ML14029A063

From kanterella
Jump to navigation Jump to search
Kewaunee,Calculation 2013-07050, Revision 2 - Maximum Cladding Temperature Analysis for an Uncovered Spent Fuel Pool with No Air Cooling
ML14029A063
Person / Time
Site: Kewaunee Dominion icon.png
Issue date: 01/16/2014
From:
Dominion Energy Kewaunee
To:
Office of Nuclear Reactor Regulation
References
13-495A 2013-07050, Rev 2
Download: ML14029A063 (22)
v • d • e


Text

CALCULATION 2013-07050, REVISION 2 MAXIMUM CLADDING TEMPERATURE ANALYSIS FOR AN UNCOVERED SPENT FUEL POOL WITH NO AIR COOLING

CalculationReview Checklist

) Dominion- I CMAA-L0 ATTACMN 4 Page 1 Calculation# 2013-07050 Rev. 2 Add. N/A NOTE: If 'Yes" is not answered, an explanation may be provided below. Reference may be made to explanations contained in the calculation or addendum.

1. Have the sources of design inputs been correctly selected and referenced in the [X] I I calculation?
2. Are the sources of design inputs up-to-date and retrievable/attached to the calculation? [X ][ ]
3. Where appropriate, have the other disciplines reviewed or provided the design inputs for which they are responsible? [X] 1 ]
4. Have design inputs been confirmed by analysis, test, measurement, field walkdown, or I I other pertinent means as appropriate for the configuration analyzed?
5. Have the bases for assumptions been adequately and clearly presented and are they [ ] I I bounded by the Station Design Basis?
6. Were appropriate calculation/analytic methods used and are outputs reasonable when compared to inputs? R I E]
7. Are computations technically accurate? IX I] ]
8. Has the calculation made appropriate allowances for instrument errors and calibration equipment errors? [X ]
9. Have those computer codes used in the analysis been referenced in the calculation? [X ] [ I
10. Have all exceptions to station design basis criteria and regulatory requirements been identified and justified in accordance with NQA-1-1994? I I [XI
11. Has the design authority/original preparer for this calculation been informed of its revision I I or addendum, if required?

Comments provided to S & Lresolved in the final draft of the calculation to Dominion's satisfaction.

Item # 4 - Input data is from the literature or provided in ETE-NAF-2013-0077, Rev. 0 (documented in S & Lcalc).

  1. 10 - Calculation provides information and is not used for design basis criteria.
  1. 11 -The original preparer of Rev. 2 is the same as Rev. 0 and 1.

Signature: N/A Date: N/A (Preparer)

Signature: M.S. Lico Date: 9-'61 13 (Reviewer)

Note: Physical or electronic signatures are acceptable.

731190 (Mar 2012)

Document No. 2013-07050 Kewaunee Power Station Revision 2 Page 1 of 10

[This page intentionally omitted]

Document No. 2013-07050 Kewaunee Power Station Revision 2 Paqe 2 of 10

1. Purpose and Scope ............................................................................................................................. 3
2. References ........................................................................................................................................... 4
3. Definitions ........................................................................................................................................... 4
4. Input Data ........................................................................................................................................... 5
5. Assum ptions ........................................................................................................................................ 6
6. M ethodology ....................................................................................................................................... 7
7. Results ................................................................................................................................................. 9
8. Conclusions and Recom m endations ........................................................................................... 10 Attachments: No. of Pages:

Attachm ent A : Generation Rate vs. Decay Tim e (Reference 2.5) ........................................................... 6 Attachm ent B: Analysis ................................................................................................................................ 2 Attachm ent C: Current SFP Temperature ................................................................................................ 2 Saergent & Ltandy-

Document No. 2013-07050 Kewaunee Power Station Revision 2 Pagee3ofl0

1. Purpose and Scope 1.1. Purpose The purpose of this calculation is to conservatively evaluate the length of time (number of hours) it takes for uncovered spent fuel assemblies to reach the temperature where the zirconium cladding would fail. This analysis conservatively assumes that there is no air cooling of the assemblies: the flow paths that would provide natural circulation cooling are assumed to be blocked.

1.2. Scope The length of time for the fuel to heat up (the heat-up time) is determined as a function of the day that the analysis is performed (the decay time). The heat load from Westinghouse 422V+ fuel is used in this analysis (Reference 2.5 and Assumption 5.1).

The zirconium cladding must remain below the temperature where it will fail. Per NUREG/CR-6451 (Ref. 2.1, see Design Input 4.1), 565 'C (1049 'F) is the lowest temperature where incipient cladding failure might occur. NUREG-1738 (Ref. 2.7, pg.

3-7) states that runaway oxidation of zirconium occurs at 900 'C. For this analysis, the NUREG/CR-6451 temperature (565 'C, 1049 'F) and the NUREG-1738 temperature (900 'C, 1652 'F) are the temperatures of interest for the zirconium cladding.

There are no specific acceptance criteria for this analysis, however, SECY-99-168 (Ref.

2.4) suggests that "10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> (is) sufficient time to take mitigative action" and that for PWRs, 2.5 years is expected to be the decay time needed to reach a 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> heat-up time from 30 'C to 900 'C. NUREG-1738 shows that a 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> heat up time to 900 'C for a PWR would occur at less than 2 years (Ref. 2.7, Fig. 2-2).

/..

Ser'gor* &' Lasrndw"

Document No. 2013-07050 Kewaunee Power Station Re~visinn 2 Page 4 of 10 Revision 2

2. References 2.1. NUREG/CR-645 1, "A Safety and Regulatory Assessment of Generic BWR and PWR Permanently Shutdown Nuclear Power Plants," August 1997.

2.2. Incropera, Frank P., and David P. DeWitt, Introduction to Heat Transfer, Fourth Edition, John Wiley & Sons.

2.3. Kewaunee USAR, Chapter 3: Reactor, Revision 24.02 - Updated Online 04/15/13.

2.4. SECY-99-168, "Improving Decommissioning Regulations for Nuclear Power Plants,"

June 30, 1999.

2.5. Document No. ETE-NAF-2013-0077, "Information for Kewaunee Spent Fuel Pool Postulated Loss of Inventory Calculation," Rev. 0, July 10, 2013.

