ML14352A190
| ML14352A190 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 12/18/2014 |
| From: | Gullott D Exelon Generation Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| 7491-318563-HAO-1, Rev. 2 | |
| Download: ML14352A190 (39) | |
Text
ATTACHMENT 3 LaSalle Requested Documents (NON-PROPRIETARY) 34 pages follow
ENCLOSURE 2 7491-318563-F1A0-1 R2 LaSalle Requested Documents Non-Proprietary Information - Class I (Public)
NON-PROPRIETARY NOTICE This is a non-proprietary version of Enclosure 1 of 7491-318563-HAO-1 R2 which has the proprietary information removed. Portions of the document that have been removed are indicated by an open and closed bracket as shown here ((
7491-318563 IA0-1 R2 Non-Proprietary Information - Class I (Public) Page I of 33 GE Hitachi Nuclear Energy HITACHI Kevin E. Baucom Project Manager Asset Enhancement Services 3901 Castle Flayne Road Wilmington, NC 28401 USA GEH-LCGS-EPU-262 T 910-819-4789 April 18, 2012 V910-547-8158 eDRF 0000-0113-9242 kevin.baucom@ge.com To: Dale Spencer (Exelon Nuclear)
From: Kevin Baucom
Subject:
Response to DIR for 10608
Reference:
- 1. Exelon Generation Co. LLC, Contract Agreement No. 00451634, Release No. 00002 (NSSS ENG SERVICES FOR EPU LS UNITS 1 & 2),
Executed June 21, 2010.
Dear Dale,
In accordance with Reference 1, this letter provides the input requested to support the T0608 UHS evaluation. Three items were requested of GEH.
- Provide confirmation that the Decay Heat Table from Table 7.1 (Design Input 4.1) of L-002453 is still acceptable for EPU.
- Provide confirmation that the Fuel Pool Heat Load from Design Input 4.6 of L-002453 is still acceptable for EPU.
- Provide confirmation that the Sensible Energy Data from Table 7.4 (Design Input 4.7) of L-002453 is still acceptable for EPU.
The first two items are addressed by the attached document which provides updated data for the decay heat and fuel pool heat. This document has been verified in accordance with GEH requirements and evidence of the verification is contained in GEH DRF section 0000-0146-7978.
For the third item, GEH has qualitatively reviewed L-002453, as well as the supporting GEH documentation. EPU does not affect the component mass of steel and water utilized in the referenced document. However, the OPL-4A data provided by Exelon is marginally different than the configuration described in L-002453. The OPL does include items, such as RCIC and HPCS piping, which were not considered in L-002453. Additionally, there is a difference in the mass of the RPV. This difference is due to the RPV and fuel reported as a combined value in L-002453, whereas these were separated in the EPU version of the OPL-4A. It is the opinion of GEH that these items, for the purpose of evaluating the UHS, are representative.
Accordingly, GEH considers it reasonable to conclude that L-002453 remains valid for EPU to evaluate the UHS. On balance, L-002453 would be expected to present a bounding sensible heat summary for EPU operation. Please note this GEH conclusion IS NOT based on a VERIFIED evaluation.
7491-318563-HAG-1 R2 Non-Proprietary Information - Class I (Public) Page 2 of 33 GEH-LCGS-EPU-262 April 18, 2012 Regards We Kevin Baucom xocer,v___
Attachment:
Decay Heat Data Decay Heat Data 0000-0146-7979-R0.1 cc Faramorz Pournia (Exelon) Bruce Hagemeier *EH)
John Morrison (Exelon) Don Hartsock (GEN Vikrom Shah (Escleonl William McDonald (Exelon)
Mike Peters (ExeIon)
7491-318563-1-IA0- I R2 Non-Proprietary Information - Class I (Public)
Enclosure 2 Page 3 of 33 GE Hitachi Nuclear Energy 0000-0146-7979-RO
Title:
LaSalle EPU Unified T0414 &I-0616 Decay Heat Report Originator: P. Guinn i NACOE DRF: 0000-0146-7978 Verified Final L GEH/GNF - Class I (Public) Date: April 2012 Sheet 1 of 14
1.0 INTRODUCTION
The purpose of this report is to document the core and spent fuel pool (SFP) heat loads calculated for Extended Power Uprate (EPU) operation at LaSalle County Station (LSCS).
2.0 CORE DECAY HEAT 2.1 Inputs and Assumptions A generic decay core heat table was previously developed based on the ANSI/ANS-5.1-1979 Standard to bound the core decay heat of most BWR plants, while also incorporating the recommendations of SIL636 in the decay heat evaluations [1,21. For evaluation of core decay heat for EPU condition at LaSalle, the LaSalle EPU equilibrium core parameters were compared to the parameters used for the generic decay heat evaluation, confirming the bounding nature of the latter and justifying the applicability of the generic decay heat table to the LaSalle EPU.
For purposes of establishing the basis for the calculated core decay heat values of Table 2, and to confirm the equivalence of these values to any values of comparison evaluated by downstream tasks, the pertinent inputs used in generating Table 2 are listed in Table 1.
