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Category:Inspection Report
MONTHYEARIR 05000336/20240032024-11-0707 November 2024 Integrated Inspection Report 05000336/2024003 and 05000423/2024003 and Apparent Violation and Independent Spent Fuel Storage Installation Inspection Report 07200008/2024001 IR 05000336/20244022024-10-0808 October 2024 Security Baseline Inspection Report 05000336/2024402 and 05000423/2024402 (Cover Letter Only) IR 05000336/20240052024-08-29029 August 2024 Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Reports 05000336/2024005 and 05000423/2024005 IR 05000336/20240022024-08-13013 August 2024 Integrated Inspection Report 05000336/2024002 and 05000423/2024002 IR 05000336/20244412024-08-0606 August 2024 Supplemental Inspection Report 05000336/2024441 and 05000423/2024441 and Follow-Up Assessment Letter (Cover Letter Only) IR 05000336/20244032024-07-22022 July 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000336/2024403 and 05000423/2024403 IR 05000336/20245012024-07-0101 July 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000336/2024501 and 05000423/2024501 IR 05000336/20240102024-06-26026 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000336/2024010 and 05000423/2024010 IR 05000336/20244402024-06-24024 June 2024 Final Significance Determination for Security-Related Greater than Green Finding(S) with Assessment Follow-up; IR 05000336/2024440 and 05000423/2024440 and Notice of Violation(S), NRC Investigation Rpt 1-2024-001 (Cvr Ltr Only) ML24142A0952024-05-20020 May 2024 End of Cycle 22 Steam Generator Tube Inspection Report IR 05000336/20240012024-05-14014 May 2024 Integrated Inspection Report 05000336/2024001 and 05000423/2024001 and Apparent Violation IR 05000336/20244012024-04-30030 April 2024 Security Baseline Inspection Report 05000336/2024401 and 05000423/2024401 (Cover Letter Only) ML24116A0452024-04-25025 April 2024 Special Inspection Follow-Up Report 05000336/2024440 and 05000423/2024440 and Preliminary Finding(S) of Greater than Very Low Significance and NRC Investigation Report No. 1-2024-001 (Cover Letter Only) IR 05000336/20240112024-04-0101 April 2024 Comprehensive Engineering Team Inspection - Inspection Report 05000336/2024011 and 05000423/2024011 IR 05000336/20230062024-02-28028 February 2024 Annual Assessment Letter for Millstone Power Station, Units 2 and 3, (Reports 05000336/2023006 and 05000423/2023006) IR 05000336/20230042024-02-14014 February 2024 Integrated Inspection Report 05000336/2023004 and 05000423/2023004 IR 05000336/20234022024-01-30030 January 2024 Security Baseline Inspection Report 05000336/2023402 and 05000423/2023402 (Cover Letter Only) IR 05000336/20234402024-01-11011 January 2024 Special Inspection Report 05000336/2023440 and 05000423/2023440 (Cover Letter Only) IR 05000336/20230032023-11-0606 November 2023 Integrated Inspection Report 05000336/2023003 and 05000423/2023003 IR 05000336/20234202023-10-0404 October 2023 Security Inspection Report 05000336/2023420 and 05000423/2023420 IR 05000245/20230012023-09-19019 September 2023 Safstor Inspection Report 05000245/2023001 IR 05000336/20230102023-09-0808 September 2023 Commercial Grade Dedication Report 05000336/2023010 and 05000423/2023010 IR 05000336/20230052023-08-31031 August 2023 Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Report 05000336/2023005 and 05000423/2023005) IR 05000336/20230022023-08-0909 August 2023 Integrated Inspection Report 05000336/2023002 and 05000423/2023002 IR 05000336/20234012023-07-17017 July 2023 Material Control and Accounting Program Inspection Report 05000336/2023401 and 05000423/2023401 - (Cover Letter Only) IR 07200047/20234012023-06-0808 June 2023 NRC Independent Spent Fuel Storage Installation Security Inspection Report No. 07200047/2023401 IR 05000336/20230012023-05-0808 May 2023 Integrated Inspection Report 05000336/2023001 and 05000423/2023001 IR 05000336/20234032023-05-0202 May 2023 Public - Millstone Power Station, Units 2 and 3 – Final Significance Determination of Green Finding; Inspection Report 05000336/2023403 and 05000423/2023403 IR 05000336/20233022023-03-0707 March 2023 Operator Licensing Retake Examination