C.Y PERFOR.'.ED T3STS AND EVOLL TIONS. reds will sive an ove 2!!
understanding of the objec:ive of this procedure and note any arer.s recui:ing added caution.
u 5.2 Since iis proced.:re will be in progress du-ing shii :umover(s).
EN the or.-coming crew will be bdefed bv de off-geia.g PSS as :o te e.t
. presen: s:mus, de objec:ive and de precautions of e precedre.
_ J._
_/
5.3 Spent hel pool ecoling pump flow shall be adjusted by thrott!!ng PP.15 w:1 efie: P-17A cr P 173 in ope = tion :o achieve 2.n individu:J. f.c :-
ber.veen 750 and 500 gpm as measured on te concolacen insmiled in step 1.13.
As an attemative, FP-7 and/or FP-17 may be iron!ed p
separately er in c:r.junc: ion with FP 15.
- j., L SA An inspec:fon of de spent ie! pool piping and cataponents shall be perfor-.ed subsequent to the throttling of te ris:e= :o ens e 1
acceptable open-ion of the system and components.
5.5 Star: the recorder and collect data with a spent nei pool cooling pump running for a :r -%um of two hours to verify proper operation of La i
e RTDs and recorder.
goo IclL1-/f 7 5.6 Sece: se open:ing spen: he! cooling pump in accordance wid V
p procedu e 1-1 <.i.
w 5.7 Record initial data on the dnta sheets provided in At:achment B.
7/
ni t
5.8 Collec
te following data every three (3) hours during the test and record te data or. te data shee: provided in Attachmen: B Acac' e tB s
Outside air temperantre
' L: T:t ce: 2:. ::.i. 2./ /C EM' 94" M b bef Outside aid.ridir.-
- 21 ft. Elevation Fue! Bldg.. Door W46at *, -
Fuei BuildingW - at Fue! Pool Elevation Tefe SF? Wate: Level Spent Fue! Pool Temperature (Points 1-12)
De:ennine Spem Fue! Pool Ave. Temperature:
v - T,.)/10 Tm = (Sum (T... T :) -T S
i i
['
gg Rev.No.0 Page 6 or,1.i
- f. (f'l
~*
INITIALS Fuel Bidg. Amb. Temperature (Point laj l
New Fuei Storage Area Temperature (Point 14)
RCA B!dg. Temperature (Point 15)
Pool Area Ambient Temperature (Point 16) 5.9 Continue the test while recording tfie~5:focou'~le data undlThe' average i
~~~
p
~
temperamre of tce spent fuci poolis equal to or exceeds 140*F.
5.10 Start a spent ici pool cooling pump in accordance with procedure
)
1-17-1.
j i
CAUTION 1
During the performance of step 5.11 primary component cooling
)
(PCC) water flow to the Spent Fuel Pool Heat Exchanger (E-25) l shall not exceed 1100 gpm as determined by the installed Controlatron flow instrument.
5.11 Adjust component cooling water flow by throttling PCC-147 to maintain IO M "
average spent fuel pool temperature at 138'F to 142*F. Allow temperature to stabilize.
M 4
5.12 Continue collecting data evety 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> until spent fuel pool level l
lc/g c, 082 o decreases 2 inches or 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> has elapsed.
CAIJTION l
During the performance of step 5.13 primary component cooling (PCC) water flow to the Spent Fuel Pool Heat Exchanger (E-25) j shall not exceed 1100 gpm as determined by the installed Controlatron flow instrument.
N.13 Throttle PCC-14 to maintain the average spent fuel pool tempe 10/26 u at 123*F to 132*F. Allow temperature to stabilize.
4 1
5.14 Continue collecting data every 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> until spent fuel pool level j
IOM N decreases 2 inches or 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> has elapsed.
p
{
7 yIg.,%J 150 gm a Pcc h b d os. w\\\\
mw- %
ap % S pcc. e so bpam j
SM us s.
i
[PC
- fj-313 fb o f~ b Rev. No. O F21:7of13 ggf
~
. TION During tue performance of step 5.15 primary component cooling (PCC) water flow to the Spent Fue! Pool Heat Exchanger (E 25) shall not exceed _1100_gp_m as determined bv the_ installed
~
Controlatrcn flow instrument.
Tarecle PCC la? o mainnin the avemee sc. ent ie! poei:empearce o.15 5
t u
g aj t " OLc at 115'? to 1:2:F. AHcw :emperamre to stabilize.
m 5.16 Con:inue collec:ing dem every 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> untii ; pent fuel pcci '.evel l */ L'f 030#
decreases 2 inches or 48 hcurs has elapsed.
-.m C A C TI O N' During the performance of step 5.17 primary component cooling (PCC) water flow to the Spent Fuel Pool Heat Exchanger (E-25) shall not exceed 1100 gpm as determined by the installed Controlatron flow instrument.
5.17 Tnronle FCC '.2 to mai.:2in the average spent kel poci te=penmre I /30 #
at 10S *? to 112*F. Allow :emperarre to stabilize.
ll/f 4.ngo 5.1S Continue collecting data every 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> until spent fuel pool leve.
decreases 2 inches or 23 hcurs has elapsed.
,h d
\\
C A L'TT O N i
During the performance of step 5.19 primary component cooling (PCC) water flow to the Spent Fuel Pool Heat Exchanger (E-25) shall not exceed 1100 gpm as determined by the installed Controlatron flow instrument.
J 0
a 5.19 Throc!e PCC-la~ to mainnin the averige spent fue! pcol te=penmre m
llff go A
at 9S 'F to 102*F. Allow :emperature to stabilize.
d
-- S 5.20 Continue collec:ing data every hours until spent fuel pool level decreases 2 inches or 48 hcurs has elapsed.
h
[l/'b I'
t6 bnn 5FP f b % gm b M N c 6 % gyF p
g 3
N 5)m,
- 4 h br.$.3 SFP de m to 110
- F g r. 5 'Pcc 4.s 6> #60 y,. 9 y~ vW Last 6 d 05" ' o I" / * #-
6.** 4 4 a u ua n. co, m r.t, / % %,. W. 6 4 c t ha.
m.
tE ED n
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Rev.No.0 gp Page 3 of 13 P 4R W ALS During the performance of step 5.21 primary component cooling (PCC) water flow to the Spent Fuel Pool Heat Exchanger (E-25) shall not exceed.1100 gpm as. determined _.by._ the-installed Controlatron flow instrument.