Table 1 - Generic Core Decay Heat Evaluation Input Parameters Fuel Type R Bundle Average Enrichment EOC Core Average Exposure Irradiation time 11 L Decay Heat Standard ANSI/ANS-5.1-1979
7491-318563-HAO-1 R2 Non-Proprietary Information - Class I (Public) Page 4 of 33 GE Hitachi Nuclear Energy 0000-0146-7979-RO
Title:
LaSalle EPU Unified T0414 &T0616 Decay Heat Report Originator: P. Guinn NACOE DRF: 0000-0146-7978 Verified Final GEI-I/GNF - Class I (Public) Date: April 2012 Sheet 2 of 14 2.2 Results The generic core decay heat table based on bounding parameters is documented in Table 2. The first column in the table is the shutdown or cooling time. The second column shows the unadjusted decay heat for the given cooling time, while the third column shows its corresponding one-sigma uncertainty. In the fourth column is the shutdown power plus the two-sigma uncertainty, and the fifth column is the integral of the decay heat (including the two sigma uncertainty). The trapezoidal rule of integration was used, thus producing a conservative, upper bound on the integral.
Cautions with Regard to Use of Table 2
- 1. The table represents the relative decay heat for a full core at End-Of-Cycle. It is not applicable to a discharged batch of fuel.
- 2. The fission power included in the table is directly applicable to Large-Break Loss of Coolant Accidents (LOCAs), which have large and immediate negative void feedback. Application to other events requires justification.
- 3. The shutdown power fraction including two a (column 5) does not include the uncertainty in the reactor power level. In most cases, this means that a factor of 1.02 must be applied to the reactor power level, consistent with NRC Regulatory Guide 1.49.
- 4. Heat from Metal-Water reactions during severe accidents, if any, must be included by the User.
- 5. Sensible heat stored in the fuel and structure must be included by the User, if appropriate.
7491-318563-11A0-1 R2 Non-Proprietary Information - Class I (Public) Page 5 of 33 GE Hitachi Nuclear Energy 0000-0146-7979-RO
Title:
LaSalle EPU Unified 10414 &T0616 Decay Heat Report Originator: P. Guinn NACOE DRF: 0000-0146-7978 Verified Final GEH/GNF - Class I (Public) Date: April 2012 Sheet 3 of 14 Table 2 - Relative Shutdown Power for LaSalle EPU Decay Heat Standard: ANSI/ANS-5.1-1979 Uncertainty: 2 Irradiation Time: I1 I]
Exposure:
Enrichment: (( 1]
Shutdown Total Unc. Shutdown Integrated Time Shutdown lsig Power Shutdown (sec) Power +2a Power
((
7491-318563-1-IA0-1 R2 Non-Proprietary Information - Class I (Public) Page 6 of 33 GE Hitachi Nuclear Energy 0000-0146-7979-RO 1
Title:
LaSalle EPU Unified 10414 &T0616 Decay Heat Report Originator: P. Guinn NACOE ORE: 0000-0146-7978 Verified Final GEH/GNF - Class I (Public) Date: April 2012 Sheet 4 of 14 Shutdown Total Unc. Shutdown Integrated Time Shutdown lsig Power Shutdown Isec) Power MI +2o Power IF
7491-318563-FIA0-1 R2 Non-Proprietary Information - Class I (Public) Page 7 of 33 GE Hitachi Nuclear Energy 0000-0146-7979-RO
Title:
LaSalle EPU Unified T0414 &T0616 Decay Heat Report Originator: P. Guinn NACOE DRF: 0000-0146-7978 Verified Final GEI-I/GNF - Class I (Public) Date: April 2012 Sheet 5 of 14 Shutdown Total Unc. Shutdown Integrated Time Shutdown lsig Power Shutdown (sec) Power (%) +2a Power If 11
7491-31 8563- FIAO-1 R2 Non-Proprietary Information - Class I (Public) Page 8 of 33 GE Hitachi Nuclear Energy 0000-0146-7979-RO
Title:
LaSalle EPU Unified T0414 &I-0616 Decay Heat Report Originator: P. Guinn NACOE DRF: 0000-0146-7978 Verified Final GEFI/GNF - Class I (Public) Date: April 2012 Sheet 6 of 14 3.0 SPENT FUEL POOL DECAY HEAT 3.1 Inputs and Assumptions For purposes of establishing the basis for the calculated SFP decay heat values of Tables 4-6, and to confirm the equivalence of these values to any values of comparison evaluated by downstream tasks, the pertinent inputs used in generating Tables 4-6 are listed in Table 3.
