IR 05000313/2013013
| ML14017A161 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/17/2014 |
| From: | Spitzberg D Division of Nuclear Materials Safety IV |
| To: | Jeremy G. Browning Entergy Operations |
| Spitzberg D | |
| References | |
| IR-13-013 | |
| Download: ML14017A161 (19) | |
Text
January 17, 2014
SUBJECT:
ARKANSAS NUCLEAR ONE, UNITS 1, 2, AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI) INSPECTION REPORT 05000313/2013013, 05000368/2013013, AND 07200013/2013001
Dear Mr. Browning:
This letter refers to the inspection conducted on December 16 - 18, 2013, of the dry cask storage activities associated with your Independent Spent Fuel Storage Installation (ISFSI). The enclosed inspection report documents the inspection results which were discussed on December 18, 2013 with members of your staff.
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.
The inspection reviewed compliance with the requirements specified in the Technical Specifications associated with Holtec Certificate of Compliance 1014, the Holtec Final Safety Analysis Report (FSAR), and Title 10 of the Code of Federal Regulations (CFR) Part 72, Part 50, and Part 20. Within these areas, the inspection included a review of the construction activities associated with the sites Cask Transfer Facility (CTF), quality assurance, corrective action program, and safety evaluations. No violations of NRC regulations were identified.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response, if you choose to provide one, will be made available electronically for public inspection in the NRC Public Document Room or from the NRC's Agencywide Document Access Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. To the extent possible, your response should not include any personal, privacy, or proprietary information so that it can be made available to the Public without redaction.
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION IV
1600 EAST LAMAR BLVD ARLINGTON, TEXAS 76011-4511 Should you have any questions concerning this inspection, please contact the undersigned at 817-200-1191 or Mr. Lee Brookhart at 817-200-1549.
Sincerely,
/RA/
D. Blair Spitzberg, Ph.D., Chief Repository & Spent Fuel Safety Branch Division of Nuclear Materials Safety
Dockets: 50-313, 50-368, 72-13 Licenses: DPR-51; NPF-6
Enclosure:
Inspection Report 05000313/2013013, 05000368/2013013 and 07200013/2013001
w/attachments:
1. Supplemental Information 2. Casks Loaded at the ANO ISFSI
cc w/attachments:
Listserv
SUMMARY OF FINDINGS
IR 05000313/2013013; 05000368/2013013; and 07200013/2013001; 12/16 - 12/18/2013;
Arkansas Nuclear One, Units 1, 2, and Independent Spent Fuel Storage Installation; Routine ISFSI Inspection Report
The report covers an announced inspection by one regional inspector. No findings or violations associated with U.S. Nuclear Regulatory Commission (NRC) regulations were identified. The significance of any Part 50 findings are indicated by their color (Green, White, Yellow, or Red)using Inspection Manual Chapter (IMC) 0609, Significance Determination Process. The cross-cutting aspect is determined using IMC 0310, Components Within the Cross-Cutting Areas.
Findings for which the significance determination process does not apply may be Green or be assigned a severity level after the NRC management review. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 4, dated December 2006. In accordance with IMC 0612 Power Reactor Inspection Reports, all of the Part 72 ISFSI inspection findings follow the traditional enforcement process and are not dispositioned through the Reactor Oversight Process or the Significance Determination Process.
NRC-Identified Findings and Self-Revealing Findings
No findings were identified.
Licensee-Identified Violations
None.
PLANT AND ISFSI STATUS
Arkansas Nuclear Ones (ANO) Independent Spent Fuel Storage Installation (ISFSI) stored twenty four Energy Solutions Ventilated Storage Cask (VSC) VSC-24 casks that had been loaded from 1996 to 2003. On the north side of the VSC-24 pad, ANO had loaded and stored thirty-seven Holtec casks with room on the pad to store eleven more. For the Holtec casks, two canister designs were used at ANO. The Multi-Purpose Canister (MPC) MPC-24 canister stored a maximum of twenty-four assemblies. The MPC-32 canister stored a maximum of thirty-two assemblies. All Unit 1 spent fuel was stored in the MPC-24 canister. Unit-2 spent fuel was stored in both the MPC-24 and MPC-32 canisters. The licensee used two versions of the Holtec HI-STORM concrete storage cask overpack designs at the ISFSI. The first twelve Holtec casks placed on the ISFSI pad were HI-STORM 100S overpacks (with nine MPC-24 canisters and three MPC-32 canisters). Since then, the HI-STORM 100S Version C overpacks have been used (containing eleven MPC-24 canisters and fourteen MPC-32 canisters).