5.21 Throttle PCC-117 to cocidown the spent fuel pool to an average-
/
mperature of!ess than 90*F.
Stop fe rec;rder.
O N
O g
.o.22 Q
f
%\\
WNb%
j 5.23 Disconnect the RTDs from the recorcer, remove the RTDs.
g/7 N 4 h I QJ FINAL CONDmONS
,N a b p.~
6.1 The spent fuel pool heat up test is comple:e.
O g
6.2 The spent ie! pool cooling system is in operation, in accordance with procedure 1-1 -1, and the spent fuel pool has been cooled to less than 90*F with level in de norma! ange.
l 6.3 A records transfer checklist, in accordance with procedure 0-17-1, QC RECORDS l
M.-\\NAGE.NENT SYSTEM, has been filled out and a copy of this completed precedure is ready to be transferred Document Control Test Enginee:
Date //-/c.-77 U
u l
6.4 A physical walkdown of the spent fuel pool area has been performed to ensure that all test & work equipment associ this procedure has been removed.
li t
Date //~h-9 ~2 Test Enginee
7.0 REFERENCES
7.1 SOURCES 7.1.1 TE 031-93, Spent Fue! Pool Heat Exchanger PCC Flow Limitations 7.1.2
.NLN-93-09, Proposed Technical Specification Change No.177: Maine Yankee Spent Fuel Pool Reracking
(b YC-7,00f gel, f, o"~
f, IO Page 9 of 13 7.1.3 inputs & Assumptions Source Document, Rev. I1 7.1.4 FSAR Section 9.8, Fuel Pool Cooling System 7.1.5 AOP 2-37.RH Response to MCB PANALARM Section RH Annunciators 7.1.6 AOP 2-52, Rev. 2 " Loss of Fuel Pool Cooling and/or Level" 7.1.7 0-17-1, QC Records Management System 7.1.8 26-309, Fuel Foreign Material Exclusion (FME) Manual 7.1.9 0-06-9, Conduct ofInfrequently Performed Tests and Evolutions
I' (hyC 400[ Rev. No. 0 l
),-
Page 10 af l3 ATTACEMENT A (Sheet 1 of 2)
Arrangement of Spent Fuel Pool RTDs for Spent Fuel Pool Heat Up Test All thermocouple location dimensions to be accurate to within +/ l'-0" l
1re I
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,a : m I
i r
m m
b O
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PLAN VEW i
[hYC-2,Oof Rev.No.0 g, gg Page iI of 13 ATTACH? VENT A (Sheet 2 of 2 )
Arrangement of Spent Fuel Fool RTDs for Spent Fuel Pool Heat Up Test
\\
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24 T
7 re
' T T
Spent FuelRade t
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p,ry m Rev.S,o.0 7
g 8*
7 Page D of 13 ATTAC'rBIENT B (Sheet 2 of D Data Sheet for Spent Fuel Pool Heat up and Evaporation Rate Tes:
SFB Amo New Fue!
RCA Bldg Pool Ares O u:. side Outsice SFS 5FP Date Time Temp AreaTemp AmbTemp Amo. Temp Air Temp Air Tems Air Temp
,, s v el Signarse Point 13 Point la Pomt 15 Point _16_
D er Sulb Wet Bulb Wet Suib
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V' W ayes nsimment
- enice, nc.
f Electronic Recair & Cali'cration 530 BOSTON ACAD (RTE. 3A)
BILLERICA, MASS. 01821 TEL. (508) E63 4800 I
FAX (5C8) E63 3812 CERT;FICATE SubrJ.tted by:
MAINE YANKEE ATCMIC PWR CM.ibraticn Date:
MARCH 12, 1997 FO#97-80369 nufacturer:
FLUKE /
e Medel:
2625 '
M Y QC REylEwEo
==
Description:==
DATALcGGER /
$ACCE.3T g ggggg7 g
BYd#J DATE d V?7 Serial Number:
5452651 Prcperty Nucl=er:
62291 v"
The abcve unit was calibraced in ac=crdance with purchase order requirements on the date noted above and was perf===ing in acccrdance with the manufacturer's specifications at the time of release from this laboratory.
This certification was performed using standards maintained by this laboratory, which are periodically certified traceable to the National Institute of Standards and Technology.
The cycling and certification of all standards of measurement used by Hayes Instrument Ser/ ice meet the requirements of ISO-9002:1994, #
MIL-STD-45662A, ISO-10012:1992 and ANSI /NCSL Z540-1-1994.
The calibration standards used have an uncertainty er:c: cf no more than 1/4 of the tolerance of the equipment being calibrated, or have an accuracy that ensures the equipment being calibrated will be within required tolerances.
(Accomplished under ~ quality system
- manual, QM-100 dated /
l l
01/00/96 Rev. A)
.i h *
,, STANDARD N.I.i.T CERT #
/d 3] M './"
&.S',
G4f E55 U.,DC Voltage 255548
($ f
'..AC Voltage Authorized Signa'ture 257311
/
M UII'.' Resistance 254739 Ten:perature & Humidity
" Frequency VIE Transmission
~7A 45' 15'
- 9 "s,g.c.t.i.
ON WWVB d f" **1 E **
- 1 3
42587' Returned in tol gut tel
- .. s.LO,Di, mensional 253059
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00 MENTATION COMPLETENESS y
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'r cujed bnstrument ervice, bnc.56 W.O. NO.DyC/fd i 168 1/9s.
PAGE DF 1.
SUEMITTED EY M A /NA' V A N !2 e ---
CAL!ERATION DATE 3-/d -97 MMUFACTURER DUE DATE 3-/d-98
~
FWE MODEL NO.
CALIBRATION ENGINEER
/80 262SA DESCRIPTION CAL PROCEDURE FIX MANUAL DATA LOGGER SERIAL NO.
SY60/o6/
/
PROPERTY NO.
6 Jd 9/
/
!H.I.S. REFi 622,1055 TEMP & *~GIDITY CALIERATION RECORD 7/
3 fjf pcy 97-Pcygc STANDARD ACTUAL MEAS.