Table 3 - EPU Equilibrium Cycle Parameters Fuel Type GNF2 Bundle Average Enrichment 11 Cycle Exposure 11 Core Size 764 assemblies 11 11 Core Power 4067MWt (102% EPU Power) 11 11 Decay Heat Standard ANSI/ANS-5.1-1979 The 102% EPU power was used as the core power input, as this input was only used in the determination of average bundle power. ((
1] Table 5 presents the abnormal maximum pool heat load assuming ((
11 Table 6 presents the abnormal maximum pool heat load assuming (( 11.
3.1.1 Spent Fuel Pool Capacity
((
7491-318563-1-1A0-1 R2 Non-Proprietary Information - Class 1 (Public) Page 9 of 33 GE Hitachi Nuclear Energy 0000-0146-7979-RO
Title:
LaSalle EPU Unified T0414 &T0616 Decay Heat Report Originator: P. Guinn NACOE ORE: 0000-0146-7978 Verified Final GEI-I/GNF - Class I (Public) Date: April 2012 Sheet 7 of 14 3.1.2 Fuel Cooling Time The normal and abnormal maximum fuel pool heat loads at various time steps are provided in Tables 4-6 to support fuel pool cooling calculations. Because the LaSalle Updated Final Safety Analysis Report (UFSAR) SFP decay heat load analysis assumes an offload rate of 15 spent fuel assemblies per hour, ((
1]
3.1.3 Fuel Pool Load Accounting LE 4.0 RESULTS Table 4 presents the normal maximum pool heat load for times provided in the ANS Standard. The first column in the table is the shutdown or cooling time, where time zero relates to the time the reactor is shutdown for the Cycle N discharge. The second column defines the total decay heat load in the pool from all previous cycles in MWt. The third column defines the decay heat load from the discharge batch that will just fill the spent fuel pool in MWt. The fourth column presents the total decay heat load in the spent fuel pool from all previous cycles and the fully offloaded Cycle N batch.
The fifth column provides the same information as column four in MBtu/hr.
Table 4 - Normal Maximum Heat Load Time Decay Heat Cycle "N" Total Decay Total Decay After Load In pool from Discharge Batch Heat Heat Shutdown All Previous Cycles Decay Heat Load Load in SFP Load in SFP (seconds) (MWt) (MWt) (MWt) IMBtu/hr)
[i ll
7491-318563-11A0-1 R2 Non-Proprietary Information - Class I (Public) Page 10 of 33 GE Hitachi Nuclear Energy 0000-0146-7979-RO 1
Title:
LaSalle EPU Unified T0414 &T0616 Decay Heat Report T Originator: P. Guinn NACOE I DRF: 0000-0146-7978 Verified Final GEH/GNF - Class I (Public) I Date: April 2012 Sheet 8 of 14 Time Decay Heat Cycle "N" Total Decay Total Decay After Load In pool from Discharge Batch Heat Heat Shutdown All Previous Cycles Decay Heat Load Load in SFP Load in SFP (seconds) (MWt) (MWt) (lv1Wt) Btu/hr)
((
11
7491-318563-HAO-1 R2 Non-Proprietary Information - Class I (Public) Page 11 of 33 GE Hitachi Nuclear Energy 0000-0146-7979-RO
Title:
LaSalle EPU Unified T0414 &I-0616 Decay Heat Report Originator: P. Guinn NACOE DRF: 0000-0146-7978 Verified Final GEI-1/GNF - Class I (Public) Date: April 2012 Sheet 9 of 14 Time Decay Heat Cycle "N" Total Decay Tata' Decay After Load In pool from Discharge Batch Heat Heat Shutdown All Previous Cycles Decay Heat Load Load in SFP Load in SFP (seconds) (MWt1 (NIWt) (MWt) (MBtuihr)
[I.
))
Table 5 presents the abnormal maximum pool heat load for times provided in the ANS Standard.
((
fine first column in the table is the shutdown or cooling time, where time zero relates to
7491-318563-HAO-1 R2 Non-Proprietary Information - Class I (Public) Page 12 of 33 GE Hitachi Nuclear Energy 0000-0146-7979-RO
Title:
LaSalle EPU Unified T0414 ELT0616 Decay Heat Report Originator: P. Guinn NACOE DRF: 0000-0146-7978 Verified I Final GEH/GNF - Class I (Public) Date: April 2012 Sheet 10 of 14 the time the reactor is shutdown for the emergency offload. The second column defines the total decay heat load in the pool from all previous cycles in MWt. The third column defines the decay heat load from the emergency offload that will just fill the spent fuel pool in MWt. The fourth column presents the total decay heat load in the spent fuel pool from all previous cycles and the fully offloaded core. The fifth column provides the same information as column four in MBtu/hr.
Table 5 - Abnormal Maximum Heat Load - (( 11 Emergency Time Decay Heat Core Offload Total Decay Total Decay After Load In pool from Decay Heat H eat Heat Shutdown All Previous Cycles Load Load in SFP Load in SFP (seconds) (MWt) (MWt) (MWt) (MBtuihr)
((
))
7491-318563-HAO-1 R2 Non-Proprietary Information - Class I (Public) Page 13 of 33 GE Hitachi Nuclear Energy 0000-0146-7979-RO
Title:
LaSalle EPU Unified T0414 &T0616 Decay Heat Report Originator: P. Guinn NACOE DRF: 0000-0146-7978 Verified Final GEI-1/GNF - Class I (Public) Date: April 2012 Sheet 11 of 14 Emergency Time Decay Heat Core Offload Total Decay Total Decay After Load In pool from Decay Heat H eat Heat Shutdown All Previous Cycles Load Load in SFP Load in SFP (seconds) (MWt) (MWt) (MWt) (MBtuihr)
((
7491-318563-HAO-1 R2 Non-Proprietary Information - Class I (Public) Page 14 of 33 GE Hitachi Nuclear Energy 0000-0146-7979-RO
Title:
LaSalle EPU Unified T0414 &T0616 Decay Heat Report Originator: P. Guinn NACOE DRF: 0000-0146-7978 Verified Final GEH/GNF - Class I (Public) Date: April 2012 Sheet 12 of 14 Emergency Time Decay Heat Core Offload Total Decay Total Decay After Load In pool from Decay Heat Heat Heat Shutdown All Previous Cycles Load Load in SFP Load in SFP (seconds) (MWt) (MWt) (MWt) (MBtuihr)
((
[I Table 6 presents the abnormal maximum pool heat load for times provided in the ANS Standard.
