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MONTHYEARML0205201012002-02-21021 February 2002 Response to Dnc'S February 7, 2002, Supplemental Response to Bulletin 2001-01, Circumferental Cracking of Reactor Pressure Vessel Head Penetration Nozzles. Project stage: Other ML0203806882002-03-12012 March 2002 1/24/2002 Meeting Summary with Dominion Nuclear Connecticut, Inc. Discussing the Licensee'S Reactor Pressure Vessel Head Penetration Nozzle Inspection Plans in Response to NRC Bulletin 2001-01 Project stage: Meeting ML0208103172002-03-12012 March 2002 Meeting Agenda, to Discuss the Licensee'S Reactor Pressure Vessel Head Penetration Nozzle Inspection Plans Project stage: Meeting ML0212805972002-05-0808 May 2002 Facsimile Transmission, Issues to Be Discussed in an Upcoming Conference Call Project stage: Other 2002-03-12
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Category:Letter
MONTHYEARML24240A1692024-09-18018 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) ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML24162A0882024-06-10010 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 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) 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) 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 ML24141A1502024-05-20020 May 2024 Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications 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 ML24123A2272024-05-0202 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 - 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Inspection Report 05000336/2024011 and 05000423/2024011 ML24092A0752024-03-28028 March 2024 3R22 Refueling Outage Inservice Inspection (ISI) Owners Activity Report Extension ML24088A2352024-03-26026 March 2024 Decommissioning Funding Status Report ML24086A4762024-03-22022 March 2024 Application for Technical Specification Change to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line-Item Improvement Process ML24086A4802024-03-22022 March 2024 Alternative Request IR-4-14, Proposed Alternative Request to Defer ASME Code Section XI Inservice Inspection Examination for Pressurizer and Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles ML24051A1922024-03-0808 March 2024 – Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) IR 05000336/20230062024-02-28028 February 2024 Annual Assessment Letter for Millstone Power Station, Units 2 and 3, (Reports 05000336/2023006 and 05000423/2023006) ML24053A2632024-02-21021 February 2024 Unit 3, and Independent Spent Fuel Storage Installation, Notification Pursuant to 10 CFR 72.212(b)(1) Prior to First Storage of Spent Fuel Under a General License ML24057A0612024-02-19019 February 2024 and Virgil C. Summer Power Nuclear Stations - Nuclear Property Insurance Coverage 2024-09-04
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February 21, 2002 Mr. J. A. Price Vice President - Nuclear Technical Services - Millstone Dominion Nuclear Connecticut, Inc.
c/o Mr. David A. Smith Rope Ferry Road Waterford, CT 06385
SUBJECT:
MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 (MILLSTONE 2) -
RESPONSE TO DNC's FEBRUARY 7, 2002, SUPPLEMENTAL RESPONSE TO BULLETIN 2001-01, CIRCUMFERENTIAL CRACKING OF REACTOR PRESSURE VESSEL HEAD PENETRATION NOZZLES
Dear Mr. Price:
On August 3, 2001, the Nuclear Regulatory Commission (NRC) staff issued Bulletin 2001-01 Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles (Agencywide Documents Access and Management System (ADAMS) Accession No. ML012080284) to the industry requesting that addressees provide information related to the structural integrity of the reactor pressure vessel head penetration (VHP) nozzles for their respective facilities, including the extent of VHP nozzle leakage and cracking that has been found to date, the inspections and repairs that have been undertaken to satisfy applicable regulatory requirements, and the basis for concluding that their plans for future inspections will ensure compliance with applicable regulatory requirements at their respective pressurized water reactor (PWR) plants.
The bulletin required a response from addressees within 30 days of issuance.
In response to Bulletin 2001-01, you provided information via letters dated September 4, 2001, December 28, 2001, and February 7, 2002. Your inspection plans were also discussed during a telephone conference on Friday, October 5, 2001, and during a public meeting on January 24, 2002.
As a follow-up to the meeting held with the NRC staff on January 24, 2002, you describe plans to perform ultrasonic testing (UT) of your reactor vessel head penetrations (RVHPs) at the next refueling outage of Millstone 2, in your letter dated February 7, 2002. This letter is consistent with the information that you presented to the staff on January 24, 2002, in that you propose to perform 100 percent volumetric inspection of the Millstone 2 RVHPs. However, you cite the possibility of UT equipment failure or some unanticipated interference due to head geometry as the basis for possibly reducing the scope of your inspection to less than 100 percent of the RVHPs, specifically a minimum of 65 out of the 78 RVHPs.