At imR ADJUST FUNCTION RANG-
-.O L:,AN C,c i
c TESTED VALUE VALUE MEAS. VALUE :
lDC VOLTS l 300mV l SHORT l
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l
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.03 TO.03 l 300mV l 290.00mV l
,QQg, /) /
l l289.89 290.11 l
3V l 2.9000V l J,ff9[
l
' 2.8988 - 2.9012 l
30V l 29.000V l M,f. h f' k l l28.990 I
29.010 l
300V l 290.00V l
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1 1289.90 290.1C AC VOLTS l
l l
l l
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l 300mV l SHORT l
, Z 2__
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hD l 3 00mV l 290. 00mV l
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l289.36 - 290.64 NY. l 3V l 2.9000V l
,Q, $g1/)3 l l
l2.8944 - 2.9056
_hE E 30V l 29.000V l
,9 9,$[ l l
l28.941 29.059
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l 300V l 290.00V l pf9,[/g l
l l289.44 - 290.56 4
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300 I
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300 l
300.00 l
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l299.80 - 300.27 I
ii i di l
3K i
3.0000 I
s,0 cop l
l 12.9981 - 3.x22 DD l
30K l
30.000 l
3d.CdO l
l29.980 - 30.020 hp l 300K l
300.00 l
3d0,00 l
l 2 9 9. 81 - 3 0 0.19 -
~~l 3M l
3.0000 l
3 006).,
l l2.9979 - 3.0021 l
10M l
10.000 l
/j.060 l
l 9.987 - 10.013 I
I I
I i
TEMPERATURE l
C' l
CHECK ff/MS l
PASS TEST l<
FREQUENCY h.0000MHz
/. d$d ////ftl
.9994 - 1. 0 0 0 6 l
- l I
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H.I.S. REFERENCE STANDARDS l
l l
CAL l DATE CYCLE l
FLK CALIBhATOR l
5 100B 2930010 l fp-g 6MO l'
3R DECAph RESIS % R M433-H 1304 l 3-97 6MO u
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- Calibration Procedure used in accordance with tha: rec:mmended by 5.anufac urer.
l INSTRUMENTATION AND CONTRCLS OE?dRTMENT j
TEST EOUI? MENT CAli3?AT?0N KN ~ M l
Maine Yankee S/N 9.
Reason for Sue' mission 1
- =: s. sdon(aiibrat& 5 Instrument Name 01how Cr ss Check U
W Failure from Damace ii Mcdel Number Ab 2.M Failure frca Ncr=al Use U
Other (Explain)
'i Serial Number s4 5' 3-b I l Manufacturer SY
- 10. Date of Last Servicing 1-21. %
Received in Tolerance E
Outside Tolerance LJ
- 11. Calibration Intervai mnths) ' Pad.)
Outside of Tolerance evaluation completed:
'cm ;...umunQllorajJD E
I I1C Supvr.
Cross Check U
See Remarks i
Returned to Tolerance 3
- 12. Servicing label Affixed Outside Tolerance I
Certificatien
! i See Remarks Calibration 2
- )A Crosscheck L]
Certified Value
/
Reject i!
(If Fixec Standard)
- 13. Next Servicine Orts 3 - 1).- V 4 ;.?y/ Q ?,jiD 6
Crosscheck L.J Remarks
$u M l
l Calibration Equipment Used (Include Cal. Due. Dates) l 4:1' criteria met or appropriate M & TE accurac eviation form completed.
I&C Supvr.
/
&lM Date I( /
' Test equipment log forms, MY-IC-1-75, for devic listed in 15 above, have been updated to identify usage.
Updated by Date Y-I'D i
I G' ' f.... *,. s
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. e v
s.
e NG -20SI MEMORANDUM SPENT FUEL POOL ISLAND PROJECT TO:
James Rogers DATE: November 6,1997 FROM: Joe Tedeschl FILE: SFPI 97-005
SUBJECT:
Combined Measurement Uncertainty for the SFP Heat Up Test Temperature Measurement Equipment The combined measurement accuracy of the SFP heat up test equipmen't for the temperature range of interest of 80 - 140 deg F (26.67 - 60 deg C), is as follows:
1.
Equipment Used in the Test -
A.
Fluke Model 2625A " Hydra" data logger B.
Rosemount model 78 platinum RTDs for SFP water temperatures C.
RDF model 22802 platinum RTDS for various ambient air temperatures 2.
Mfgr's Accuracy Specs. -
Manufacturer's stated accuracy and related specifications for the above equipment, as identified in Attachment "A" is as follows:
A.
Fluke Model 2625A -
1.)
Accuracy:
i0.0.69 deg C @ slow response and 0 -60 deg C room temp. range = i1.24 deg F 2.)
Max. Current through RTD:
imA B.
Rosemount Series 78100 Ohm Platinum RTDs -
1.)
Repeatability:
- 0.05% (0.23 deg F) max. Ice pt. resistance shift 2.)
Stability:
10.08% (.38 deg F) max. ice pt. resistance shift per 1000 hrs (conservative for the 2 week duration of the heat up test) 3.)
Self Heating:
60mW min. Power dissipation required to cause I
a 1 deg C (1.8 deg F) temp. rise
V u
RYC - 2DW
(R SFPI 97-005 Page 2 of 3 C.
i
_ *0.1. Ohms or 0.4% of temperature, whichever is greater 1.)
Accuracy:
(t0.4% of 60 deg C is 20.24 deg C; t0.1 Ohms is greater = 10.26 deg C or *0.47 deg F) 2.)
Stability (Drift): <0.05% per year (0.23 deg F, conservative for the 2 week duration of the SFP heat up test) 3.)
Self Heating: < 1 deg C for 35 milliwatt dissipation 3.
RTD Self Heating Analysis -
Self Heating Bias error (deg C) = Power Dissipated (mW)/Self Heating Coefficient (mW/deg C)
The power (P) dissipated in the RTDs for the heat up test temperature range of interest is as follows:
Temp (*C)
Temp (*F)
R(0)*
l(mA)
P(i2R, mW) 26.67 80 110.27 1
0.11 43.33 110 116.68 1
0.12 60 140 123.10 1
0.12
- Resistance values based on DIN 43760, a = 0.00385 For all the RTDs, the maximum self heating error would occur at the maximum power dissipation value in the above table (0.12 mW @60 C).