[1 1] Information provided in Table 6 is similar in format to that which was provided in Table 5.
Table 6 - Abnormal Maximum Heat Load - 36 EFPD Operation Prior to Full Offload Emergency Time Decay Heat Core Offload Total Decay Total Decay After Load In pool from Decay Heat Heat Heat Shutdown All Previous Cycles Load Load in SFP Load in SFP (seconds) (MWt) (MWt) (MWt) (MBtu/hr)
IL 11
7491-318563-HAO-1 R2 Non-Proprietary Information - Class I (Public) Page 15 of 33 GE Hitachi Nuclear Energy 0000-0146-7979-RO
Title:
LaSalle EPU Unified T0414 &10616 Decay Heat Report Originator: P. Guinn NACOE DRF: 0000-0146-7978 Verified I Final I GEI-1/GNF - Class I (Public) Date: April 2012 Sheet 13 of 14 Emergency Time Decay Heat Core Offload Total Decay Total Decay After Load In pool from Decay Heat Heat Heat Shutdown All Previous Cycles Load Load in SFP Load in SFP (seconds) (MWt) (MWt) (MWt) IM Btu/hr)
E[
7491-318563-I-IA0-1 R2 Non-Proprietary Inthrmation - Class I (Public) Page 16 of 33 GE Hitachi Nuclear Energy 0000-0146-7979-RO
Title:
LaSalle EPU Unified 10414 & T0616 Decay Heat Report Originator: P. Guinn NACOE DRF: 0000-0146-7978 Verified 1 Final GEH/GNF - Class I (Public) Date: April 2012 Sheet 14 of 14 Emergency Time Decay Heat Core Offload Total Decay Total Decay After Load In pool from Decay Heat Heat Heat Shutdown All Previous Cycles Load Load in SFP Load in SFP (seconds) (MWt) (MWt) (MWt) IM Btu/hr) 11 Jl
5.0 REFERENCES
- 1. "American National Standard for Decay Heat Power in Light Water Reactors", ANSI/ANS-5.1-1979.
.7491-318563-HAO-1 R2 Non-Proprietary Information - Class I (Public)
Eno4osure 2
- Page 17 of 33 GE Nuclear Energy Graserareacarc COMany f 7S Colter Avenue. San Jose CA 95, n February 18, 1999 Action Requested by: N/A GE-LPUP-024 Response to: N/A DRF A13-00384-00 Project Deliverable: Yes cc: C. Mowry (GE)
M. Shepherd (GE)
C. Dinh (GE)
J. Lesiuk (GE)
To: Mr. Dave Rogowski LaSalle County Station 2601 N. 21' Road Marseilles, IL 61341 From: E.G. Thacker (GE)
Author: F.T. Bolger (GE)
Subject:
LaSalle I and 2 Heat Balances at 105% Uprated Power
References:
Drafi Report, "105% Core Thermal Power Uprate Turbine - Generator Engineering Study LaSalle Station Unit No. 2 - S/N 170X579, August 1998 Per the reference, the heat balance calculations were re-run to incorporate the FW temperatures for 105% uprated power. The table below summarizes the results. The reactor heat balance diagram for the 105% uprate is also attached (Figure 1.). Per the reference letter, notice that this is the final FW temperatures for the uprated conditions.
Revised ' ,at Balance Parameter Summary Current Power 105!. , wer 3323 c'i. hated Ft 100 Core Flow i Mlb./hr) 108.5
% Rated Flow 100 100 Steam Flow (Mlb./hr) 14.291 15.145 Dome Pressure (psia) 1020 1020 Slop Valve (TSV) Inlet Pressure (psia) 983 977 TSV Inlet Enthalpy (13tuilb ) 1191.6 1191.6 TSV Inlet Motsrure (%) 030 0.34 Feedwater Flow (Mlb Ihr) 34.266 15.113 Feedwater Temperature (T) 420.0 426.5 Core Inlet Enthalpy (13tu/lbj 527.7 527.5 Dome to TSV Pressure Droptpsia) 38 43
- -7491-318563-HAO-1 R2 Non-Proprietary Information - Class 1 (Public)
Enclosure 2. Page 18 of 33 LaSalle I and 2 Heat Balances at 105% Upratcd Power GE-LPUP-024 DRF A13-00384-00 February 18, 1999 Page 2 Legend N Flow, Ibrahr 1020 Enthalpy, Bru/Ibm F Temperature, F M Moisture. /a Main Steam Flow 15 145E3-06 N
- P = Pressure. psia 1191.6 H 0_34 M
- 977 P
- 3489 Main Feed Flow M WI 35700E'06 0 15..246E+06 A 15.113E+06#
528_5 H 404.7 H 404.7 H 533.5 F Total 426.6 F 426.5 F Core Flow 108.5E+06 4.5h- 1.2 H N 1.330E+05 415 1 H 436.0 F Cleanup Dernineralizer System 3.200E+04 # 1 Control I Rod Drive 1.330E+05 a 48.0 H Feed Flow 5273 H 80.0 F 532.6 F From Condensate Storage Tank
" Conditions at upstream side of TSV Core Thermal Power 3489.0 Pump lleatine 114 Cleanup Losses -4.4 Other System Losses -1.1 Turbine Cycle use 3495.9 MWt Figure 1. NSSS Heat Balance @ 105% Core Thermal Power Uprate
.7491-318563-HAO-1 R2 Non-Proprietary Information - Class I (Public)
Enclosure 2 . Page 19 of 33 LaSalle 1 and 2 Heat Balances at 105% Uprated Power GE-LPUP-024 DRF A13-00384-00 February IS, 1999 Page 3 ComEd and GEPGS need to confirm by 2/26/99 that the result for the 105% uprate case is acceptable.