Report 05000336/2023302 IR 05000336/20220062023-03-0101 March 2023 Annual Assessment Letter for Millstone Power Station, Units 2 and 3 (Reports 05000336/2022006 and 05000423/2022006) IR 05000336/20220042023-02-13013 February 2023 Integrated Inspection Report 05000336/2022004 and 05000423/2022004 IR 05000336/20224012023-01-26026 January 2023 Security Baseline Inspection Report 05000336/2022401 and 05000423/2022401 and Preliminary Finding(S) of Greater than Very Low Significance and Apparent Violation(S) (Cover Letter Only) IR 05000245/20220012023-01-0909 January 2023 – Safstor Inspection Report 05000245/2022001 IR 05000336/20224032023-01-0505 January 2023 Cyber Security Inspection Report 05000336/2022403 and 05000423/2022403 IR 05000336/20225012022-12-14014 December 2022 Reissued Emergency Preparedness Biennial Exercise Inspection Report 05000336/2022501 and 05000423/2022501 IR 05000336/20223012022-11-22022 November 2022 Initial Operator Licensing Examination Report 05000336/2022301 ML22325A1042022-11-21021 November 2022 Emergency Preparedness Biennial Exercise Inspection Report 05000336/2022501 and 05000423/2022501 IR 05000336/20220032022-11-14014 November 2022 Integrated Inspection Report 05000336/2022003 and 05000423/2022003 IR 05000336/20220102022-11-0101 November 2022 Biennial Problem Identification and Resolution Inspection Report 05000336/2022010 and 05000423/2022010 IR 05000336/20220112022-09-0808 September 2022 Triennial Fire Protection Inspection Report 05000336/2022011 and 05000423/2022011 IR 05000336/20220052022-08-31031 August 2022 Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Report 05000336/2022005 and 05000423/2022005) IR 05000336/20220022022-08-11011 August 2022 Integrated Inspection Report 05000336/2022002 and 05000423/2022002 IR 05000336/20224022022-05-23023 May 2022 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000336/2022402 and 05000423/2022402 IR 05000336/20220012022-05-10010 May 2022 Integrated Inspection Report 05000336/2022001 and 05000423/2022001 IR 05000423/20223022022-03-0707 March 2022 Operator Licensing Retake Examination Report 05000423/2022302 IR 05000336/20210062022-03-0202 March 2022 Annual Assessment Letter for Millstone Power Station, Units 2 and 3 (Reports 05000336/2021006 and 05000423/2021006) IR 05000336/20210042022-02-10010 February 2022 Integrated Inspection Report 05000336/2021004 and 05000423/2021004 IR 05000336/20210112022-01-20020 January 2022 Post-Approval Site Inspection for License Renewal - Phase 4 Inspection Report 05000336/2021011 IR 05000336/20210032021-11-12012 November 2021 Integrated Inspection Report 05000336/2021003 and 05000423/2021003 IR 05000423/20213012021-11-10010 November 2021 Initial Operator Licensing Examination Report 05000423/2021301 2024-08-06
[Table view] Category:Letter
MONTHYEARIR 05000336/20240032024-11-0707 November 2024 Integrated Inspection Report 05000336/2024003 and 05000423/2024003 and Apparent Violation and Independent Spent Fuel Storage Installation Inspection Report 07200008/2024001 ML24289A0152024-10-21021 October 2024 Review of the Fall 2023 Steam Generator Tube Inspection Report 05000423/LER-2024-001, Loss of Safety Function and Condition Prohibited by Technical Specifications for Loss of Secondary Containment Boundary2024-10-14014 October 2024 Loss of Safety Function and Condition Prohibited by Technical Specifications for Loss of Secondary Containment Boundary IR 05000336/20244022024-10-0808 October 2024 Security Baseline Inspection Report 05000336/2024402 and 05000423/2024402 (Cover Letter Only) ML24281A1102024-10-0707 October 2024 Requalification Program Inspection 05000423/LER-2023-006-02, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-09-26026 September 2024 Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24260A2192024-09-16016 September 2024 Decommissioning Trust Fund Disbursement - Revision to Previous Thirty-Day Written Notification ML24260A1952024-09-16016 September 2024 Response to Request for Additional Information Regarding Proposed Amendment to Support Implementation of Framatome Gaia Fuel ML24248A2272024-09-0404 September 2024 Operator Licensing Examination Approval