A.
For the Rosemount RTDs:
The self Heating Blas error for the Rosemount RTDs is therefore:
Self Heating Error = 0.12/60 =.002 *C, or.004 F (considered negligible)
B.
For the RDF RTDs:
The self Heating Bias error for the RDF RTDs is therefore:
Self Heating Error = 0.12/35 =.003 *C, or.005 *F (considered negligible)
(r y(-wo; n
f.(po SFPI 97-005 Page 3 of 3 4.
Calculation of Total Uncertainties:
_, The abov_e. uncertainties for the Fluke Data Logger an.d the RTDs_are. stat.istically.
combined to arrive at the total measurement uncertainty associated with each RTD type as follows:
A.
Rosemount RTDs:
Total measurement uncertainty ( F) = i[(1.24)2 + (0.23)2 + (0.38)2]v2 Total measurement uncertainty ( F) = 1.32 B.
RDF RTDs:
Total measurement uncertainty ( F) = i[(1.24)2 = (0.47)2 + (0.23)2)u2 Total measurement uncertainty ( F) = 11.35 Should you have any questions or comments regarding the above, please do not hesitate to contact me at x-5737.
/
. [} -
h_;
Joseph S. Tedeschi Jr.
Instrument and Controls Group SFPI Project C:
W. Henc a
I[
1 f'
TTACHMEMT A P e ICPS A/ SPECIFICATIONS q
--j l
m' -~n j!
IhYc-2.cor
.=i l
. _....m I ~Eg g l RTD INPUTS j
3,.
.-DIN /IEC-75t, tootWlatinum 1
RTD 1 Year.4-Wire Accuracy (t*C)
Temperature Resolution 18'C to 28'C 0*C to 60*C
- [
(*C)
Slow Fast Slow Fast Slow Fast 5
200.00 0.02 0.1 0.08 0.49 0.12 0.54 0.00 0.02 0.1 0.21 0.67 0.50 0.96 l
100.00 0.02 0.1 0.27 0.75
'i).69 1.17 8
300.00 0.02 0.1 0.41 0.92 1.10' 1.60 600.00 0.02 0.1 0.65 1.21 1.77 2.33 ll s,
2 Wire Accuracy
-! 4 For 2. wire sencors with R,.1000:
degrade accuracy by 5.0*C per le ddhm, plus degrade accuracy an additional 4*C for channels 1 to 20 and 0.05'C for channel 0.
"l i
Maximum Current Through Sensor 1 mA
.I Typical Full Scale Voltage 0.22V Maximum Open Circuit Voltage "l
3.2V
,1 E?
l Maximum Sensor Temperature 1
600*C nominal 999.99'F max displayed i
Cross-Talk Rejection d..
Refer to Appendix E.
j jij EXCERPT FRot \\
4 J
FLOKE USER's MAMDAL.
lj i
i I
l i
A-4 qix s
t
Tcmpiratura Sansors, Asrsmblisc and Accas:ry Hirdwira
':WF.L SWOCT5 R% M $ '
AT7 ACHMOR A v
SERIES 78 RTD SERIES 78 SPECIFICATIONS
[hg S:rics 78* sensors are intended for special applications Series 78 Performance Specifications b hE-
~
that require high temperature, compensation loop, or dual Temperature Range olem:nt sensors.
be used from -200 to 400,C (-328 to 752yF). Inconel e es 78 &al element and cornpensahn op sensors may
'osemount Senes 78 RTD temperature sensors are for asurements from -200 to 660 *C (-328 to 1220 *F).
sheaths for single element sensors are provided for high Series 78 sensors are available in capsule, general pur-8
- " * * * #8 e rang of 0 660* (32 pos3, spring-loaded, and bayonet spring-Joadari.rtesigns, in 3
.p)
O i:ngths from 1 to 24 inches.
- E**
- Tabl] 3 shows the interchangeability of the Series 78. As t0.05% (0.13 *C or 0.23 *F) maximum ice-point resistance an option, Rosemount Inc. can provide calibration data at she following 10 cycles over the specified temperature specific t;mperature points for maximum accuracy. See optional characterization (calibration) schedules on pages range.
20 and 21.
Steility TABLE 3. Series 78 interchangeability 0.08% maximum ice-point resistance shift following 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> at maximum specified temperature (400 *C).
Time Constant
'~
5 seconds maximum required to reach 63.2% sensor re.
sponse in water flowing at 3 ft/s (0.91 m/s),8 seconds for dual element sensors.
Self Heating
' i' '
~~.
60 mW minimum power dissipation required to cause a 1 *C (1.8 *F) temperature measurement error in water flowing at 3 ft/s.
CONSTRUCTION Series 78 Environmental Specifications Tha dIsign and construction of the Series 78 sensors Humidity Limits allows direct immersion in non-corrosive fluids at static Lead sealis capable of withstanding 100% relative humidity, pressurIs to 4400 psig at 400 *C. For high temperature Pressure IJmits
~1plicati:ns to 660 *C, an inconel sheath is used. For resivo environments or many industrial applications.
Maximum working pressure is 4400 psig at 400 *C (725 *F).
i uless s:nsor,i are widely used with standard thermowell Vibration Limits ass;mblies.
0.05% maximum Ice-point resistance shift due to 30 minutes of 14 g peak vibration from 5 to 350 Hz at 20 *C (68 'F) for unsupported stem length of less than 6 inches.
Platinum Element and Leadwire Configurations Quality Assurance Singla element. nigh temperature sensors have four Each sensor is tested to verify ice-point interchangeability le-dwir:s and may be used in 2,3, and 4-wire signal and rear sealintegrity.
conditioning systems, Duit element sensors have bilitar wound elements to provida separate readout and control signals from a single Series 78 Physical Specifications miasurzment point. Dual element sensors have three leidwirzs for each element and may be used with 2 or Sheath Material 3-wirs systems.
316 SST for service to 400 *C;inconel for service to 660 *C.
Compensation loop sensors have a single element with Leadwires four I;cdwires configured for use with such products Teflon insulated, nickel-coated,22-gauge stranded copper as thi Rosemount Model 444 Differential Temperature w e.