REPORT DETAILS
OTHER ACTIVITIES
4OA5 Other Activities
.1 Operations of an Independent Spent Fuel Storage Installation at Operating Plants
(60855.1)
a. Inspection Scope
- (1) Cask Transfer Facility Overview
There had been no loading operations performed since the last ISFSI inspection performed in December 2012. ANO had halted loading activities to construct a Cask Transfer Facility (CTF) outside the refueling building. This action was necessitated from an ANO internal review which identified errors in their trainbay floor loading calculations during a seismic event. This issue was previously reviewed by the NRC inspectors and was documented in the last ISFSI inspection report (ML13057A986).
ANO had performed a number of construction activities and purchased a variety of new equipment, since the last NRC ISFSI inspection, to support continued dry cask loading operations utilizing a Cask Transfer Facility. The CTF was classified as a Part 72 Important to Safety (ITS) structure. The CTF will support the stack-up configuration of a fully-loaded HI-TRAC, Mating Device, HI-STORM, and the Vertical Cask Transporter (VCT) during MPC transfer operations from the HI-TRAC into the HI-STORM. The ANO CTF is a passive reinforced concrete structure. The structure is composed of a base slab, four walls, and a top slab. The CTF features a 12-8 x 12-8 by approximately 14 feet deep cavity in the ground for placement of the empty HI-STORM prior to the MPC transfer. Inside of the cavity, four removable Upper Lateral Restraints and four removable Lower Lateral Restraints would be installed in the cavity to horizontally restrain the HI-STORM and assist in energy absorption and transferring loads to the surrounding soil during a seismic event.
The CTF was designed to accommodate both the HI-STORM 100S, Version C, and HI-STORM 100S, which are currently in use at ANO. The CTF was designed to support the combined loads of a fully-loaded HI-STORM 100S, Version C with high density concrete shielding during both placement and retrieval. In addition, the CTF is designed to physically accommodate the potential future use of HI-STORM 100S, Version B and HI-STORM Forced Wind (FW), both using high density concrete shielding.
To support transportation from the refueling building to the CTF, ANO had constructed two passive reinforced concrete turning pads with an embedded rail spur and a new rail heavy haul path that extended from the currently loaded ISFSI pads to the north-end of the ANO site to where the new CTF was located. The new CTF facility with haul path and turning pads will facilitate:
- (1) unloading of the fully-loaded HI-TRAC/MPC from the Holtec Railcar;
- (2) transfer of the fully-loaded HI-TRAC/MPC to the CTF for placement of the MPC within the HI-STORM; and
- (3) transfer of the fully-loaded HI-STORM from the CTF to the ISFSI pad. At the time of the inspection the CTF was outside the existing site Protected Area (PA).
Eventually the PA fence will be extended around the new CTF facility. In the future, ANO plans to build four reinforced concrete storage pads which will provide for 94 storage casks with four temporary storage locations for placement of casks after the current ISFSI pads are filled.
The new equipment that ANO purchased included a new VCT, a low profile transporter, new MPC downloading slings, new HI-STORM slings, and new VCT special lifting device brackets to carry the HI-STORMs.
- (2) Design and Evaluations of the Cask Transfer Facility
The ANO CTF was a reinforced concrete structure with designed minimum concrete compression strength of 4,500 psi at 28 days. All compressive strength test results that were reviewed demonstrated that the concrete compression strength exceeded the design requirement and were found to be greater than 5,000 psi. The CTF Environmental and Design Conditions were contained in the Holtec FSAR Section 2.3.3.1 B. The Design Basis Earthquake (DBE) event applicable to the CTF is in Holtec FSAR Section 2.3.3.1 B.vii and stated that the DBE should be specified as a set of response spectra or acceleration time-histories for use in the CTF structural and impact consequence analyses. Engineering Calculation (CALC)-13-D-2001-14, ANO CTF Seismic/Structural Report, provided a summary of the seismic-structural analyses, which were performed for the stack-up configuration of a fully-loaded HI-TRAC, Mating Device, and HI-STORM during MPC transfer operations from the HI-TRAC to the HI-STORM.
