IR 05000458/2014008

IR 05000458/2014008; and 07200049/2014001; on 08/19 - 22/2014; River Bend Station and Independent Spent Fuel Storage Installation (Isfsi); Routine ISFSI Inspection Report

ML14262A413
Person / Time
Site:	River Bend
Issue date:	09/19/2014
From:	Ray Kellar Division of Nuclear Materials Safety IV
To:	Olson E Entergy Operations
Kellar R
References
IR-2014-001, IR-2014-008
Download: ML14262A413 (20)

Text

September 19, 2014

SUBJECT:

RIVER BEND STATION AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI) INSPECTION REPORT 05000458/2014008 AND 07200049/2014001

Dear Mr. Olson:

This letter refers to a routine inspection conducted on August 19-22, 2014, 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 August 21, 2014 with you and 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 International HI-STORM 100 Certificate of Compliance 1014, the HI-STORM 100 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 No.: 05000458, 07200049 Licenses No.: NPF-47

Enclosure:

Inspection Report 05000458/2014008 and 07200049/2014001

w/attachments:

1. Supplemental Information 2. Loaded Casks at the River Bend ISFSI

SUMMARY OF FINDINGS

IR 05000458/2014008; and 07200049/2014001; 08/19-22/2014; River Bend Station 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

River Bend Station (RBS) Independent Spent Fuel Storage Installation (ISFSI) stored nineteen loaded Holtec HI-STORM 100S Version B casks and two HI-STORM 100S casks at the time of the routine inspection. RBS was loading the third canister in their four cask loading campaign.

Inspectors observed loading operations associated with cask number 22 at the time of the routine inspection. The licensee utilized a general Part 72 license in accordance with the Holtec HI-STORM 100 System, approved under Certificate of Compliance 1014, License Amendment 5 and Final Safety Analysis Report (FSAR), Revision 7. The version of the Holtec systems used by the licensee included the MPC-68, a 68 fuel bundle multi-purpose canister (MPC), designed to hold 68 boiling water reactor (BWR) fuel assemblies. The ISFSI consisted of one concrete pad that could accommodate 40 casks. The storage casks were located inside the Part 50 facilitys protected area (PA).

The reactor at RBS is a BWR with a core containing 624 fuel assemblies. Refueling outages are performed approximately every 24 months. The spent fuel pool capacity at RBS is 3,104 spaces. After the current loading campaign is complete, spent fuel pool will contain 946 spaces that are open and available for use. The licensee has maintained the ability to perform a full core off-load.

REPORT DETAILS

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

An on-site review of Quality Assurance (QA) audits and surveillance reports related to dry cask storage activities at the River Bend Station ISFSI was performed by NRC inspectors. Since the last NRC inspection in September 2012, RBS had not issued a completed ISFSI QA audit report. The last ISFSI QA audit was performed in August 2012 and was reviewed in the last ISFSI inspection report. At the time of this routine ISFSI inspection RBS had completed the 2014 ISFSI QA audit but the report had not been issued yet. Two licensee surveillances documented in Oversight Observation Checklist (O2C) reports were reviewed during this inspection. The OC2 reports documented QA observations made in ISFSI areas of radiation protection and maintenance. The surveillances did not result in any QA findings.

(2) Radiological Conditions Related to Stored Casks

The RBS ISFSI was located approximately 500 feet south of the reactor building within the plant protected area (PA). The pad was roughly 60 feet wide and 209 feet long designed to hold 40 HI-STORM 100S spent fuel storage casks configured in a 4 by 10 array. The pad was also designed to contain four extra cask spaces which were intended to facilitate cask movement operations. The RBS ISFSI was protected on all sides by an exclusion area fence, which was properly posted as a Radioactive Materials Area. No flammable or combustible materials, debris, or notable vegetative growth were observed inside the ISFSI area. Twenty-one casks were loaded with spent fuel at the time of the inspection. The current ISFSI loading campaign was scheduled to add an additional two casks to the pad, bringing the total number to 23 by the end of September 2014. The inspectors found the 21 HI-STORM casks to be in good physical condition.