Transmitter.
Identification Data hhk The series and serial numbers are electro-etched on bach sensor. An extra charge will be made where stainless steel k}
tags are requested.
or -
hh l
Weight Capsule sensors: 5 ounces.
General purpose and spring loaded sensors: 9 ounces.
1ee ordering table on pages 16 - 17.
6 i,
w SFPI 97-oc6 /FrTAckMENT A -
ily 383o4risseerso.nso (Redacca 36071)
MOhE 22802 HEAVY DUTY INDUSTRIAL-RTD 0
SURFACE SENSOR This s: ries of HEAVY DU1Y surisce sensors provides a pmctical method for measuring surface tempera-tutes in areas where the sensor may be subjected to ruggad use during servica These sensors can be bcIted or clamped in place on a flat surface. Mount-ing plates can be brmed to mate with specific radii on mquest.
Performance Specifications Operating Temperature Range Self Heating "S" standard -200*Cto +260*C(-320*F to +500*F)
The bare senser will rise less than 1*C while cissipating i
"H" high +0*O to 540*C (32*F to 1000*F) an 18R power of 35 mittiwatts in still air.
(ASTME 644)
S:nsing Element The standard sensing element is platinum with a insulation Resistance j
resistance of 100 ottms at O'C and temperature coef-The insulation resistance between outer sensor 'ous-r ficie1t 0.00385 O/Gl*C nominal (DIN 43780). Also ing and commoned leadwires is 50 megonms with 50 optiona'ly available on special request are reference Voits DC applied to a dry sensor at room temperature.
1 grace platinum, nickel and nickel-iron al!ay.
(ASTM E-644)
Accuracy Lead Wire A0.1 ohms (ic.25'C) or 0.4% of temperature, which.
"S" #22 M/G stranded nickel piated copper TFE Teton*
ever is greater.
insulated,3-wire confquration.
"H" #22 AWG stranded nickel plated copper fiberglass Stability insursed. :wre enfiguraten.
The sensor will naw less than 0.05*C dntt per year at rated service ternparature wi,n proper mounting.
Mountirig Sensor can be bolted, clamped or welded into place.
Timo Response 8 seconds for the sensor to reach 63.2% of a step Reference Data charige in temperature in water flowing at 3 feet per For installacon and mounting consideratens refer to '
second transverse to the sensor.
Application Note AN.S.
- (ASTM E 644) wen. ouem me.
Specialists in Temperature Measurement
ayed ndbrKMenb
- Grv5Ce, NC.
(I f Electronic Repair & Cahbration 530 BOSTON ROAD (RTE. 3A)
BILLERICA, MASS. 01821 TEL. (508) 663 4800 FAX (508) 663 3812 CERTIFlCATE Submitted by:
MAINE YANKEE ATOMIC PWR Calibration Date:
OCT 10, 1997 PO#97-03494
/
Manufacturer:
FLUKE Medel:
2625A M Y QC REVIEWED
==
Description:==
DATA LOGGER
@ ACCEPT O REJECT Serial Number:
6914606 BY N.L Sh
_DATE lo 1677 Property Number:
The above unit was calibrated in accordance with purchase order requirements on the date'noted above and was performing in accordance with the manufacturer 's specifications at the time of release from this laboratory.
This certification was performed using standards maintained by this laboratory, which are periodically certified traceable to the National Institute of Standards and Technology.
The cycling and certification of all standards of measurement used by Hayes Instrument Service meet the requirements of I50-9002:1994, MIL-STD-45662A, ISO-10012:1992 and ANSI /NCSL Z540-1-1994.
The calibration standards used have an uncertainty error of no more than 1/4 of the tolerance of the equipment being calibrated, or have an accuracy that ensures the equipment being calibrated will be within required tolerances.
f (Accomplished under quality syst
- manual, M-100 dated 01/00/96 Rev. A) h M' N/A STANDARD N.I.S.T CERT #
t['
(jr
\\
DC Voltage 255548 Authorized Signature AC Voltage 257311 Resistance 254739 Ternperature & Humidity Frequency VLF Transmission
_2C 45% t ist Received in tol / ut tol MASS 42587 Returned in tel ut tol Dimensional 253059 avM ENiMIC.'l "f)S.1FLEU.'EU A
,o (10.*
Dl:E:///3 #
mur, nc,(
l
" " T V.
. NO. ?_9f 22-/
168 2/95 a ed
/Zd[/N(/ JIG /1[
61'U[CG; llc-PAGE OF 1
8810MITTED BY
_A* esc Y:
J'd.,-
CALIBRATION DATE
[6 -/ # ~ 9 7
/g MANUFACTURER FLUKE DUE DATE
/0 ~ /0 I MODEL NO.
2625A CALIGRATION ENGINEER
/Jf i
GESCRIPTION cATA LoccEa CA
L. PROCEDURE
FLK MANUAL SERIAL NO.
l4/'/606 PROPERTY NO.
i H.I.S. REF# 622,1055 TEMP & HUMIDITY CAllBRATION RECORD 2d' N
g g7 pf i
FUNCTION TESTED RANGE STANDARD ACTUAL MEAS.
AFTER ADJUST VALUE VALUE MEAS. VALUE TOI.ERANCe i
m DC VOLTS 300mV SHORT
//,, d [J
. '.3 TO.03 O
Uu 7 c,,.f,.gj
/
289.89 - 290.11 300mV 290.00mV 3V 2.9000V y_pq9q f
2.8988 - 2.9012, 30V 29.000V 7pcffer th 28.990 - 29.010' 3007 290.00V 7pf_Qf 239.90 - 290.10l f
AC VOLTS i
@ 1KHz 300mV SHORT
, f gg
< 75 COUNTS j
300mV 290.00mV
<7p t.(, 4 /f/
289.36 - 290.64I-N 3V 2.9000V 2,4 0D 4' 2.8944 - 2.9056 l hI 30V 29.000V
- '7 9, y./ /,
28.941 - 29.059 l k1 300V 290.00V 2 M, ? l 289.44 - 290.56!
c3-w W K U l
hS@N E 300 l
SHORT
. u) /
<.09 300 300.00
%,,_jzt 299.80 -300.27l n
y 3K 3.0000 g. v,,.yo 2.9981 - 3.0022 fy k 30K 30.000 70 pr.m 29.980 - 30.020 h$Q 300K 300.00 yce g 299.81 - 300.19..
