IR 05000528/2015007
| ML15086A433 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 03/27/2015 |
| From: | Ray Kellar NRC/RGN-IV/DNMS/RSFSB |
| To: | Edington R Arizona Public Service Co |
| References | |
| IR 2015001, IR 2015007 | |
| Download: ML15086A433 (29) | |
Text
March 27, 2015
SUBJECT:
PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, 3, AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
INSPECTION REPORT 05000528/2015007, 05000529/2015007, 05000530/2015007, AND 07200044/2015001
Dear Mr. Edington:
This letter refers to a routine inspection conducted on February 22-26, 2015, 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 February 26, 2015 with Mr. Dwight Mims and other 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 NAC International (NAC) Universal Multi-Purpose Canister System (UMS) Certificate of Compliance No. 1015 and the associated Technical Specifications, the NAC-UMS 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 radiation safety, cask thermal monitoring, quality assurance (QA), your corrective action program, safety evaluations, observations of dry fuel loading activities, and changes made to your ISFSI program since the last routine ISFSI inspection that was conducted by the U.S. Nuclear Regulatory Commission (NRC). The ISFSI facility was found to be in good physical condition. No violations of NRC regulations were identified.
In accordance with title 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 E LAMAR BLVD ARLINGTON, TX 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/
Ray L. Kellar, P.E., Chief Repository & Spent Fuel Safety Branch Division of Nuclear Materials Safety
Dockets: 50-528, 50-529, 50-530, 72-44 Licenses: NPF-41, NPF-51, NPF-74
Enclosure:
Inspection Report 05000528/2015007; 05000529/2015007; 05000530/2015007; 07200044/2015001
w/attachments:
1. Supplemental Information 2. Loaded Casks at Palo Verde Nuclear Generating Station ISFSI
cc w/encl: Electronic Distribution
SUMMARY OF FINDINGS
IR 05000528, 529, 530/2015007; and 07200044/2015001; 02/22-26/2015; Palo Verde Nuclear
Generating Station Units 1, 2, 3, and Independent Spent Fuel Storage Installation (ISFSI);
Routine ISFSI Inspection Report
The report covers an announced inspection by one regional inspector and one inspector-in-training. 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 the NRC Enforcement Policy, all of the Part 72 ISFSI inspection findings follow the traditional enforcement process and are not disposition 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
Palo Verde Nuclear Generating Station (PVNGS) Independent Spent Fuel Storage Installation (ISFSI) stored 124 loaded NAC International (NAC) vertical concrete casks (VCCs) at the time of the routine inspection. PVNGS was loading the 125th canister, which was the third canister in their nine cask loading campaign for the Unit 1 facility in this calendar year. Inspectors observed loading operations associated with cask number 125 at the time of the routine inspection. The licensee utilized a general Part 72 license in accordance with the NAC,
Universal Multi-Purpose Canister System (UMS), approved under Certificate of Compliance (CoC) No. 1015, Amendment 5 and the NAC UMS Final Safety Analysis Report (FSAR),
Revision 10. The version of the NAC UMS systems used by the licensee included the TSC-24, a 24 fuel bundle transportable storage canister (TSC), designed to hold 24 pressurized water reactor (PWR) fuel assemblies. The ISFSI at Palo Verde contained a large earthen berm within the ISFSI protected area which was outside the Part 50 protected area. The berm was 120 feet wide at the base, 12 feet wide at the top, and 18 feet tall. The earthen berm extended around the ISFSI pad on three sides, specifically on the east, west, and south. The ISFSI consisted of twelve large rectangular concrete storage pads. The concrete storage pads were approximately 285 feet long by 35 feet wide. Each storage pad was designed to accommodate 28 VCCs arranged in two parallel rows of 14 casks. The design capacity allowed for a total of 336 VCCs.
The licensee had loaded the casks on the southernmost pads deepest into the earthen berm.
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) Quality Assurance Audits and Surveillances
The Palo Verde Nuclear Assurance Department (NAD) had included ISFSI related activities in their audit and surveillance program. The licensee performed a focused audit of its ISFSI program once every two years. NAD ISFSI Audit Plan and Report 2014-010 (Audit Report), dated January 16, 2015, was reviewed during this inspection. The quality assurance (QA) audits performed by the licensee reviewed activities and documentation to determine the effectiveness of the dry fuel storage program to operate safely in accordance with the requirements in the NAC-UMS Certificate of Compliance, the FSAR, the QA program, and their 10 CFR Part 72 program.
The Audit Report reviewed five program elements and eight administrative elements of ISFSI operation, as well as providing follow up on deficiencies identified in the previous ISFSI audit. The program elements included program and licensing requirements, design control, operation, maintenance, and Special Nuclear Material (SNM). The administrative elements included organization and responsibilities, department document control, QA records, task/job qualifications, corrective action, self-assessment, nuclear safety culture, and industry experience.
The licensees QA audit determined that all five ISFSI program elements were being effectively implemented at PVNGS. Six of the eight administrative elements of ISFSI operation were found to be effective, and two were found to be deficient: QA records and corrective action. The QA records program element was found to be deficient because SNM inventory records were not turned over to Support Services within the specified time frame and previous corrective actions identified during the 2012 ISFSI Audit were found to be ineffective. The corrective actions program element was found to be deficient because of several failures to implement corrective actions in a timely manner, including nonconforming conditions associated with the Vertical Concrete Cask (VCC)
The 2014 Audit produced a total of ten Palo Verde Action Requests (PVARs).
Three PVARs were associated with the QA audit of the ISFSI program elements and seven PVARs were associated with the QA audit of the administrative elements. All ten PVARs were entered into the licensees Corrective Action Program. NRC inspectors reviewed the corrective actions related to the findings to ensure that the identified deficiencies were properly categorized based on their safety significance and properly resolved. All identified deficiencies had been properly categorized and resolved by the licensee.