Radiological conditions at the RBS ISFSI were determined from the most recent semi-annual radiological survey and records from three years of optically stimulated luminescence dosimeter (OSLD) monitoring results. There were eight OSLD monitoring locations that were positioned along the four sides of the ISFSI exclusion area fence, two OSLDs per side.

A RBS radiation protection (RP) technician accompanied the NRC inspectors during the walk-down of the ISFSI pad area. A radiological survey was performed by the RP technician with an ion-chamber to record gamma exposure rates in milli-roentgens per hour (mR1/h). The RP technician also carried a survey meter that measured neutron exposure in units of dose equivalent, millirem per hour (mrem/h).

The NRC inspector carried a Ludlum Model 19 scintillation detector 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, at selected areas between casks, and at HI-STORM lower vent locations.

General area gamma background readings outside the power plant prior to entry into the ISFSI pad area were 6 µR/h. The 21 storage casks were situated along the eastern edge and northeastern corner of the ISFSI pad. Radiation readings taken along the fence-line showed radiation levels ranging from 20 to 44 µR/h. General area measurements on the pad ranged from 60 to 300 µR/h. Several cask lower vent measurements were taken. The vent measurements ranged from 0.3 to 1.1 mR/h gamma and 0.5 to 1.0 mrem/h neutron. The measurements recorded by the NRC inspector and RP technician confirmed the most recent semi-annual ISFSI survey. The radiological conditions of the ISFSI were as expected for the age and heat-load of the 21 (at the time of inspection) loaded spent fuel storage casks. The licensee was properly posting and controlling the ISFSI pad area consistent with 10 CFR Part 20 requirements.

The licensee provided personnel dose estimates associated with the first two casks loaded during the current ISFSI loading campaign, which began in late July 2014.

The estimated worker doses ranged from 0.334 to 0.194 person-rem per cask. The dose estimates were consistent with worker doses seen in previous loading campaigns at RBS. Personnel radiation doses were estimated using electronic

1 For the purposes of making comparisons between NRC regulations based on dose-equivalent and measurements made in Roentgens, it may be assumed that one Roentgen equals one rem. (http://www.nrc.gov/about-nrc/radiation/protects-you/hppos/qa96.html)personnel dosimeters (EPDs) that were sensitive to both gamma and neutron radiation.

(3) Environmental Radiological Monitoring Program

The primary purpose of the RBS 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. By design, there were no airborne or liquid effluents released from the RBS ISFSI. NRC reviewed the Spent Fuel Storage Radioactive Effluent Release Reports for 2012 (ML13064A382)and 2013 (ML14064A206) for RBS, which confirmed that the RBS ISFSI did not produce any effluent radioactive releases during 2012 or 2013.

The REMP monitors direct radiation impacts using thermoluminescent dosimeter (TLD) monitoring. The ISFSI was monitored for direct radiation using OSLDs.

TLDs and OSLDs report in the same units and are considered to be functionally equivalent. The OSLD data for the ISFSI and the TLD data for the REMP were handled by different programs at RBS for different purposes. The ISFSI OSLD monitoring was performed by the RP department to track radiological exposures at the ISFSI boundary to ensure that NRC occupational limits for unmonitored individuals were not exceeded. The REMP monitoring was performed to provide an annual assessment of the licensees total impacts to the environment, which includes contributions from the ISFSI.

OSLDs were placed at eight monitoring locations on the fence around the ISFSI.

The OSLD monitoring results from 2012, 2013, and 2014 were reviewed by NRC inspectors (see Table 1, below). The OSLDs were collected and replaced twice a year.

Table 1 OSLD Monitoring Results for River Bend ISFSI in mR/yr OSLD #

Location 2012 2013 20142 Z58 ISFSI North Fence 1

Z60 ISFSI North Fence 2 115 116 108 Z61 ISFSI South Fence 1

Z62 ISFSI South Fence 2

Z63 ISFSI East Fence 1

Z64 ISFSI East Fence 2

Z65 ISFSI West Fence 1

Z66 ISFSI West Fence 2

NRC Inspectors verified the radiation exposure rates at each OSLD monitoring location during the ISFSI walk-down. The highest reported dose rate, 116 mrem per year, was measured at the ISFSI North Fence 2 monitoring location. All accessible areas near the RBS ISFSI boundary were below the 10 CFR 20.1502(a)(1) limit, of 500 mrem per year for unmonitored workers.