M 3M 3.0000 y, vee 3 2.9979 3.0021 !.
10M 10.000 f g.
,f.,.7 9.987 10.01':
TEMPERATURE C'
CHECK f// dg PASS TES{'
FREQUENCY 1.0000MHz
/, e-emo
)J/
.9994 - 1.0006 H.I.S. REFERENCE STANDARDS l
CAL DATE CYCLE
'FLK CALIBitATOR l
51008 2930010 6 97 6MO GR DECADI: RESIShR 1 433-H 1304 3-77 6MO 10
/O c
.wrnuo nW.6rmy,1 f
,igy,,
um
~.
W.O. #97 03393-00, ATTACHMENT 97-3393-00-1 PAGE 4 OF 4 SEENI_EU.EL_ED.OL HEGI_:.U.P_IEST RTD._CHANNELJLSSIGNMEN_T (nfC-2.00 0' O W.O. 97-FROC 4-17-23 03393-00 8TD LOCATION FLUKE, INFUT CH.
ATT. "B" CROSS-NUMEER NO.
I NO.
RE: TEMP. PT. NC.
l 1U SFP SOUTHEAST CORNER 1
1 1
1L SFP SOUTHEAST CORNER 1
2 2
2U SFP SOUTHWEST CORNER 1
3 3
l l
2L SFP SOUTHWEST CORNER 1
4 4
GU SFP EAST SIDE (MIDDLE) 1 5
5 l
3L SFP EAST SIDE (MIDDLE) 1 6
6 4U SFP WEST SIDE (MIDDLE) 1 7
7 l
4L' SFP TNEST SIDE (MIDDLE) 1 8
8 l
SU SFP NORTHEAST CORNER 1
9 9
10 10 1
6U SFP NORTHWEST CORNER 2
1 11 6L SFP NORTHWEST CORNEP 2
2 12 7
ABOVE SFP WATER 2
3 16 SURFACE 8
FUEL Bl.DG AMBlENT 2
4 13 9
NEW FUEL ROOM 2
5 14
-10 RCA STORAGE AREA 2
6 15 NOT USED 2
7 NOT USED 2
8 NOT USED 2
9 NOT USED 2
10
- U = UPPER RTD, L = LOWER RTD
q
.. e i
i Spent Fuel Fool Passive Cooling MYC-2005 Rev.0 December 1,1997 Prepared by MWS Reviewed byM Page _62. of _
8.3 Spent Fuel Pool Heat-up Rate Test Data Any infornWion in this section that is not legible is not important and was not used in the calculation.
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D Spent Fuel Pool Passive Cooling MYC-2005 Rev.0 December 1,1997
. Prepared by MWS Reviewed by _:tL.
Page 104 of _
8.4 Memo. " References for Spent Fuel Pool Heat up Cale" O
9 i
~
g t
l m][-lDOS MEMORANDUM V 105 YANKEE ATOMIC - BOLTON To Michael Scott Date.
I l-25-97 l
WO#
... Front ImesE_Rosm Group #
SFPI 97-020 Req #
Subject References for Spent Fuel Pool Heat up Calc File #
MEM 97-020 DISCUSSION Per you E-Mail of 11/24/97, the following are the references you requested:
1.
Thermal Conductivity of Concrete: From Marks Handbook for Mechanical Engineering, 8th edition,
- p. 4-63, k = 1.05. See attached copy of page.
2.
During the test, a ruler was attached to the pool measuring down from the 46' elevation into the pool.
Ruler measurement at 46' = 0". Ruler extended 48" into the pool from the 46' elevation.
3.
Grade level at the fuel building appears to vary somewhat. I1550-FA-12B, Rev. 7 indicates grade elevation as either 20' or 21'.
l 4.
Fuel Pool wall thickness is o' from 11530-FC-27B, Rev. 6.
[
\\
A
~
/
fG. kogeff SFPI Mechanical Systems Engineer MY Design Engineering hf Mll&
V/.E. Henries SFPI Lead Engineer MY Design Engineering cc:
File
/
(hyc 400.5 O. /0 b j
FILM COEFFICIENTS E 4-63 i
il*
l Tabte 3. Thermal Conductivttles of Mlacelianeoue Sand Substances *
.l Values c( & sre to be regarded as rough average values for the ternperansre range indicated
{
Bulk Bulk e
M *'*"*I A
M *'*"*I O
a.,
lb s
lb r as g
eu f t eu f t n
M Ambestas board, eota-Quarts, trystal, paral-
'l pressed asbestos and lea to C-aus.
- 300.
25.0 i
f eement..........
125.
86.
0.225 0,
8.3 Aabestos millboard..
60.5 86.
0.070 300.
4.2 Aabeston wool.....
25.
212.
0.054 Rubber, bard......
74.3
- 100, 0.092 I
')
Ashes. sof t wood..
12.5 61.
0.018 Rubber. sof t vulcan.
ll Aabes, volcanas.
St.
300.
O.125 ined.....
68.6 86 0.08 Carbon black..
12.
133.
0.012 Sand. dry...
94.8 68.
O.188 i'
0.037 Sawdust, dry..
I 3. 4 68.
0.042 Cardboard, corrugated.
...87.3
...86.
O.I2 8them, f used.....
...32.5 131.
0.049 Cellulo6d..
200.
O.83 Cellulose sponge.
Sabes gel, powder.
du Pont...........
5.4 82.
0.035 f, oil, dry........
68.
0.075 Concrete, sand. and 6cil dry. Laeluding grsvel.......
142.
75.
1.05 stones.
127.
68.
0.30 Concrete. asader.
97.
75.
0.41 Enow............
7-31 32 0.34-1.3 Chareaal, powder, i1.5 63.
0.029 Titanium oxide. Snely Cork, granulated..
5.4 23.
0.028 ground.
52.
1000.
0.041 Cotton wool...
5.0
- 100, 0.035 Wool, pure..
- 5. 6 86.
0.021 DiamonJ.......
151.
70.
