ML12335A484
| ML12335A484 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 11/30/2009 |
| From: | - No Known Affiliation |
| To: | Atomic Safety and Licensing Board Panel |
| SECY RAS | |
| References | |
| RAS 21619, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01 NUREG-1930 | |
| Download: ML12335A484 (7) | |
Text
United States Nuclear Regulatory Commission Official Hearing Exhibit NYS00326F Entergy Nuclear Operations, Inc. Submitted: December 22, 2011 In the Matter of:
(Indian Point Nuclear Generating Units 2 and 3)
V\..~P.R REG(J<.q)<o ASLBP #: 07-858-03-LR-BD01 l~\
Docket #: 05000247 l 05000286
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Exhibit #: NYS00326F-00-BD01 Identified: 10/15/2012
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'" ~ Admitted: 10/15/2012 Withdrawn:
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'1"'....1-: 0' i Rejected: Stricken:
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. "APPENDIX D: REFERENCES
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SER Related to Alternate Shutdown Power Supply, Process Monitoring and PORV Operator Action per Appendix R, Sections IILG.3 and IILL, dated April 16, 1984 (ADAMS Public Legacy Library Accession Nos. 8405010052, 8405010057, 8405010061)
SER Related to Exemption from Requirements of Appendix R to 10 CFR 50 re Fire Protection, dated October 16, 1984 (ADAMS Public Legacy Library Accession Nos. 8410290219, 8410290223, 8410290224)
SER Supporting NRC Recommendation to Grant Licensee Exemption Request re Penetration Seals in Control Room Floor, dated September 16, 1985 (ADAMS Public Legacy Library Accession No. 8509190273)
SER Granting July 13, 1985 Request for Exemption from 10 CFR 50, Appendix R, Section IILJ, dated November 13, 1985 (ADAMS Public Legacy Library Accession Nos. 8511250495, 8511250496,8511250498)
SER for Exemption Granting Seven Exemptions from the Technical Requirements of Sections IILG and IILJ of Appendix R to 10 CFR 50, dated January 7, 1987 (ADAMS Accession No.
SER for Exemption Granting July 13, 1983 Request for Relief from Technical Requirements of Section IILG.2 of 10 CFR 50, Appendix R, dated March 4, 1987 (ADAMS Public Legacy Library Accession Nos. 8703110128 and 8703110193)
SER Accepting Utility Reevaluation of Alternative Shutdown Capability in Accordance with Requirements of Appendix R to 10 CFR 50, Section IILG.3 and III.L, dated September 9, 1988 (ADAMS Public Legacy Library Accession Nos. 8809150139 and 8809150145)
SER Supporting September 11, 1985 and September 14, 1988 Submittals of Clarifications to Post-Fire Safe Shutdown Methodology and Fire Protection Program, dated January 12, 1989 (ADAMS Public Legacy Library Accession Nos. 8901190302 and 8901190306)
SER Related to the Issuance of Amendment 110 to Facility Operating License No. DPR-64 for the Indian Point Nuclear Generating ~nit No.3, dated October 21, 1991 (ADAMS Accession No. ML003779328)
SER Related to the Issuance of Amendment 146 to Facility Operating License No. DPR-64 for the Indian Point Nuclear Generating Unit No.3, dated April 20, 1994 (ADAMS Accession No.
SER Related to the Issuance of an Exemption from the Requirements of 10 CFR Part 50, Appendix R, Section III,G.2 -Indian Point Nuclear Generating Unit No.3, dated January 5, 1995, (ADAMS Accession No. ML003780510)
D-8 OAGI0001368_00994
APPENDIX D: REFERENCES SER Related to the Issuance of Amendment 186 to Facility Operating License No. DPR-26, dated March 26, 1996 (ADAMS Accession No. ML003778424)
SER for IP2 dated October 15, 2004 (ADAMS Accession No. ML042890389)
SER for IP3 dated April 4, 2005 (ADAMS Accession No. ML050940136)
SER for IP3 dated March 18, 2005 (ADAMS Accession No. ML050770010),
SER for IP2 dated February 27,2006 (ADAMS Accession No. ML060090142)
Title 10 of the Code ,of Federal Regulations, Part 20, "Standards for Protection Against Radiation" Title 10 of the Code of Federal Regulations, Part 50, "Domestic Licensing of Production and Utilization Facilities" Title 10 of the Code of Federal Regulations, Part 54, "Requirements for Renewal of Operating Licenses for Nuclear Power Plants" Title 10 of the Code of Federal Regulations, Part 100, "Reactor Site Criteria" WCAP-12866, "Bottom-Mounted Instrumentation Flux Thimble Wear," January 1991 WCAP-13587, "Reactor Vessel Upper Shelf Energy Bounding Evaluation for Westinghouse Pressurized Water Reactors," February 1993 (ADAMS Public Legacy Library Accession No.
