ML093140625

Summary of Teleconference Verbal Authorization for Relief Request RR-89-67

ML093140625
Person / Time
Site:	Millstone
Issue date:	11/17/2009
From:	Sanders C Plant Licensing Branch 1
To:	Chernoff H Plant Licensing Branch 1
Sandeers, Carleen, NRR/DORL, 415-1603
References
TAC ME2296, FOIA/PA-2011-0115
Download: ML093140625 (3)

Text

November 17, 2009 MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Carleen J. Sanders, Project Manager /ra/

Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

SUBJECT:

MILLSTONE POWER STATION, UNIT NO. 2 -

SUMMARY

OF TELECONFERENCE RE: VERBAL AUTHORIZATION FOR RELIEF REQUEST RR-89-67 (TAC NO. ME2296)

This memorandum summarizes the telephone discussion on November 10, 2009, between the U.S. Nuclear Regulatory Commission (NRC) staff and Dominion Nuclear Connecticut, Inc. (DNC or the licensee) regarding DNCs request for relief RR-89-67 for Millstone Power Station, Unit No. 2 (MPS2).

By letter dated September 22, 2009 (Agencywide Documents Access and Management System Accession No. ML092710151), DNC submitted RR-89-67 as an alternative for the repair examination requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section Xl. In July 2009, the licensee repaired the degraded partial penetration weld, RCPA-RC-95-W-4, and base metal of the P40A reactor coolant pump (RCP) seal cooler return line at MPS2. Alternative Request RR-89-67 provides an alternative to the examination requirements in the ASME Code,Section XI.

The NRC staff has completed its review and finds that requiring radiographic testing and hydro testing for the repair of weld RCPA-RC-95-W-4 would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. The NRC staff concludes that the proposed alternative in Request RR-89-67 is acceptable because it provides reasonable assurance of structural integrity of weld RCPA-RC-95-W-4.

Therefore, pursuant to Title 10 of the Code of Federal Regulations, Part 50.55a(a)(3)(ii), the NRC staff verbally authorized the use of Relief Request RR-89-67 for the repair of weld RCPA-RC-95-W-4 for the remainder of the life of the A RCP seal cooler at MPS2.

The NRC's written final safety evaluation will follow. A list of the participants on the call is enclosed.

Docket No. 50-336

Enclosure:

As stated

November 17, 2009 MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Carleen J. Sanders, Project Manager /ra/

Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

SUBJECT:

MILLSTONE POWER STATION, UNIT NO. 2 -

SUMMARY

OF TELECONFERENCE RE: VERBAL AUTHORIZATION FOR RELIEF REQUEST RR-89-67 (TAC NO. ME2296)

This memorandum summarizes the telephone discussion on November 10, 2009, between the U.S. Nuclear Regulatory Commission (NRC) staff and Dominion Nuclear Connecticut, Inc. (DNC or the licensee) regarding DNCs request for relief RR-89-67 for Millstone Power Station, Unit No. 2 (MPS2).

By letter dated September 22, 2009 (Agencywide Documents Access and Management System Accession No. ML092710151), DNC submitted Alternative Request RR-89-67 as an alternative for the repair examination requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section Xl. In July 2009, the licensee repaired the degraded partial penetration weld, RCPA-RC-95-W-4, and base metal of the P40A reactor coolant pump (RCP) seal cooler return line at MPS2. Alternative Request RR-89-67 provides an alternative to the examination requirements in the ASME Code,Section XI.

The NRC staff has completed its review and finds that requiring radiographic testing and hydro testing for the repair of weld RCPA-RC-95-W-4 would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. The NRC staff concludes that the proposed alternative in Request RR-89-67 is acceptable because it provides reasonable assurance of structural integrity of weld RCPA-RC-95-W-4.

Therefore, pursuant to Title 10 of the Code of Federal Regulations, Part 50.55a(a)(3)(ii), the NRC staff verbally authorized the use of Relief Request RR-89-67 for the repair of weld RCPA-RC-95-W-4 for the remainder of the life of the A RCP seal cooler at MPS2.

The NRC's written final safety evaluation will follow. A list of the participants on the call is enclosed.

Docket No. 50-336

Enclosure:

As stated Distribution:

PUBLIC RidsNrrMillstone Resource RidsNrrDorlLpl1-2 Resource RidsNrrLAABaxter Resource RidsRgn1MailCenter Resource RidsNrrDciCpnb Resource LPLI-2 Reading JTsao, NRR ADAMS Accession No.: ML093140625 TITLE LPL1-2/PM LPL1-2/LA CPNB/BC LPL1-2/BC NAME CSanders ABaxter TChan HChernoff (w/comment)

DATE 11/16/2009 11/16/2009 11/16/2009 11/17/2009 Official Record Copy

LIST OF PARTICIPANTS NOVEMBER 10, 2009, CONFERENCE CALL RELIEF REQUEST RR-89-67 MILLSTONE POWER STATION, UNIT NO. 2 DOCKET NO. 50-336 U.S. Nuclear Regulatory Commission Terence Chan, NRR Harold Chernoff, NRR Carleen Sanders, NRR Thomas Setzer, RI Steven Shaffer, RI John Tsao, NRR Brian Haagensen, RI James Krafty, RI Lauren Gibson, NRR Harold Gray, RI Dominion Nuclear Connecticut, Inc William Bartron A.J. Jordan Rich MacManus Jeff Semancik Clark Maxson Brian Krauth