Other analyses were preformed that demonstrated continued compliance to the Holtec FSAR for environmental hazards which included flooding, lightning strike, explosions, fires, tornado winds, and tornado missiles. These analyses were documented in CALC-ANO-CS-13-00004, ANO CTF Hazards Technical Summary Report.
Inspectors reviewed the design of the heavy haul path from the existing ISFSI docking station to the ANO CTF. Engineering Change Report 45253 provided the design of the haul path based on the weight of a fully loaded HI-STORM and the weight of the VCT. Calculation-13-D-2001-12 Structural Evaluation of Haul Path at ANO evaluated the maximum bearing pressure under the concrete tracks, stability of the haul path, including sliding and overturning, and the reinforcement for the concrete tracks. The calculation determined that the maximum calculated bearing pressure of 3,245 psf was less than the allowable designed bearing pressure of 3,500 psf, the calculated factors of safety for sliding was 2.77 and the overturning was 4.91 which exceeded the minimum required factor of safety of 1.5 from NUREG-0800, Section 3.8.5. Also the steel reinforcement sizes, configurations, and lap splices lengths demonstrated compliance with the American Concrete Institute (ACI)-318 and ACI-349 requirements. All concrete compressive strength test results that were reviewed exceed their design requirements.
- (3) Design and Evaluations of the Vertical Cask Transport
Inspectors reviewed documentation that demonstrated that the VCT had been load tested to 125 percent of its rated load. The VCT is rated to lift a maximum of 415,000 lbs. The 125 percent load test lifted slightly more than 518,750 lbs, meeting the requirement. A loaded HI-STORM 100S with high density concrete was documented as weighing 389,025 lbs. The loaded HI-STORM 100S weighs more than the loaded HI-STORM Version C with high density concrete (382,470 lbs).
The reason for the higher load rating was to accommodate the future use of the HI-STORM FW which contains more fuel assemblies than the HI-STORM 100S or HI-STORM Version C.
ANO had performed analyses to demonstrate the structural integrity and kinematic stability of the VCT under dead and seismic loads. These analyses were documented in CALC-ANO-CS-13-00009 Generic VCT Seismic Technical Summary Report and CALC-ANO-CS-13-00007 VCT Technical Summary Report.
The VCT that was purchased by ANO was found to be qualified to perform all operations associated with the loading activities at ANO.
- (4) Special Lifting Devices and Slings
Documentation associated with the newly purchased special lifting devices for the HI-TRAC and HI-STORM were documented in Purchase Specification (PS)-2301-02 Purchase Specification for ANO HI-STORM/HI-TRAC Integrated Lifting Brackets.
The special lifting devices were documented as meeting American National Standard Institute (ANSI) N14.6 requirements as specified by the Holtec FSAR.
Additionally, all special lifting devices were load tested to 300% of the rated load as required by ANSI N14.6. These lift tests were documented in Documentation Package (DP) 13158-001 Lift Brackets for ANO.
The MPC downloader slings and HI-STORM slings that were purchased by ANO were proof load tested to 200 percent of their rated load. These proof load tests were documented in Certificate of Conformance (CoC) 13158-002 Lift Bracket Slings for ANO and CoC 13268-001 MPC Downloader Slings for ANO. The tests were performed in accordance with American Society of Mechanical Engineers (ASME) B.30.9 requirements.
- (5) Corrective Action Program
A list of condition reports issued since the last NRC inspection in December of 2012, was provided by the licensee for ISFSI activities. Of the list of condition reports provided relating to the ISFSI and new CTF construction activities, four condition reports were selected by the NRC inspector for further review. The condition reports reviewed were well documented and properly categorized based on the significance of the issue. The corrective actions taken were appropriate for the situations. No NRC concerns were identified related to the condition reports reviewed.
- (6) Observed Activities and Loading Procedures
During the week of the NRC inspection, ANO was in the process of performing the site acceptance testing of their new VCT. The inspector observed the raising and lowering of a weighted dummy MPC with the sites new downloading slings and the VCT. The VCT raised and lowered the weighted dummy MPC with no issues. ANO had prepared a new loading procedure to address the use of the CTF and VCT.
