ML102530142

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Calculation 1095-20, Rev. 1, Maximum Operating Pressures, Storage & Transfer, Enclosure 4 and Attachment 2
ML102530142
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 05/21/2004
From:
Transnuclear
To:
Office of Nuclear Material Safety and Safeguards
References
1095-20, Rev 1
Download: ML102530142 (15)
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Text

ENCLOSURE4 Non-Proprietary Transnuclear Calculation 1095-20, Revision 1, Maximum Operating Pressures, Storage and Transfer, May 2004 Calvert Cliffs Nuclear Power Plant, LLC September 1, 2010

A Form 3.1-1 C aic. No.:

1095-20 TRANSNUCLEAR Calculation Rev. No.:

1 Proect No.:

10950 DCR No.:

f 10950-16, re6.0 Page:

1 1 of 1 6 Project Name:

NUHOMS-32P for CCNPP Calculation

Title:

Maximum Operating Pressures, Storage. and Transfer Number-of CDs attached:

0 If original issue, I1CFR72A8 revieW:required?:

[ No(explain)

El Yes, LR NO.

00AIMILLIWWRYO.. ý0- -_9t This calculation is performed in support of the iLcensee, CCNPP 1,

This calculation Is complete and ready for independent review Originator's Signature 4 Date: 4Zr*..

2.

This calculation has been checked fOr consistency, completeness, and arithmetic correctness.

All comments have been Incorporated or otherwise resOlved satisfactorily.

AllUnoll Items In the Review Checklist have been resolved satisfactorily.

A91

/' 1ý4ý Date:

Ad___-

Checker Signature

3.

Calculation preparation and check complies with procedure - package Is complete P~s Sgnatue Dae:

,,,/,,

PE's Signature Date:

ý Z-2

A

.Form 3,1-1 Cac No.:..

1095-20 TRANSNUCLEAR Calculation Rev. No.:

I Paoe:,.

2 _ of L* 6 1.0 Purpose To determine maximum pressures within the canister during storage and transfer conditions.

2.0 References

1) Calculation 1095-29, Rev. 0, "NUHOMS-32P, DSC Thermal Analysis, Normal Storage Conditions."
2) Calculation 1095-30, Rev. 0, "NUHOMS-32P, HSMThermal Analysis. Off-Normal Storage Conditions"
3) Calculation 1095-28, Rev. 0, uNUHOMSý32P, Thermal Analysis, Accident Conditions (Blocked Vent)"
4) Calculation 1095-6, Rev. 0, "NUHOMS-32P, Transfer Thermal Analysis, 103 "F Ambient"
5) CCNPP Calculation CA03947, Rev. 1, "DSO Internal Pressure" 6). Calculation 1095-1, Rev.O,, NUHO IMS-32P Weight Calculations of DSC/TC System"
7) Calvert Cliffs ISFSI, Volume V, *Technical Specifications Manual" Rev. 11
8) Calculation 1095-53, Rev. 0, "Thermal Analysis of Transfer Cask with Poison Material"
9) Calculation 1095-56, Rev. 0, "Thermal Analysis of Storage Cases with Poison Plates in the Basket" 3.0 Assumptions and Discussion The following approach is used in the determination of maximum pressures: within the canister during storage and transfer conditions:

First, average cavity gas temperaturesare derivedfrom componenttemperatures.

Next, the amouritof helium present within the canister-after the initial backfllling is determined 'via theideal gas law.

T Then, the total'amount of free gaS within'the fuel assemblies, including both fill and fission gases, is calculated.