ML24240A1532024-09-0303 September 2024 Summary of Regulatory Audit Supporting the Review of License Amendment Request for Implementation of Framatome Gaia Fuel IR 05000336/20240052024-08-29029 August 2024 Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Reports 05000336/2024005 and 05000423/2024005 IR 05000336/20240022024-08-13013 August 2024 Integrated Inspection Report 05000336/2024002 and 05000423/2024002 ML24221A2872024-08-0808 August 2024 Independent Spent Fuel Storage Installation (ISFSI) - Submittal of Cask Registration for Spent Fuel Storage IR 05000336/20244412024-08-0606 August 2024 Supplemental Inspection Report 05000336/2024441 and 05000423/2024441 and Follow-Up Assessment Letter (Cover Letter Only) ML24212A0742024-08-0505 August 2024 Request for Withholding Information from Public Disclosure - Millstone Power Station, Unit No. 3, Proposed Alternative Request IR-4-13 to Support Steam Generator Channel Head Drain Modification ML24211A1712024-07-25025 July 2024 Associated Independent Spent Fuels Storage Installation, Revision to Emergency Plan - Report of Change IR 05000336/20244032024-07-22022 July 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000336/2024403 and 05000423/2024403 IR 05000336/20245012024-07-0101 July 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000336/2024501 and 05000423/2024501 ML24180A0932024-06-28028 June 2024 Readiness for Additional Inspection: EA-23-144 IR 05000336/20240102024-06-26026 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000336/2024010 and 05000423/2024010 ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 IR 05000336/20244402024-06-24024 June 2024 Final Significance Determination for Security-Related Greater than Green Finding(S) with Assessment Follow-up; IR 05000336/2024440 and 05000423/2024440 and Notice of Violation(S), NRC Investigation Rpt 1-2024-001 (Cvr Ltr Only) ML24280A0012024-06-20020 June 2024 Update to the Final Safety Analysis Report (Redacted Version) ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24176A2622024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 ML24281A2072024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 (Redacted Version) ML24176A1782024-06-20020 June 2024 Update to the Final Safety Analysis Report ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code 05000336/LER-2024-001, Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications2024-06-10010 June 2024 Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications ML24165A1292024-06-0505 June 2024 ISFSI, 10 CFR 50.59 Annual Change Report for 2023 Annual Regulatory Commitment Change Report for 2023 ML24128A2772024-06-0404 June 2024 Issuance of Amendment No. 290 to Revise TSs for Reactor Core Safety Limits, Fuel Assemblies, and Core Operating Limits Report for Use of Framatome Gaia Fuel (EPID L-2023-LLA-0074) (Non-Proprietary) ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24109A0032024-05-21021 May 2024 Issuance of Amendment No. 289 to Revise Technical Specifications to Use Framatome Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limit (EPID L-2023-LLA-0065) (Non-Proprietary) ML24110A0562024-05-21021 May 2024 Exemption from the Requirements of 10 CFR Part 50, Section 50.46, and Appendix K Regarding Use of M5 Cladding Material (EPID L-2023-LLE-0013) (Letter) ML24141A2432024-05-20020 May 2024 Response to Request for Additional Information Regarding Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment No. 15 ML24142A0952024-05-20020 May 2024 End of Cycle 22 Steam Generator Tube Inspection Report 05000423/LER-2023-006-01, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-05-20020 May 2024 Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications IR 05000336/20240012024-05-14014 May 2024 Integrated Inspection Report 05000336/2024001 and 05000423/2024001 and Apparent Violation 05000423/LER-2023-006, Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-05-0202 May 2024 Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications ML24123A2042024-05-0202 May 2024 Pre-Decisional Replay to EA-23-144 ML24123A1222024-04-30030 April 2024 Inservice Inspection Program - Owners Activity Report, Refueling Outage 22 IR 