2.6. Email from Michael Lico (Dominion) to Matthew Ross (S&L), "KPS sfp temp today,"

July 22nd, 2013. Included as Attachment C.

2.7. NUREG-1738, "Technical Study of Spent Fuel Pool Accident Risk at Decommissioning Nuclear Power Plants," February 2001.

3. Definitions 3.1. Decay Time The decay time is the time since the reactor was shut down (May 7th, 2013).

3.2. Heat-up Time The heat-up time is the amount of time between when the fuel becomes uncovered and when the zirconium cladding reaches the failure temperatures of interest, 565 'C (1049

'F) and 900 'C (1652 'F).

Sargent &iLurody",

Document No. 2013-07050 Kewaunee Power Station Revision 2 Paqe 5 of 10

4. Input Data 4.1. Maximum Zirconium Temperature Several studies are presented in NUREG/CR-6451 (Ref. 2.1) discussing the maximum allowable temperature of zirconium cladding that will ensure that failure of the zirconium cladding will not occur. Per NUREG/CR-6451 (Ref. 2.1, see Design Input 4.1), 565 -C (1049 'F) is the lowest temperature where incipient cladding failure might occur. NUREG-1738 uses 900 'C (1652 'F) as the temperature where "runaway oxidation" is expected to occur (Ref. 2.7, pg. 3-7). These two temperatures are the failure temperatures of interest for this calculation 4.2. Zirconium Properties The specific heat of zirconium at 600 K (620 'F) is 322 J/kg-K and the density of zirconium is 6570 kg/m 3 (Ref. 2.2, pg. 822). A temperature of 620 'F is in the temperature range (less than the midpoint for both ranges) of this analysis. From Reference 2.2, the specific heat slightly increases with an increase in temperature. At higher temperatures, the zirconium would heat up more slowly. This temperature is representative of the full temperature range for this analysis.

4.3. Uranium Properties The specific heat of uranium at 600 K (620 'F) is 146 J/kg-K and the density of uranium is 19070 kg/mi3 (Ref. 2.2, pg. 822). A temperature of 620 'F is in the temperature range (less than the midpoint for both ranges) of this analysis. From Reference 2.2, the specific heat slightly increases with an increase in temperature. At higher temperatures, the uranium would heat up more slowly. This temperature is representative of the full temperature range for this analysis.

4.4. Geometry for Westinghouse 422V+ Assemblies The table below shows the geometry inputs for the fuel assemblies used in this analysis.

Table 4-1: Fuel Assembly Inputs (from USAR Table 3.2-8, Ref. 2.3)

Uranium Pellet Diameter 0.3659 inches Inner Diameter of Cladding 0.3734 inches Outer Diameter of Cladding 0.422 inches Rod Configuration and Total Rods 14 x 14, 196 total spaces Number of Guide Tubes, Instrument Tubes 16 guide, 1 instrument Total Number of Heated Rods 179 rods Inner Diameter of Guide Tubes (Above Dashpot) 0.492 inches Outer Diameter of Guide Tubes (Above Dashpot) 0.526 inches Ssrgornt a, Lunody.

Document No. 2013-07050 Kewaunee Power Station Revision 2 Paqe 6 of 10 Table 4-1 Continued Heated Height of Rods 143.25 inches Cladding and Guide Tube Material ZIRLO Zirconium Theoretical Uranium Density Percentage 96.56%

4.5. Heat Load Reference 2.5 determines the maximum heat load from a single assembly. The assembly with the highest heat load will have the shortest heat-up time. The table showing the maximum fuel assembly heat generation rate for several years is located in Attachment A. The heat generation rates were calculated using the computer program HEATUP. Per Reference 2.5, the results in HEATUP are conservative compared to ORIGEN models.

5. Assumptions 5.1. All of the fuel assemblies are assumed to be Westinghouse 422V+ fuel. This is appropriate because the most recent design consisted of a full core of 422V+ assemblies (Ref. 2.3, pg. 3.2-22). The most recently offloaded assemblies are limiting in terms of heat generation.

5.2. The properties of pure zirconium are used for the specific heat and density of the zirconium alloy cladding. Based on an examination of alloys of some metals (e.g.

aluminum, nickel, or steel) in Table A. 1 of Reference 2.2, the density and specific heat are not significantly impacted by alloying.

5.3. Details of the thermal mass of the instrument tube are unavailable. For simplicity, the instrument tube is assumed to be identical to the guide tubes. This is appropriate because there are 16 guide tubes and one instrument tube, and the guide tubes are hollow while the instrument tube may have other thermal mass of the instruments.

5.4. The starting temperature for the heat-up analysis is assumed to be uniform and 90 OF (32 °C). A temperature of 90 OF is selected as representative of the current pool conditions (see Attachment C). The water temperature in the pool will continue to decrease over time due to a reduction in the heat load. It is appropriate to use a realistic value for the initial temperature due to the inherently conservative methodology (i.e. no heat transfer to the environment). In addition, this temperature is consistent with the sample analysis performed in SECY-99-168, where the starting temperature was 30 'C (86 °F).

5.5. The heat-up time is assumed to start when the spent fuel pool has been completely drained. This is conservative. It is likely that site personnel will start to respond to an incident when draindown starts.

Sargent C.%Lu-"

Document No. 2013-07050 Kewaunee Power Station Revision 2 Page 7ofl01

6. Methodology This analysis determines the heat-up time of the fuel assembly using the thermal capacity of materials (Based on Section 2.3 of Ref. 2.2).

PVxCPxAT q =pxVxcp AT t Equation 6-1 Where:

4 is the heat generation rate in BTU/hr 3

p is the density of the material in lb/ft 3

V is the volume of the material in ft cp is the specific heat in BTU/lb-OF AT is the temperature increase in OF t is the heat-up time in hr For this analysis, there are two materials being heated: the uranium fuel pellets and the ZIRLO zirconium alloy cladding. The zirconium is in the cladding and the instrument tubes, which are also being heated. The zirconium and the uranium are modeled as heating up at the same rate, so the AT/t will be the same for both materials.

q=ATt xo,xvx +pzx xc.) Equation 6-2 Where:

X, signifies the property is for uranium X, signifies the property is for zirconium This calculation seeks the heat-up time, so Equation 6-2 is solved for t.