A signed copy of this letter is included in DRF A13-00384-00. Supporting technical information and evidence of verification for this information are contained in DRF A13-00384-01.
E. G. Thacker 11 Project Manager
7491-3185634-IA0- I R2 /1...r\ ri-Eroprietary Information - Class I (Public)
Enclosure 2 Page 20 o133 sO G °nem. E *clic Company 175 Curtner Avenue. 5cfn .kse CA 95125 June 22, 1999 Action Requested by: N/A GE-LPUP-204 Response to: Request DRF A13-00384-00 Project Deliverable: N/A cc: C. Shaw (GE)
M. Peters (CornEd)
D. Pankratz (GE)
P. Doverspike (GE)
To: Mr. Dale Spencer LaSalle County Station 2601 N. 21" Road Marseilles, IL 61341 From: E.G. Thacker (GE)
Subject:
Response to Request for Sensible Energy Data
Dear Dale:
Attached is a table of verified sensible energy information which was requested to support tasks associated with the ComEd scope of the power uprate for LaSalle.
A signed copy of this letter is included in DRF A13-00384-00. Supporting technical information and evidence of verification for the attached data are contained in DRF A13-00384-02.
E. G. Thacker II Pro.ject Manager, LaSalle Power Upratc Au.
7491-318563-HAO-1 R2 Non-Proprietary Information - Class I (Public)
Enclosure 2 Page 21 of 33 Table 1. Summary of Task 400 Requested Information by S&L UFSAR Table Item No. Requested Input Value 6.2-3 A.4 Mass of reactor coolant system liquid 607,084 lbm*
A.5 Mass of reactor coolant system steam 24,179 lbm A.6 Liquid plus steam energy 362x 106 Btu*
A.7 Vol of water in vessel 11,946 113 A.8 Vol of steam in vessel 8,826 ft3 A.9 Vol of water in recirc. loops 909 ft3 A. I 0 Vol of steam in steamlines 1,494 ft3 A.11 Vol of water in feedwater line 12,906 ft3 A.12 Vol of water in misc. lines 343 ft3 A. 13 Total reactor coolant volume 23,518 ft3 6.2-4 D.1 Primary system steam energy 29 x 106 Btu" D.2 Primary system liquid energy 333 x 106 Btu**
D.3a Reactor vessel sensible energy 106.0 x 106 Btu" D.3b Reactor internals sensible energy 58.5 x 106 Btu" D.3c Primary system piping sensible energy 27.8 x 106 Btu" D.3d Fuel sensible energy 27.7 106 Btu*"
'Does not include liquid in feedwater piping.
- *flased on a 32°F datum.
- Based on a datum of 285°F.
7491-318563-HAO-1 R2 Non-Proprietary Information - Class I (Public) Page 22 of 33
- GE Nuclear Energy General berm Company 175 Curtner Avenue, San Jose. CA 95173 NSA-0l -404, Revision 1 September 4, 2001 Mr. Michael Doromal SUBJECT- Decal Heat Table for LaSalle County Station Power Llorate (Including Contributions from Additional Actinides and Activation Products and a Custom G-factor)
Design Record File: E12-00)41-02 Section 17
References:
- 1. "American National Standard for Decay Heat Power in Light Water Reactors". ANSVANS-
- 5. I -1979.
- 2. GE Nuclear Energy Services Information Letter (S11) Number 636, Revision 1, June 6, 2001.
- 3. Pallotta, A. S., "LaSalle Generic 24 Month Parameters for Containment Analysis Decay Heat Generation", Nuclear Design Information Transmittal, NFM9900058, March 26, 1999.
- 4. Martin, C. L., "Decay Heat Table for LaSalle County Station", letter to J. Rhee, March 29, 1999.
- 5. Martin, C. L.. "Parameters for Decay Heat Evaluations", GE-NE-El 200141-01R2, Class III, May 2000.
- 6. Croff, A. G., "A User's Manual for the ORIGEN2 Computer Code," ORN1JTM-7175, July 1980.