320.
zireunin g min..
Ill.
600.
0.18 Earth plus 42 % water.
108.
O.
0.62 Woods, even dry.
Tiber red.........,
80.5 63.
6.27 seroes grainf:
Tiotofemm" (U.S.
Aspen.
26.
85.
0.069 Rubber Co.).
1.6 92.
0.017 Bald cypress.
24 85.
0.063 Class. pyres....
159 200.
0.59 Balas....
10.
85.
0.034 200.
0.59 haswood..
24.
45.
0.058 Glass soda hae.
...93.5 122.
87.
Dousias Fir..
29.
85.
0.063 G raphite, solid.
G ra vel.........
lie.
68.
0.22 Elm. rock..
48.
85.
0.097 Gyprum board.
St.
99.
0.062 Fir, wtute..
26.
85.
0.069 2 ee..........
57.5 0.059 Larch, western.
36.
85.
0.078 1.26 Hemlock..
29.
85.
0.066 Kaolin wool..
10.6 800.
1Aather sole.
62.4 0.092 Maple sugar.
45.
85.
0.094 Mies.,,
122.
0.25 Oak. red........
42.
85.
0.099 Pearlite. Artsona.
Pine, southern yal-spheneal ehall oi si-now......
35.
85.
0.078 liemous matenal.....
9.1 112.
0.035 Pine, white..
25.
85.
0.060 Polystyrene. aspanded Red eedar. western.
21.
85.
0.053 "8tyrofoam"..
1.7 0.021 Red wood.
25, 85.
0.062 Punuce. powderw'..
49, 300.
0.11 8prues..
21.
85.
0.052 Quarts, crystal. per-pendicular to C.azia.
- 300.
12.5 0.
4.3 300.
- 2. 5
- The thermal conductwwy of dderent metensis varus gready For metals and allove i es lugh. o hde for cenam insulatirq maerssis, such as glass wool, curl. and kapok. it es very low, la general. A vares with the emperature, but a the case of rentals, the tensten a relanwely small. Wah most other subeances, & enciosers with namg emperatures. but m the case af many crystallane maeenals, the reverse is true.
tWith heat ikvw persilal so the gram. A may be 2 m I tunes thap wwh hese fbw perpendiculst m the gram, the selves for wool are taken chmey from J. D. MacLama. Teses. ASNA4f., 47,19et, p. 32 5.
Y = ordinate number of transfer units. The alternatives are basically equiv-o crue mesa ternp difference alent, but one or the other may enjoy a computational advan-loganthmic mean temp difference for counter flow tage. The latter method is presented in detail by Kays and
~
London and by Mickley and Korchak (Chem. Eng., 69,196L For the other symbols see Sec. 4. (from Trans. ASME, si, pp.181-188 and 239-242).
1940, pp. 281-294.)
If U varira considerably with temperature, the apparatus FILM COEFFICIENTS should be considered to be divided mto stages, m each of which variation of U with temperature or temperature differ-The important physical properties which affect film coef6-y ence is linear. Then for parallel or counterflow operation, the cients (see Sec. 4) are thermal conductivity, viscosity, density, following relation may be applied to each stage:
and specific heat. Factors within the control of the designer
( = A(Us(Ath - Ut(Afles]/In [Us(Asb/U (As).s] ($b) jnclude fluid vel and shape and anangement.of the heat-mg surface. With orced flow of gases or water, under the t
The above discussion focuses on the concepts of an overall conditions usually met in practice, the fiow is turbulent (see coefficient and a mean-temperature difference An alternative Sec. 3) and under these conditions the film coefficient can be approach focuses on the concepts of effectiveness and the gre dy increased by increasing the velocity of the fluid at the
Spent Fuel Pool Passive Cooling MYC-2005 Rev.0 December 1,1997 Prepared by MWS Reviewed by k Page 101.of._
8.5 Evaluation of Computer Code Use Form I
i l
a 0
R \\O$
EVALUATION OF COMPUTER CODE USE g
CALCULATION NO. MYC-2005 REVISION NO.
0 List the computer codes used, and complete the following:
l Approved Appropri-ateness per Verified 2 Outstanding WE 108' SPRs' Code Name/ Version Yes No Yes No Yes No QuatroPro for Windows, Version 6.0 X
X X
8 Refer to Section 4.1.4.4, Bullet 3, of this procedure.
8 Refer to Section 4.1.4.4, Bullet 2, of this procedure.
8 Refer to WE-108, Section 4.4.
If a computer code was not verified per WE-108, or if there are outstanding SPRs, state below why it is appropriate.
Code Name Appropriateness QuatroPro for Windows, Spreadsheet verified in calculation.
t Version 6.0 i
e FORM WE-103-2 Revision 2
~.
l Spent Fuel Pool Passive Cooling MYC-2005 Rev.0 December 1,1997 l
Prepared by MWS Reviewed by.)k.
Page_1Q9_of_
8.6 ('miculation/ Analysis Review Form 6
e
CALCULATI0il/ ANALYSIS REVIEW FORM D
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CALCULATI0ft NO.
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CALCULAT10ft/AllALYSIS REVIEW FORM 90j CALCULAT!0fl fl0.
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WE-103-25 FORM WE 103-3 Revision 4 l
0V D
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l Spent Fuel Pool Passive Cooling MYC-2005 Rev.0 December 1,1997 Prepared by MWS Reviewed by Page 113 of I
1 8.7 NED WE-103 Review Checklist I
6 I
O NED Procedure No. 3 Rev. S_ Date 8/22/96 Page 3 of 5 ggg OY NED WE-103 REVIEW CHECKLIST Compliance Reviewer-Reviewer
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Ensure the title page is appropriately filled out.
es. /
Correct number of pag /
QA Record filled out.
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IMS number filled out. N'l4 Record number filled out (13.C09.001 included if microfiche or hard copy of computer runs are attached to the calculation). /
Descriptive title. /
Plant, cycle number and calculation number included. "N/A" can be used for plant and cycle number. /
Signatures and dates are included, and are in correct e
chronological order. Print the name and individuals' organization (if other than YAEC) below the signature. The title page reviewer and approver dates do not pre-date any date in the calculation except for changes containing that individual's initials and date.