Equation 6-3 4

The volume of uranium is given below.

1/U= Cx4 NhrxL Equation 6-4 Where:

Dp is the diameter of the uranium pellet Nhr is the number of heated rods L is the heated length of the rods Sar'gontv &ý Lurody-

Document No. 2013-07050 Kewaunee Power Station Revision 2 Paqe 8 of 10 The volumes of zirconium in the heated rods and in the guide tubes are given below. The length of the cladding and guide tubes that are heated is conservatively modeled as being the same as the heated length of uranium. The guide tubes and cladding are longer than the length of the uranium pellets.

, Dco* ,' Nh, xL Equation 6-5 Vz g ' grx 4- Ng xL Equation 6-6 V_ = V_.' + V_.. Equation 6-7 Where:

Vz, is the volume of zirconium in the cladding of heated tubes Vz,g is the volume of zirconium in the guide tubes Dc,, is the outer diameter of the cladding Dci is the inner diameter of the cladding Dg,o is the outer diameter of the guide tubes Dgji is the inner diameter of the guide tubes Ngt is the number of guide tubes The temperature increase (AT) for this analysis is taken to be from the initial temperature of the pool, 90 'F (Assumption 5.4), to the zirconium cladding failure temperatures of interest, 1049 'F and 1652 'F (Input 4.1).

The heat-up time is calculated as a function of the decay time.

To avoid rounding, the Hottest Assembly column is recalculated in Attachment A based on the equations presented in Reference 2.5. Per Reference 2.5, the hottest assembly is calculated as:

Hottest Assembly =(Heat Load from Cycle 32 Discharge Assemblies x1.449 Hottest =121x Asembly 44 Sewgonc r- Lundy-

Document No. 2013-07050 Kewaunee Power Station Revision 2 Pae 9of 10

7. Results The results are shown in Table 7-1 below (from Attachment B).

Table 7-1: Results Date End Temperature Decay Time Heat-Up Time

(°C, OF) (months) (hours)

October 4 th, 2013 565, 1049 -5 2.0 April 8t h, 2014 565, 1049 - 11 4.0 July 7th, 2014 565, 1049 14 4.9 October 7 t , 2014 565, 1049 17 6.0 August 21s t , 2015 565, 1049 - 28 10.0 July 18th, 2013 900, 1652 -2 2.0 November 16t', 2013 900, 1652 -6 4.0 March 11th, 2014 900, 1652 -10 6.0 October 21st , 2014 900, 1652 -17 10.0 The 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> heat-up time to a temperature of 565 'C (1049 OF) occurs at a decay time of under 2.5 years, which is the expected decay time to a temperature of 900 °C (1652 OF) stated in SECY-99-168 (Ref. 2.4). The 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> heat-up time to a temperature of 900 'C (1652 OF) occurs at a decay time of roughly 1.5 years, which is less than the expected decay time calculated in NUREG-1738 (Ref. 2.7, pg. 2-3).

A plot showing the heat-up time to the temperatures of interest as a function of decay time is Figure 7-1.

Seigent* &* L.rid-

Document No. 2013-07050 Kewaunee Power Station Revision 2 Paae 10 of 10 Figure 7-1: Heat-Up Time vs. Decay Time 12 10 CL E

8 0.

0-6 00 E 4 0

IL E0 CL 2

0 k 1/1/2013 7/2/2013 1/1/2014 7/2/2014 1/1/2015 7/3/2015 1/1/2016 7/2/2016 Day (Shutdown was May 7, 2013)

8. Conclusions and Recommendations The Kewaunee results are more favorable than the analyses performed for SECY-99-168 (Ref. 2.4) and NUREG-1738 (Ref. 2.7). There are no acceptance criteria for this analysis.

There are no specific recommendations for this analysis.

The primary input to this analysis is the heat generation rate, which is conservative. The heat generation rates were calculated using the computer program HEATUP. Per Reference 2.5, the results in HEATUP are conservative compared to ORIGEN models.