The QA surveillance report issued since the last NRC ISFSI inspection was reviewed by the NRC inspectors. Arizona Public Service (APS) QA personnel led a Nuclear Utility Procurement Issues Committee (NUPIC) audit of the NAC International production facility in Norcross, GA. NUPIC is a partnership involving all domestic and several international nuclear utilities that evaluates suppliers furnishing safety-related components and services and commercial-grade items to nuclear utilities. The QA surveillance was documented in APS Audit Report Number: A-NAC1-14-06/NUPIC Audit No. 23744, dated July 9, 2014. The audit team reviewed the following activities:
order entry, design, licensing, software quality assurance, procurement, fabrication/assembly activities, tests, inspections, calibration, document control, nonconforming items, corrective action, training, internal audits, and records. The audit team concluded that NAC International Inc. was effectively maintaining and implementing their Nuclear Quality program and complied with 10 CFR 72 Subpart G.
- (2) Radiological Conditions Related to Stored Casks
The PVNGS ISFSI was located approximately 2,600 feet east of the Unit 2 reactor containment building outside of the sites Part 50 protected area (PA). The ISFSI consisted of 12 concrete pads, situated in three columns of four arranged east to west. Each pad was designed to hold 28 NAC-UMS storage casks configured in a two by 14 array. The Palo Verde ISFSI was protected on three sides by an earthen berm that exceeded the height of the spent fuel storage casks. The open side of the berm faces plant west. Outside of the berm, the ISFSI was protected on all sides by two exclusion fences. On the inside of the inner fence was a roped boundary facing the entrance to the ISFSI that was posted as a Radioactive Materials Area. No flammable or combustible materials, debris, or excessive vegetative growth were observed inside the ISFSI area. One hundred twenty-four VCCs were loaded with spent fuel at the time of the inspection. The 124 VCCs completed four of the 12 pads and almost half of a fifth pad. VCC number 125 was being loaded at the time of the NRC ISFSI inspection. The inspector found the 124 NAC-UMS casks to be in good physical condition.
Radiological conditions at the Palo Verde ISFSI were determined from the most recent radiological survey (dated January 22, 2015) and records from the previous three years of thermoluminescent dosimeter (TLD) monitoring results. There were eight TLD monitoring locations that were positioned outside of the ISFSI exclusion area fence, two TLDs per side.
A PVNGS radiation protection (RP) technician accompanied the NRC inspector during the walk-down of the ISFSI pad area. Radiological measurements were taken by the RP technician with a Geiger-Mueller detector to record gamma exposure rates. The NRC inspector carried an NRC issued Ludlum Model 19 scintillation detector (NRC number 016337, calibration due date of 7/21/2015) that was capable of measuring low level gamma radiation exposure rates in micro-Roentgens per hour (µR/h). Survey measurements were taken at ISFSI area fence locations, around the perimeter of the ISFSI pad, and at selected areas between VCCs.
A gamma background reading outside the power plant prior to entry into the ISFSI pad area was approximately 10 µR/h. Radiation readings taken along the fence-line showed radiation levels ranging from 17 to 41 µR/h. General area measurements inside the berm and on the storage pads ranged from 32 µR/h, at the far empty side of the ISFSI to 1 mR/h in areas adjacent to and between loaded casks. The radiological conditions of the ISFSI were as expected for the age and heat-load of the 124 loaded spent fuel storage casks. The licensee was properly posting and controlling the ISFSI pad area consistent with 10 CFR Part 20 requirements.
- (3) Environmental Radiological Monitoring Program
The primary purpose of the Palo Verde Radiological Environmental Monitoring Program (REMP) was to evaluate the radiological impacts that reactor operations and stored radioactive materials may have on the local environment. The REMP was focused on measuring airborne (gaseous and particulate), liquid effluent, and direct radiation levels onsite, at the site boundary, and at offsite locations. The REMP monitored direct radiation impacts using TLDs. The licensee had established 50 REMP TLD monitoring stations for measuring and recording dose rates continuously throughout the year. Sixteen of those monitoring locations formed an inner ring at the site boundary, one in each meteorological sector. By design, there were no airborne or liquid effluents released from the Palo Verde ISFSI. NRC received the Annual Radioactive Effluent Release Reports for 2012 (ML13128A007) and 2013 (ML14125A295) for PVNGS, which confirmed that the ISFSI did not produce any effluent radioactive releases during 2012 or 2013.
The PVNGS ISFSI was monitored for direct radiation using TLDs that included direct gamma and neutron dose. The ISFSI TLDs were mounted on polymer phantoms to simulate the presence of a human body. This allowed for a more accurate neutron dose assessment. REMP TLDs only measured direct gamma dose. The TLD data for the ISFSI and the TLD data for the REMP were handled by different programs at PVNGS for different purposes. The ISFSI TLD monitoring was performed by the Palo Verde Area Monitoring Program to track radiological exposures near the ISFSI boundary to ensure that NRC occupational limits for unmonitored individuals were not exceeded. The REMP monitoring was conducted by APS for PVNGS to provide an annual assessment of the licensees total impacts to the environment, which includes contributions from the ISFSI.
ISFSI TLDs were placed at eight monitoring locations outside the outer exclusion fence. The TLD monitoring results from 2012, 2013, and 2014 were reviewed by NRC inspectors (see Table 1, below). The TLDs were collected and replaced each quarter of the year.
Table 1: PVNGS ISFSI Pad TLD Monitoring Data in µrem/h ISFSI TLD Location #
Location (outside of fence)2012 2013 2014 3-Year Average South Fence SW TLD (gamma)
(neutron)
(total)13.7 0.6 14.3 13.8 13.8 13.9 13.9 13.8 0.2 14.0 South Fence SE TLD (gamma)
(neutron)
(total)21.6 7.9 29.5 24.1 9.8 33.9 23.8 4.6 28.4 23.2 7.4 30.6 East Fence SE TLD (gamma)
(neutron)
(total)21.0 7.3 28.3 22.2 8.1 30.3 21.9 4.0 25.9 21.7 6.5 28.2 East Fence NE TLD (gamma)
(neutron)
(total)20.0 8.2 28.2 20.6 8.7 29.3 21.5 3.4 24.9 20.7 6.8 27.5 North Fence NE TLD (gamma)
(neutron)
(total)18.3 7.1 25.4 19.0 6.5 25.5 19.4 3.4 22.8 18.9 5.7 24.6 North Fence NW TLD (gamma)
(neutron)
(total)15.0 2.0 17.0 14.4 1.8 16.2 15.3 0.3 15.6 14.9 1.4 16.3 West Fence NW TLD (gamma)
(neutron)
(total)14.3 14.3 13.8 0.8 14.6 14.6 14.6 14.2 0.3 14.5 West Fence SW TLD (gamma)
(neutron)
(total)13.6 0.3 13.9 14.0 0.3 14.3 14.4 14.4 14.0 0.2 14.2
NRC Inspectors verified the radiation exposure rates at each TLD monitoring location during the ISFSI walk-down. The highest average annual dose rate, approximately 270 mrem per year (30.6 µrem/h), was measured at the TLD #52 location. The three-year average of all ISFSI TLD monitoring locations has been trending upward as compared to the results of the previous three-year average (2010 - 2012) documented in the inspection report dated April 2, 2013 (ML13094A435). All accessible areas near the PVNGS ISFSI boundary, however, were below the 10 CFR 20.1502(a)(1) limit, of 500 mrem per year for unmonitored workers.