As summarized at the January 24, 2002, meeting, the staff has found that the examination equipment, technology, and methods that you proposed to utilize in your upcoming outage will provide an effective examination to ensure the public health and safety for subsequent operation of the plant. However, the staff does not agree with your statistical analysis used to justify inspecting fewer than 100 percent of the nozzles, and as stated during the January 24, 2002, meeting, the staff concludes that inspection of 100 percent of the nozzles is necessary to ensure the public health and safety for subsequent operation of the plant.
J. Price If you have any questions or comments concerning this issue, please contact me via telephone at (301) 415-3199, or e-mail jth2@nrc.gov.
Sincerely,
/RA/
John T. Harrison, Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-336 cc: See next page
J. Price If you have any questions or comments concerning this issue, please contact me via telephone at (301) 415-3199, or e-mail jth2@nrc.gov.
Sincerely,
/RA/
John T. Harrison, Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-336 cc: See next page DISTRIBUTION:
PUBLIC JClifford OGC WBateman PDI-2 R/F JHarrison ACRS AHiser EMCB R/F JZimmerman CCowgill, RI JCollins TClark LAbramson SLong JChung MReinhart RBarrett ALee BWetzel EAdensam ACCESSION NO. ML020520101 OFFICE PDI-2/PM PDI-2/LA EMCB/BC PDI-2/SC NAME JHarrison TClark WBateman JClifford DATE 2/21/02 2/21/02 2/21/02 2/21/02 OFFICIAL RECORD COPY
Millstone Nuclear Power Station Unit 2 cc:
Ms. L. M. Cuoco Mr. P. J. Parulis Senior Nuclear Counsel Manager - Nuclear Oversight Dominion Nuclear Connecticut, Inc. Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Rope Ferry Road Waterford, CT 06385 Waterford, CT 06385 Edward L. Wilds, Jr., Ph.D. Mr. D. A. Christian Director, Division of Radiation Senior Vice President - Nuclear Operations Department of Environmental Protection and Chief Nuclear Officer 79 Elm Street Innsbrook Technical Center - 2SW Hartford, CT 06106-5127 5000 Dominion Boulevard Glen Allen, VA 23060 Regional Administrator, Region I U.S. Nuclear Regulatory Commission Mr. C. J. Schwarz 475 Allendale Road Director - Nuclear Operations and Chemistry King of Prussia, PA 19406 Dominion Nuclear Connecticut, Inc.
Rope Ferry Road First Selectmen Waterford, CT 06385 Town of Waterford 15 Rope Ferry Road Mr. John Markowicz Waterford, CT 06385 Co-Chair Nuclear Energy Advisory Council Charles Brinkman, Manager 9 Susan Terrace Washington Nuclear Operations Waterford, CT 06385 ABB Combustion Engineering 12300 Twinbrook Pkwy, Suite 330 Mr. Evan W. Woollacott Rockville, MD 20852 Co-Chair Nuclear Energy Advisory Council Senior Resident Inspector 128 Terry's Plain Road Millstone Nuclear Power Station Simsbury, CT 06070 c/o U.S. Nuclear Regulatory Commission P.O. Box 513 Mr. D. A. Smith Niantic, CT 06357 Manager - Regulatory Affairs Dominion Nuclear Connecticut, Inc.
Mr. W. R. Matthews Rope Ferry Road Vice President and Senior Nuclear Waterford, CT 06385 Executive - Millstone Dominion Nuclear Connecticut, Inc. Ms. Nancy Burton Rope Ferry Road 147 Cross Highway Waterford, CT 06385 Redding Ridge, CT 00870 Ernest C. Hadley, Esquire P.O. Box 1104 West Falmouth, MA 02574-1104
Millstone Nuclear Power Station Unit 2 cc:
Mr. G. D. Hicks Director - Nuclear Training Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Mr. J. Alan Price Vice President - Nuclear Operations - Millstone c/o Mr. David A. Smith Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385