Sargent&C Lurady"I

Calculation 2013-07050 Rev. 0 Kewaunee Power Station Page Al of 6 Attachment A: Heat Generation Rate vs. Decay Time (from Ref. .5 Heat Load from Hottest Fuel Recalculated Cycle 32 Discharge Assembly Hottest Assemblies Only Estimate Date Days since Assembly Date Time (MBTU/hr) (MBTU/hr) __(Reprinted) May 8, 2013 (MBTU/hr) 5/8/2013 0:00 32.25 0.386 5/8/2013 0 0.3862 5/8/2013 8:00 28.23 0.338 15/8/2013 0.33 0.3381 5/8/2013 16:00 26.62 0.319 5/8/2013 0.67 0.3188 5/9/2013 0:00 25.39 0.304 5/9/2013 1 0.3041 5/9/2013 8:00 24.36 0.292 5/9/2013 1.33 0.2917 5/9/2013 16:00 23.45 0.281 5/9/2013 1.67 0.2808 5/10/2013 0:00 22.62 0.271 5/10/2013 2 0.2709 5/10/2013 8:00 21.86 0.262 15/10/2013 2.33 0.2618 5/10/2013 16:00 21.15 0.253 5/10/2013 2.67 0.2533 5/11/2013 0:00 20.5 0.246 5/11/2013 3 0.2455 5/11/2013 8:00 19.9 0.238 5/11/2013 3.33 0.2383 5/11/2013 116:00 19.33 0.232 5/11/2013 3.67 0.2315 5/12/2013 0:00 18.81 0.225 _ 5/12/2013 4 0.2253 5/13/2013 0:00 17.44 0.209 1_5/13/2013 5 0.2088 5/14/2013 0:00 16.3 0.195 __5/14/2013 6 0.1952 5/15/2013 0:00 15.34 0.184 5/15/2013 7 0.1837 5/16/2013 0:00 14.52 0.174 -5/16/2013 8 0.1739 5/17/2013 0:00 13.81 0.165 5/17/2013 9 0.1654 5/18/2013 10:00 13.19 0.158 __5/18/2013 10 0.1580 5/19/2013 0:00 12.65 0.151 15/19/2013 11 0.1515 5/20/2013 0:00 12.16 0.146 __5/20/2013 12 0.1456 5/21/2013 0:00 11.73 0.140 __5/21/2013 13 0.1405 5/22/2013 0:00 11.34 0.136 __5/22/2013 14 0.1358 5/23/2013 0:00 10.99 0.132 __5/23/2013 15 0.1316 5/24/2013 10:00 10.67 0.128 __5/24/2013 16 0.1278 5/25/2013 0:00 10.38 0.124 15/25/2013 17 0.1243 5/26/2013 0:00 10.11 0.121 __5/26/2013 18 0.1211 5/27/2013 0:00 9.87 0.118 __5/27/2013 19 0.1182 5/28/2013 0:00 9.64 0.115 __5/28/2013 20 0.1154 5/29/2013 0:00 9.43 0.113 __5/29/2013 21 0.1129 5/30/2013 10:00 9.24 0.111 5/30/2013 22 0.1107 5/31/2013 0:00 9.06 0.108 1_5/31/2013 23 0.1085 6/1/2013 0:00 8.88 0.106 __6/1/2013 24 0.1063 6/3/2013 0:00 8.57 0.103 _ 6/3/2013 26 0.1026 6/5/2013 0:00 8.29 0.099 _ 6/5/2013 28 0.0993 6/7/2013 0:00 8.04 0.096 6/7/2013 30 0.0963 6/9/2013 10:00 7.8 0.093 _ 6/9/2013 32 0.0934 6/11/2013 0:00 7.59 0.091 16/11/2013 34 0.0909 6/13/2013 0:00 7.38 0.088 -6/13/2013 36 0.0884 6/15/2013 0:00 7.19 0.086 -6/15/2013 38 0.0861 6/17/2013 0:00 7.01 0.084 _ 6/17/2013 40 0.0839 6/19/2013 0:00 6.84 0.082 _ 6/19/2013 42 0.0819 6/21/2013 10:00 6.68 0.080 __6/21/2013 44 0.0800 6/25/2013 0:00 6.38 0.076 1_6/25/2013 48 0.0764 6/29/2013 0:00 1 6.11 0.073 1_6/29/2013 52 0.0732 7/3/2013 10:00 1 5.86 0.070 17/3/2013 56 1 0.0702

Calculation 2013-07050 Rev. 0 Kewaunee Power Station Page A2 of 6 Attachment A: Heat Generation Rate vs. Decay Time (from Ref. .5 Heat Load from Hottest Fuel Recalculated Cycle 32 Discharge Assembly Hottest Assemblies Only Estimate Date Days since Assembly Date Time (MBTU/hr) (MBTU/hr) __(Reprinted) May 8, 2013 (MBTU/hr) 7/7/2013 0:00 5.64 0.068 _ 7/7/2013 60 0.0675 7/11/2013 10:00 5.43 0.065 1_7/11/2013 64 0.0650 7/15/2013 0:00 5.24 0.063 __7/15/2013 68 0.0628 7/19/2013 0:00 5.07 0.061 7/19/2013 72 0.0607 7/23/2013 0:00 4.91 0.059 __7/23/2013 76 0.0588 7/27/2013 0:00 4.76 0.057 7/27/2013 80 0.0570 8/6/2013 0:00 4.42 0.053 __8/6/2013 90 0.0529 8/16/2013 0:00 4.13 0.049 __8/16/2013 100 0.0495 8/26/2013 10:00 3.88 0.046 1_8/26/2013 110 0.0465 9/5/2013 0:00 3.66 0.044 __9/5/2013 120 0.0438 9/15/2013 0:00 3.46 0.041 9/15/2013 130 0.0414 9/25/2013 0:00 3.27 0.039 9/25/2013 140 0.0392 110/5/20113 0:00 3.11 0.037 _ 10/5/2013 150 0.0372 10/15/2013 0:00 2.96 0.035 _ 10/15/2013 160 0.0354 10/25/2013 10:00 2.82 0.034 1__10/25/2013 170 0.0338 11/4/2013 0:00 2.69 0.032 _ 11/4/2013 180 0.0322 11/24/2013 0:00 2.46 0.030 _ 11/24/2013 200 0.0295 12/14/2013 0:00 2.27 0.027 _ 12/14/2013 220 0.0272 1/3/2014 0:00 ___ 2.1 0.025 1/3/2014 240 0.0251 1/23/2014 0:00 1.96 0.023 _ 1/23/2014 260 0.0235 2/12/2014 10:00 1.84 0.022 1_2/12/2014 280 0.0220 3/4/2014 0:00 1.73 0.021 _ 3/4/2014 300 0.0207 3/24/2014 0:00 1.63 0.020 _ 3/24/2014 320 0.0195 4/13/2014 0:00 1.54 0.018 _ 4/13/2014 340 0.01184 5/3/2014 0:00 1.47 0.018 _ 5/3/2014 360 0.0176 5/23/2014 0:00 ____1.4 0.017 5/23/2014 380 0.0168 6/12/2014 10:00 1.33 0.016 1_6/12/2014 400 0.0159 7/2/2014 0:00 1.28 0.015 7/2/2014 420 0.0153 7/22/2014 0:00 1.22 0.015 _ 7/22/2014 440 0.0146 8/11/2014 0:00 1.17 0.014 __8/11/2014 460 0.0140 8/31/2014 0:00 1.13 0.013 __8/31/2014 480 0.0135 9/20/2014 0:00 1.08 0.013 __9/20/2014 500 0.0129 10/10/2014 10:00 1.04 0.012 110/10/2014 520 0.0125 10/30/2014 0:00 1 0.012 __10/30/2014 540 0.0120 11/19/2014 0:00 0.97 0.012 11/19/2014 560 0.0116 12/9/2014 0:00 0.93 0.011 12/9/2014 580 0.0111 12/29/2014 0:00 0.9 0.011 12/29/2014 600 0.0108 1/18/2015 0:00 0.87 0.010 1/18/2015 620 0.0104 2/7/2015 10:00 0.84 0.010 12/7/2015 640 0.0101 2/27/2015 0:00 0.81 0.010 __2/27/2015 660 0.0097 3/19/2015 0:00 0.79 0.009 _ 3/19/2015 680 0.0095 4/8/2015 0:00 0.76 0.009 _ 4/8/2015 700 0.0091 4/28/2015 0:00 0.74 0.009 __4/28/2015 720 0.0089 5/18/2015 0:00 0.72 0.009 __5/18/2015 740 0.0086 6/7/2015 10:00 0.7 0.008 1 1 6/7/2015 1 760 00084 6/27/2015 10:00 0.68 0.008 1 16/27/2015 1 780 1 0.0081