A new decay heat table has been generated for LaSalle County Station based upon the ANSI/ANS-5.1-1979 standard (Reference 1) with an added conservatism corresponding to two sigma uncertainty. This new table was prepared with an allowance for miscellaneous Actinides and Activation Products consistent with the recommendations of SIL 636 (Reference 2). It also includes a custom G-factor evaluation (adjustment for the neutron capture effect). The fuel cycle assumptions which were obtained from Reference 3 are as follows:
Fuel Type: ((
Bundle Average Enrichment:
EOC Core Average Exposure:
Core Average Time at Power:
i]
(These are the same parameters previously used in Reference 4.)
7491-318563-HAO-1 R2 Non-Proprietary Information - Class I (Public) Page 23 of 33 According to Reference 3, the enrichment for future reload batches is expected to be within the range of(( ))enrichment. However, in the near ten-n, the core average enrichment will be lower(( Efor LaSalle 2 and(( ))for LaSalle 1). Therefore. the enrichment was chosen reasonably to be(( ))the average of these two figures. In general, lower enrichment is more conservative than higher enrichment. However, differences of one quarter of one percent are not significant.
The new decay heat table is also applicable to other fuel product lines, including those of other fuel manufacturers, which have the same general configuration.
Using the information in the table above, the inputs for the decay heat standard were obtained from Reference 5. The procedure used in Reference 5 was to perform a lattice evaluation with the production lattice physics code, TGBLA04. The lattice chosen was a typical GE1 2 design with an average enrichment of(( ))According to the recommended procedure in Reference 5, linear interpolation of the constants was performed between the two closest exposure points
}]The following is the list of the parameters determined in this
[Em anner:
((
ii Fissions in materials other than Pu239 and U238 are included with U2" as required by the standard.
The decay heat tables of Reference I represent the heat produced from an ideal situation in which the fission products are allowed to decay in the absence of any competing effect, such as neutron capture. However, in a reactor, the fission products are exposed to a substantial neutron flux, which results in many captures and transmutations of the fission products. The net effect is to produce more decay heat after shutdown. This is known as the Neutron Capture Effect (NCE).
The NCE is formally defined as the additional decay heat which results from the decay of the isotopes produced by neutron capture in fission products, which are exposed to a neutron flux for a finite irradiation period.
The NCE is incorporated into the decay heat standard through a parameter called the G-factor, which is the ratio of the decay heat from fission products exposed to a finite neutron flux to the decay heat from fission products in a zero flux environment. Note that the G-factor does not apply to the decay heat contributions from actinides, structural materials or delayed neutron fission.
The G-factor depends on the reactor type, the irradiation history and the neutron flux level and spectrum. For the purpose of the standard, Reference 1, a G-factor table was calculated which was intended to represent in a conservative way, all Light Water Reactors (LWRs). Since this 2
7491-318563-HAO-1 R2 Non-Proprietary Information - Class I (Public) Page 24 of 33 may be overly conservative in some cases, the User of the standard is given the option of calculating and justifying the G-factor.
The G-factor in the standard was calculated for the following specific conditions:
a) Cross section data in ENDF13-1V averaged in a typical LWR spectrum; b) Constant power for(( ]}prior to shutdown:
c) Thermal neutron flux tom =(( ))nicm2-sec (equivalent to a flux of 1014 applied to effective cross sections at 0.0253 eV); epithennal neutron flux 4, Britm2-sec (where 6p, is the total resonance region flux in the range of 0.625 eV to 5.53 x 103 eV);
d) U2" thermal fission.
The neutron fluxes in item c significantly exceed those normally found in BWRs, Therefore, a separate evaluation of the G-factor was made with the well-known computer program ORJGEN2 (Reference 6), The results are shown in Figure 3.
The OR1GEN2 G-factor is smaller than the standard for all cooling times less than(( 11 seconds. Beyond that point, it is approximately 1% larger. In the range of greatest interest, between 104 and 105 seconds, the OR1GEN2 G-factor is smaller by(( ))The differences are attributed mainly to the neutron fluxes, which were approximately a factor of five 1ower than assumed in the standard.
It should be remarked that the G-factor shown in Figure 3 is specific to the fuel product line, enrichment, exposure, irradiation time and power level for the LaSalle County Station Power Uprate, as specified in Reference 3.
The decay heat table based on the parameters above and the custom G-factor is shown in Table 1.
The first column in the table is the shutdown or cooling time. The second column shows the unadjusted decay heat for the given cooling time and the third column the uncertainty. In the fourth column, the decay heat is shown with two sigma of uncertainty added. The final column is the integral of the decay heat (including the two sigma uncertainty) from time zero up to the cooling time. The trapezoidal rule of integration was used, thus producing a conservative, upper bound on the integral.
Table 2 is a comparison between the shutdown power (plus two sigma) for the Power Uprate case and the previous case, which did not have an allowance for miscellaneous Actinides and Activation Products or a custom G-factor. Figure 1 is a plot of the two curves and Figure 2 shows the difference in percent.
The new table shows more decay heat than the old one for most cooling times, but the difference is less than 1% for cooling times up to 3 days. This is regarded as an insignificant difference when compared with one sigma uncertainty.
