ML031480155

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Memorandum, Facsimile Transmission Issues Discussed in Phone Conversation. TAC Nos MB7926 and MB7927
ML031480155
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 06/06/2003
From: Spaulding D
NRC/NRR/DLPM/LPD3
To:
NRC/NRR/DLPM
Spaulding D, NRR/DE/EEIB, 415-2928
References
TAC MB7926, TAC MB7927
Download: ML031480155 (4)


Text

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