Calculation 2013-07050 Rev. 0 Kewaunee Power Station Page A3 of 6 Attachment A: Heat Generation Rate vs. Decay Time (from Ref. 2.5)

Heat Load from Hottest Fuel Recalculated Cycle 32 Discharge Assembly Hottest Assemblies Only Estimate Date Days since Assembly Date Time (MBTU/hr) (MBTU/hr) (Reprinted) May 8, 2013 (MBTU/hr) 7/17/2015 0:00 0.66 0.008 7/17/2015 800 0.0079 8/6/2015 0:00 0.64 0.008 8/6/2015 820 0.0077 8/26/2015 0:00 0.62 0.007 8/26/2015 840 0.0074 9/15/2015 0:00 0.6 0.007 9/15/2015 860 0.0072 10/5/2015 0:00 0.59 0.007 10/5/2015 880 0.0071 10/25/2015 0:00 0.57 0.007 10/25/2015 900 0.0068 11/14/2015 0:00 0.56 0.007 111/14/2015 920 0.0067 12/4/2015 0:00 0.54 0.007 1 12/4/2015 940 0.0065 12/24/2015 0:00 0.53 0.006 12/24/2015 960 0.0063 1/13/2016 0:00 0.52 0.006 1/13/2016 980 0.0062 2/2/2016 0:00 0.5 0.006 2/2/2016 1000 0.0060 2/22/2016 0:00 0.49 0.006 2/22/2016 1020 0.0059 3/13/2016 0:00 0.48 0.006 3/13/2016 1040 0.0057 4/2/2016 0:00 0.47 0.006 1 4/2/2016 1060 0.0056 4/22/2016 0:00 0.46 0.005 4/22/2016 1080 0.0055

Calculation 2013-07050 Rev. 0 Kewaunee Power Station Page A4 of 6 Attachment A: Heat Generation Rate vs. Time (from Ref. 2.5)

Heat Load from Cycle Hottest Fuel 32 Discharge Assembly Assemblies Only Estimate Date Days since Recalculated Hottest Date Time (MBTU/hr) (MBTU/hr) 1 (Reprinted) May 8, 2013 Assembly (MBTU/hr) 41402 0 32.25 0.386 =A3+B3 =0 =(C3/121)*1.449 41402 0.3333333, 28.23 0.338 =A4+B4 =F4-F$3 =(C4/121)'1.449 41402 0.6666666E 26.62 0.319 =A5+B5 =F5-F$3 =(C5/121)*1.449 41403 0 25.39 0.304 =A6+B6 =F6-F$3 =(C6/121)*1.449 41403 0.3333333" 24.36 0.292 =A7+B7 =F7-F$3 =(C7/121)*1.449 41403 0.6666666 23.45 0.281 _ =A8+B8 =F8-F$3 =(C8/121)*1.449 41404 0 22.62 0.271 =A9+B9 =F9-F$3 =(C9/121)*1.449 41404 0.3333333 21.86 0.262 =A10+B10 =F10-F$3 =(C10/121)*1.449 41404 0.6666666 21.15 0.253 =A11+B11 =F11-F$3 =(C11/121)*1.449 41405 0 20.5 0.246 =A12+B12 =F12-F$3 =(C12/121)*1.449 41405 0.3333333 19.9 0.238 =A13+B13 =F13-F$3 =(C13/121)'1.449 41405 0.6666666E 19.33 0.232 =A14+B14 =F14-F$3 =(C14/121)*1.449 41406 0 18.81 0.225 =A15+B15 =F15-F$3 =(C15/121)'1.449 41407 0 17.44 0.209 =A16+B16 =F16-F$3 =(C16/121)*1.449 41408 0 16.3 0.195 =A17+B17 =F17-F$3 =(C17/121)'1.449 41409 0 15.34 0.184 =A18+B18 =F18-F$3 =(C18/121)*1.449 41410 0 14.52 0.174 =A19+B19 =F19-F$3 =(C19/121)*1.449 41411 0 13.81 0.165 =A20+B20 =F20-F$3 =(C20/121)'1.449 41412 0 13.19 0.158 =A21+B21 =F21-F$3 =(C21/121)'1.449 41413 0 12.65 0.151 =A22+B22 =F22-F$3 =(C22/121)*1.449 41414 0 12.16 0.146 =A23+B23 =F23-F$3 =(C23/121)*1.449 41415 0 11.73 0.14 =A24+B24 =F24-F$3 =(C24/121)*1.449 41416 0 11.34 0.136 =A25+B25 =F25-F$3 =(C25/121)*1.449 41417 0 10.99 0.132 =A26+B26 =F26-F$3 =(C26/121)*1.449 41418 0 10.67 0.128 =A27+B27 =F27-F$3 =(C27/121)*1.449 41419 0 10.38 0.124 =A28+B28 =F28-F$3 =(C28/121)'1.449 41420 0 10.11 0.121 =A29+B29 =F29-F$3 =(C29/121)*1.449 41421 0 9.87 0.118 =A30+B30 =F30-F$3 =(C30/121)*1.449 41422 0 9.64 0.115 =A31+B31 =F31-F$3 =(C31/121)*1.449 41423 0 9.43 0.113 =A32+B32 =F32-F$3 =(C32/121)*1.449 41424 0 9.24 0.111 =A33+B33 =F33-F$3 =(C33/121 )1.449 41425 0 9.06 0.108 =A34+B34 =F34-F$3 =(C34/121)'1.449 41426 0 8.88 0.106 =A35+B35 =F35-F$3 =(C35/121)*1.449 41428 0 8.57 0.103 =A36+B36 =F36-F$3 =(C36/121)*1.449 41430 0 8.29 0.099 =A37+B37 =F37-F$3 =(C37/121)'1.449 41432 0 8.04 0.096 _ =A38+B38 =F38-F$3 =(C38/121)*1.449 41434 0 7.8 0.093 =A39+B39 =F39-F$3 =(C39/121)'1.449 41436 0 7.59 0.091 =A40+B40 =F40-F$3 =(C40/121)*1.449 41438 0 7.38 0.088 =A41+B41 =F41-F$3 =(C41/121)'1.449 41440 0 7.19 0.086 =A42+B42 =F42-F$3 =(C42/121)*1.449 41442 0 7.01 0.084 =A43+B43 =F43-F$3 =(C43/121)*1.449 41444 0 6.84 0.082 _ =A44+B44 =F44-F$3 =(C44/121)*1.449 41446 0 6.68 0.08 _ =A45+B45 =F45-F$3 =(C45/121)*1.449 41450 0 6.38 0.076 _ =A46+B46 =F46-F$3 =(C46/121)'1.449 41454 0 6.11 0.073 =A47+B47 =F47-F$3 =(C47/121)'1.449 41458 0 5.86 0.07 =A48+B48 =F48-F$3 =(C48/121)'1.449 41462 0 5.64 0.068 =A49+B49 =F49-F$3 =(C49/121 )'1.449 41466 0 5.43 0.065 =A50+B50 =F50-F$3 =(C50/121)'1.449