2 The annual radiological exposure data for 2014 was estimated from actual monitoring data for the first half of the year.

The yearly results of the REMP were issued in an Annual Radiological Environmental Operating Report (AREOR). NRC reviewed the RBS AREORs for 2012 (ML12157A078), issued May 1, 2013 and 2013 (ML14126A007), issued May 1, 2014. The AREORs did not include the OSLD direct radiation monitoring results for the ISFSI, but provided reporting and analyses for the REMP TLD monitoring results.

The RBS ISFSI was located approximately 0.1 miles from the reactor building in the in the southern (S) REMP monitoring sector. Two of the 24 total REMP TLD monitoring sites were at site boundary locations in reasonably close proximity to the RBS ISFSI: TJ1, 0.9 miles from the reactor in the southern (S) sector and TK1, 0.6 miles from the reactor, in the south-southwest (SSW) sector. TEC was a control monitoring station located 9.9 miles east of the RBS reactor building. This TLD can be treated as a radiological background.

Table 2, TLD Monitoring Results near RBS ISFSI in mR/yr TLD#

Station and Location 2012 2013 TJ1 S Sector, 0.9 miles from reactor 53.2 54.7 TK1 SSW Sector, 0.6 miles from reactor 55.0 58.5 TEC (Control)

E Sector, 9.9 miles from reactor 57.8 57.9

Both REMP TLD monitoring results in close proximity to the RBS ISFSI were close to background (control levels). The most elevated readings were from the TK1 monitoring location for the years reviewed. That monitoring location was slightly below background in 2012 and slightly above background for 2013. Correcting the 2013 value for background yielded a net annual exposure rate of 0.6 mR1. This was well below the 10 CRF 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 site boundary locations was minimal.

(4) Records Related to Fuel Stored in the Casks

A site review of dry fuel storage records for eight randomly selected loaded casks at the RBS ISFSI was performed to determine whether adequate descriptions of the spent fuel was documented as a permanent record as required by 10 CFR 72.212(b)(12). In addition, the fuel contents of the first two casks loaded during the current four cask loading campaign were verified against Holtec CoC 1014 Technical Specification (TS) requirements for BWR fuel assemblies loaded into an MPC-68 canister. The spent fuel contents of the eight randomly selected casks were recorded in documents that included procedure REP-0061, Fuel Selection for Dry Storage, dated November 18, 2005 and October 22, 2008; and EN-DC-215, Fuel Selection for Holtec Dry Cask Storage, Revs. 3 and 5. These procedures included multi-purpose canister (MPC) 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. A complete set of forms were reviewed for the first two casks loaded of the current campaign and eight of the previously loaded MPCs. Select fuel data is tracked by cask on Attachment 2 of this inspection report. RBS was in compliance with all applicable license and FSAR requirements for fuel stored at the ISFSI and met retrievability requirements for storage of spent fuel records.

(5) Technical Specification 3.1.2, Cask Temperature Monitoring

Technical Specification (TS) 3.1.2 included a surveillance requirement for either a daily inspection of the inlet and outlet vents for blockage or daily verification that the temperature difference between the HI-STORM outlet temperature and ISFSI ambient temperature was 126 degrees F for all casks loaded under Certificate of Compliance (CoC) Amendment 2 (casks 1-7) and 137 degrees F for casks loaded under CoC Amendment 5 (casks 8-21). None of the 21 total HI-STORM casks placed on the RBS ISFSI at the time of the inspection were equipped with remote temperature monitoring equipment. The vent inspection surveillances were performed using Surveillance Test Procedure STP-000-0001, Daily Operating Logs, Revisions 72, 74, and 76. Documentation was reviewed for three randomly selected weeks, the weeks of December 16, 2012, March 17, 2013, and November 24, 2013, for compliance with the TS surveillance. Of the three weeks selected for review, the surveillance requirement was met by performing daily vent inspections and logging the results into the aforementioned operating log. No cask inlet or outlet vents were reported as being blocked.