The yearly results of the REMP were compiled in an Annual Radiological Environmental Operating Report (AREOR). NRC reviewed the PVNGS AREORs for 2012 (ML13128A006), issued April 26, 2013 and 2013 (ML14129A007), issued May 2, 2014. The AREORs did not include the TLD direct radiation monitoring results for the ISFSI, but provided reporting and analyses for the REMP TLD monitoring results.
The PVNGS ISFSI was located 4,000 feet (0.8 miles) from the nearest site boundary monitoring location in the east sector. The REMP TLD monitoring site at the site boundary in closest proximity to the ISFSI was TLD #17. TLD monitoring locations #6 and #44 were control monitoring stations located 31 miles south-southeast and 35 miles east-northeast, respectively, from PVNGS. These TLDs can be treated as radiological backgrounds and have been averaged for this purpose (see Table 2, below).
Table 2, PVNGS Site Boundary TLD Result near ISFSI in mrem/yr TLD Site Station and Location 2012 2013
- 17 E Sector, 4,000 feet east of ISFSI 98.2 96.9
- 6 (control)
SSE Sector, 31 miles from PVNGS 94.8 99.7
- 44 (control)
ENE Sector, 35 miles from PVNGS
Table 2 (above) shows that direct radiation from the ISFSI and Part 50 activities had a negligible impact on site boundary ambient radiation levels. REMP results show that the site boundary dose at TLD #17 was slightly above background for 2012 and slightly below background in 2013. Correcting the 2012 value for background yielded a net annual dose of 3.4 mrem. This was well below the 10 CFR 72.104(a)(2) requirement of less than 25 mrem annual dose equivalent to any real individual located beyond the site controlled area. The radiological influence of the ISFSI on this site boundary location was minimal.
- (4) Records Related to Fuel Stored in the Casks
A review of dry fuel storage records for canisters 102 through 125 were selected to determine whether adequate descriptions of the spent fuel stored in each cask was documented as a permanent record as required by 10 CFR 72.212(b)(12). In addition, the fuel contents of these casks were verified against NAC CoC 1015 Technical Specification requirements for PWR fuel assemblies loaded into a TSC-24 canister. The spent fuel contents of the 24 selected casks were recorded in Analysis Report Numbers RE-02-C18-2013-003, RE-03-C17-2013-012, RE-03-C17-013, RE-02-C18-2013-003, RE-03-C18-2014-003, RE-C18-2014-010, RE-02-C19-2014-011, RE-01-C-19-2015-002, and RE-01-C19-2015-003. These reports included the TSC loading maps and fuel assembly qualification data, including fuel assembly identifiers, decay heat (kW), cooling time (years), initial assembly average U-235 enrichment (%), burn-up values (MWd/MTU), and other fuel assembly characterization information. Select fuel data is tracked by cask on Attachment 2 of this inspection report. PVNGS was in compliance with all applicable license and FSAR requirements for the fuel stored at the ISFSI and met retrievability requirements for storage of spent fuel records.
- (5) Technical Specification 3.1.6, Cask Temperature Monitoring
Technical Specification 3.1.6 required the casks heat removal system to be operable during storage on the ISFSI pad. Surveillance Requirement 3.1.6.1 required the licensee to verify daily the difference between the ISFSI ambient temperature and the average outlet air temperature as 102 degrees F or visually verify all four air inlet or outlet screens were unobstructed once each day. All casks in storage on the ISFSI pad were equipped with temperature monitoring equipment.
The licensee performed daily temperature monitoring for compliance with Technical Specification 3.1.6.1. Whenever the temperature monitoring equipment was malfunctioning or not in operation for a cask, the licensee performed daily vent inspections for that particular cask.
The licensee utilized Procedure 40ST-9ZZM1 Operations Mode 1 Surveillance Logs, Revision 63, during normal operations to comply with the Technical Specification 3.1.6. The procedures required operators to verify that the difference in the ambient temperature and each cask outlet temperature was < 90 degrees F.
If the acceptance criteria was not met, the operators were required to check the affected cask vent openings and remove any blockages, if found.
Documentation was reviewed for the months of September 2013, December 2013, February 2014, and July 2014 for compliance with Technical Specification 3.1.6. Of the four months selected for review, temperature monitoring was performed daily as required. The provided documentation showed a daily printout of the difference between the ambient temperature and each casks temperature. For all the days selected for review, no temperature difference between the ambient and a casks vents were found to be > 90 degrees.
- (6) Corrective Action Program
A list of Condition Reports (CRs) issued since the last NRC inspection in February of 2014 was provided by the licensee for the cask handling cranes from each unit and the ISFSI operations. Issues were processed in accordance with Procedure 90DP-0IP10, Condition Reporting, Revision 57. When a problem was identified the licensee documented the issue as a PVAR in the licensees corrective action program. Once a PVAR was initiated, the Action Request Review Committee determined if a Condition Report/Disposition Request (CRDR) per Procedure 90DP-0IP10 Condition Reporting, Revision 53 was required.
Of the list of PVARs/CRDRs provided relating to the ISFSI and the cask handling cranes, 29 documents were selected by the NRC inspectors for further review. The PVARs/CRDRs related to a variety of issues. The PVARs/CRDRs reviewed were well documented and properly categorized based on the safety significance of the issue. The corrective actions taken were appropriate for the situations. Based on the level of detail of the corrective action reports, the licensee demonstrated a high attention to detail in regard to the maintenance and operation of their ISFSI program and the cask handling cranes. No NRC safety concerns were identified related to the PVARs/CRDRs reviewed.