Calculation 2013-07050 Rev. 0 Kewaunee Power Station Page A5 of 6 Attachment A: Heat Generation Rate vs. Decay Time (from Ref. 2.5)

Heat Load from Cycle Hottest Fuel 32 Discharge Assembly Assemblies Only Estimate Date Days since Recalculated Hottest Date Time (MBTU/hr) (MBTU/hr) 1 (Reprinted) May 8, 2013 Assembly (MBTU/hr) 41470, 0 5.24 0.063 =A51+B51 =F51-F$3 =(C51/121)*1.449 41474 0 5.07 0.061 =A52+B52 =F52-F$3 =(C52/121)*1.449 41478 0 4.91 0.059 =A53+B53 =F53-F$3 =(C53/121)'1.449 41482 0 4.76 0.057 =A54+B54 =F54-F$3 =(C54/121)'1.449 41492 0 4.42 0.053 =A55+B55 =F55-F$3 =(C55/121)*1.449 41502 0 4.13 0.049 _ =A56+B56 =F56-F$3 =(C56/121)*1.449 41512 0 3.88 0.046 =A57+B57 =F57-F$3 =(C57/121)*1.449 41522 0 3.66 0.044 =A58+B58 =F58-F$3 =(C58/121)*1.449 41532 0 3.46 0.041 =A59+B59 =F59-F$3 =(C59/121)*1.449 41542 0 3.27 0.039 =A60+B60 =F60-F$3 =(C60/121)*1.449 41552 0 3.11 0.037 =A61+B61 =F61-F$3 =(C61/121)*1.449 41562 0 2.96 0.035 =A62+B62 =F62-F$3 =(C62/121)'1.449 41572 0 2.82 0.034 =A63+B63 =F63-F$3 =(C63/121)*1.449 41582 0 2.69 0.032 =A64+B64 =F64-F$3 =(C64/121)'1.449 41602 0 2.46 0.03 =A65+B65 =F65-F$3 =(C65/121)*1.449 41622 0 2.27 0.027 =A66+B66 =F66-F$3 =(C66/121 )*1.449 41642 0 2.1 0.025 =A67+B67 =F67-F$3 =(C67/121)'1.449 41662 0 1.96 0.023 =A68+B68 =F68-F$3 =(C68/121)*1.449 41682 0 1.84 0.022 =A69+B69 =F69-F$3 =(C69/121)*1.449 41702 0 1.73 0.021 =A70+B70 =F70-F$3 =(C70/121)*1.449 41722 0 1.63 0.02 =A71+B71 =F71-F$3 =(C71/121)*1.449 41742 0 1.54 0.018 =A72+B72 =F72-F$3 =(C72/121)*1.449 41762 0 1.47 0.018 =A73+B73 =F73-F$3 =(C73/121)'1.449 41782 0 1.4 0.017 =A74+B74 =F74-F$3 =(C74/121)'1.449 41802 0 1.33 0.016 =A75+B75 =F75-F$3 =(C75/121)*1.449 41822 0 1.28 0.015 =A76+B76 =F76-F$3 =(C76/121)*1.449 41842 0 1.22 0.015 =A77+B77 =F77-F$3 =(C77/121)*1.449 41862 0 1.17 0.014 =A78+B78 =F78-F$3 =(C78/121)*1.449 41882 0 1.13 0.013 =A79+B79 =F79-F$3 =(C79/121)*1.449 41902 0 1.08 0.013 =A80+B80 =F80-F$3 =(C80/121)*1.449 41922 0 1.04 0.012 =A81+B81 =F81-F$3 =(C81/121)'1.449 41942 0 1 0.012 =A82+B82 =F82-F$3 =(C82/121)*1.449 41962 0 0.97 0.012 =A83+B83 =F83-F$3 =(C83/121)'1.449 41982 0 0.93 0.011 =A84+B84 =F84-F$3 =(C84/121)'1.449 42002 0 0.9 0.011 =A85+B85 =F85-F$3 =(C85/121 )*1.449 42022 0 0.87 0.01 =A86+B86 =F86-F$3 =(C86/121)'1.449 42042 0 0.84 0.01 =A87+B87 =F87-F$3 ,=(C87/121)*1.449 42062 0 0.81 0.01 =A88+B88 =F88-F$3 1=(C88/121)*1.449 42082 0 0.79 0.009 =A89+B89 =F89-F$3 =(C89/121)*1.449 42102 0 0.76 0.009 =A90+B90 =F90-F$3 =(C90/121)*1.449 42122 0 0.74 0.009 1=A91+B91 =F91-F$3 =(C91/121)*1.449 42142 0 0.72 0.009 =A92+B92 =F92-F$3 =(C92/121)*1.449 42162 0 0.7 0.008 =A93+B93 =F93-F$3 =(C93/121)*1.449 42182 0 0.68 0.008 =A94+B94 =F94-F$3 =(C94/121)*1.449 42202 0 0.66 0.008 =A95+B95 =F95-F$3 =(C95/121)'1.449 42222 0 0.64 0.008 =A96+B96 =F96-F$3 =(C96/121)*1.449 42242 0 0.62 0.007 =A97+B97 =F97-F$3 =(C97/121)'1.449 42262 0 0.6 0.007 ____ =A98+B98 =F98-F$3 =(C98/121)'1.449

