Letter Sequence Other |
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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:Memoranda
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Summary of April 21, 2022, Public Meeting to Discuss Potential Emergency Preparedness License Amendment Request
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2017 Summary of Annual Decommissioning Funding Status Reports for Reactors in Decommissioning
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Reactor Coolant System Alloy 600 Inspection Program for License Renewal Commitment No. 14. (Tac No. MF3433)
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Closed Meeting Announcement Millstone Drop-In
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2012 Annual Summary of the Green Mountain Power Special Nuclear Committee
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2024-08-16
[Table view] |
Text
May 8, 2002 MEMORANDUM TO: James W. Clifford, Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Sr. Project Manager, Section 2 /RA/
Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
SUBJECT:
MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2, FACSIMILE TRANSMISSION, ISSUES TO BE DISCUSSED IN AN UPCOMING CONFERENCE CALL (TAC NO. MB2639)
The attached information was transmitted by facsimile on May 8, 2002, to Mr. David Dodson of Dominion Nuclear Connecticut, Inc. (the licensee). This information was transmitted to facilitate a upcoming conference call in order to clarify the licensees submittal dated April 30, 2002, pertaining to Nuclear Regulatory Commission (NRC)Bulletin 2001-01, Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles. This memorandum and the attachment do not convey a formal request for information or represent an NRC staff position.
Docket No. 50-336
Attachment:
Issues for Discussion in Upcoming Telephone Conference
MEMORANDUM TO: James W. Clifford, Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Sr. Project Manager, Section 2 /RA/
Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
SUBJECT:
MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2, FACSIMILE TRANSMISSION, ISSUES TO BE DISCUSSED IN AN UPCOMING CONFERENCE CALL (TAC NO. MB2639)
The attached information was transmitted by facsimile on May 8, 2002, to Mr. David Dodson of Dominion Nuclear Connecticut, Inc. (the licensee). This information was transmitted to facilitate a upcoming conference call in order to clarify the licensees submittal dated April 30, 2002, pertaining to Nuclear Regulatory Commission (NRC)Bulletin 2001-01, Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles. This memorandum and the attachment do not convey a formal request for information or represent an NRC staff position.
Docket No. 50-336
Attachment:
Issues for Discussion in Upcoming Telephone Conference DISTRIBUTION PUBLIC AHiser JClifford BWetzel REnnis SCoffin PDI-2 Reading ACCESSION NO.: ML021280597 OFFICE PDI-2/PM NAME REnnis DATE 5/8/02 OFFICIAL RECORD COPY
Issues for Discussion in Upcoming Telephone Conference Related to NRC Bulletin 2001-01 Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles Millstone Nuclear Power Station, Unit No. 2 NRC Bulletin 2001-01, Question 5, part a, requests licensees to provide, within 30 days after plant restart following the next refueling outage, a description of the extent of vessel head penetration (VHP) nozzle leakage and cracking detected at your plant, including the number, location, size, and nature of each crack detected. Dominion Nuclear Connecticut, Inc., provided the 30-day response for Question 5 for Millstone Unit No. 2 by letter dated April 30, 2002. The staff has reviewed your response and would like to discuss the following issues:
- 1) The response stated that three control element drive mechanism (CEDM) nozzles were determined to contain indications of discontinuities that could be attributed to service induced degradation and that indications were found in CEDM Nozzles 21, 34 and 50.
The response included tables to provide details regarding the indications found in each of the 3 nozzles. The tables for Nozzles 34 and 50 each contain a row to provide the depth in inches for the indications found. However, the table for Nozzle 21 does not provide depth information. Please provide this information.
- 2) The information in the three tables states that the location of each of the indications found is OD downhill. The staff requests more specific information regarding the locations. If possible, please provide information similar to that provided in Figures 8 through 12 of the Root Cause Analysis Report for Davis-Besse dated April 18, 2002.
These figures are shown on the NRC website at:
http://www.nrc.gov/reactors/operating/ops-experience/vessel-head-degradation/vessel
-head-degradation-files/figures-cr02-0891.pdf ATTACHMENT