- (7) Preparation of Loading Activities
The inspectors requested documentation related to maintenance of the fuel building cask handling crane for Unit 1, the annual maintenance of the licensees special lifting devices, and the calibration of various gauges associated with the loading activities.
Documents were reviewed that demonstrated that the Unit 1 cask handling crane was inspected on an annual basis in accordance with American Society of Mechanical Engineers (ASME) B30.2 prior to the 2015 loading campaign. PVNGS utilized Work Order (WO) 4437112 dated October 21, 2014, to perform the annual maintenance in October of 2014.
The annual maintenance as required by American National Standards Institute (ANSI) N14.6 for special lifting devices was completed for the following special lifting devices: the Safelift (Lift Beam) and the canister shield lift rig. Documentation reviewed included WO 4465187 and associated non-destructive examination documentation associated with the testing. All equipment passed the magnetic particle, liquid penetrant, and dimensional testing.
The FSAR Section 9.2.2 required annual visual inspections of the transfer cask lifting trunnions, shield door, and shield door rails for permanent deformation and cracking. In addition, dimensional inspection of load-bearing components and a nondestructive examination of the major load-bearing welds were required annually.
The transfer cask annual inspections for 2013 through 2014 were reviewed. The licensee implemented the annual inspections using WO 4165175, dated August 14, 2013 and WO 4414043, dated August 14, 2011. For each year, magnetic particle examination was the method of nondestructive examination utilized. No indications were identified during the visual, dimensional, or magnetic particle examination for the years reviewed.
Calibration documentation of the hydrostatic pressure gages and the vacuum drying gage were reviewed to ensure the equipment had been properly calibrated prior to the loading operations. All calibration certificates reviewed demonstrated that the gages were properly calibrated prior to the loading campaign. After each canister loading the licensee performed a post-calibration on the hydrostatic pressures gages to verify the calibration of the gages in accordance with AMSE Section III NB-6413.
- (8) VCC and ISFSI Yearly Maintenance
The NAC UMS FSAR, Section 9.2.1 required an annual inspection of the concrete casks that included visual examination of the concrete, vent screens, and other attached hardware for damage. If concrete defects were found that were larger than 1-inch in diameter and deeper than 1-inch, repair by grouting was required.
The annual visual inspections for 2013 through 2014 were reviewed. The 2013 annual inspection was documented in Component Observation Report (COR) 13-9-001, Revision 0. The 2014 report was documented in COR 14-9-001, Revision 0.
Both reports documented that no new indications of concrete pop-outs or voids
> 1/2-inch in depth, no indications of spalling or scaling, and no new indications of concrete reinforcing bar corrosion were observed. The deficiencies noted during the inspections included minor efflorescence in portions of concrete surfaces typically in the upper half of the cask, random map cracks ranging from hairline to 0.016 inches, and rust on VCC steel lifting lugs which was removed and touched up a corrosion-inhibiting coating. All other deficiencies noted, were minor superficial surface issues that did not affect the function of the casks.
- (9) Cask Loading Observations
Various loading activities were observed by the NRC inspectors during the course of the routine ISFSI inspection. PVNGS was in the process of loading canister #125 at the time of the inspection. The NRC inspectors observed the fuel movement activities to place spent fuel assemblies into canister #125. The licensees staff was experienced in moving the spent fuel assemblies and was proficient in locating the correct assembly, verifying the assembly, moving the assembly from the rack to the canister, and inserting the assembly into the assigned canister slot. The time from grappling the assembly, placing the assembly into the assigned canister slot, and returning to the next assigned spent fuel assembly was approximately six to seven minutes.
Selected welding and non-destructive examination activities were observed during the loading associated with canister #125. An automatic welding process was used to weld the canister lid. The automated welding machine utilized one weld head to weld the lid to shell weld. The welders operated the equipment remotely in a low dose rate area. Hydrogen monitoring was performed during the welding of the root weld. Additionally, the NRC inspectors observed the non-destructive dye penetrant exams conducted on the lid-to-shell weld, the TSC structural lid weld, and the welds on the vent and drain port covers. If any welding defects were found the defects were removed by the welders and subsequent NDE examinations passed with clear results.
Other activities that were observed by NRC inspectors during the loading of canister
- 125 included the draining of the TSC, drying of the TSC, lifting the transfer cask and fully loaded TSC out of the cask loading pit, and downloading of the TSC into the VCC storage cask. The licensees cask handling crane was able to handle the heavy load without any observed problems.
- (10) Vertical Cask Transporter Lifting Brackets
PVNGS utilized a Vertical Cask Transport (VCT) to move the VCC from outside the fuel building to ISFSI pad. The FSAR section 8.1.3 allows a license to utilize a mobile lifting frame (or transporter) when the lift height is limited to 24 inches and the mobile lifting device follows the requirements of Section A5.6.c of the Technical Specifications. The NAC FSAR does not specifically address the type of the mobile lifting device or the lifting brackets that lift the VCC to transport the cask to the ISFSI at PVNGS. PVNGS utilized a 72.48 safety evaluation to evaluate the use of the VCT to transport the VCC to the ISFSI pad. The 72.48 safety evaluation, procedures, and process performed at PVGNS abided by the Technical Specification requirement of A5.6.a. limiting the lift height of the VCC to 24 inches.
Table 1.5-1, NUREG-1536 Compliance Matrix from the FSAR, Chapter 3 - Structural Evaluation stated that: the lifting equipment design and devices for lifting the system components that are important to safety must comply with American National Standards Institute (ANSI) Standard N14.6. The VCC is listed as a system component that is important to safety. ANSI N14.6, Section 6.3.1 requires that each special lifting device be subjected to either a load test or dimensional checks, non-destructive examination and a visual examination annually, not to exceed 14 months.