(6) Corrective Action Program

A list of Condition Reports (CRs) issued since the last NRC inspection in September of 2012 was provided by the licensee for the cask handling crane and the ISFSI.

Issues were processed in accordance with Procedure EN-LI-102, Corrective Action Process, Revision 23. When a problem was identified the licensee documented the issue as a CR in the licensees corrective action program (CAP).

Of the list of CRs provided relating to the ISFSI and the cask handling crane, approximately 15 CRs were selected by the NRC inspectors for further review. The CRs related to a variety of issues. The CRs 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 crane. No NRC concerns were identified related to the CRs reviewed.

(7) Preparation of Loading Activities

The inspectors requested documentation related to maintenance of the fuel building cask handling crane, 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 cask handling crane was inspected on an annual basis in accordance with American Society of Mechanical Engineers (ASME) B30.2 prior to the 2014 loading campaign. RBS utilized Procedure PM MHF-CRN2, Crane Periodic Inspection Mechanical, dated April 24, 2012 and Work Order (WO) 52506664 to perform the annual maintenance in June 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 lift yoke, HI-STORM brackets, and the HI-TRAC lifting trunnions.

Documentation reviewed included WO 52494786, WO 52472971, WO 00383578, WO 00382024, and WO 00382023 and associated non-destructive examination documentation associated with the testing. All equipment passed the magnetic particle, liquid penetrant, and dimensional testing.

Calibration documentation of the hydrostatic pressure gages 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. Documentation of the calibration was recorded in WO 00388250.

(8) HI-STORM 100 Cask Yearly Maintenance

Holtec Final Safety Analysis Report (FSAR), Section 9.2, Maintenance Program, specified the HI-STORM maintenance schedule in Table 9.2.1. Among other tasks, the schedule called for annual visual inspection of the storage casks external surfaces and identification markings for signs of damage or degradation. NRC inspectors reviewed the documentation related to the annual visual examination of the HI-STORM casks for 2012 and 2013. Those documents included the work orders and filled out copies of Procedure WM-105-00, Attachment 1, HI-STORM Annual Inspection Form, dated, November 10, 2010. Those visual examination checklists included 25 points of inspection that were verified as satisfactory, unsatisfactory, or not applicable (N/A). For the years reviewed, one instance of an unsatisfactory condition was identified: A bolt holding a vent air screen in place was broken and needed to be replaced during the 2013 inspection. A work order was initiated to replace the broken bolt. The NRC inspectors determined that the licensees yearly maintenance activities and records satisfied the requirements of FSAR Section 9.2.

(9) Cask Loading Observations

Various loading activities were observed by the NRC inspectors during the course of the routine ISFSI inspection. RBS was in the process of loading canister #22 at the time of the inspection. The NRC inspectors observed the fuel movement activities to place spent fuel assemblies into canister #22. 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 nine to ten minutes.

Selected welding and non-destructive examination activities were observed during the loading associated with canister #22. 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 and subsequent passes. The licensee monitored for combustible gas every ten minutes utilizing an in-line monitor through the MPC vent port until the final weld pass had been completed. Additionally, the NRC inspectors observed the non-destructive dye penetrant exams conducted on the shell to lid welds. No weld indications were identified from the various non-destructive examinations.

Other activities that were observed by NRC inspectors during the loading of canister

1. 22 included the lifting the HI-TRAC transfer cask and fully loaded MPC out of the spent fuel pool. The licensees cask handling crane was able to handle the heavy load without problems.

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 Holtec HI-STORM 100 cask systems design basis. RBS had not made any changes to the Appendix D 72.212 Report since the last ISFSI inspection in September 2012. The Appendix D 72.212 Report with RBS specific information was at Revision 2, dated October 20, 2008.

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 since the last NRC routine ISFSI inspection were reviewed to determine compliance with regulatory requirements.

RBS had not performed any 72.48 screens associated with the ISFSI equipment or operations. Additionally, no modifications had been performed on the cask handling crane which 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 September of 2012.

b. Findings

No findings were identified.

