ML112660097

10 CFR Part 50, Appendix H. Test Report Requirements: Review of Report WCAP-17365-NP for Calvert Cliffs Unit No. 1 Reactor Vessel Surveillance Capsule 284 (TAC No. ME5964)

ML112660097
Person / Time
Site:	Calvert Cliffs
Issue date:	09/28/2011
From:	Pickett D V Plant Licensing Branch 1
To:	Gellrich G H Calvert Cliffs
Pickett D V, NRR/DORLLPL1-1, 415-1364
References
TAC ME5964
Download: ML112660097 (3)

Text

UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 September 28, 2011 Mr. George H. Gellrich, Vice President Calvert Cliffs Nuclear Plant, LLC Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702 TITLE 10 OF THE CODE OF FEDERAL REGULATIONS (10 CFR) PART 50, APPENDIX H, TEST REPORT REQUIREMENTS: REVIEW OF REPORT WCAP-17365-NP FOR CALVERT CLIFFS UNIT NO.1 REACTOR VESSEL SURVEILLANCE CAPSULE 284' (TAC NO. ME5964) Dear Mr. Gellrich: Appendix H to Part 50 of Title 10 of the Code of Federal Regulations (10 CFR Part 50), "Reactor Vessel Material Surveillance Program Requirements" (the rule), provides the Nuclear Regulatory Commission's (NRC's) surveillance and testing requirements for ferritic components of the reactor vessels (RVs) of operating U.S. light-water reactors. The rule requires licensed owners of U.S. light-water reactor facilities to install a number of surveillance capsules within the cavities of their RVs and to remove capsules and test the capsule materials in accordance with the withdrawal schedule and testing requirements of the American Society for Testing and Materials (ASTM) Standard Practice E-185. Paragraph IV.A of the rule requires the RV material surveillance capsule test results to be the subject of a summary technical report that is required to be submitted to the NRC within 1 year of the capsule withdrawal date. Paragraph IV.B of the rule requires that these reports shall include all data specified by ASTM Standard Practice 185-82 and the results of all fracture toughness tests conducted on the surveillance capsule materials in both the unirradiated and irradiated condition. By letter dated March 29, 2011, Calvert Cliffs Nuclear Power Plant, LLC, the licensee, submitted WCAP-17365-NP, "Analysis of Capsule 2840 from the Calvert Cliffs Unit No.1 Reactor Vessel Radiation Surveillance Program," to comply with the above requirements. WCAP-17365-NP provides the applicable fracture toughness test data for surveillance capsule 284' that was removed from the Calvert Cliffs Nuclear Power Plant, Unit No.1 (CCNPP1) having received a fluence (E > 1.0 MeV) of 2.33 x 1019 n/cm2. This report also re-analyzes all prior data that was reported in earlier reports for Standard Reference Material, as well as the fluence received by Capsule 97'. The surveillance program for the CCNPP1 RV currently utilizes the plant's own surveillance capsules as the basis for monitoring the embrittlement trends for the RV beltline materials. The surveillance weld material being irradiated in the CCNPP1 RV surveillance capsules was fabricated from Heat No. 33A277 weld wires. The Heat No. 33A277 surveillance weld is representative of the intermediate-to-Iower shell circumferential weld in the CCNPP1 RV. The surveillance plate materials being irradiated in the CCNPP1 RV surveillance capsules are representative of RV intermediate shell plate 0-7206-3.

G. Gellrich -2 The NRC staff has performed its review of report number WCAP-17365-NP and has confirmed that the report includes all of the data and test results that are required by Paragraph IV. B of 10 CFR Part 50, Appendix H and by ASTM Standard Practice E185-82. Furthermore, based on this review, the staff has not identified any immediate safety issues associated with the information provided in report number WCAP-17365-NP. The licensee will be expected to incorporate the updated surveillance data into the next revision of the plant's temperature limits report, as required by 10 CFR Part 50, Appendix G. Please contact me at 301-415-1364 if you have any questions. Sincerely, Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-317 cc: Distribution via Listserv G. Gellrich -The NRC staff has performed its review of report number WCAP-17365-NP and has confirmed that the report includes all of the data and test results that are required by Paragraph IV. B of 10 CFR Part 50, Appendix H and by ASTM Standard Practice E185-82. Furthermore, based on this review, the staff has not identified any immediate safety issues associated with the information provided in report numberWCAP-17365-NP. The licensee will be expected to incorporate the updated surveillance data into the next revision of the plant's temperature limits report, as required by 10 CFR Part 50, Appendix G. Please contact me at 301-415-1364 if you have any questions. Sincerely, Ira! Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-317 cc: Distribution via Listserv DISTRIBUTION: PUBLIC LPL1-1 r/f RidsNrrDorlLpL1-1 RidsNrrPMCalvertCliffs RldsOgcMailCenter RidsAcrsAcnwMailCenter RidsNrrDciCvib RidsRegion1 MailCenter DWidrevitz, I\IRR GDentel, R1 RidsNrrLASLittle ADAMS Accession No. ML112660097 LPL 1-1/PM LPL1-1/LA CVIB/BC SSheng for NAME DPickett SLittle MMitchell DATE 09128/11 09/28/11 09/20/11 OFFICIAL RECORD COPY OFF LPL1-1/BC