05000336/20244012024-04-30030 April 2024 Security Baseline Inspection Report 05000336/2024401 and 05000423/2024401 (Cover Letter Only) ML24116A0452024-04-25025 April 2024 Special Inspection Follow-Up Report 05000336/2024440 and 05000423/2024440 and Preliminary Finding(S) of Greater than Very Low Significance and NRC Investigation Report No. 1-2024-001 (Cover Letter Only) ML24114A2662024-04-24024 April 2024 Submittal of 2023 Annual Radioactive Effluent Release Report ML24116A1742024-04-24024 April 2024 Annual Radiological Environmental Operating Report ML24103A0202024-04-22022 April 2024 Summary of Regulatory Audit in Support of License Amendment Request to Use Framatome Small Break and Realistic Large Break Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limits ML24106A2032024-04-15015 April 2024 2023 Annual Environmental Operating Report ML24088A3302024-04-0404 April 2024 Regulatory Audit Plan in Support of License Amendment Request to Implement Framatome Gaia Fuel ML24093A1022024-04-0101 April 2024 Alternative Request IR-4-13, Proposed Alternative Request to Support Steam Genera Tor Channel Head Drain Modification 2024-09-04
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UNITED STATES NUCLEAR REGULATORY COMiIISSION REGION
't"ffi I
21OO RENAISSANCE BOULEVARD, SUITE 1OO KING OF PRUSSLA, PENNSYLVANIA 1940G2713 September 12, 2OI3 Docket No. 05000245 License No. DPR-21 David President and Chief Nuclear Officer Dominion Resources 5000 Dominion Blvd.
Glen Allen. VA 23060-6711 SUBJECT: DOMINION NUCLEAR CONNECTICUT, lNC., MILLSTONE POWER STATION uNtr 1 - NRC INSPECTION REPORT NO. 05000245t2013009
Dear Mr. Heacock:
On June 4 - 5,2013 and July 30 - August 2, 2013, the U.S. Nuclear Regulatory Commission (NRC) conducted an inspection at the Millstone Power Station Unit 1 (MS-1). The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations, and the conditions of your license. The inspection consisted of observations by the inspectors, interviews with personnel, and a review of procedures and records. The results of the inspection were discussed with William Bartron, Licensing Supervisor, and other members of your staff on August 19,2013, via telephone, at the conclusion of the inspection; and are described in the enclosed report. No findings of safety significance were identified.
Current NRC regulations and guidance are included on the NRC's website at wwtrv.nrc.qov; select Nuclear Materials; Med, Ind, & Academic Uses; then Regulations, Guidance and Gommunications. The current Enforcement Policy is included on the NRC's website at www.nrc.qov; select About NRC, Organizations & Functions; Office of Enforcement; Enforcement documents; then Enforcement Policy (Under'Related Information'). You may also obtain these documents by contacting the Government Printing Office (GPO) toll-free at 1-866-512-1800. The GPO is open from 8:00 a.m. to 5:30 p.m. EST, Monday through Friday (except Federal holidays). Please contact Laurie Kauffman (610-337-5323) if you have any questions regarding this matter.
Sincerely,
/t-Marc S. Ferdas, Chief Decommissioning Branch Division of Nuclear Materials Safety Enclosure: Inspection Report No. 0500024512013009 cc: Distribution via ListServ
EXECUTIVE SUMMARY
Dominion Nuclear Connecticut, lnc.
Millstone Power Station Unit 1 NRC lnspection Report No. 0500024512013009 A routine announced safety inspection was conducted on June 4 - 5, 2013 and July 30 - August 2,2013 at MS-1. The inspection included a review of operations and management oversight, maintenance, corrective action program (CAP) implementation, fire protection, and plant support activities while in safe storage (SAFSTOR) status. The inspection consisted of observations by the inspectors, interviews with Dominion personnel, and a review of procedures and records. The NRC's program for overseeing the safe operation of a shut-down nuclear power reactor is described in Inspection Manual Chapter (tMC) 2561, "Decommissioning Power Reactor lnspection Program."
There are currently no ongoing decommissioning activities being conducted at MS-1.
Based on the results of this inspection, no findings of safety significance were identified.
