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MONTHYEARML0314801552003-06-0606 June 2003 Memorandum, Facsimile Transmission Issues Discussed in Phone Conversation. TAC Nos MB7926 and MB7927 Project stage: Other NRC 2003-0091, Request for Withdrawal, and Resubmittal, of Request for Exemptions to 10 CFR 50.61, Appendices G and H to 10 CFR 50, Approval of PTS Application for Pbnp Unit 2 and Withdrawal of Associated License Amendment Request (LAR) 235 and Submi2003-09-26026 September 2003 Request for Withdrawal, and Resubmittal, of Request for Exemptions to 10 CFR 50.61, Appendices G and H to 10 CFR 50, Approval of PTS Application for Pbnp Unit 2 and Withdrawal of Associated License Amendment Request (LAR) 235 and Submittal Project stage: Withdrawal 2003-06-06
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Category:Memoranda
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ML0526203802005-09-30030 September 2005 Fiscal Year 2005 Evaluation of the Operating Reactor Licensing Program ML0523801282005-08-31031 August 2005 Unit 2 - Closeout Letter for Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors ML0626504112005-08-29029 August 2005 Memorandum to Region III Office Allegation Coordinator from P. Louden, Review of Discrimination Complaint Filed with Department of Labor ML0518203592005-07-0808 July 2005 Notice of Meeting with Nuclear Management Company Regarding the Planned Amendment to the Point Beach Nuclear Plant, Unit 1, Updated Safety Analysis Report Relating to Movement of the Reactor Vessel Head ML0626504042005-06-22022 June 2005 Memorandum to P. Louden from P. Pelke, Review of Receipt of Allegation, Allegation No. RIII-05-A-0062 (Point Beach) ML0626802612005-06-21021 June 2005 Memorandum to Allegation File from P. Pelke Receipt of Allegation (Point Beach) IR 05000266/20040032005-05-24024 May 2005 or Inspection Report Input to Point Beach Integrated Report 50-266/04-003 & 50-301-04-003 ML0515202472005-05-24024 May 2005 Previous Revision of Inspection Input to Point Beach Integrated Report 50-266-04-003 & 50-301-04-003 ML0502700462005-01-19019 January 2005 Summary of Telephone Conference Held on January 10, 2005, Between the U.S. Nuclear Regulatory Commission and Nuclear Management Company, LLC, Concerning Draft Requests for Additional Information Pertaining to the Point Beach Nuclear ML0432706522004-11-17017 November 2004 Summary of Telephone Conference Heldon November 17, 2004, Between the U.S. Nuclear Regulatory Commission and Nuclear Management Company, Llc. Concerning Draft Requests for Additional Information Pertaining to the Point Beach Nuclear Plan, U ML0432705872004-11-16016 November 2004 Summary of Telephone Conference Held on October 26, 2004, Between the U.S. Nuclear Regulatory Commission and Nuclear Management Company, LLC, Concerning Draft Requests for Additional Information Pertaining to the Point Beach Nuclear Plant, ML0420404302004-07-22022 July 2004 Notice of Meeting Between the U.S. Nuclear Regulatory Commission (NRC) Staff and Nuclear Management Company, LLC (NMC) on Recent Decisions Involving Unit 2 Reactor Vessel Pressurized Thermal Shock ML0419604622004-07-0707 July 2004 Wpdes Permit Reissuance ML0421003322004-06-30030 June 2004 Close-out of Tacs Relating to the Review of 35-day Letters Submitted in Response to the April 29, 2003, Orders Revising the Design Basis and Security Guard Force Training Enhancements and Physical Fitness Requirements ML0418803242004-06-29029 June 2004 Audit and Review Plan for Plant Aging Management Reviews and Programs at Point Beach Nuclear Power Plant, Units 1 and 2 ML0417400862004-06-21021 June 2004 All Region III Facility Training Managers Revised NRC Form 398 - Personal Qualification Statement Licensee ML0508304222004-06-0202 June 2004 Memo T.Chan, NRR, to L. Raghavan, NRR, Safety Evaluation for Point Beach Unit 1 First Revised Order 2023-02-15
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June 6, 2003 MEMORANDUM TO: File FROM: Deirdre W. Spaulding, Project Manager, Section 1 /RA/
Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 - FACSIMILE TRANSMISSION FOR ISSUES DISCUSSED IN TELEPHONE CONFERENCE (TAC NOS. MB7926 AND MB7927)
The attachment was transmitted by fax to Mr. Jack Gadzala, Nuclear Management Company, LLC, in preparation for a telephone conference held on May 8, 2003. This memorandum and the attachment do not convey a formal request for information or represent an NRC staff position.
Docket Nos. 50-266 and 50-301
Attachment:
Discussion Points
ML031480155 OFFICE PDIII-1/PM PDIII-1/LA PDIII-1/SC NAME DSpaulding RBouling LRaghavan DATE 06/05/03 06/05/03 06/06/03 Point Beach Units 1 and 2 Discussion Items Tac MB7926/7 Nuclear Management Company LLC, licensee for the Point Beach Units 1 and 2, in a letter dated March 3, 2003 requested exemptions to 10 CFR 50.61, Appendices G and H to 10 CFR 50 and approval of PTS for Unit 2 and approval of PT curves for both units. The submittal is based on an ATI report regarding the Master Curve fracture toughness application for Unit 2 and WCAP-15976 for the PT curves.
Regarding the values of the fluence used for the Point Beach units as well as the capsules which were irradiated outside the Point Beach Units, please respond to the following questions:
what is the axial position of the limiting intermediate to lower shell circumferential weld (SA-1484) and what is the axial average source used for the calculation of the fluence?
WCAP-15976 states that the fluence values used are based on calculations conforming to the guidance in RG 1.190. The values were transferred from the ATI report which states the values but does not indicate their origin. Please indicate where these values come from and provide the documents which substantiate the statement regarding RG 1.190.
Regarding circumferential weld SA-1484, material/irradiation data from non-Westinghouse plants were used without an integrated surveillance program (ISP).
Please state how the provisions of Appendix H for sharing irradiation data are satisfied?
(Is this the subject of the Appendix H exemption?)
Describe the assumptions used in your fluence calculations regarding the removal of the Hafnium rods and the projected power uprate.
Will future loadings maintain low leakage configurations?
ATTACHMENT