PVNGS had not been performing an annual inspection of the VCT lifting brackets used to lift the VCC in accordance with ANSI N14.6 Section 6.3.1. Since the lifting brackets of the VCT were not specifically identified in the NAC FSAR, PVGNS has placed this issue into their corrective action program to confer with NAC to understand if the lifting brackets of the VCT shall conform to the requirement listed in FSAR Table 1.5-1 and be in compliance with the ANSI N14.6 Standard. This applicability of the VCT lifting brackets to comply with the ANSI N14.6 Standard is being tracked as an Unresolved Item (URI 72-44/1501-01).
b. Findings
No findings were identified.
.2 Review of 10 CFR 72.212(b) Evaluations at Operating Plants (60856.1)
a. Inspection Scope
Changes to the 10 CFR 72.212 Evaluation Report were reviewed to verify site characteristics were still bounded by the NAC UMS cask systems design basis.
PVNGS had not made any changes to their 72.212 Evaluation Report since the last ISFSI inspection in February 2013. The 72.212 Evaluation Report was at Revision 11, dated January 18, 2013.
b. Findings
No findings were identified.
.3 Review of 10 CFR 72.48 Evaluations
a. Inspection Scope
The licensees 10 CFR 72.48 screenings and evaluations for ISFSI program changes and 50.59 screenings and evaluations for changes made to the cask handling cranes since the last NRC routine ISFSI inspection were reviewed to determine compliance with regulatory requirements. PVNGS had performed six 72.48 screens associated with changes to the ISFSI equipment or operations. No modifications had been performed on any of the cask handling cranes which had required a 50.59 screen. The licensee had not performed any 72.48 full safety evaluations for the ISFSI or any 50.59 full safety evaluations for the cask handling cranes since the last NRC inspection in February of 2013.
Inspectors reviewed the six 72.48 screens provided by the licensee. The licensee utilized Procedure 93DP-0LC07, 10 CFR 50.59 and 72.48 Screenings and Evaluations, Revision 26 to perform the 10 CFR 72.48 safety screening. None of the screenings reviewed required a full 10 CFR 72.48 safety evaluation. All screenings were determined to be adequately evaluated.
b. Findings
No findings were identified.
4OA6 Meetings, Including Exit
Exit Meeting Summary
On February 26, 2015, the inspectors presented the inspection results to Mr. Dwight Mims, Senior Vice President, Regulatory & Oversight, 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
B. Hansen, Department Leader, NFM D. Heckman, Compliance, Regulator Affairs M, Kohrt, Operations Manager M. McGhee, Department Leader, Regulatory Affairs D. Mims, Senior Vice President, Regulatory and Oversight H. Nelson, Director of Maintenance Projects C. Stephenson, Licensing, Regulatory Affairs S. Toone, Dry Cask Storage Engineering A. Wrape, Director of Fuel Management
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
72-44/1501-01
VCT Lifting Bracket compliance with ANSI N14.6.
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
Drawings
NUMBER
TITLE
DATE
0-M-20150122-2
VSDS Standard Map Survey Report
01/22/15
Procedures
NUMBER
TITLE
REVISION
Control of SNM Transfer and Inventory
Rev. 45
Spent Fuel Handling Machine
Rev. 55
NAC-UMS Cask Loading Operations
Rev. 32
GQP-9.6
Visual Examinations of Welds
Rev. 14
Helium Testing of TSC Shield Lid Welds
Rev. 7
PI-CNSTR-T-OP-210
Closure Welding of NAC Dry Cask Storage Canisters
for APS
Rev. 7
GQP-9.2
High Temperature Liquid Penetrant Examination and
Acceptance Standards for Welds, Base Materials and
Cladding (50o - 350oF)
Rev. 7
Condition Reporting
Rev. 57
CFR 50.59 and 72.48 Screenings and Evaluations
Rev. 26
CFR 50.59 and 72.48 Administrative Guidelines
Rev. 2
Operations Mode 1 Surveillance Logs
Rev. 62, 63
Design Basis Documents
NUMBER
TITLE
REVISION
PVNGS ISFSI 72.212 Evaluation Report
Rev. 11
Certificate of Compliance 72-1015 NAC International
Inc., NAC-UMS System
Amendment 5
NAC International FSAR for the UMS Cask System
Rev. 10
- 2 -
Miscellaneous Documents
NUMBER
TITLE
REVISION / DATE
RE-02-C18-2013-003
U2C18 Spent Fuel Selection for Dry Casks 101-104
Rev. 1
RE-03-C17-2013-012
U3C17 Spent Fuel Selection for Dry Casks 105-106
Rev. 0
RE-02-C18-2013-013
U3C17 Spent Fuel Selection for Dry Casks 107-110
Rev. 0
RE-03-C18-2014-003
U3C18 Spent Fuel Selection for Dry Casks 111-113
Rev. 0
RE-03-C18-2014-010
U3C18 Spent Fuel Selection for Dry Casks 114-116
Rev. 0
RE-02-C19-2014-011
U2C19 Spent Fuel Selection for Dry Casks 117-122
Rev.0
RE-01-C19-2015-002
U1C19 Spent Fuel Selection for Dry Casks 123-124
Rev. 0
