|
---|
Category:Inspection Report
MONTHYEARIR 05000220/20243022024-10-0303 October 2024 Initial Operator Licensing Examination Report 05000220/2024302 IR 05000220/20240052024-08-29029 August 2024 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2024005 and 05000410/2024005) IR 05000220/20240102024-08-22022 August 2024 Age-Related Degradation Inspection Report 05000220/2024010 and 05000410/2024010 IR 05000220/20240022024-08-0505 August 2024 Integrated Inspection Report 05000220/2024002 and 05000410/2024002 IR 05000220/20244012024-05-30030 May 2024 Security Baseline Inspection Report 05000220/2024401 and 05000410/2024401(Cover Letter Only) IR 05000220/20240012024-05-10010 May 2024 Integrated Inspection Report 05000220/2024001 and 05000410/2024001 IR 05000220/20230062024-02-28028 February 2024 Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2, (Reports 05000220/2023006 and 05000410/2023006) IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 IR 05000220/20234022023-11-28028 November 2023 Security Baseline Inspection Report 05000220/2023402 and 05000410/2023402 IR 05000220/20234202023-11-0101 November 2023 – Security Baseline Inspection Report 05000220/2023420 and 05000410/2023420 IR 05000220/20230032023-10-25025 October 2023 Integrated Inspection Report 05000220/2023003 and 05000410/2023003 IR 05000220/20235012023-10-17017 October 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000220/2023501 and 05000410/2023501 IR 05000220/20230112023-10-16016 October 2023 Comprehensive Engineering Team Inspection Report 05000220/2023011 and 05000410/2023011 IR 05000220/20233032023-09-20020 September 2023 Retake Operator Licensing Examination Report 05000220/2023303 IR 05000220/20230052023-08-31031 August 2023 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2023005 and 05000410/2023005) IR 05000220/20234012023-08-0808 August 2023 Cyber Security Inspection Report 05000220/2023401 and 05000410/2023401 (Cover Letter Only) IR 05000220/20230022023-08-0101 August 2023 Integrated Inspection Report 05000220/2023002 and 05000410/2023002 IR 05000220/20230102023-06-29029 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000220/2023010 and 05000410/2023010 IR 05000410/20233022023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000410/2023302 IR 05000220/20230012023-05-0505 May 2023 Integrated Inspection Report 05000220/2023001 and 05000410/2023001 IR 05000220/20233012023-03-29029 March 2023 Initial Operator Licensing Examination Report 05000220/2023301 IR 05000220/20220062023-03-0101 March 2023 Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2 (Reports 05000220/2022006 and 05000410/2022006) IR 05000220/20220042023-01-23023 January 2023 Integrated Inspection Report 05000220/2022004 and 05000410/2022004 IR 05000220/20220102022-11-22022 November 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000220/2022010 and 05000410/2022010 IR 05000220/20220032022-11-0404 November 2022 Integrated Inspection Report 05000220/2022003 and 05000410/2022003 IR 05000220/20220052022-08-31031 August 2022 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Reports 05000220/2022005 and 05000410/2022005) IR 05000220/20224012022-08-30030 August 2022 Security Baseline Inspection Report 05000220/2022401 and 05000410/2022401 IR 05000220/20220022022-08-0808 August 2022 Integrated Inspection Report 05000220/2022002 and 05000410/2022002 and Independent Spent Fuel Storage Installation Report 07201036/2022001 IR 05000220/20220012022-04-29029 April 2022 Integrated Inspection Report 05000220/2022001 and 05000410/2022001 IR 05000220/20210062022-03-0202 March 2022 Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2 (Reports 05000220/2021006 and 05000410/2021006) IR 05000220/20210042022-01-26026 January 2022 Integrated Inspection Report 05000220/2021004 and 05000410/2021004 IR 05000220/20210122022-01-10010 January 2022 Biennial Problem Identification and Resolution Inspection Report 05000220/2021012 and 05000410/2021012 IR 05000220/20210032021-11-0909 November 2021 Integrated Inspection Report 05000220/2021003 and 05000410/2021003 and Independent Spent Fuel Storage Installation Report 07201036/2021001 IR 05000220/20215012021-10-14014 October 2021 Emergency Preparedness Biennial Exercise Inspection Report 05000220/2021501 and 05000410/2021501 IR 05000220/20214012021-09-0101 September 2021 Material Control and Accounting Program Inspection Report 05000220/2021401 and 05000410/2021401 (Letter Only) IR 05000220/20210052021-09-0101 September 2021 Updated Inspection Plan for the Nine Mile Point Nuclear Station, Units 1 and 2 (Reports 05000220/2021005 and 05000410/2021005) IR 05000220/20210102021-08-24024 August 2021 Triennial Fire Protection Inspection Report 05000220/2021010 and 05000410/2021010 IR 05000220/20210022021-08-10010 August 2021 Integrated Inspection Report 05000220/2021002 and 05000410/2021002 and Independent Spent Fuel Storage Installation Report 07201036/2021002 IR 05000220/20214022021-06-22022 June 2021 Security Baseline Inspection Report 05000220/2021402 and 05000410/2021402 IR 05000410/20213022021-05-12012 May 2021 Initial Operator Licensing Examination Report 05000410/2021302 IR 05000220/20210012021-05-0505 May 2021 Integrated Inspection Report 05000220/2021001 and 05000410/2021001 IR 05000220/20210112021-05-0404 May 2021 Temporary Instruction 2515/194 Inspection Report 05000220/2021011 and 05000410/2021011 IR 05000220/20200062021-03-0303 March 2021 Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2020006 and 05000410/2020006) IR 05000220/20200042021-02-11011 February 2021 Integrated Inspection Report 05000220/2020004 and 05000410/2020004 and Independent Spent Fuel Storage Installation Report 07201036/202004 IR 05000220/20203012021-01-25025 January 2021 Initial Operator Licensing Examination Report 05000220/2020301 ML20343A0112020-12-0909 December 2020 Security Inspection Report Cover Letter 05000220/2020420 and 05000410/2020420 IR 05000220/20204202020-12-0909 December 2020 Security Inspection Report 05000220/2020420 and 05000410/2020420 2020 Report IR 05000220/20200102020-11-24024 November 2020 Design Basis Assurance Inspection (Teams) Inspection Report 05000220/2020010 and 05000410/2020010 IR 05000220/20200032020-11-10010 November 2020 Integrated Inspection Report 05000220/2020003 and 05000410/2020003 2024-08-05