° Assuming that 100% of fuel rods develop cladding breaches during accident conditions and none: develop breaches during normal and off-normal conditions, the total amount *of gas within. the icanister iS determined,

' Finally, the maximum cavity pressures are determined via-the ideal gas law,

A Form 3,.1-C ale. No.:

1095-20 TRANSNUCLEAR Calculation

}Rev. No.:

cases Consiere Storage Long-Term Normal OperatJng Conditions:

  • 70 OF ambient temperature :

interior HSM module

  • 2' walls Insulated (DSC within.adjacent HSMs)
  • vents open
  • solar heat flux of 82.0 Btu/hr/ft2 Storage Off-Normal Conditions:

103 °F ambient temperature

  • interior HSM module 2' walls insulated (DSC within adjacent HSMs)
  • vents open
  • solar heat flux of 127.0 Btuhr/

Storage Accident Conditions:

a 103 OF ambient temperature

  • interior:HSM module 2' wails Insulated (DSC within adjacent HSMs)
  • vents blocked:for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> blocked vent'conditions result in 100% of, fuel rods developing cladding breaches s Solar heat flux of 127.0 Btulr/ft2 Transfer wI Drop Conditions:

o 103 OF ambient temperature o dropCondition results in 100% of fuel rods developing cladding breaches

  • solar heat flux of 127.0 Btu/hrlft2 Transfer wlo Drop Conditions:

103:'F ambient temperature

  • solar heat flux of 127-0 Btu/hr/f2

A Fonr 3.1-1 Calc. No.:

1095-20 TRANSNUCLEAR Calculation Rev. No.:

1 Page:

4 1 of I 6

3.2 Average

Caviyb Gas Temperatures To determine the average gas temperature, a volume average temperature is calculated as follows. All the elements of the finite element model with the material property of Helium are selected. Since a large volume portion of the fuel assembly is consisted of Helium, the elements with the fuel properties are added to the above group. A volume average temperature is calculated for these selected elements. For an average gas temperature, the mass and volume average temperatures are equal. Theý results are summarized below.

Operating Condition Result File T..as.avp.

(---)

I (9F)

Normal Storage.7-Calc 1095-29, DSC". nc.rth 484 Off-Normal StorageoO Calc 1095-ý30, DSC sum.rth 509 Accident Storagep(7 CaIc 1095-28, DSC acc48.rthl 725 Transfere4 Calc 1095-6, CCBasketrth 621 The average gas temperatures are also calculated for basket with poison plates based on results from references 8 and 9. The average gas temperature forthe baskets with poison plates differs less than 1 OF from the corresponding valuesý in the above table. Therefore the effect of the poison plates in the basket on the gas temperature is insignificant.

3.3 Amount-6of Initial Heliumi Backfill The initial helium fill pressure within the canister is 17.2 +/- 2.5 psia (Reference 7). It is assumed, as per Reference 5, that the initial temperature 0fthe backfill: gas within the canister is 290 OF.

From the backfill pressure and initial backfill gas temperature, the amount of helium backfill gas can be calculated.

n = (PV)/(RT)

P = maximum initial canister fill pressure = 19.7 psia = 1.34 atm V

Canister free volume (loaded) = 295,713 in 171.13 ft3 (Reference 6)

T = initial fill temperature = 290 OF = 750 OR R = universal gas constant = 0.730 atm-ft3/lbmoles-'R nbaa = 0.419 Ibmoles 3.4 Free Gas within Fuel Assemblies

A Form 3.1-1 1 Caic. No.:

1095-20 TRANSNUCLEAR Calculation I

Rev. No.:

I 3.5 Total Amount of, Gases, WithinI Canister The total amount of gas within the canister is equal to the amount of initial helium fill plus any

.free gases within the assemblies that are released.

All free-gases within fuel rods that develop breaches will be released into the canister.

I 3.6 Maximum Pressures Maximum cavity pressures are determined via the ideal gas law:

P = (ntotaiRTgas,avg)/V P = pressure (atm)

V = Free volume =1 71.13 ft3 (ft3)

R = universal gas constant = 0.730 atm-ft3/Ibmoles-9R I

A NUIForm 31r-1 Cale.

No.:-,[

1006-20'

  • _ TRANSNUCLEAR ICalculation ReV. No.