RE-01-C19-2015-003
U1C19 Spent Fuel Selection for Dry Casks 125-131
Rev. 0
N/A
NAD Audit Plan and Report 2014-010 ISFSI
01/16/15
N/A
NUPIC Audit # 23744 / APS Audit # A-NAC1-14-06
07/09/14
N/A
ISFSI TLD Trending 2003 - Present
N/A
COR-13-9-001
VCC Annual Inspection
Rev. 0
COR-13-9-002
ISFSI berms, culverts, ditches, etc., inspections
Rev. 0
COR 14-9-002
ISFSI berms, culverts, ditches, etc., inspections
Rev. 0
COR-14-9-001
VCC Annual Inspection
Rev. 0
N/A
04/26/13
N/A
05/04/14
N/A
PVNGS 2012 Annual Radioactive Effluent Release
Report
04/30/13
N/A
PVNGS 2013 Annual Radioactive Effluent Release
Report
04/30/14
2.48 Screenings
2.48 Screening S-14-003
2.48 Screening S-14-002
2.48 Screening S-14-001
2.48 Screening S-13-003
2.48 Screening S-13-002
2.48 Screening S-13-001
Work Orders
WO 4465187
WO 4414043
PVARs/CRDRs
CRDR-4444058
CRDR-4459713
CRDR-4354531
CRDR-4605390
CRDR-4606985
CRDR-4601795
CRDR-4563698
CRDR-4558044
CRDR-4555811
CRDR-4548986
CRDR-4518912
CRDR-4459713
CRDR-4444078
CRDR-4424784
CRDR-4421994
CRDR-4386426
CRDR-4396605
CRDR-4356970
CRDR-4354530
CRDR-4353777
CRDR-4335239
CRDR-4562047
CRDR-4534473
CRDR-4558044
PVAR-4628208
PVAR-4627111
PVAR-4627295
CRDR-4627418
PVAR-4455514
- 3 -
LIST OF ACRONYMS
Agencywide Documents Access and Management System
ANSI
American National Standards Institute
Arizona Public Service
Annual Radiological Environmental Operating Report
American Society of Mechanical Engineers
Combustion Engineering
CFR
Code of Federal Regulations
Certificate of Compliance
COR
Component Observation Report
CRDR
Condition Report/Disposition Report
Division of Nuclear Material Safety
F
Fahrenheit
Final Safety Analysis Report
IMC
Inspection Manual Chapter
IP
inspection procedure
Independent Spent Fuel Storage Installation
kW
killo-watt
mR
milliRoentgen
micro(µ)R/hr
microRoentgen per hour
micro(µ)rem/hr
microRoentgen equivalent man per hour
multipurpose canister
mrem
milliRoentgen equivalent man
MWD/MTU
megawatt days/metric ton uranium
NAD
Nuclear Assurance Department
NRC
U.S. Nuclear Regulatory Commission
Nuclear Utility Procurement Issues Committee
Protected Area
PVAR
Palo Verde Action Request
Palo Verde Nuclear Generating Station
pressurized water reactor
quality assurance
Radiological Environmental Monitoring Program
radiation protection
thermoluminescent dosimeter
TFR
transfer cask
transportable storage canister
UMS
Universal Multi-Purpose Canister System
VCC
vertical concrete cask
work order
ATTACHMENT 2:
LOADED CASKS AT THE PALO VERDE NUCLEAR GENERATING STATION ISFSI
LOADING
ORDER
VCC
ID No.
Canister
ID No.
Unit
DATE
ON PAD
HEAT LOAD
(kW)
BURNUP
MWd/MTU (max)
MAXIMUM FUEL
ENRICHMENT %
PERSON-
DOSE
AMZDNE001
AMZDFX001
Unit 2
3/15/03
7.59
2,833
4.0334
0.552
AMZDNE002
AMZDFX002
Unit 2
4/15/03
7.76
41,841
4.0368
0.402
AMZDNE003
AMZDFX003
Unit 2
5/15/03
10.17
40,737
4.0397
0.507
AMZDNE004
AMZDFX004
Unit 2
5/29/03
10.04
40,408
4.0098
0.351
AMZDNE005
AMZDFX005
Unit 2
6/12/03
10.96
38,357
4.044
0.260
AMZDNE006
AMZDFX008
Unit 1
7/24/03
10.37
2,318
4.050
0.286
AMZDNE007
AMZDFX007
Unit 1
8/07/03
10.48
2,214
4.046
0.262
AMZDNE008
AMZDFX006
Unit 1
8/21/03
11.03
2,168
4.057
0.325
AMZDNE009
AMZDFX009
Unit 1
9/05/03
11.52
2,050
4.057
0.253
AMZDNE010
AMZDFX010
Unit 1
9/18/03
7.14
30,134
3.309
0.251
AMZDNE011
AMZDFX011
Unit 3
1/23/04
2.16
39,735
3.905
0.259
AMZDNE012
AMZDFX012
Unit 3
2/06/04
2.13
39,574
3.917
0.239
AMZDNE013
AMZDFX013
Unit 3
2/26/04
2.26
39,821
3.913
0.297
AMZDNE014
AMZDFX014
Unit 3
3/11/04
11.52
39,640
3.919
0.207
- 2 -
LOADING
ORDER
VCC
ID No.
Canister
ID No.
Unit
DATE
ON PAD
HEAT LOAD
(kW)
BURNUP
MWd/MTU (max)
MAXIMUM FUEL
ENRICHMENT %
PERSON-
DOSE
AMZDNE015
AMZDFX015
Unit 3
3/25/04
11.73
39,180
3.917
0.218
AMZDNE016
AMZDFX016
Unit3
5/27/04
11.74
39,939
3.913
0.202
AMZDNE017
AMZDFX017
Unit 2
7/15/04
10.65
44,693
4.041
0.195
AMZDNE018
AMZDFX018
Unit 2
7/29/04
10.66
44,637
4.050
0.164
AMZDNE019
AMZDFX019
Unit 2
8/12/04
9.71
43,369
4.030
0.137
AMZDNE020
AMZDFX020
Unit 2
8/26/04
9.73
43,362
4.043
0.095
AMZDNE021
AMZDFX021
Unit 2
9/10/04
9.73
43,350
4.044
0.125
AMZDNE022
AMZDFX022
Unit 2
9/23/04
9.73
43,205
4.036
0.115
AMZDNE023
AMZDFX023
Unit 1
1/22/05
2.28
44,953
4.032
0.165
AMZDNE024
AMZDFX024
Unit 1
3/17/05
2.28
44,973
4.035
0.178
AMZDNE025
AMZDFX025
Unit 1
3/24/05
2.05
44,973
4.033
0.193
AMZDNE026
AMZDFX026
Unit 1
3/03/05
2.40
44,992
4.033
0.097
AMZDNE027
AMZDFX027
Unit 1
3/10/05
2.40
44,608
4.032
0.126
AMZDNE028
AMZDFX028
Unit 1
3/30/05
2.06
44,957
4.033
0.115
AMZDNE029
AMZDFX029
Unit 3
8/03/05
10.33
41,361
3.528
0.144
AMZDNE030
AMZDFX030
Unit 3
8/11/05
10.24
41,603
3.528
0.142
- 3 -
LOADING
ORDER
VCC
ID No.
Canister
ID No.