The NRC inspector reviewed Procedure 3406.005 HI-STORM and HI-Track Transport Operations Using LPT, VCT, and Holtec Rail Car for the use of the new equipment.
b. Findings
No findings were identified.
4OA6 Meetings, Including Exit
Exit Meeting Summary
On December 18, 2013 the inspectors presented the inspection results to Mrs. Stephanie Pyle, and other members of the licensee staff. The licensee acknowledged the inspection details presented. The inspector asked the licensee whether any materials examined during the inspection should be considered proprietary. No proprietary information was identified.
SUPPLEMENTAL INSPECTION INFORMATION KEY POINTS OF CONTACT
Licensee Personnel
D. Bauman, Project Manager B. Clark, Licensing D. Eichenberger, Project Manager M. Estep, Engineering S. Pyle, Regulatory Assurance Manager M. Smith, Project Manager C. Walker, Engineering
INSPECTION PROCEDURES USED
Operations of an ISFSI at Operating Plants IP 60856.1 Review of 10 CFR 72.212(b) Evaluations at Operating Plants IP 60857
Review of 10 CFR 72.48 Evaluations
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Opened
None
Discussed
None
Closed
None LIST OF
DOCUMENTS REVIEWED
The following is a list of documents reviewed during the inspection. Inclusion on this list does
not imply that the NRC inspectors reviewed the documents in their entirety, but rather, that
selected sections of portions of the documents were evaluated as part of the overall inspection
effort. Inclusion of a document on this list does not imply NRC acceptance of the document or
any part of it, unless this is stated in the body of the inspection report.
4OA5.1 Other Activities
Calculations
NUMBER
TITLE
REVISION / DATE
Calc-13-D-2001-12
Structural Evaluation of Haul Path at ANO
Revision 0
Calc-13-D-2001-13
Thermal Evaluation of HI-STORM System in CTF at
Revision 0
Calc-13-D-2001-14
ANO CTF Seismic/Structural Report
Revision 0
Calc-ANOC-CS-13-
00004
ANO CTF Hazards Technical Summary Report
Revision 0
Calc-ANOC-CS-13-
00007
VCT Technical Summary Report
Revision 0
Calc-ANOC-CS-13-
00009
Generic VCT Seismic Technical Summary Report
Revision 0
Calc-ANOC-CS-13-
00005
Revision 0
Procedures
NUMBER
TITLE
REVISION / DATE
3406.005
HI-STORM and HI-Track Transport Operations Using
LPT, VCT, and Holtec Rail Car
Draft
203.052
Dry Fuel Storage Emergencies
Revision 0
3403.005
HI-STORM 100 System Loading Operations
Revision 31D
Design Basis Documents
NUMBER
TITLE
REVISION / DATE
CFR 72.212 Evaluation Report App B ANO Specific
Information for ISFSI Using Holtec HI-STORM
Revision 6
Certificate of Compliance 72-1014 HI-STORM 100
Cask System
Amendment 5
Holtec International Final Safety Analysis Report for
the HI-STORM 100 Cask System
Revision 7
Miscellaneous Documents
NUMBER
TITLE
REVISION / DATE
ANO ISFSI Facility Expansion Civil-Structural Design
Revision 0
- 3 -
Miscellaneous Documents
NUMBER
TITLE
REVISION / DATE
Commercial Fire Hydrant, Outside North SOCA
Fence, Near Truck Access Gate
Revision 0
ANO ISFSI Facility Expansion Utility Interferences