14;0~ S Re'lsand Conclusions*

i ri

.operatin Condition Pressure Pressure

( ).o, (psia)

(psig)

Normal Storage 24.8r 10:0.1 Off-Normal, Storage' 25.5 10.8 Accident Storage 113.2 98.5 1

Transfer w/ Drop 103.2 88.5 Transfer w/o Drop 28.4 13.7 I

Since the average gas temperature differs less than +/-1 OF from the above values for the basket with poison plates, the effect on, the pressure. is insignificant (less than 5xl0"3 psia). Therefore,

,the above. maximum pressures are also valid for the. basket design

ENCLOSURE5 File Listing for 3 DVDs containing LS-DYNA Files for NUH32P+.0204 CD1 Case 1 14x14 elem.k 14x14 node.k 14x14 nodeset.k 14x14_segset.k 32P-ce14x14_IP.d3plot 32P-ce14x14_IP.d3pIotO1 32P-ce14x14_IP.d3pIotO2 32P-ce14x14_IP.d3pIotO3 32P-ce14x14_IP.d3pIotO4 32P-ce14x14_IP.d3pIotO5 32P-ce14x14_IP.d3pIotO6 32P-ce14x14_IP.d3pIotO7 32P-ce14x14_IP.d3piotO8 32P-ce14x14_IP.d3pIotO9 32P-ce14x14_IP.d3pIotlO 32P-ce14x14_IP.d3plotl 1 32P-ce14x14_IP.d3p*ot12 32P-ce14x14_IP.d3pIotl3 32P-ce14x14_IP.d3p1ot14 32P-ce14x14_IP.d3pIot15 32P-ce14x14_IP.d3pIot16 32P-ce14x14_IP.d3pIot17 32P-ce14x14_IP.d3pIot18 32P-cel4xl4_P.el 1937 32P-cel4xl4_lP.k 32P-cel4xl4_ P.o11937 32P-ce14x14_IPout elout glstat matsum messag nodout readme spcforc status.out Case 2 14x14_elem.k 14x14_node.k 14x14_nodeset.k 14x14_segset.k 32P-ce14x14_noIP.d3plot 32P-ce14x14_noIP.d3pIotO0 32P-ce14x14_noIP.d3pIotO2 32P-cel4xl4 noIP.d3plotO3 32P-ce14x14_noIP.d3pIotO4 32P-ce14x14_noIP.d3pIotO5 32P-ce14x14_noIP.d3pIotO6 32P-ce14x14_noIP.d3pIotO7 32P-ce14x14_noIP.d3pIotO8 32P-ce14x14_noIP.d3pIotO9 32P-ce14x14_noIP.d3pIotlO 32P-ce14x14_noIP.d3pIot11 32P-ce14x14_noIP.d3pIot12 32P-ce14x14_no IP.d3plotl3 32P-cel4x14_noIP.d3pIot14 32P-ce14x14_noIP.d3pIot15 32P-ce14x14_noIP.d3pIot16 32P-ce14x14_noIP.d3pIot17 32P-ce14x14_noIP.d3pIot18 32P-cel4xl4_IP.el 1949 32P-cel4xl4 no IP.k 32P-ce14x14_IP.o11949 32P-ce14x14_noIPout elout glstat Ispost matsum messag nodout readme spcforc status.out Case 3 14x14_elem.k 14x14_node.k 14x14_nodeset.k 14x14_segset.k 32P-ce14x14_1.25F1lP.d3plot 32P-ce14x14_1.25FrP.d3ploto0 32P-ce14x14_1.25F1lP.d3pIotO2 32P-cel4xl4_1.25F1lP.d3plot03 32P-ce14x14_1.25F1lP.d3pIot4 32P-ce14x14_1.25F1IP.d3pIot5 32P-ce14x14_1.25F1lP.d3pIot6 32P-ce14x14_1.25F1lP.d3pIotO7 32P-ce14x14_1.25F1lP.d3pIot8 32P-ce14x14_1.25F1lP.d3pIot9 32P-ce14x14_1.25F1lP.d3pIot1O 32P-ce14x14_1.25F IP.d3plot1 I 32P-ce14x14_1.25F1lP.d3pIot12 32P-ce14x14_1.25F.iP.d3pIot13 32P-ce14x14_1.25F1lP.d3pIot14 32P-ce14x14_1.25F1lP.d3pIot15 32P-ce14x14_1.25F1lP.d3pIot16 32P-ce14x14_1.25F1lP.d3pIot17 32P-cel4xl4_1.25FlP.d3plotl8 32P-cel4xl4_1.25FIP.e11959 32P-cel4xl4_1.25FlP.k 32P-cel4xl4_1.25F_ P.ol 1959 32P-ce14x14_1.25F IP.out elout glstat matsum messag nodout readme spcforc status.out Calvert Cliffs Nuclear Power Plant, LLC September 1, 2010