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REPORT DETAILS
1.0 Background MS-1 is located in the town of Waterford, Connecticut. MS-1 was a single cycle, boiling water reactor with a thermal output of 2011 megawatts and a net electrical output of 652.l megawatts. The plant went into commercial operation on December 28, 1970 and permanently ceased operations on July 17, 1998. Subsequently, the fuel was permanently removed from the reactor vessel and is currently stored in the spent fuel pool (SFP). MS-1 is in SAFSTOR and Dominion plans to actively decommission MS-1 in parallel with the decommissioning of the operational units after they have been permanently shut down.
The NRC's program for overseeing the safe operation of a shut-down nuclear power reactor is described in IMC 2561.
2.0 Safe Storage (SAFSTOR) Performance and Status Review a. lnspection Scope (lnsoection Procedures (lPs) 36801, 37801. 40801. 60801. 62801.
64704. 71801. 83750. 84750. 86750)
A routine announced safety inspection was conducted on June 4 - 5, 2013 and July 30 - August 2,2013 at MS-1. The inspection consisted of observations by the inspectors, interviews with Dominion personnel, and a review of procedures and records.
The inspectors reviewed the SAFSTOR program as outlined in the Defueled Safety Analysis Report (DSAR), Technical Specifications (TS), and Technical Requirements Manual (TRM) and assessed the adequacy of management oversight of SAFSTOR responsibilities for the MS-1 facility. Specifically, the inspectors reviewed the decommissioning management and staff organization and Dominion's implementation of SAFSTOR activities related to safe storage of radioactive material. The inspectors discussed any design changes or modifications since the previous inspection and reviewed the material condition of MS-1 facilities during plant tours of the reactor building, the fuel handling floor, and the radioactive waste building.
The inspectors reviewed the quarterly surveys of the standby shutdown heat exchanger room and the maintenance and surveillance tests for the SFP cooling pumps and motors; the decay heat removal pumps, fans, and motors; the ventilation fans and motors; and the emergency diesel generator to verify that work was being performed within the established frequencies and that the equipment was being properly maintained.
The inspectors also reviewed activities and documentation associated with the following SAFSTOR programs: occupational exposure, fire protection, radioactive effluent control, and site radiological environmental monitoring program (REMP). The inspectors reviewed radioactive gaseous and liquid effluent release permits, the annual REMP report, and the annual effluent report, which included a summary of the radioactive waste management and transportation programs. The inspectors reviewed radioactive waste and transportation documents related to dry active waste generated from MS-1.
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On July 30 - August2,2013, the inspectors observed in-situ measurements of neutron absorber material in spent fuel pool racks. The in-situ measurement test is also known as "Boron Areal Density Gauge for Evaluating Racks" (BADGER) testing. The inspectors observed Dominion's contractor perform equipment preparations, such as set up and calibration, and portions of the BADGER testing. The inspectors reviewed procedures and documentation related to the BADGER testing.
The inspectors reviewed CAP condition reports associated with MS-1 to determine if issues were being properly identified, evaluated, and prioritized. The inspectors also reviewed NRC Event Notification 49175, "Unit 1 Spent Fuel Pool lsland Radiation Monitor Inoperable," dated July 6, 2013.
Observations and Findinqs The inspectors noted that there were no personnel changes within the Dominion organization related to the SAFSTOR activities and confirmed that the staff was adequately implementing SAFSTOR activities. The inspectors reviewed one design modification related to improving the longevity of the SFP pumps and decay heat removal pumps. The inspectors verified that the maintenance and surveillance program for systems and components had been conducted in accordance with thd TS and TRM requirements and established procedures. The inspectors noted that no significant water intrusion was evident and the material condition of components had remained unchanged in the reactor building, the fuel handling floor, and the radioactive waste building since the previous inspection. The inspectors also confirmed that no dismantlement or decommissioning activities were performed since the previous inspection.
ln June 2011, Dominion had contracted a vendor to conduct BADGER testing on specific spent fuel racks in the SFP. During an NRC inspection conducted on July 11 - 13,2011, the inspectors noted that the final test results were not yet available and would be reviewed during a subsequent inspection. In August 2011, Dominion generated CAP Condition Report (CR) 436420 to report that the final test results from the June 20'11 BADGER test were inconclusive and that a subsequent BADGER test would be required to adequately assess the condition of the spent fuel racks. On July 30 - August 2, 2013, the inspectors observed Dominion's contractor perform BADGER testing. The results of the BADGER test were not available prior to the conclusion of this inspection.