[Table view] Category:Letter
MONTHYEARML24268A3382024-10-16016 October 2024 Issuance of Amendment No. 253 Regarding the Modification of TS Surveillance Requirement 4.3.6.a Related to Adoption of TSTF-425, Revision 3 RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP2L2890, Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6)2024-10-0404 October 2024 Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6) ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing IR 05000220/20243022024-10-0303 October 2024 Initial Operator Licensing Examination Report 05000220/2024302 ML24190A0012024-09-26026 September 2024 Issuance of Amendment Nos. 252 and 197 Regarding the Revision to Technical Specification Design Features Section to Remove Nine Mile Point Unit 3 Project Designation NMP1L3608, Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-09-20020 September 2024 Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024 Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000220/20240052024-08-29029 August 2024 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2024005 and 05000410/2024005) IR 05000220/20240102024-08-22022 August 2024 Age-Related Degradation Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3603, Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan2024-08-20020 August 2024 Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000220/20240022024-08-0505 August 2024 Integrated Inspection Report 05000220/2024002 and 05000410/2024002 ML24215A3002024-08-0202 August 2024 Operator Licensing Examination Approval NMP1L3601, Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-07-31031 July 2024 Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML24213A1412024-07-31031 July 2024 Requalification Program Inspection NMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024 Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations ML24198A0852024-07-16016 July 2024 Senior Reactor and Reactor Operator Initial License Examinations RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3584, License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2024-06-13013 June 2024 License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling IR 05000220/20244012024-05-30030 May 2024 Security Baseline Inspection Report 05000220/2024401 and 05000410/2024401(Cover Letter Only) ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 NMP1L3591, Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request2024-05-18018 May 2024 Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request NMP1L3589, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-05-16016 May 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable ML24158A2052024-05-15015 May 2024 Annual Radioactive Environmental Operating Report NMP1L3582, 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 22024-05-15015 May 2024 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 2 IR 05000220/20240012024-05-10010 May 2024 Integrated Inspection Report 05000220/2024001 and 05000410/2024001 RS-24-049, Updated Notice of Intent to Pursue Subsequent License Renewal Applications2024-05-0909 May 2024 Updated Notice of Intent to Pursue Subsequent License Renewal Applications RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024 Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds 05000410/LER-2024-001, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum2024-05-0101 May 2024 Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP1L3581, Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report2024-04-30030 April 2024 Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report NMP2L2877, 2023 Annual Environmental Operating Report2024-04-19019 April 2024 2023 Annual Environmental Operating Report NMP2L2878, Core Operating Limits Report2024-04-16016 April 2024 Core Operating Limits Report ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24092A3352024-04-0101 April 2024 NRC Office of Investigations Case No. 1-2023-002 ML24074A2812024-03-14014 March 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3577, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-03-13013 March 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable IR 05000220/20230062024-02-28028 February 2024 Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2, (Reports 05000220/2023006 and 05000410/2023006) IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 NMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation 05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater2024-01-30030 January 2024 Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 05000220/LER-2023-002, Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 122023-12-15015 December 2023 Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 12 NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station 2024-09-04
[Table view] |
Text
UNITED STATES NUGLEAR REGULATORY COMiIISSION
REGION I
.IOO 21OO RENAISSANCE BOULEVARD, SUITE
SUBJECT:
NINE MILE POINT NUCLEAR STATION - NRC INDEPENDENT SPENT FUEL sroRAGE TNSTALLATTON (lSFSl) INSPECTION REPORT NOS.