All WE-108 computer codes and other keywords not in the title which can be used to retrieve the calculation are listed E/
Id IC-in the keyword field. /
Nb Ensure the Form WE-103-2 is included and properly completed when a J@
computer. code,is used.
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Ensure. Form WE-10331s-included,.and has41gnatu'r 1/ dates.from'.both the'preparef and the reviewer and that all comments have been addressed. If no comments, use the following statement:" Reviewed in eg accordance with WE-103 with no comments".
tJ Ensure review of the calculation can be done without recourse to 60 N/A the originator.
7 Ensure computer codes are used in accordance with WE-103 N
Steps 4.1.4.4 through 4.1.4.6.
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Form NED 3.1 Rev.1 (effective 9/1/96)
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t' NED Procedure No. 3 Rev. _0_ Date 8/22/96 Page 4 of 5 g,gg ttc~ j NED-WE-103 REVIEW CHECKLIST p
(continued)
Compliance Reauirement Reviewer Reviewer Ensure the calculation includes a title page, objectivo method, inputs, Essumptions, calculations, results, conclusions and references.
4R Ensure the inputs are referenced to formal documents, e.g., WE-103.
The reference can not be a YAEC report unless formal QA records are checked aid also referenced.
AP N/A Ensure design input intemal and extemal correspondence is prepared j
cnd reviewed, and is, therefore, a QA record. If there is only one j
signature on the correspondence, verify that it is a QA record.
g N/A Ensure that if design specifications were used as input to the calculation, the performance characteristics are verified in writing by the provider of the component / product or by cognizant YAEC/ plant personnel.
,nD N/A Ensure that input and modeling uncertainties are explicitly addressed in the calculation.
N/A Ensure that the applicable input considerations from WE-100, Table i s
h:ve been incorporated and are explicitly addressed within the eWP N/A
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calculation.
' Ensure individuals responsible for' ach giortion of the ' calculation are e
identified when multipL preparers and/or reviewers are utilized. Page initialing is optional, even in the cases where initial boxes are provided
)
en the pages.
M l
l Ensure each page has a page number and the calculation number and j
revision number if applicable. Dates on each page are optional.
M Yud Ensure that every page of every attachment (or Appendix) contains its tttachment (or Appendix) number.
.hk YM Ensure a conclusion is stated in a supplemental Revision.
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Ensure corrections are addressed in one of the following approaches:
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.e.'..yetyiSH.Nid55tified th a'vstt'ic51'liiieYIth *reviiilb'rE ~. ' '. '
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number, if applicable, in the right margin; OR Lined out, initialed and dated by preparer; OR Photocopy of original to eliminate any previous correction e
tape, whiteout, or erasures.
M Yt3C.
Ensure enhancements and clouding are initiated and dated.
Yd Fonn NED 3.1 Rev.1 (effective 9/1/96)
NED Procedure No. 3 Rev. _Q. Date 8/22/96 Page 5 of 5 M-M9 NED-WE-103 REVIEW CHECKLIST gg (continued)
Compliance Reauirement Reviewer Reviewer Confirm legibility meets WE-103, Attachment A. Specific pages can be cxempt if they are: (1) documents received from another organization who is the original QA custodian, or (2) supplemental pages included for information only. In these two cases, make sure a memo was issued to RMS per WE-002 Section 3.4.3.
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R; view of 10CFR50.46 reporting requirements has been documented for d
N/A analyses wh'ch assess conformance with 10CFR50.46.
Ensure computer codes are validated for the computing environment.
d N/A Ensure script files are included in the calculation or referenced to another calculation. Also, ensure the preparer identifies how tha N
N/A code / script was run.
Ensure applicable outstanding Engineering Deficisney Repcrts (EDRs) hive been reviewed for influence on the calculation and note review in M
N/A calculation.
Ensure relevant SER conditions / limitations have been reviewed for their g '4 C E_
cffect on this calculation and the review is noted in the calculation.
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Spent Fuel Pool Passive Cooling MYC-2005 Rev.0 l
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Prepared by MWS Reviewed by_$2 Page_n2.of__
8.8 NED Analysis Process Checklist l
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NED Procedure No. 6 g 116 1
Rev. _2_ Date 5/7/97 Page 7 of 9 I
Table 1 NED ANALYSIS PROCESS CHECKLIST Reviewer Preparer b\\klikhTW, hYYWf (pie se print)
Nj A?[ M,[(,,e[
please print)
Organization V/]/(,
Organization
- MEC, Signature h
Mg Signature h h o,
, Date 1Z// /47 Date d / t ICM Reauirement Preoarer Reviewer W
N Ensure that the method described in the MOM, if applicable, and the base calculation, if one exists, has been followed W
N if not, ensure lead engineer / manager is consulted and documentvariation in calculation W
d Ensure that other applicable NED Procedures are implemented M
N Ensure inputs / assumptions are obtained from appropriate sources M
VW1 Ensure any change to an input / assumption is consistent with operating practice at the plant M
Ensure that the safety analysis conforms to applicable requirements Ensure that intermediate results that would require a change to W
N/A l7evA plant operating practice are dispositioned and documented W
N/A l12t#A Ensure, if reporting preliminary results, that the standard memorandum clearly states the results are preliminary and provides the status of the final analysis W
N/A l12evJ-Ensure that issues found when performing an analysis are dispositioned and documented d
Ensure a standard memorandum is written describing the snarysis pedeimed and containing the following elements:
Any documents affected by the analysis are M
updated N
Recommend updates be incorporated in the
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affected documents and include an action taken
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NED Procedure No. 6 Rev. 2. Date 5.7/97 Page 8 of 9
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l NED ANALYSIS PROCESS CHECKLIST (continued)
Reauirement Preoarer Reviewer if the memorandum recommends updates to
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affected documents, copy the NED Administrative Assistant Provide a list of personnel for distribution at YNSD 17 N 3
and the sponsor h
Notify project and sponsor Scensing groups of any
/hd known NRC reporting requirements include a safety evaluation, if a plant operating Ph*7 practice is known to be affected Ensure that this checidist has been filled out and is attached to both DrU the memorandum, placed in department chronological files, and the calculation. [ NOTE: 1he checidist does not need to be attached to distributed copies of the memorandum.]
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