Unit
DATE
ON PAD
HEAT LOAD
(kW)
BURNUP
MWd/MTU (max)
MAXIMUM FUEL
ENRICHMENT %
PERSON-
DOSE
AMZDNE031
AMZDFX031
Unit 3
8/19/05
11.60
44,247
3.970
0.116
AMZDNE032
AMZDFX032
Unit 3
8/31/05
11.56
43,594
4.000
0.105
AMZDNE033
AMZDFX033
Unit 3
9/08/05
11.57
44,247
3.992
0.104
AMZDNE034
AMZDFX034
Unit 3
9/16/05
11.57
43,594
4.001
0.094
AMZDNE035
AMZDFX035
Unit 2
1/20/06
11.98
44,849
4.384
0.100
AMZDNE036
AMZDFX036
Unit 2
1/27/06
2.00
44,877
4.386
0.091
AMZDNE037
AMZDFX037
Unit 2
2/09/06
11.98
44,877
4.388
0.064
AMZDNE038
AMZDFX038
Unit 2
2/17/06
11.98
44,877
4.386
0.066
AMZDNE039
AMZDFX039
Unit 2
2/24/06
11.99
44,877
4.390
0.078
AMZDNE040
AMZDFX040
Unit 2
3/03/06
2.01
44,390
4.383
0.051
AMZDNE041
AMZDFX041
Unit 2
3/10/06
2.02
43,877
4.380
0.064
AMZDNE042
AMZDFX042
Unit 1
7/21/06
8.52
44,801
4.162
0.035
AMZDNE043
AMZDFX043
Unit 1
7/29/06
8.39
44,801
4.149
0.042
AMZDNE044
AMZDFX044
Unit 1
8/04/06
8.41
44,801
4.148
0.035
AMZDNE045
AMZDFX045
Unit 1
8/18/06
8.41
44,801
4.144
0.041
AMZDNE046
AMZDFX046
Unit1
8/25/06
8.46
44,706
4.146
0.044
- 4 -
LOADING
ORDER
VCC
ID No.
Canister
ID No.
Unit
DATE
ON PAD
HEAT LOAD
(kW)
BURNUP
MWd/MTU (max)
MAXIMUM FUEL
ENRICHMENT %
PERSON-
DOSE
AMZDNE047
AMZDFX047
Unit 1
9/01/06
8.45
44,706
4.146
0.032
AMZDNE048
AMZDFX048
Unit 3
4/06/07
9.07
44,841
4.287
0.058
AMZDNE049
AMZDFX049
Unit 3
4/13/07
8.81
44,778
4.287
0.058
AMZDNE050
AMZDFX050
Unit 3
4/20/07
8.76
44,778
4.266
0.049
AMZDNE051
AMZDFX051
Unit 3
4/28/07
8.80
44,778
4.272
0.049
AMZDNE052
AMZDFX052
Unit 3
5/04/07
8.67
44,841
4.269
0.046
AMZDNE053
AMZDFX053
Unit 3
5/11/07
8.64
44,841
4.298
0.043
AMZDNE054
AMZDFX054
Unit 2
9/25/08
9.46
44,822
4.208
0.074
AMZDNE055
AMZDFX055
Unit 2
2/06/08
9.54
44,822
4.208
0.107
AMZDNE056
AMZDFX056
Unit 2
2/16/08
9.53
44,822
4.206
0.051
AMZDNE057
AMZDFX057
Unit 2
2/31/08
9.56
44,822
4.387
0.040
AMZDNE058
AMZDFX058
Unit 1
2/28/09
2.70
44,850
4.375
0.096
AMZDNE059
AMZDFX059
Unit 1
3/10/09
14.17
53,665
4.378
0.124
AMZDNE060
AMZDFX060
Unit 1
3/20/09
14.18
2,637
4.379
0.089
AMZDNE061
AMZDFX061
Unit 1
6/09/09
14.21
2,874
4.381
0.121
AMZDNE062
AMZDFX062
Unit 1
6/24/09
14.23
2,915
4.379
0.096
- 5 -
LOADING
ORDER
VCC
ID No.
Canister
ID No.
Unit
DATE
ON PAD
HEAT LOAD
(kW)
BURNUP
MWd/MTU (max)
MAXIMUM FUEL
ENRICHMENT %
PERSON-
DOSE
AMZDNE063
AMZDFX063
Unit 3
8/08/09
13.61
51,122
4.288
0.108
AMZDNE064
AMZDFX064
Unit 3
8/21/09
13.61
51,122
4.289
0.094
AMZDNE065
AMZDFX065
Unit 3
8/28/09
13.84
49,692
4.381
0.096
AMZDNE066
AMZDFX066
Unit 3
9/04/09
13.86
49,692
4.384
0.106
AMZDNE067
AMZDFX067
Unit 3
9/11/09
13.88
49,692
4.387
0.104
AMZDNE068
AMZDFX068
Unit 2
1/29/10
2.73
49,797
4.387
0.099
AMZDNE069
AMZDFX069
Unit 2
2/05/10
2.73
49,797
4.384
0.097
AMZDNE070
AMZDFX070
Unit 2
2/12/10
2.73
49,797
4.390
0.096
AMZDNE071
AMZDFX071
Unit 2
2/26/10
14.02
49,487
4.384
0.091
AMZDNE072
AMZDFX072
Unit 2
3/05/10
14.02
49,487
4.386
0.102
AMZDNE073
AMZDFX073
Unit 2
3/12/10
13.97
49,487
4.390
0.089
AMZDNE074
AMZDFX074
Unit 1
8/07/10
2.80
51,421
4.401
0.084
AMZDNE075
AMZDFX075
Unit 1
8/13/10
2.80
51,528
4.402
0.060
AMZDNE076
AMZDFX076
Unit 1
8/20/10
2.80
51,529
4.400
0.062
AMZDNE077
AMZDFX077
Unit 1
9/03/10
2.81
2,548
4.407
0.060
AMZDNE078
AMZDFX078
Unit 1
9/10/10
2.41
53,779
4.388
0.059
- 6 -
LOADING
ORDER
VCC
ID No.
Canister
ID No.