CD2 Case 4 14x14 elem.k 14x14_node.k 14x14_nodeset.k 14x14_segset.k 32P-ce14x14_0.75F_IP.d3plot 32P-cel4x14_0.75F_lP.d3plotOl 32P-ce14x14_0.75F_IP.d3plotO2 32P-ce14x14_0.75FIP.d3pIotO3 32P-ce14x14_0.75FIP.d3pIotO4 32P-ce14x14_0.75FIP.d3pIotO5 32P-ce14xI4_0.75FIP.d3pIotO6 32P-ce14x14_0.75F_IP.d3pIotO7 32P-ce14x14_0.75F_IP.d3pIot8 32P-ce14x14_0.75F_IP.d3pIotO9 32P-ce14x14_0.75F_IP.d3pIot10 32P-cel4xl4_0.75F_lP.d3plotl1 32P-ce14x14_0.75F_IP.d3pIot12 32P-ce14x14_0.75FlP.d3plotl3 32P-ce14x14_0.75FIP.d3pIot14 32P-ce14x14_0.75F_IP.d3pIot15 32P-ce14x14_0.75F_IP.d3pIot16 32P-ce14x14_0.75FIP.d3pIot17 32P-ce14x14_0.75FlP.d3plot18 32P-ce14x14_0.75FIP.k 32P-ce14x14_0.75FlPout elout glstat matsum messag nodout readme spcforc status.out Case 5 Case 6 14x14_elem.k 14x14 node.k 14x14_nodeset.k 14xl4_segset.k 32P-ce14xl4_1.25K_1P.d3plot.

32P-ce14x14_1.25KIP.d3pIotO1 32P-ce14x14_1.25KIP.d3piotO2 32P-ce14x14_1.25KIP.d3pIot3 32P-ce14x14_1.25KIP.d3pIot4 32P-ce14x14_1.25KIP.d3pIotO5 32P-ce14x14_1.25KIP.d3pIotO6 32P-ce14x14_1.25KIP.d3pIot7 32P-ce14x14_1.25KIP.d3pIotO8 32P-ce14x14_1.25KIP.d3pIot9 32P-ce14x14_1.25KIP.d3pIot10 32P-ce14xl4_1.25KIP.d3pIotl 1 32P-cel4xl4_1.25KiP.d3plot12 32P-ce14x14_1.25KIP.d3pIotI3 32P-ce14x14_1.25KIP.d3pIot14 32P-ce14x14_1.25KIP.d3pIot15 32P-ce14x14_1.25KIP.d3pIot16 32P-ce14x14_1.25KIP.d3pIot17 32P-ce14x14_1.25KIP.d3pIot18 32P-ce14x14_1.25KIP.k 32P-ce14x14_1.25K_, IPout elout glstat matsum messag nodout readme spcforc status.out 14x14_elem.k 14x14 node.k 14x14_nodeset.k 14x14_segset.k 32P-ce14x14_0.75KlP.d3plot 32P-ce14x14_0.75K1lP.d3pIotO1 32P-ce14x14_0.75K1lP.d3pIot2 32P-ce14x14_0.75KIP.d3pIotO3 32P-ce14x14_0.75K1lP.d3pIot4 32P-ce14x14_0.75K-iP.d3pIot5 32P-ce14x14_0.75K1lP.d3pIot6 32P-ce14x14_0.75K1lP.d3pIot7 32P-ce14x14_0.75KIP.d3pIotO8 32P-ce14x14_0.75K1lP.d3pIot9 32P-ce14x14_0.75K1lP.d3pIot10 32P-ce14x14_0.75K1lP.d3plotl 1 32P-cel4xl4_0.75K1lP.d3plot12 32P-ce14x14_0.75K1lP.d3pIot13 32P-ce14x14_0.75K1lP.d3pIot14 32P-ce14x14_0.75K-IP.d3pIot15 32P-ce14x14_0.75K1lP.d3pIot16 32P-ce14x14_0.75K1lP.d3pIot17 32P-ce14xl4_0.75K1lP.d3pIot18 32P-cel4xl4_0.75KIP.k 32P-ce14x14_0.75KlP.out eccp-dyna-job elout glstat matsum messag nodout readme spcforc status.out Calvert Cliffs Nuclear Power Plant, LLC September 1, 2010

