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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 ML24176A1782024-06-20020 June 2024 Update to the Final Safety Analysis Report ML24281A2072024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 (Redacted Version) 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) 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 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 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 IR 05000336/20244012024-04-30030 April 2024 Security Baseline Inspection Report 05000336/2024401 and 05000423/2024401 (Cover Letter Only) ML24123A1222024-04-30030 April 2024 Inservice Inspection Program - Owners Activity Report, Refueling Outage 22 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) ML24116A1742024-04-24024 April 2024 Annual Radiological Environmental Operating Report ML24114A2662024-04-24024 April 2024 Submittal of 2023 Annual Radioactive Effluent Release 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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Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BLVD., SUITE 100 KING OF PRUSSIA, PA 19406
-2713 July 11, 2018 Docket No.
05000245License No.
DPR-21 Mr. Daniel President and Chief Nuclear Officer Dominion Energy, Inc. Innsbrook Technical Center 5000 Dominion Blvd.
Glen Allen, VA 23060
-6711 SUBJECT: MILLSTONE POWER STATION UNIT 1
- SAFE STORAGE INSPECTION REPORT NO. 05000245/201 8 00 1
Dear Mr. Stoddard:
On June 11 - 1 4, 201 8 , 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 inspector, interviews with personnel, and a review of procedures and records. The results of the inspection were discussed with Michael O'Connor , Director - Nuclear Safety & Licensing, and other members of your organization on June 1 4, 201 8, at the conclusion of the inspection. The enclosed report presents the results of this inspection. No findings of safety significance were identified.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure(s), and your response will be made available electronically for public inspection in the NRC Public Document Room or from the NRC document system (ADAMS), accessible from the NRC website at http://www.nrc.gov/reading
-rm/adams.html. To the extent possible, your response should not include any personal privacy, proprietary, or safeguards information so that it can be made available to the Public without redaction.
Current NRC regulations and guidance are included on the NRC's website at www.nrc.gov; select Radioactive Waste; Decommissioning of Nuclear Facilities; then Regulations, Guidance and Communications. The current Enforcement Policy is included on the NRC's website at www.nrc.gov; 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). No reply to this letter is required. Please contact Katherine Warner at 610-337-5389 if you have any questions regarding this matter.
Sincerely,
/RA/ Raymond J. Powell, Chief Decommissioning, ISFSI, and Reactor HP Branch Division of Nuclear Materials Safety Enclosure: Inspection Report No. 05000245/201 8 00 1 cc: w/encl: Distribution via ListServ
EXECUTIVE SUMMARY
Dominion Energy, Inc. Millstone Power Station Unit 1
NRC Inspection Report No. 05000245/
201 8 00 1 A n announced safety inspection was conducted on June 11 - 1 4, 201 8 at MS-1. The inspector reviewed MS
-1's activities related to the safe storage of radioactive material, including site operations, engineering, maintenance, plant support activities, management oversight, and corrective action program (CAP) implementation. The inspection consisted of observations by the inspector, interviews with Dominion personnel, a review of procedures and records, and plant walk-downs. There are currently no ongoing decommissioning activities being conducted at MS
-1. The NRC's program for overseeing the safe operation of a shut-down nuclear power reactor is described in Inspection Manual Chapter (IMC) 2561, "Decommissioning Power Reactor Inspection Program." Based on the results of this inspection, no findings of safety significance were identified.
1 Inspection Report No. 05000245/201 800 1
REPORT DETAILS
1.0 Background MS-1 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 safe storage (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. Operations and radiation protection/chemistry personnel from Millstone Unit
-2 (MS-2) provide routin e support functions to MS
-1.
The NRC's program for overseeing the safe operation of a shut
-down nuclear power reactor is described in IMC 2561.