4OA6 Meetings, Including Exit

Exit Meeting Summary

On August 21, 2014, the lead inspector presented the inspection results to Mr. Richard Gadbois, General Manager of Plant Operations, 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

J. Blair, Reactor Engineer T. Bolke, Senior Licensing Engineer, Regulatory Assurance J. Campbell, Senior Project Manager, ISFSI J. Clark, Manager, Regulatory Assurance B. Cole, Manager, Radiation Protection L. Dautel, ALARA Supervisor, Radiation Protection P. Ellis, RP Lead Tech, Radiation Protection R. Gadbois, General Manager of Plant Operations M. Heimberger, NDE Inspector, Acuen K. Huffstatler, Senior Licensing Engineer, Regulatory Assurance M. Mella, Reactor Engineer D. Meyers, Welding Supervisor, PCI S. Patterson, Dosimetry, Radiation Protection

INSPECTION PROCEDURES USED

IP 60855.1

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

Drawings

NUMBER

TITLE

DATE

RBS-1408-0193

000 OS Dry Fuel Cask Storage Area

08/20/14

Procedures

NUMBER

TITLE

REVISION

EN-LI-102

Corrective Action Process

Rev. 23

EN-LI-100

Process Applicability Determination

Rev. 13

EN-LI-112

CFR 72.48 Evaluations

Rev. 11

PM-MHF-CRN2

Crane Periodic Inspection Mechanical

04/24/12

EN-FAP-OU-108

Fuel Handling Process

Rev. 5

EN-DC-215

Fuel Selection for Holtec Dry Cask Storage

Rev. 3, 5

DFS-0140

MPC Forced Helium Dehydration Operation

Rev. 4

DFS-0005

DFS Rigging Plan

Rev. 302

DFS-0003

MPC Transfer Operations and HI-STORM Transport

Rev. 004

DFS-0002

Dry Fuel Cask Loading

Rev. 306

EN-RE-210

BWR Reactor Core and MPC Cask Fuel Verification

Rev. 3

REP-0061

Fuel Selection for Dry Storage

11/18/05,

10/22/08

STP-000-0001

Daily Operating Logs

Rev. 72, 74, 76

VM-105-00

HI-STORM Annual Inspection Form

11/10/10

Design Basis Documents

NUMBER

TITLE

REVISION

Appendix D River Bend Station 10 CFR 72.212

Report Utilizing the HI-STORM 100 System

Rev. 2

Certificate of Compliance 72-1014 HI-STORM 100

Cask System

Amendment 5

Holtec International FSAR for the HI-STORM 100

Cask System

Rev. 7

- 3 -

Miscellaneous Documents

NUMBER

TITLE

REVISION / DATE

QA-20-2012-

RBS-1

Quality Assurance Audit Report

09/06/12

2480023

PG&E/NUPIC Joint Audit of Holtec International

01/03/14

MW-105-00

HI-STORM Container Inspection

11/10/10

River Bend Station Annual Radiological Environmental

Operating Report for 2012

05/01/13

River Bend Station Annual Radiological Environmental

Operating Report for 2013

05/01/14

Oversight Observation Checklists

O2C-RBS-2012-0167

O2C-RBS-2012-0169

Work Orders

WO 5250664

WO 52494786

WO 52472971

WO 00383578

WO 00382024

WO 00382023

WO 00388250

Condition Reports

CR-2014-4023

CR-2014-3963

CR-2014-3586

CR-2014-3326

CR-2014-3164

CR-2014-3114

CR-2014-3074

CR-2014-2714

CR-2014-1992

CR-2013-1274

CR-2013-0748

CR-2014-4022

CR-2014-3211

CR-2012-6443

CR-2012-6153

CR-2014-2714

CR-2014-3758

- 5 -

LIST OF ACRONYMS

ADAMS

Agencywide Documents Access and Management System

ANSI

American National Standards Institute

AREOR

Annual Radiological Environmental Operating Report

ASME

American Society of Mechanical Engineers

BWR