9303230154)
WCAP-13587, Revision 1, "Reactor Vessel Upper Shelf Energy Bounding Evaluation for Westinghouse Pressurized Water Reactors," September 1993 Safety Evaluation for WCAP-13587, Revision 1 (ADAMS Public Legacy Library Accession No.
9405060287)
Safety Evaluation for WCAP-14574, Revision 0, dated October 26, 2000 (ADAMS Accession No. ML003763768)
WCAP-14577, Revision 1-A, "License Renewal Evaluation: Aging Management for Reactor Internals," dated April 9, 1001 (ADAMS Accession No. ML011080790)
WCAP-15557, Revision 0, "Qualification of the Westinghouse Pressure Vessel Neutron Fluence Evaluation Methodology," S. L. Anderson, August 2000 0-9 OAGI0001368 00995
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APPENDIX D:'REFERENCES WCAP-15629, Revision 1, "Indian Point Unit 2 Heatupand Cooldown Limit Curves for Normal Operation and PTLR Support Documentation," T. J. Laubham, December 2001 (ADAMS Accession No. ML020170071)
WCAP-15805, "Analysis of Capsule X from the Carolina Power and Light Company H.B.
Robinson Unit 2 Reactor Vessel Radiation Surveillance Program," T. J. Laubham et aI.,
Westinghouse Electric Company LLC, March 2002. (ADAMS Accession No. ML0211190313)
WCAP-16157-NP, "Stretch Power Uprate NSSS and BOP" (ADAMS Accession No.
ML040370423 WCAP-16251-NP, "Analysis of Capsule X from Entergy's Indian Point Unit 3 Reactor Vessel Radiation Surveillance Program," July 292004 (ADAMS Accession No. ML042320088) 0-10 OAGI0001368 00996
NRC FORM 335 U.S. NUCLEAR ~EGULATORY COMMISSION 1. REPORT NUMBER
. j9-20(4) (Assigned by NRC, Add Vol., Supp., Rev.,
NRCMD3.7 and Addenduni Numbers, if any.)
BIBLIOGRAPHIC DATA SHEET (See instructions on the reverse) NUREG-1930, Volume 2
- 2. TITLE AND SUBTITLE 3. DATE REPORT PUBLISHED Safety Evaluation Report MONTH YEAR Related to the License Renewal of Indian Point Nuclear Generating Unit Nos. 2 and 3 November 2009
- 5. AUTHOR(S) 6. TYPE OF REPORT Kimberly Green Technical
- 7. PERIOD COVERED (Inclusive Dates) 04/23/07 -08/06/09 B. PERFORMING ORGANIZATION - NAME AND ADDRESS (If NRC, provide Division, Office or Region, U.S. Nuclear Regulatory Commission, and mailing address; if contractor, provide name and mailing address.)
Division of License Renewal Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
- 9. SPONSORING ORGANIZATION - NAME AND ADDRESS (If NRC. type "Same as above"; if contractor, provide NRC Division, Office or Region, U.S. Nuclear Regulatory Commission, and mailing address.)
Same as above
- 10. SUPPLEMENTARY NOTES 11 . ABSTRACT (200 words or less)
This safety evaluation report (SER) documents the technical review of the Indian Point Nuclear Generating Unit Nos. 2 and 3 (IP2 and IP3) license renewal application (LRA) by the U.S. Nuclear Regulatory Commission (NRC) staff. By letter dated April 23, 2007, and as supplemented by letters dated May 3 and June 21, 2007, Entergy Nuclear Operations, Inc. (Entergy or the applicant), submitted the LRA in accordance with Title 10, Part 54, of the Code of Federal Regulations. Entergy requests renewal of the IP2 and IP3 operating licenses for a period of 20 years beyond the current expirations at midnight on September 28, 2013, for IP2, and at midnight on December 12, 2015, for IP3.
Indian Point is located approximately 24 miles north of the New York City boundary line. The NRC issued operating licenses on September 28, 1973, for IP2, and on December 12,1975, for IP3. IP2 and IP3 employ a pressurized water reactor design with a dry ambient containment. Westinghouse Electric Corporation supplied the nuclear steam supply system. The licensed output of each unit is 3216 megawatts thermal with a gross electrical output of approximately 1080 megawatts electric.
On January 15, 2009, the staff issued an SER with open items, in which it identified 20 open items necessitating further review.
This SER presents the staffs review of information submitted through August 6, 2009. The staff resolved the 20 open items before it made its final determination on the LRA.
- 12. KEY WORDSIDESCRIPTORS (Ust words or phrases that will assist researchers in locating the report.) 13. AVAILABILITY STATEMENT 10 CFR Part 54, license renewal, Indian Point, scoping and screening, aging management, aging unlimited
- 14. SECURITY CLASSIFICATION effects, time-limited aging analysis, safety evaluation report (This Page) unclassified (This Report) unclassified
- 15. NUMBER OF PAGES
- 16. PRICE NRC FORM 335 (9-2004) . PRINTED ON RECYCLED PAPER OAGI0001368 00997
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