Revision 0
ANO Cask Transfer Facility
Revision 0
ANO ISFSI Facility Expansion Heavy Haul Path
Revision 0
ANO ISFSI Facility Expansion-Electrical Design
Revision 0
CoC 13158-002
Lift Bracket Slings for ANO
Revision 0
DP 13158-001
Lift Brackets for ANO
Revision 0
PS-2301-02
Purchase Specification for ANO HI-STORM/HI-TRAC
Integrated Lifting Bracket
Revision 0
HI-2135644
Structural Evaluation of HI-STORM/HI-TRAC
Integrated Lifting Bracket
Revision 0
CoC 13268-001
Revision 0
PS-2301-01
Purchase Specification for ANO CTF
Revision 0
CoC 13157-001
Revision 0
CoC 13157-002
Revision 0
CoC 13157-003
Revision 0
CoC 13157-004
CTF Components (CTF Cover) for ANO
Revision 0
CoC 13157-005
CTF Components (Wedge Spacer Weldment) for ANO
Revision 0
CoC 13157-006
CTF Components (4 Wedge Assemblies) for ANO
Revision 0
CoC 13157-007
CTF Components (9021-300) for ANO
Revision 0
Concrete Compression Test Results from ARK-CON
Testing Service Inc. for CTF Bottom Slab, Walls, Top
Mat
October 2013
ARK-CON Testing Service Inc. Soil Testing Data
October 2013
PS 2301-03
Purchase Specification for ANO Low Profile
Transporter
Revision 1
DOC-1027-121-424 LPT for ANO
Revision 0
CoC 13308-001
VCT Cask Restraint Straps for ANO
Revision 0
HPP-2301-7
Entergy-ANO Factory Acceptance Test Procedure
Revision 0
HPP-2301-10
VCT415 Site Acceptance Test at ANO
Revision 0
Condition Reports
CR-ANO-C-2013-00575
CR-ANO-C-2013-02482
CR-ANO-C-2013-02484
CR-ANO-C-2013-02977
-4-
LIST OF ACRONYMS
American Concrete Institute
Agencywide Documents Access and Management System
ANSI
American National Standard Institute
Arkansas Nuclear One
American Society of Mechanical Engineers
Calc
Calculation
Certificate of Compliance
Cask Transfer Facility
CFR
Code of Federal Regulations
Division of Nuclear Material Safety
DP
Documentation Package
FHD
Forced Helium Dehydrator
Final Safety Analysis Report
Forced Wind
IMC
Inspection Manual Chapter
IP
Inspection Procedure
Independent Spent Fuel Storage Installation
Important to Safety
kW
kilo-watt
Multi-Purpose Canister
MWd/MTU
megawatt days/metric ton uranium
NRC
U.S. Nuclear Regulatory Commission
Protected Area
PS
Purchase Specification
Uranium 235
Vertical Cask Transporter
VSC
Ventilated Storage Cask
ATTACHMENT 2
VSC-24 CASKS
LOADING
ORDER
VSC
ID No.
Unit
DATE
ON PAD
HEAT LOAD
(kW)
BURNUP
MWd/MTU (max)
MAXIMUM FUEL
ENRICHMENT %
PERSON-REM
DOSE
24-01
Unit 1
2/17/96
5.2
19,905
2.07
0.185
24-03
Unit 1
01/28/97
10.7
2,599
3.19
0.384
24-05
Unit 2
04/02/97
4.2
20,318
1.93
0.291
24-06
Unit 2
04/06/97
6.2
30,149
2.94
0.469
24-12
Unit 2
09/23/98
10.8
34,938
3.38
0.900
24-11
Unit 2
10/01/98
8.0
33,075
2.94
0.553
24-07
Unit 2
10/21/98
8.0
34,891
3.33
0.567
24-02
Unit 2
10/30/98
8.1
34,773
3.34
0.483
24-04
Unit 1
04/13/99
9.1
33,051
3.06
0.236
24-08
Unit 1
04/27/99
9.2
33,255
3.06
0.231
24-09
Unit 1
05/18/99
9.1
33,194
3.21
0.189
24-13
Unit 1
06/16/99
7.3
33,066
3.05
0.112
24-14
Unit 1
07/14/99
10.7
34,646
3.21
0.383
24-10
Unit 2
04/18/00
2.2
40,211
3.37
0.602
- 2 -
LOADING
ORDER
VSC
ID No.