2.0 SAFSTOR Performance and Status Review
a. Inspection Scope
(Inspection Procedures 36801, 37801, 40801, 60801 , 62801, 64704 , 71801, 83750, 84750, 86750) A n announced safety inspection was conducted on June 11 - 14, 201 8. The inspection consisted of observations by the inspector, interviews with Dominion personnel, a review of procedures and records, and plant walk
-downs. The inspector reviewed the SAFSTOR program as outlined in the defueled safety analysis report , and Technical Specifications (TS) and assess ed the adequacy of management oversight of SAFSTOR responsibilities for the MS
-1 facility. Specifically, the inspector reviewed the decommissioning management and staff organization and Dominion's implementation of SAFSTOR activities related to safe storage of radioactive material. The inspector also conducted a walk-down to assess the material condition of the MS
-1 facility (reactor building, the fuel
-handling floor, building exterior, condenser bay, and drywell
) and discussed any design changes or modifications since the previous inspection.
The inspector reviewed MS
-1's program for the safe wet storage of spent fuel. The inspector performed walk
-downs of the SFP and associated support systems to assess material condition, configuration control, and system operation.
The inspector observed activities associated with Boron Arial Density Gauge Evaluating Racks (BADGER) Testing. The inspector reviewed activities, components, and documentation associated with the following SAFSTOR programs:
occupational exposure, fire protection, radioactive effluent control, site radiological environmental monitoring program (REMP), maintenance and surveillance, and decommissioning organization and staffing. The inspector reviewed radiological survey reports, radioactive liquid effluent release permits, the annual REMP report, the annual effluent release report, condition reports, and MS-1 firefighting strategies and procedures
. The inspector reviewed Dominion fleet audit reports and CAP documents associated with MS-1 to determine if issues were being appropriately identified, assessed and reviewed and that corrective actions were being appropriately implemented.
Inspection Report No. 05000245/201800
b. Observations and Findings
The inspector confirmed that the SAFSTOR program was being effectively implemented. The inspector verified that the maintenance and surveillance program for systems and components had been conducted in accordance with the TS requirements and established procedures. T he inspector also confirmed that no dismantlement or decommissioning activities were performe d since the previous inspection.
The inspector determined that MS
-1 was safely storing spent fuel in wet storage.
The inspector noted that the design change to the MS-1 central monitoring station has been completed since the last inspection.
The inspector noted that the upgrade included alarms for exterior temperature indications for decay heat removal components.
BADGER Testing involves using a neutron source and an array of neutron sensitive instruments to determine the reactivity "effectiveness" of the MS
-1 SFP carborundum fuel racks.
The inspector observed activities associated with BADGER testing including pre-job briefs, troubleshooting, assembly, and testing. The inspector noted that MS
-1 tested 39 panels and will perform this test every 5 years in accordance with guidance from NEI 16
-03. As previously indicated, MS
-2 operations support operations at MS
-1. The inspector reviewed MS
-1's firefighting strategies and noted that the fire brigade staffed from MS
-2 and Millstone Unit 3's operations would respond in the event of a fire at MS-1. Fire drills are routinely performed at MS
-1 and staff are familiarized with MS
-1 during training. The inspector noted that MS
-2 health physics support operations at MS
-1 by performing surveys, providing radiation protection coverage for work, and providing RP briefings as necessary.
The annual radiological effluent and the annual REMP reports demonstrated that all calculated doses were below regulatory dose criteria of 10 Code of Federal Regulations 50, Appendix I
. The inspector noted that Dominion had one shipment of Class A dry active waste and one shipment of limited quantity material shipped for offsite disposal from MS-1 since the last inspection.
The inspector discussed shipping requirements and processes with Millstone Power Station staff.
Findings or issues identified from audits, plant equipment operator's rounds, and staff observations were entered into the CAP. Dominion effectively addressed identified issues, implemented corrective actions, and tracked them to closure. Condition reports and corrective actions appeared to be prioritized and evaluated commensurate with their safety significance.
c. Conclusions
Based on the results of this inspection, no findings of safety significance were identified.
Inspection Report No. 05000245/201800 3.0
Exit Meeting Summary
On June 14, 201 8 , the inspector presented the inspection results to Michael O'Connor, Director - Nuclear Safety & Licensing, and other members of Dominion's staff.