05000220t201 2009 AN D 05000 41 0 1201 2009
Dear Mr. Langdon:
On September 14,2012, the U.S. Nuclear Regulatory Commission (NRC) completed an ISFSI inspection at your Nine Mile Point Nuclear Station, Units 1 and 2. The enclosed inspection report documents the inspection results which were discussed on September 19, 2012, with Ken Phy, ISFSI Project Manager, and other members of your staff.
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license.
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
Based on the results of this inspection, no findings were identified.
ln accordance with 10 CFR Part 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of the NRC's document system (ADAMS). ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/(" >,4A -
Marc S. Ferdas. Chief Decommissioning Branch Division of Nuclear Materials Safety Docket Nos. : 50-220, 50-410, 72-1036 License Nos.: DPR-63, NPF-69 Enclosure: lnspection Report 0500022012012009 and 0500041012Q12O09 MAttachment: Supplementary Information cc w/encl: Distribution via ListServ
SUMMARY OF FINDINGS
lR 0500022012012009 and 0500041012012009:0712312012-0911412012; Nine Mile Point
Nuclear Station, Units 1 and 2; Preoperational Testing of lndependent Spent Fuel Storage f nstallations (lSFSl) at Operating Plants, Review of 10 CFR 72.212(b) Evaluations, and Operation of ISFSI's at Operating Plants.
This report covers the ISFSI operational dry run and initial loading inspection conducted by a team of six NRC inspectors. 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.
No findings were identified.
REPORT DETAILS
4. OTHER ACTTVTTTES (OA)
4OA5 Other Activities
.1 Preooerational Test Proqram (60854, 60854.1. and 60856)
a. Inspection Scope
The inspectors evaluated NMPNS's performance during NRC observed pre-operational dry run activities that were performed in order to fulfill requirements in Technical Specifications (TS) 1.1.6. The inspectors observed NMPNS dry run activities on July 23-26,2012, and August 27-31,2012. During the first week the inspectors observed cask processing activities including: blowdown, vacuum drying, helium backfilling, reflooding, gas sampling, welding, non-destructive examinations, and helium leak testing. During the second week the inspectors observed canister loading operations including:
insertion and removal of the dry shielded canister (DSC) from the transfer cask (TC),movement of the TC/DSC into the spent fuel pool, movement of a dummy fuel assembly into several locations in the DSC, removal of the TC/DSC from the spent fuel pool, moving of the TCIDSC to the cask processing area, down-ending the TC onto the transporter, transporting the TC to the ISFSI pad, and retrieving and inserting a weighted DSC into a horizontalstorage module (HSM).
The inspectors reviewed DSC loading, unloading, and processing procedures to ensure that they contained commitments and requirements specified in the Certificate of Compliance (CoC), TS, Final SafetyAnalysis Report (FSAR), and Title 10 of the Code of Federal Regulations (CFR) Part7Z. The inspectors reviewed the ISFSI seismic calculations and the analysis of the heavy haul path from the reactor building to the ISFSI pad. Also, the inspectors reviewed fuel selection procedures to ensure they appropriately incorporated the requirements in the TS.