Unit
DATE
ON PAD
HEAT LOAD
(kW)
BURNUP
MWd/MTU (max)
MAXIMUM FUEL
ENRICHMENT %
PERSON-REM
DOSE
24-15
Unit 2
06/06/00
9.86
40,220
3.37
0.603
24-16
Unit 1
07/25/00
13.37
40,180
3.21
0.528
24-18
Unit 1
01/21/01
14.67
38,794
3.45
0.628
24-17
Unit 2
06/06/01
14.23
41,188
4.01
0.695
24-19
Unit 2
06/26/01
14.17
41,193
4.01
0.659
24-20
Unit 2
07/25/01
14.24
41,204
4.01
0.554
24-21
Unit 2
08/14/01
14.26
40,931
4.01
0.666
24-22
Unit 1
08/30/02
14.69
38,909
3.46
0.407
24-23
Unit 1
09/11/02
14.66
38,981
3.46
0.567
24-24
Unit 2
06/12/03
9.36
36,021
3.49
0.296
Unit 1: 11 casks loaded, average heat load = 10.8 kW; average man-hours to load = 1374 hrs; average dose = 0.350 person-rem
Unit 2: 13 casks loaded, average heat load = 10.3 kW; average man-hours to load = 1477 hrs; average dose = 0.564 person-rem
Note: Unit 2 fuel is 18 inches longer than Unit 1 fuel.
VSC-24 Casks # 1 through 14 were loaded to CoC No. 1007, Amendment 0, FSAR Revision 0
VSC-24 Casks # 15 through 16 were loaded to CoC No. 1007, Amendment 1, FSAR Revision 1
VSC-24 Casks # 17 was loaded to CoC No. 1007, Amendment 2, FSAR Revision 1
VSC-24 Casks # 18 through 21 were loaded to CoC No. 1007, Amendment 3, FSAR Revision 2
VSC-24 Casks # 22 and 23 were loaded to CoC No. 1007, Amendment 3, FSAR Revision 4
VSC-24 Casks # 24 was loaded to CoC No. 1007, Amendment 4, FSAR Revision 5
All VSC-24 Casks are being monitored to CoC No. 1007, Amendment 4, FSAR Revision 5
NOTES:
Heat load (kW) is the sum of the heat load values for all spent fuel assemblies in the cask
Burn-up is the value for the spent fuel assembly with the highest individual discharge burn-up
Fuel enrichment is the spent fuel assembly with the highest individual initial enrichment per cent of U-235
- 3 -
LOADED HI-STORMS CASKS
LOADING
ORDER
Serial #
HI-STORM
100S No.
Unit
DATE
ON PAD
HEAT LOAD
(kW)
BURNUP
MWd/MTU (max)
MAXIMUM FUEL
ENRICHMENT %
PERSON-REM
DOSE
Serial No.
24-3
Serial No.
Unit 1
2/13/03
16.4
41,045
3.50
0.525
Serial No.
24-4
Serial No.
Unit 1
01/13/04
16.7
41,130
3.50
0.755
Serial No.
24-2
Serial No.
Unit 1
01/21/04
17.5
41,044
3.50
0.707
Serial No.
24-1
Serial No.
Unit 1
2/15/04
15.5
39,807
3.50
0.667
Serial No.
24-5
Serial No.
Unit 1
2/23/04
2.1
38,697
3.50
0.267
Serial No.
24-6
Serial No.
Unit 1
03/05/04
10.5
37,751
3.50
0.277
Serial No.
24-10
Serial No.
Unit 2
09/10/04
14.4
2,043
4.02
0.498
Serial No.
24-14
Serial No.
Unit 2
09/19/04
17.7
45,798
4.02
0.745
Serial No.
24-43
Serial No.
Unit 2
09/25/04
18.6
47,116
4.02
0.492
Serial No.
2-1
Serial No.
Unit 2
11/16/04
18.3
43,960
4.02
0.430
Serial No.
2-2
Serial No.
Unit 2
11/20/04
18.6
2,934
4.02
0.355
Serial No.
2-9
Serial No.
Unit 2
2/03/04
21.0
43,903
4.01
0.511
Serial No.
2-3
Serial No.
Unit 2
2/12/04
18.2
43,840
4.01
0.422
Serial No.
24-44
Serial No.
Unit 1
07/01/05
18.02
40,158
3.50
0.755
- 4 -
LOADING
ORDER
Serial #
HI-STORM
100S No.
Unit
DATE
ON PAD
HEAT LOAD
(kW)
BURNUP
MWd/MTU (max)
MAXIMUM FUEL
ENRICHMENT %
PERSON-REM
DOSE
Serial No.