The inspector confirmed that no copies of proprietary information were used during this inspection and none were removed from the site.
Inspection Report No. 05000245/
201800 1 PARTIAL LIST OF PERSONS CONTACTED Licensee J. Armstrong Fire Protection Program Engineer W. Brown Licensing Technical Lead C. Dix Health Physics Supervisor Site M. Goolsb e y Unit 2 Superintendent Nuclear Unit 2 Operations B. Graber Radioactive Analysis Group Supervisor J. Nelson Health Physicist T. Schleicher Nuclear Core Design Supervisor G. Sturgeon Operations Nuclear Specialist MS
-1 M. Wood Radioactive Material Control Supervisor M. Wynn Acting RP and Chemistry Manager P. Vernacchio NETCO Engineer ITEMS OPEN, CLOSED, AND DISCUSSED None LIST OF
DOCUMENTS REVIEWED
2017 Radioactive Effluent Release Report and Off
-Site Dose Calculation Manual
(REMODCM), May 1, 2018
2017 Annual Radiological Environmental Operating Report, May 1, 201 8 Audit 17-04: Fire Protection and SPS Refueling, July 20, 2017
Defueled Safety Analysis Report
ETE-NAF-2018-0047, Review of NEI 16
-03 Guidance in Preparation for the 2018 Millstone Unit
Spent Fuel Pool BADGER Carborundum Areal Density Measurements
Liquid Discharge Permit, L
-EFF1-20171205-601-B, December 4, 2017
Liquid Discharge Permit, L
-EFF1-20180410-191-B, April 10, 2018
RP-AA-300 Micro ALARA Plan BADGER (Blackness Testing and Support Activities Unit 1, May
21, 2018 Millstone Nuclear Power Station Unit 1 , Spent Fuel Pool Island Vent Filters Sample
, February 27, 2017 Millstone Unit 1 Exposure Report, January 3, 2018
Millstone Unit 1 Exposure Report, April 2, 2018
Millstone Unit 1 Defueled Technical Requirements Manual
Millstone Power Station Unit 1 Permanently Defueled Technical Specifications (TS)
MS-1 Operational Issues Tracking Report
MS-1 Radiation Surveys 201
Package Characterization Report, C20312, October
3, 2018 Package Characterization Report, C21630 , October 10, 201 8 Radiation Work Permit (RWP) 1170007
- Low Risk Areas in RCA
- Self Briefing, Revision 0
RWP 1170008 - NRC, Revision 1
SP 1054A, Spent Fuel Rack Surveillance Program
- Boron Carbide Plate, Revision 005
Special Engineering Procedure 28099
-000-01, Procedure for Assembly and Testing of the
Boron-10 Areal Density Meter at Millstone Power Station, Revisio
n 0 Worker Qualification Status, NU
-MPSU1CFH - Millstone Unit 1 Certified Fuel Handler (CFH)
Inspection Report No. 05000245/
2018001 Work Orders:
53102445515
53102996223
53103054328
53103124688
203160248
Condition Reports:
1067839 1069125 1069130 1076366 1079068 1079069 1080284 1080368 1081457 1082035 1082070 1082542 1082544 1083609 1084397 1084599 1086632 1087203 1090510 1091163 1091175 1091176 1091181 1091184 1091266 1091411 1091486 1091488 1091491 1092019 1093319 1099410 1099537 1099561 1099662 LIST OF ACRONYMS USED
BADGER Boron Arial Density Gauge Evaluating Racks
CAP Corrective Action Program
Dominion Dominion Energy, Inc. IMC Inspection Manual Chapter
MS-1 Millstone Power Station Unit 1
MS-2 Millstone Power Station Unit 2
NRC U.S. Nuclear Regulatory Commission
REMP Radiological Environmental Monitoring Program
SAFSTOR Safe Storage
SFP Spent Fuel Pool
TS Technical Specification