Boiling Water Reactor

CAP

Corrective Action Program

CoC

Certificate of Compliance

CR

Condition Report

CFR

Code of Federal Regulations

DLR

Dose of Legal Record

DNMS

Division of Nuclear Material Safety

EPD

Electronic Personnel Dosimeter

FSAR

Final Safety Analysis Report

IMC

Inspection Manual Chapter

ISFSI

Independent Spent Fuel Storage Installation

kW

kilo-watt

mR/h

milliroentgen per hour

mrem/h

millirem per hour

µR/h

microroentgen per hour

MPC

Multi-Purpose Canister

MWd/MTU

megawatt days per metric ton uranium

NRC

U.S. Nuclear Regulatory Commission

PA

Protected Area

O2C

Oversight Observation Checklist

OSLD

Optically Stimulated Luminescence Dosimeter

QA

Quality Assurance

RBS

River Bend Station

REMP

Radiological Environmental Monitoring Program

RP

radiation protection

TBD

To Be Determined

TLD

thermoluminescent dosimeter

TS

Technical Specification

ATTACHMENT 2:

LOADED CASKS AT THE RIVER BEND NUCLEAR STATION ISFSI

LOADING

ORDER

MPC

SERIAL No.

HI-STORM

No.

DATE

ON PAD

HEAT LOAD

(kW)

BURNUP

MWd/MTU (max)

MAXIMUM FUEL

ENRICHMENT %

PERSON-REM

DOSE

Serial No.

Serial No.

2/29/05

16.55

39,391

3.34

1.028

Serial No.

Serial No.

06/22/06

16.99

39,402

3.33

1.036

Serial No.

Serial No.

07/19/06

19.16

41,203

3.35

0.845

Serial No.

Serial No.

07/20/07

18.03

41,568

3.35

0.901

Serial No.

Serial No.

08/01/07

17.43

40,412

3.35

0.570

Serial No.

Serial No.

08/17/07

18.76

41,886

3.35

0.580

Serial No.

Serial No.

11/15/07

18.98

41,109

3.35

0.637

Serial No.

Serial No.

236

11/06/08

9.85

31,010

2.49

0.720

Serial No.

216

Serial No.

313

11/21/08

2.34

34,446

3.01

0.477

Serial No.

217

Serial No.

314

2/09/08

2.32

33,670

3.07

0.504

Serial No.

218

Serial No.

315

2/16/08

15.97

40,496

3.36

0.503

Serial No.

295

Serial No.

2

08/12/10

14.81

38,983

3.54

0.362

Serial No.

296

Serial No.

443

08/26/10

14.76

38,973

3.54

0.246

Serial No.

297

Serial No.

444

09/15/10

14.87

40,944

3.54

0.281

Serial No.

304

Serial No.

460

09/27/10

14.85

39,320

3.54

0.199

Serial No.

375

Serial No.

2

08/25/12

17.51

44,253

3.88

0.307

-2-

LOADING

ORDER

MPC

SERIAL No.

HI-STORM

No.

DATE

ON PAD

HEAT LOAD

(kW)

BURNUP

MWd/MTU (max)

MAXIMUM FUEL

ENRICHMENT %

PERSON-REM

DOSE

Serial No.

376

Serial No.

603

09/14/12

17.37

43,604

3.87

0.225

Serial No.

377

Serial No.

604

09//28/12

17.40

43,608

3.88

0.215

Serial No.

378

Serial No.

605

10/10/12

17.34

43,480

3.88

0.213

Serial No.

459

Serial No.

806

08/03/14

14.65

2,890

3.86

TBD

Serial No.

460

Serial No.

807

08/15/14

14.65

44,245

3.86

TBD

Serial No.

461

Serial No.

808

08/28/14

14.95

44,199

3.87

TBD

Serial No.

2

Serial No.

809

09/11/14

14.54

44,867

3.87

TBD

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

TBD means to be determined from worker TLDs

Casks 1 - 7 were loaded under Certificate of Compliance, Amendment 2; Holtec Final Safety Analysis Report, Revision 3

Casks 8 - 23 were loaded under Certificate of Compliance, Amendment 5; Holtec Final Safety Analysis Report, Revision 7