3
7491-318563-HAO-1 R2 Non-Proprietary Information - Class I (Public) . Page 25 of 33 Applicability of Table Ito Transition Cycles The general practice is to generate a decay heat table for an equilibrium cycle consisting entirely of a single fuel product line. The table is expected to be conservative not only for the equilibrium cycle, but also for the transition cycles which lead up to equilibrium.
The two most significant parameters affecting decay heat are the average irradiation time of the fuel and the average initial enrichment of the fuel. As a rule, longer irradiation times always Tenth in higher decay heat. Higher enrichments in general result in a reduction in decay heat, due principally to the reduced production of Actinides. Fuel product line on the other hand, is not a significant factor in decay heat.
Recognizing these sensitivities, it is the general practice to add a margin to the calculated irradiation time for the equilibrium cycle to ensure that the decay heat calculations are conservative. Also, if a range of enrichments are projected for the equilibrium cycle, a value near the low end of the range is generally chosen, also for the sake of conservatism. Several additional conservatisms are also used, including: ignoring refueling outages, assuming that the capacity factor is 1.0 and performing the calculation at the end of the cycle. Finally, an additional allowance corresponding to two sigma of uncertainty is also applied. Taken altogether, these assumptions and conservatisms are expected to result in a decay heat curve which is conservative for the equilibrium cycle.
Transition cycles, in general, have a lower average enrichment than the equilibrium cycle they are transitioning toward. As a direct result of the lower enrichment, the transition core has either a smaller energy capability or a large proportion of fresh fuel. In either case, the average irradiation time is reduced (relative to the equilibrium cycle) and the net effect is a reduction in decay heat. For these reasons, as well as the other conservatisms mentioned above, it is expected that the decay heat table for the equilibrium cycle is also conservative for transition cycles.
Cautions with Retard to Use of Table I. The table represents the decay heat for a full core at End-Of-Cycle. It is not applicable to a discharged batch of fuel.
- 2. The fission power included in the table is directly applicable to Large-Break LOCAs, which have large, immediate negative void feedback. Application to other events requires justification.
- 3. The shutdown power fraction including two sigma uncertainty (column 4 of Table 1) does not include the uncertainty in the reactor power level. In most cases, this means that a factor of 1.02 must be applied to the reactor power level, consistent with NRC Regulatory Guide 1.49. in some cases, such as when Thermal Power Optimization (TP0) is in place, a smaller factor may be justified.
- 4. Heat from Metal-Water reactions during severe accidents, if any, must be included by the User.
- 5. Sensible heat stored in the fuel and structure must be included by the User, if appropriate.
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7491-318563-}1A0- l R2 Non-Proprietary Information - Class I (Public) Page 26 of 33 Sincerely, Charles L. Manin Nuclear & Safety Analysis Tel: (408)925-6892 Fax: (408)925-1674 E-Mail: chaxles.manin@gene.ge.com 5
7491-318563-HAO-1 R2 Non-Proprietary Information - Class I (Public) Page 27 of 33 Table 1, Shutdown Power for LaSalle County Station Decay Heat Standard: ANSI/ANS-5.1-19-19 Uncertainty: 2 0 Irradiation Time: a 1]
Exposure: [E l]
Enrichment: U 1]
Shutdown Total Unc. Shutdown Integrated Time Shutdown lo Power Fract. Shutdown (sec) Power Fract. (%) +20 Power Fr+20
((
1]
6
7491-318563-HAO-1 R2 Non-Proprietary Information - Class I (Public) Page 28 of 33 Table 1, Shutdown Power for LaSalle County Station (continued)
Decay Heat Standard: ANSI/ANS-5.1-1979 Uncertainty: 2a Irradiation Tirc: ((
Exposure: (( 1]
Enrichment: ((
Shutdown Total Unc. Shutdown Integrated Time Shutdown lo Power Fract. Shutdown (sec) Power Fract. (%) 420 Power Fri-2a
((
7
7491-318563-HAO-1 R2 Non-Proprietary Intbrmation - Class I (Public) Page 29 of 33 Table 2, Shutdown Power Comparison Previous New Previous New Shutdown Shutdown Shutdown Difference Integrated Integrated Difference Time Power Power (%) Shutdown Shutdown (70)
(sec) 4 2sig 4 25i9 Power Power
+2sig 4 2sig
((
.2 rn
° cr)
CI)
CID C/)
- ^-4 Cd a) 0 121-1 0
7491-318563-HAO- 1 R2
7491- 3 18563-HAO-1 R2 ***
7491-318563-HAO-I R2 Figure 3, G-facto r Comparison
ATTACHMENT 4 Affidavit of GEH Supporting Proprietary Nature of Attachment 2 (NON-PROPRIETARY) 4 pages follow
ENCLOSURE 3 7491-318563-HAO-1 R2 Affidavit for Enclosure 1
GE-Hitachi Nuclear Energy Americas LLC AFFIDAVIT I, James F. Harrison, state as follows:
I am the Vice President, Fuel Licensing, Regulatory Affairs, GE-Hitachi Nuclear Energy Americas LLC ("GEH"), and have been delegated the function of reviewing the information described in paragraph (2) which is sought to be withheld, and have been authorized to apply for its withholding.
