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MONTHYEARML1126600972011-09-28028 September 2011 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 Project stage: Approval 2011-09-28
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Category:Letter
MONTHYEARIR 05000317/20230042024-02-0101 February 2024 Integrated Inspection Report 05000317/2023004 and 05000318/2023004 ML24029A0102024-01-29029 January 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000317/2024010 and 05000318/2024010 ML24003A8872024-01-19019 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0033 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 05000318/LER-2023-004, Submittal of LER 2023-004-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Submittal of Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-01-16016 January 2024 Submittal of LER 2023-004-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Submittal of Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer ML24011A0732024-01-11011 January 2024 Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping 05000318/LER-2023-002, Forward LER 2023-002-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-01-0808 January 2024 Forward LER 2023-002-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer 05000318/LER-2023-003, Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip2024-01-0808 January 2024 Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip ML24005A0222024-01-0505 January 2024 Revised Steam Generator Tube Inspection Reports ML23304A0642024-01-0202 January 2024 Issuance of Amendment No. 349 to Modify the Long-Term Coupon Surveillance Program RS-23-125, Request for Exemption from 10 CFR 2.109(b)2023-12-0707 December 2023 Request for Exemption from 10 CFR 2.109(b) ML23331A2992023-11-27027 November 2023 Submittal of Condition Prohibited by Technical Specifications Due to Failure to Sample Diesel Generator Fuel Oil Storage Tank IR 05000317/20230102023-11-20020 November 2023 Biennial Problem Identification and Resolution Inspection Report 05000317/2023010 and 05000318/2023010 ML23318A4722023-11-14014 November 2023 Supplement to License Amendment Request to Adopt TSTF-59-A ML23317A1032023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums ML23310A0442023-11-0707 November 2023 Project Manager Assignment IR 05000317/20230402023-11-0202 November 2023 95001 Supplemental Inspection Report 05000317/2023040 and Follow-Up Assessment Letter IR 05000317/20230032023-11-0101 November 2023 Integrated Inspection Report 05000317/2023003 and 05000318/2023003 IR 05000317/20230902023-10-26026 October 2023 Final Significance Determination of a White Finding with Assessment Follow-Up and Notice of Violation; 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UNITED STATES NUCLEAR REGULATORY COMMISSION 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
SUBJECT:
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 E 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 0
WCAP-17365-NP, "Analysis of Capsule 284 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 10 19 n/cm 2 . 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 pressure 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
ML112660097 OFF LPL 1-1/PM LPL 1-1/LA CVIB/BC LPL 1-1/BC SSheng for NAME DPickett SLittle MMitchell DATE 09128/11 09/28/11 09/20/11