Calculation 2013-07050 Rev. 0 Kewaunee Power Station Page A6 of 6 Attachment A: Heat Generation Rate vs. Decay Time (from Ref. 2.5)

Heat Load from Cycle Hottest Fuel 32 Discharge Assembly Assemblies Only Estimate Date Days since Recalculated Hottest Date Time (MBTU/hr) (MBTU/hr) (Reprinted) May 8, 2013 Assembly (MBTU/hr) 42282 0 0.59 0.007 =A99+B99 =F99-F$3 =(C99/121 )'1.449 42302 0 0.57 0.007 =A100+B1300 =F100-F$3 =(C100/121)*1.449 42322 0 0.56 0.007 =A101+B101 =F101-F$3 =(C101/121)*1.449 42342 0 0.54 0.007 =A102+B102 =F102-F$3 =(C102/121)*1.449 42362 0 0.53 0.006 =A103+B103 =F103-F$3 =(C103/121)*1.449 42382 0 0.52 0.006 _ =A104+B104 =F104-F$3 =(C104/121)*1.449 42402 0 0.5 0.006 =A105+B105 =F105-F$3 =(C105/121)*1.449 42422 0 0.49 0.006 =A106+B106 =F106-F$3 =(C106/121)'1.449 42442 0 0.48 0.006 =A107+B107 =F107-F$3 =(C107/121)'1.449 42462 0 0.47 0.006 =A108+B108 =F108-F$3 =(C108/121)*1.449 42482 0 0.46 0.005 =A109+B109 =F109-F$3 =(C109/121)*1.449

Calculation 2013-07050 Rev. 2 Kewaunee Power Station Page B1 of 2 Attachment B: Analysis Specific Heat of Uranium 146 J/kg-K Input 4.3 Specific Heat of Uranium 0.035 BTU/Ib-F Conversion Specific Heat of Zirconium 322 J/kg-K Input 4.2 Specific Heat of Zirconium 0.077 BTU/Ib-F Conversion Diameter of Fuel Uranium 0.3659 inches Input 4.4 Inner Diameter of Zirconium 0.3734 inches Input 4.4 Outer Diameter of Zirconium 0.422 inches Input 4.4 Heated Rods per Assem 179 Rods Input 4.4 Unheated Rods (Guide or Instrument Tubes) 17 Tubes Input 4.4 ID of Guide Tubes 0.492 inches Input 4.4 OD of Guide Tubes 0.526 inches Input 4.4 Density of Uranium 19,070 kg/m3 Input 4.3 Theoretical Density 96.56% Input 4.4 3

Density of Uranium 1149.5 lb/ft Conversion Density of Zirconium 6570 kg/m3 Input 4.2 3

Density of Zirconium 410.2 lb/ft Conversion Heated Length of Uranium 11.9375 feet Input 4.4 Initial Temperature 90 F Assumption 5.4 Final Temperature 1049 F Input 4.1 Total temperature Increase 959 F Initial Minus Final 3

Volume of Uranium 1.560 ft Equation 6-4 3

Volume of Zirconium in a Heated Rod 0.451 ft Equation 6-5 Volume of Zirconium in a Guide Tube 0.038 ft 33 Equation 6-6 Total Volume of Zirconium 0.489 ft Equation 6-7 Assem Heat Generation at 14 Months 0.01515 MBTU/hr Interpolated from Aft. A Time to Failure 4.94 hrs Equation 6-3 Assem Heat Generation at 17 Months 0.01253 MBTU/hr Interpolated from Aft. A Time to Failure 5.97 hrs Equation 6-3 Heat Generation that Gives 2 Hour Heat-Up 0.03739 MBTU/hr Iterated Time to Failure 2.00 hrs Equation 6-3 Date of Associated Heat Generation 10/4/2013 Interpolated from Aft. A Heat Generation that Gives 4 Hour Heat-Up 0.01869 MBTU/hr Iterated Time to Failure 4.00 hhrs Equation 6-3 Date of Associated Heat Generationr 4/8/20 14 Interpolated from Aft. A Heat Generation that Gives 10 Hour Heat-Up 0.00748 MBTU/hr Iterated Time to Failure 10.00 hrs Equation 6-3 Date of Associated Heat Generation 8/21/2015 Interpolated from Aft. A NUREG-1783 Maximum Temperature (900 C) 1652 F Input 4.1 Temperature Increase 1562 F Initial Minus Final Heat Generation that Gives 10 Hour Heat-Up 0.01218 MBTU/hr Iterated Time to Failure 10.00 hrs Equation 6-3 Date of Associated Heat Generation 10/21/2014 Interpolated from Aft. A Heat Generation that Gives 6 Hour Heat-Up 0.02030 MBTU/hr Iterated Time to Failure 6.00 hrs Equation 6-3 Date of Associated Heat Generation 3/11/2014 Interpolated from Att. A Heat Generation that Gives 4 Hour Heat-Up 0.03045 MBTU/hr Iterated Time to Failure 4.00 hrs Equation 6-3 Date of Associated Heat Generation 11/16/2013 Interpolated from Att. A Heat Generation that Gives 2 Hour Heat-Up 0.06089 MBTU/hr Iterated Time to Failure 2.00 hrs Equation 6-3 Date of Associated Heat Generation 7/18/2013 Interpolated from Att. A

Calculation 2013-07050 Rev. 2 Kewaunee Power Station Page B2 of 2 A B C D E F 1 Attachment B: Analysis 2