Unit
DATE
ON PAD
HEAT LOAD
(kW)
BURNUP
MWd/MTU (max)
MAXIMUM FUEL
ENRICHMENT %
PERSON-
DOSE
AMZDNE079
AMZDFX079
Unit 3
1/28/11
13.01
2,283
4.406
0.169
AMZDNE080
AMZDFX080
Unit 3
2/04/11
2.73
50,399
4.401
0.117
AMZDNE081
AMZDFX081
Unit 3
2/11/11
2.59
50,399
4.404
0.086
AMZDNE082
AMZDFX082
Unit 3
2/25/11
2.58
50,457
4.401
0.074
AMZDNE083
AMZDFX083
Unit 3
3/04/11
2.62
51,402
4.403
0.061
AMZDNE084
AMZDFX084
Unit 3
3/11/11
2.66
51,402
4.404
0.076
AMZDNE085
AMZDFX085
Unit 2
7/29/11
14.03
51,119
4.396
0.109
AMZDNE086
AMZDFX086
Unit 2
8/06/11
14.04
51,119
4.400
0.140
AMZDNE087
AMZDFX087
Unit 2
8/12/11
14.06
51,116
4.391
0.108
AMZDNE088
AMZDFX088
Unit 2
8/26/11
14.06
51,116
4.407
0.106
AMZDNE089
AMZDFX089
Unit 2
9/02/11
14.05
51,046
4.400
0.101
AMZDNE090
AMZDFX090
Unit 1
1/20/12
13.89
48,347
4.394
0.138
AMZDNE091
AMZDFX091
Unit 1
1/27/12
13.90
47,489
4.392
0.119
AMZDNE092
AMZDFX092
Unit 1
2/10/12
13.91
49,253
4.390
0.118
AMZDNE093
AMZDFX094
Unit 1
2/17/12
13.90
48,750
4.392
0.100
AMZDNE094
AMZDFX096
Unit 1
2/24/12
13.92
48,388
4.394
0.089
- 7 -
LOADING
ORDER
VCC
ID No.
Canister
ID No.
Unit
DATE
ON PAD
HEAT LOAD
(kW)
BURNUP
MWd/MTU (max)
MAXIMUM FUEL
ENRICHMENT %
PERSON-
DOSE
AMZDNE095
AMZDFX095
Unit 1
8/18/12
13.79
51,957
4.406
0.104
AMZDNE096
AMZDFX093
Unit 1
8/24/12
13.77
49,876
4.407
0.085
AMZDNE097
AMZDFX097
Unit 1
8/31/12
13.77
49,876
4.412
0.095
AMZDNE098
AMZDFX098
Unit 1
9/07/12
13.74
49,876
4.404
0.084
AMZDNE099
AMZDFX099
Unit 2
2/09/13
13.08
49,876
4.391
0.135
100
AMZDNE100
AMZDFX100
Unit 2
2/15/13
13.08
49,886
4.655
0.109
101
AMZDNE101
AMZDFX101
Unit 2
2/25/13
13.08
49,895
4.655
0.113
2
AMZDNE102
AMZDFX103
Unit 2
05/10/13
13.17
54,062
4.646
0.155
103
AMZDNE103
AMZDFX106
Unit 2
05/17/13
13.26
50,058
4.656
0.086
104
AMZDNE104
AMZDFX104
Unit 2
05/24/13
14.86
48,548
4.206
0.113
105
AMZDNE105
AMZDFX105
Unit 3
08/13/13
13.62
54,507
4.410
0.136
106
AMZDNE106
AMZDFX102
Unit 3
08/24/13
13.62
54,507
4.406
0.191
107
AMZDNE107
AMZDFX107
Unit 3
08/30/13
13.43
54,507
4.403
0.075
108
AMZDNE108
AMZDFX108
Unit 3
09/30/13
13.45
54,507
4.401
0.136
109
AMZDNE109
AMZDFX109
Unit 3
2/13/13
13.44
54,507
4.407
0.156
110
AMZDNE110
AMZDFX110
Unit 3
2/14/14
13.42
2,971
4.402
0.102
- 8 -
LOADING
ORDER
VCC
ID No.
Canister
ID No.
Unit
DATE
ON PAD
HEAT LOAD
(kW)
BURNUP
MWd/MTU (max)
MAXIMUM FUEL
ENRICHMENT %
PERSON-
DOSE
111
AMZDNE111
AMZDFX111
Unit 3
2/21/14
13.54
48,507
4.404
0.107
2
AMZDNE112
AMZDFX112
Unit 3
2/28/14
13.55
48,704
4.409
0.085
113
AMZDNE113
AMZDFX113
Unit 3
03/07/14
13.56
48,501
4.404
0.070
114
AMZDNE114
AMZDFX114
Unit 3
05/16/14
13.4
49,388
4.411
0.100
115
AMZDNE115
AMZDFX115
Unit 3
05/27/14
13.39
49,388
4.412
0.073
116
AMZDNE116
AMZDFX116
Unit 3
05/30/14
13.33
45,139
4.409
0.084
117
AMZDNE117
AMZDFX117
Unit 2
07/18/14
2.96
54,554
4.381
0.089
118
AMZDNE118
AMZDFX118
Unit 2
07/25/14
2.96
54,554
4.391
0.078
119
AMZDNE119
AMZDFX119
Unit 2
08/01/14
2.95
54,554
4.385
0.094
20
AMZDNE120
AMZDFX120
Unit 2
08/08/14
13.17
54,554
4.390
0.075
21
AMZDNE121
AMZDFX121
Unit 2
08/29/14
13.22
54,542
4.386
0.091
2
AMZDNE122
AMZDFX122
Unit 2
09/05/14
13.31
54,542
4.654
0.070
23
AMZDNE123
AMZDFX123
Unit 1
2/13/15
2.70
48,792
4.407
0.089
24
AMZDNE124
AMZDFX124
Unit 1
2/20/15
2.75
51,006
4.404
0.102
25
AMZDNE125
AMZDFX125
Unit 1
2/27/15
13.09
49,387
4.515
0.124
- 9 -
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
Casks #1 through 16 were loaded to CoC No. 1015, Amendment 2
Casks #17 through 34 were loaded to CoC No. 1015, Amendment 3
Casks #35 through 58 were loaded to CoC No. 1015, Amendment 4
Casks #59 through 125 were loaded to CoC No. 1015, Amendment 5
All casks are currently maintained under CoC No. 1015, Amendment 5, and FSAR Revision 10