CD3 Final 14x14 elem.k 14x14 node.k 14x14_nodeset.k 14x1 4segset. k 32P-cel4x14_1P.d3plot 32P-cel4x14_lP.d3plotOl 32P-ce14x14_IP.d3plotO2 32P-cel4x14_1P.d3plot03 32P-cel4x14_lP.d3plotO4 32P-cel4x14_lP.d3plotO5 32P-cel4x14_lP.d3plotO6 32P-cel4x14_lP.d3plotO7 32P-ce14x14_1P.d3plotO8 32P-cel4x14_1P.d3plotO9 32P-cel4x14_lP.d3plotl0 32P-ce14x14_lP.d3plotl 1 32P-ce14x14_1P.d3plot12 32P-ce14x14_IP.d3plot13 32P-ce14x14_1P.d3plot14 32P-ce14x14_lP.d3plot15 32P-ce14x14_lP.d3plot16 32P-ce14x14_lP.d3plot17 32P-ce14x14_1P.d3plot18 32P-ce14x14_lP.d3plot19 32P-ce14x14_1P.d3plot2O 32P-ce14x14_lP.d3plot21 32P-ce14x14_lP.d3plot22 32P-ce14x14_lP.d3plot23 32P-ce14x14_lP.d3plot24 32P-ce14x14_IP.d3plot25 32P-ce14x14_IP.d3plot26 32P-ce14x14_1P.d3plot27 32P-ce14x14_1P.d3plot28 32P-ce14x14_IP.d3plot29 32P-ce14x14_lP.d3plot3O 32P-ce14x14_lP.d3plot31 32P-ce14x14_1P.d3plot32 32P-cel4xl4_lP.k 32P-ce14x14_1P.out elout glstat matsum messag nodout readme spcforc status.out Calvert Cliffs Nuclear Power Plant, LLC September 1, 2010

ATTACHMENT (2)

PROPRIETARY AFFIDAVITS FOR CALCULATIONS 972-179, REVISION 0, 1095-20, REVISION 1, AND NUH32P+.02402, REVISION 1 Calvert Cliffs Nuclear Power Plant, LLC September 1, 2010

AFFIDAVIT PURSUANT TO 10 CFR 2.390 Transnuclear, Inc.

)

State of Maryland

)

SS.

County of Howard

)

I, Jayant Bondre, depose and say that I am a Vice President of Transnuclear, Inc., duly authorized to execute this affidavit, and have reviewed or caused to have reviewed the information which is identified as proprietary and referenced in the paragraph immediately below. I am submitting this affidavit in conformance with the provisions of 10 CFR 2.390 of the Commission's regulations for withholding this information.