24-45
Serial No.
Unit 1
08/09/05
19.99
45,141
3.49
0.776
Serial No.
24-46
Serial No.
Unit 1
08/18/05
19.31
45,007
3.50
0.624
Serial No.
2-19
Serial No.
114
Unit 2
09/17/05
25.38
2,294
4.01
1.001
Serial No.
2-26
Serial No.
115
Unit 2
11/14/05
23.33
46,788
4.02
0.624
Serial No.
2-49
Serial No.
113
Unit 2
11/21/05
23.39
51,778
4.02
0.378
Serial No.
2-16
Serial No.
29
Unit 2
04/05/06
23.50
51,542
4.01
0.331
Serial No.
2-24
Serial No.
230
Unit 2
04/10/06
25.91
50,363
4.02
0.376
Serial No.
2-25
Serial No.
243
Unit 2
05/19/06
25.57
50,465
4.02
0.358
Serial No.
24-47
Serial No.
245
Unit 1
08/05/06
11.51
43,171
3.45
0.274
Serial No.
24-48
Serial No.
246
Unit 1
11/10/06
2.54
43,386
3.46
0.189
Serial No.
24-49
Serial No.
247
Unit 1
2/11/07
9.74
36,982
3.21
0.079
Serial No.
2-67
Serial No.
244
Unit 2
07/27/07
27.64
2,088
4.16
0.665
Serial No.
2-66
Serial No.
248
Unit 2
08/04/07
26.67
54,078
4.02
0.485
Serial No.
24-50
Serial No.
Unit 1
08/24/07
18.16
46,101
3.89
0.409
Serial No.
24-51
Serial No.
Unit 1
09/01/07
14.31
44,919
3.90
0.182
Serial No.
24-52
Serial No.
105
Unit 1
05/04/09
23.21
44,801
4.06
0.499
- 5 -
LOADING
ORDER
Serial #
HI-STORM
100S No.
Unit
DATE
ON PAD
HEAT LOAD
(kW)
BURNUP
MWd/MTU (max)
MAXIMUM FUEL
ENRICHMENT %
PERSON-REM
DOSE
Serial No.
2-84
Serial No.
104
Unit 2
05/29/09
26.59
2,605
4.32
0.493
Serial No.
2-85
Serial No.
25
Unit 2
11/05/09
26.01
54,232
4.32
0.616
Serial No.
24-53
Serial No.
24
Unit 1
2/10/09
10.86
41,358
4.05
0.095
Serial No.
24-54
Serial No.
26
Unit 1
09/29/10
10.99
41,478
4.06
0.141
Serial No.
2-159
Serial No.
474
Unit 2
10/20/10
26.36
49,952
4.30
0.645
Serial No.
2-163
Serial No.
475
Unit 2
10/28/10
26.15
48,000
4.30
0.473
Serial No.
2-164
Serial No.
476
Unit 2
11/03/10
26.46
47,778
4.29
0.420
NOTES:
Heat load (kW) is the sum of the heat load values for all spent fuel assemblies in the cask
Burn-up is the value for the spent fuel assembly with the highest individual discharge burn-up
Fuel enrichment is the spent fuel assembly with the highest individual initial enrichment per cent of U-235
HI-STORM Casks # 1 through 9 were loaded to CoC No. 1014, Amendment 1, FSAR Revision 1
HI-STORM Casks # 10 through 13 were loaded to CoC No. 1014, Amendment 1, FSAR Revision 2
HI-STORM Casks # 14 through 22 were loaded to CoC No. 1014, Amendment 2, FSAR Revision 3
HI-STORM Casks # 23 through 29 were loaded to CoC No. 1014, Amendment 2, FSAR Revision 4
HI-STORM Casks # 30 through 37 were loaded to CoC No. 1014, Amendment 5, FSAR Revision 7
Use of the Forced Helium Dehydrator (FHD) commenced with HI-STORM Cask #7
The first two digits in the serial number under the column MPC Serial # indicates whether the cask is a MPC-24 or a MPC-32
Unit 2 is Combustion Engineering fuel and is 18 inches longer than the Unit 1 Babcock & Wilcox fuel