3 Specific Heat of Uranium 146 J/kg-K Input 4.3 4 Specific Heat of Uranium =B3*0.0009478/2.20462J(9/5) BTU/Ib-F Conversion 5 Specific Heat of Zirconium 322 J/kg-K Input 4.2 6 Specific Heat of Zirconium =B5"0.0009478/2.20462/(9/5) BTU/Ib-F Conversion 7 Diameter of Fuel Uranium 0.3659 inches Input 4.4 8 Inner Diameter of Zirconium 0.3734 inches Input 4.4 9 Outer Diameter of Zirconium 0.422 inches Input 4.4 10 Heated Rods per Assem 179 Rods Input 4.4 11 Unheated Rods (Guide or Instrument Tubes) 17 Tubes Input 4.4 12 ID of Guide Tubes 0.492 inches Input 4.4 13 OD of Guide Tubes 0.526 inches Input 4.4 3

14 Density of Uranium 19070 kg/m Input 4.3 15 Theoretical Density 0.9656 Input 4.4 3

16 Density of Uranium =B14*2.20462/3.28084^3*B15 lb/ft Conversion 3

17 Densit of Zirconium 6570 kg/m Input 4.2 18 Density of Zirconium =1B17*2.20462/3.28084^3 Ib/ft' Conversion 19 Heated Length of Uranium =143.25/12 feet Input 4.4 20 Initial Temperature 90 F Assumption 5.4 21 Final Temperature 1049 F Input 4.1 22 Total temperature Increase =B21-B20 F Initial Minus Final 23 24 Volume of Uranium =PI(*B7^2/4*B19/144*B10 ftW Equation 6-4 25 Volume of Zirconium in a Heated Rod =PI0*(B9^2-8^2)/4*B19/144*B10 ftW Equation 6-5 3

26 Volume of Zirconium in a Guide Tube =Plf)*(B13^2-B122)/4*B19/144*B11 ft Equation 6-6 27 Total Volume of Zirconium =B25+B26 ft3 Equation 6-7 28 29 Assem Heat Generation at 14 Months ='AttachmentA'?H76-(5/20)°('Attachment ANH76-'Attachment A!H77) MBTU/hr Interpolated from Alt. A 30 Time to Failure =$B$22/ B29*10^6 *($B$16*$B$24*$B$4+$B$18*$B$27*$B$6) hrs Equation 6-3 31 32 Assam Heat Generation at 17 Months ='AttachmentA N8-17/0*'tahet H0'tahet'H81) MBTU/hr Interpolated from All. A 33 Time to Failure =$B$22/(B32*106 *$B$16$B$24*$B$4+$B$18*$B$27*$B$6) hrs Equation 6-3 34 35 Heat Generation that Gives 2 Hour Heat-Up 0.0373850764604915 MBTU/hr Iterated 36 Time to Failure =$B$22/(B35"106)*($B$16*$B$24*$B$4+$B$18*$B$27*$B$6) hrs Equation 6-3 37 Date of Associated Heat Generation ='Attachment A'1F60+('Attachment A!H60-B35)/('Attachment A!H60-Attachment AIH61H'10 Interpolated from Alt. A 38 39 Heat Generation that Gives 4 Hour Heat-Up 0.0186925354210505 MBTU/hr Iterated 40 Time to Failure =$B$22/ B3910'6)*$B$16*$B$24*$B$4+$B$18*$B$27*$B$6) hrs Equation 6-3 41 Date of Associated Heat Generation ='Attachment A'F71+('Attachment A'!H71-B39 /'Attachment A'NH71-'Attachment A1H72)*20 Interpolated from Att. A 42 43 Heat Generation that Gives 10 Hour Heat-Up 0.00747701366999636 MBTU/hr Iterated 44 Time to Failure =$B$22/8B43*85106A$B$161$B$24*$B$4+$B$18*$B$27*$B$6) hrs Equation 6-3 45 Date of Associated Heat Generation ='Attachment A'F96+'(Attachment A'HH7-B43)/'Attachment A'H76-Attachment A'H71*20 Interpolated from Alt. A 46 47 NUREG-1783 Maximum Temperature (900 C) 1652 F Input 4,1 48 Temperature Increase =1347-1320 F Initial Minus Final 49 Heat Generation that Gives 10 Hour Heat-Up 0.0121784105537324 MBTU/hr Iterated 50Time to Failure =$B$48/(B49*10^6)*($B$16*$B$24*$B$4+$B$18*$B$27*$S$6) firs Equation 6-3 51 Date of Associated Heat Generation ='Attachment ANIF81 +(Atcmn AH8-4/'tacmnA'81Atachment A'IH82)*20 Interpolated from All. A 53 Heat Generation that Gives 6 Hour Heat-Up 0.0202973514135572 MBTU/hr Iterated 54 Time to Failure =$B$48/(B53*10^6)*($B$16*$B$24*$B$34+$B$18*$B$27*$8$6) hra Equation 6-3 55 Date of Associated Heat Generation ='Attachment ANlF70+('Attarhment A'IH70-B53y//'Attachment ANlH70-'Attachment ANIH71)*20 Interpolated from Aft. A N"

57 Heat Generation that Gives 4 Hour Heat-Up 10.0304460281462153 MSTU/hr Iterated Time to F. 7-10A6)'($B$16S8B$24S6BS4+$B$1 8*$$271B8$6) fhs Equation 6-3 1_______________

59 ate of Associated Heat Gener men' ,1*H,-1:

-/*1 + -*1~acn ý -[,acn-men, -,*H1-,-amren, " rolz III][BrI*I*ItF*U IrUlrl P.*..*

Interpolated from w ý -

MBI "ted T hrs ationd -3 631 Date of Associated Hea Date ofAssociated Heal from All. A I________ rp~~olated_________

Calculation 2013-07050, Rev 2 Page Cl of 2 Kewaunee Power Station

[This page intentionally omitted]

x 0 1* ,ýcSOMS uite Narratiý Logs - [iELFENDERGER,JOHN -[Control Rooni Log -Monday, July Z2, 2013- Day Shift -Active& Current] CD Q) i ,Ele Mdl Iurrmv Reperts Reup En~d- U*~

CD~

CD

-01 0 C)

CD -

C-)

CD 0

N),

0)

Retrieved from "https://kanterella.com/w/index.php?title=ML14029A063&oldid=2054203"