The information for which proprietary treatment is sought is listed below:

1. Transnuclear, Inc. Calculation No. 972-179, "TN-68 High Burnup Cladding Mechanical Properties," Revision 0.
2.

Transnuclear, Inc. Calculation No. 1095-20, Maximum Operating Pressure, Storage and Transfer", Revision 1.

These documents have been appropriately designated as proprietary.

I have personal knowledge of the criteria and procedures utilized by Transnuclear, Inc. in designating information as a trade secret, privileged or as confidential commercial or financial information.

Pursuant to the provisions of paragraph (b) (4) of Section 2.390 of the Cohmmission's regulations, the following is furnished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure, included in the above referenced document, should be withheld.

1)

The information sought to be withheld from public disclosure are portions of certain TN-40HT spent fuel storage cask design drawings and analyses which are owned and have been held in confidence by Transnuclear, Inc.

2)

The information is of a type customarily held in confidence by Transnuclear, Inc. and not customarily disclosed to the public. Transnuclear, Inc. has a rational basis for determining the types of information customarily held in confidence by it.

3)

Public disclosure of the information is likely to cause substantial harm to the competitive position of Transnuclear, Inc. because the information consists of descriptions of the design and analysis of dry spent fuel storage systems, the application of which provide a competitive economic advantage. The availability of such information to competitors would enable them to modify their product to better compete with Transnuclear, Inc., take marketing or other actions to improve their product's position or impair the position of Transnuclear, Inc.'s product, and avoid developing similar data and analyses in support of their processes, methods or apparatus.

Further the deponent sayeth not.

Page 1 of 2

Jayant Bondre Vice President, Transnuclear, Inc.

me before this 30t0" day of July, 2010.

0 *

. Z~

5: AV z r v/

(

Page 2 of 2

AFFIDAVIT PURSUANT TO 10 CFR 2.390 Transnuclear, Inc.

)

State of Maryland

)

SS.

County of Howard

)

I, Jayant Bondre, depose and say that I am a Vice President of Transnuclear, Inc., duly authorized to execute this affidavit, and have reviewed or caused to have reviewed the information which is identified as proprietary and referenced in the paragraph immediately below. I am submitting this affidavit in conformance with the provisions of 10 CFR 2.390 of the Commission's regulations for withholding this information.

The information for which proprietary treatment is sought is listed below:

1. Transnuclear, Inc. Calculation NUH32P+.0204, "Fuel End Drop Analysis for NUH32P+ Using LSDYNA", Revision 1, dated August 25, 2010.

This document has been appropriately designated as proprietary.

I have personal knowledge of the criteria and procedures utilized by Transnuclear, Inc. in designating information as a trade secret, privileged or as confidential commercial or financial information.

Pursuant to the provisions of paragraph (b) (4) of Section 2.390 of the Commission's regulations, the following is furnished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure, included in the above referenced document, should be withheld.

1)

The information sought to be withheld from public disclosure are portions of the structural analysis of a spent fuel storage dry shielded canister design during fuel end drop, which is owned and has been held in confidence by Transnuclear, Inc.

2)

The information is of a type customarily held in confidence by Transnuclear, Inc. and not customarily disclosed to the public. Transnuclear, Inc. has a rational basis for determining the types of information customarily held in confidence by it.

3)

Public disclosure of the information is likely to cause substantial harm to the competitive position of Transnuclear, Inc. because the information consists of descriptions of the design and analysis of dry spent fuel storage systems, the application of which provide a competitive economic advantage. The availability of such information to competitors would enable them to modify their product to better compete with Transnuclear, Inc., take marketing or other actions to improve their product's position or impair the position of Transnuclear, Inc.'s product, and avoid developing similar data and analyses in support of their processes, methods or apparatus.

Page 1 of 2

Further the deponent sayeth not.

Jayant Bondre Vice President, Transnuclear, Inc.

Subscribed and sworn to before this 2 5th day of August, 2010.

My Commission Expires 10 / i4 /1Dj9,w Page 2 of 2

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