The inspectors evaluated NMPNS's compliance with the requirements of 10 CFR 72.212 and 10 CFR72.48. The inspectors verified NMPNS's written evaluations were in accordance with 10 CFR72.212(bX2Xi) and confirmed:
- (1) the conditions set forth in the CoC had been met prior to use,
- (2) the ISFSI pad had been designed to support the load of stored casks, and
- (3) the radiological requirements of 72.104 had been met. The inspectors verified that applicable reactor site parameters, such as fire and explosions, tornadoes, wind-generated missile impacts, seismic qualifications, lightning, flooding and temperature, had been evaluated for acceptability with bounding values specified in the FSAR and the NRC Safety Evaluation Report (SER). The inspectors also verified that a 50.59 evaluation of the construction and operation of the ISFSI and plant interfaces were not required and that ISFSI related work activities would not impact the safe operation of Nine Mile Point. Units 1 and 2.
b. Findinqs No findings were identified.
Initial Loadinq of the ISFSI (60855 and 60855.1)
a. Inspection Scope
The inspectors observed and evaluated the licensee's loading of the first of six DSCs associated with the initial ISFSI dry cask campaign on September 10-14, 2O12. The inspectors also reviewed the licensee's planned activities related to long-term operation and monitoring of the lSFSl. The inspectors verified compliance with the CoC, TS, regulations, and station procedures.
The inspectors observed the heavy load movement of the TC and loaded DSC from the spent fuel pool to the cask decontamination and processing area. The inspectors also observed DSC processing operations including: decontamination and surveying, welding, non-destructive weld examinations, DSC draining, vacuum drying, and helium backfilling.
During performance of these activities, the inspectors verified that procedure use, communication. and coordination of ISFSI activities met established standards and requirements.
The inspectors reviewed the licensee's program associated with fuel characterization and selection for storage. The inspectors reviewed the first cask fuel selection package to verify that the licensee was loading fuel in accordance with the CoC, TS, and procedures.
The inspectors reviewed radiation protection procedures and radiation work permits (RWPs) associated with the ISFSI loading campaign. The inspectors also reviewed the established radiological controls. The inspectors assessed whether workers were aware of the radiological conditions in their work area and the RWP controls/limits. The inspectors reviewed radiological records from the first DSC loading to confirm that radiation survey levels measured were within limits specified by the TS and consistent with values specified in the FSAR.
The inspectors performed a walk-down of the heavy haul path and toured the ISFSI pad to assess the material condition of the pad and the HSMs. The inspectors also verified that transient combustibles were not being stored on the ISFSI pad or the vicinity of the HSMs. The inspectors also confirmed that vehicle entry onto the ISFSI pad was controlled in accordance with procedures.
The inspectors reviewed corrective action reports and the associated follow-up actions that were generated since NMPNS started planning for their initial ISFSI campaign to ensure that issues were entered into the corrective action program, prioritized, and evaluated commensurate with their safety significance.
b.
Findinss No findings were identified.
Meetinqs. includino Exit On September 19, 2012, the team presented the results via telephone to Ken Phy, ISFSI Project Manager, and Madhav Shanbhag, Licensing Engineer. The inspectors verified that no proprietary information was retained by the inspectors or documented in this report.
- Supplementary Information
SUPPLEMENTARY INFORMATION
KEY POINTS OF CONTACT
PARTIAL LIST OF PERSONS CONTACTED
NMPNS
- D. Bensel, Reactor Engineer
G.Connor, Design Engineer
- J. DeSando, Fleet Maintenance
J.Henry, Radiation Protection
J.Jock, ISFSI Foreman
J.Kidd, Quality Assurance
M.Lavery, ISFSI Supervisor
- P. Mills, Radiation Protection
J.Olmundsen, ISFSI Supervisor
S.Penney, Reactor Engineer
K.Phy, ISFSI Project Manager
M.Philippon, Plant General Manager
A.Ross, Reactor Engineer
M.Shanbhag, Licensing Engineer
T.Sollenberger, Radiation Protection .,
NRC Personnel
D.Dempsey, Resident Inspector
E.Miller, Resident Inspector
ITEMS OPEN. CLOSED. AND DISCUSSED
Opened/Closed/Discussed
None
LIST OF DOCUMENTS REVIEWED