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Category:Safety Evaluation Report
MONTHYEARML0407005612004-03-10010 March 2004
3/10/04, H.B.Robinson, Amendment, Deletion of Additional Condition Related to Cycle Length
ML0402009912004-01-20020 January 2004
App. D - References
ML0402009902004-01-20020 January 2004
App. C - Principal Contributors
ML0402009892004-01-20020 January 2004
App. B - Chronology
ML0402009882004-01-20020 January 2004
App. a - Commitment Listing Table
ML0402009872004-01-20020 January 2004
Sect. 5 - Review by the Advisory Committee on Reactor Safeguards and Sect. 6 - Conclusions
ML0402009862004-01-20020 January 2004
Sect. 4 - Time Limited Aging Analyses
ML0402009852004-01-20020 January 2004
Section 3 - Aging Management Reviews
ML0402009842004-01-20020 January 2004
Sect. 2 - Structures and Components Subject to an Aging Management Review
ML0402009832004-01-20020 January 2004
Sect. 1 - Introduction and General Information
ML0335606222003-12-22022 December 2003
Amendment No. 198, Elimination of Neutron Absorption Credit for Boraflex
ML0323705022003-08-25025 August 2003
SER-Appendix D: References
ML0323704072003-08-25025 August 2003
SER-Cover Page, H. B. Robinson
ML0323704232003-08-25025 August 2003
SER-Section 1, Introduction and General Discussion
ML0323704342003-08-25025 August 2003
SER-Section 2, Structures and Components Subject to an Aging Management Review
ML0323704432003-08-25025 August 2003
SER-Section 3, Aging Management Review
ML0323704472003-08-25025 August 2003
SER-Section 4, Time-Limited Aging Analyses
ML0323704562003-08-25025 August 2003
SER-Section 5 & 6, Review by the Advisory Committee on Reactor Safeguards and Conclusions
ML0323704742003-08-25025 August 2003
SER-Appendix a, Commitment Listings
ML0323704822003-08-25025 August 2003
SER-Appendix B: Chronology
ML0323704872003-08-25025 August 2003
SER-Appendix C: Principal Contributors
ML0201504992002-01-14014 January 2002
Amendment, Elimination of Requirements for the Post-Accident Sampling System
2004-03-10
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5 REVIEW BY THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS The Advisory Committee on Reactor Safeguards (ACRS) will review the 10 CFR 54 portion of the Robinson Nuclear Plant (RNP) license renewal application(LRA). The Carolina Power and Light (CP&L) Company and the staff will meet with ACRS full committee to discuss issues associated with the review of the LRA.
After the ACRS completes its review of the RNP LRA and SER, the full committee will issue a report discussing the results of its review. This ACRS report will be included in an update to this SER. The staff will address any issues and concerns identified in that report.
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6 CONCLUSIONS The staff reviewed Robinson Nuclear Plant (RNP) license renewal application in accordance with Commission regulations and NUREG-1800, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants, dated July, 2001. In 10 CFR 54.29, the staff identifies the standards for issuance of a renewed license.
On the basis of its evaluation of the application as discussed above, the staff has determined that the requirements of 10 CFR 54.29 have been met.
The staff notes the requirements of Subpart A of 10 CFR Part 51 are documented in NUREG-1437, Supplement 13, Generic Environmental Impact Statement for License Renewal of Nuclear Plants, dated December 12, 2003.
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