The annual radiological effluent and the annual REMP reports demonstrated that all calculated doses were below regulatory dose criteria of 10 CFR 50, Appendix l. The inspectors noted that radioactive waste was not shipped for offsite disposal since the last inspection.
The inspectors determined that issues were entered into the CAP, prioritized, and evaluated commensurate with their safety significance. Corrective actions were implemented to address identified issues and were being tracked to closure using the CAP.
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c. Conclusions
Based on the results of this inspection, no findings of safety significance were identified.
3.0
Exit Meeting Summary
On August 19,2013, the inspectors presented the inspection results to Mr. William Bartron, Licensing Supervisor, and other members of Dominion's staff. The inspectors confirmed that proprietary information was not removed from the site.
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PARTIAL LIST OF PERSONS CONTACTED Licensee W. Bartron Supervisor, Nuclear Licensing W. Craft Nuclear Licensing - Innsbrook J. Drzewianowski Radiation Protection Technician A. Elms Organizational Effectiveness Manager C. Gannon Health Physicist, Radiation Protection R. Hall Innsbrook Nuclear Fuels Engineering Consultant J. Laine Acting Director NS&L E. Palmieri Nuclear Maintenance Supervisor MS-1 L. Salyards Lead Licensing Engineer T. Schleicher Supervisor, Nuclear Core Design G. Sturgeon Operations Nuclear Specialist MS-1 P. Tulba Radioactive Material Control Supervisor S. Turowski HP Technical Services Supervisor ITEMS OPEN. CLOSED. AND DISCUSSED None LIST OF
DOCUMENTS REVIEWED
Defueled Safety Analysis Report
Millstone Power Station Unit 1 Permanently Defueled Technical Specifications (TS)
2012Radioactive Effluent Release Report and Off-Site Dose Calculation Manual (REMODCM)
2012 Annual Radiological Environmental Operating Report
Audit 1 1-09: Technical Specifications, Licensing Conditions and Chemistry
Audit 13-04: Fire Protection QA Program & MPS Refueling
Audit 1 2-06: Radiological Protection/Process Control Program/Chemistry
Event Notification 49175, Unit 1 Spent Fuel Pool lsland Radiation Monitor Inoperable,
dated July 6, 2013
ONP 540 F, Loss of Normal Power
OP 312 l, Waste Water Evaporator System
OP 312 K, Waste Water Processing System
OP 328 A, Refueling Platform
OP 328 C, Main Hoist Operations
OP 360, Programmable Logic Controller
MS-1 Radiation Surveys conducted between June2012 and July 2013
MS-1 Radiation Exposure (ALARA) Reports for 2012, and most current through July 2013
MS-1 Surveillance Form for Operator Logs and Inspections (Unit 1 rounds)
RP-AA-220, Radiological Survey Scheduling
SP 852, Spent Fuel Pool Chemistry Control
SP-608AA, Backup Diesel Generator Loaded Run Condition Reports:
CR436420; CR519917; CR520025; CR509725; CR509290; CR505117;CR521333; CR21163;
CR521244; CR5084 1 8 ; CR52 1 942; CR521 950 ; CR52215 1 ; CR5220 1 5
Inspection Report No.05000245/2013009
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LIST OF ACRONYMS USED
BADGER Boron Areal Density Gauge for Evaluating Racks
CAP Corrective Action Program
CFR Code of Federal Regulations
CR Condition Report
Dominion Dominion Nuclear Connecticut, lnc.
DSAR Defueled Safety Analysis Report
tMc Inspection Manual Chapter
IP lnspection Procedure
MS-1 Millstone Power Station Unit 1
NRC U.S. Nuclear Regulatory Commission
REMP Radiological Environmental Monitoring Program
SAFSTOR Safe Storage
SFP Spent Fuel Pool
TRM Technical Requirements Manual
TS Technical Specification
Inspection Report No.05000245/2013009
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