(2) The information sought to be withheld is contained in Enclosure 1 of GEH letter 7491-318563-HAO-1 R2, "Requested Documents with Revised Marking of GEH Proprietary Information," dated December 4, 2014. The GEH proprietary information in Enclosure 1, which is entitled "LaSalle Requested Documents," is identified by a dotted underline inside double square brackets. ((This sentence is an example.{3})) Figures and large objects containing GEH proprietary information are identified with double square brackets before and after the object. In each case, the superscript notation 131 refers to Paragraph (3) of this affidavit, which provides the basis for the proprietary determination.
(3) In making this application for withholding of proprietary information of which it is the owner or licensee, GEH relies upon the exemption from disclosure set forth in the Freedom of Information Act ("FOIA"), 5 U.S.C. Sec. 552(b)(4), and the Trade Secrets Act, 18 U.S.C.
Sec. 1905, and NRC regulations 10 CFR 9.17(a)(4), and 2.390(a)(4) for trade secrets (Exemption 4). The material for which exemption from disclosure is here sought also qualifies under the narrower definition of trade secret, within the meanings assigned to those terms for purposes of FOIA Exemption 4 in, respectively, Critical Mass Energy Project v. Nuclear Regulatory Commission, 975 F.2d 871 (D.C. Cir. 1992), and Public Citizen Health Research Group v. FDA, 704 F.2d 1280 (D.C. Cir. 1983).
(4) The information sought to be withheld is considered to be proprietary for the reasons set forth in paragraphs (4)a. and (4)b. Some examples of categories of information that fit into the definition of proprietary information are:
- a. Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by GEH's competitors without license from GEH constitutes a competitive economic advantage over other companies;
- b. Information that, if used by a competitor, would reduce their expenditure of resources or improve their competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product;
- c. Information that reveals aspects of past, present, or future GEH customer-funded development plans and programs, resulting in potential products to GEH;
- d. Information that discloses trade secret or potentially patentable subject matter for which it may be desirable to obtain patent protection.
Affidavit for 7491-318563-HAO-1 R2 Page! of 3
GE-Hitachi Nuclear Energy Americas LLC (5) To address 10 CFR 2.390(b)(4), the information sought to be withheld is being submitted to NRC in confidence. The information is of a sort customarily held in confidence by GEH, and is in fact so held. The information sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by GEH, not been disclosed publicly, and not been made available in public sources. All disclosures to third parties, including any required transmittals to the NRC, have been made, or must be made, pursuant to regulatory provisions or proprietary or confidentiality agreements that provide for maintaining the information in confidence. The initial designation of this information as proprietary information, and the subsequent steps taken to prevent its unauthorized disclosure, are as set forth in the following paragraphs (6) and (7).
(6) Initial approval of proprietary treatment of a document is made by the manager of the originating component, who is the person most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge, or who is the person most likely to be subject to the terms under which it was licensed to GEH.
(7) The procedure for approval of external release of such a document typically requires review by the staff manager, project manager, principal scientist, or other equivalent authority for technical content, competitive effect, and determination of the accuracy of the proprietary designation. Disclosures outside GEH are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary or confidentiality agreements.
(8) The information identified in paragraph (2), above, is classified as proprietary because it contains the detailed GEH methodology for decay heat, uprate, and energy data for the GEH Boiling Water Reactor (BVVR). These methods, techniques, and data along with their application to the design were achieved at a significant cost to GEH.
The development of the evaluation processes along with the interpretation and application of the analytical results is derived from the extensive experience databases that constitute a major GEH asset.
(9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to GEH's competitive position and foreclose or reduce the availability of profit-making opportunities. The information is part of GEH's comprehensive BWR safety and technology base, and its commercial value extends beyond the original development cost.
The value of the technology base goes beyond the extensive physical database and analytical methodology and includes development of the expertise to determine and apply the appropriate evaluation process. In addition, the technology base includes the value derived from providing analyses done with NRC-approved methods.
The research, development, engineering, analytical and NRC review costs comprise a substantial investment of time and money by GEH. The precise value of the expertise to devise an evaluation process and apply the correct analytical methodology is difficult to quantify, but it clearly is substantial. GEH's competitive advantage will be lost if its Affidavit for 7491-318563-HAO-1 R2 Page 2 of 3
GE-Hitachi Nuclear Energy Americas LLC competitors are able to use the results of the GEH experience to normalize or verify their own process or if they are able to claim an equivalent understanding by demonstrating that they can arrive at the same or similar conclusions.
The value of this information to GEH would be lost if the information were disclosed to the public. Making such information available to competitors without their having been required to undertake a similar expenditure of resources would unfairly provide competitors with a windfall, and deprive GEH of the opportunity to exercise its competitive advantage to seek an adequate return on its large investment in developing and obtaining these very valuable analytical tools.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on this 4th day of December 2014.
James F. Harrison Vice President, Fuel Licensing, Regulatory Affairs GE-Hitachi Nuclear Energy Americas LLC 3901 Castle Hayne Rd.
Wilmington, NC 28401 James.Harrison@ge.com Affidavit for 7491-318563-HAO-1 R2 Page 3 of 3