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MONTHYEARML0806601102008-03-0505 March 2008 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule Project stage: Other ML0809201702008-04-0909 April 2008 Revision to Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedule Project stage: Other ML0821105672008-07-29029 July 2008 Proposed Revision to the Schedule for Withdrawal of Reactor Vessel Material Surveillance Capsules Project stage: Withdrawal ML0821105652008-07-29029 July 2008 Transmittal of Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule Project stage: Request 2008-04-09
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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; Inspection Report 05000317/2023090 ML23289A1202023-10-16016 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML23279A1202023-10-0606 October 2023 Response to NRC Inspection Report and Preliminary White Finding IR 05000317/20230502023-09-29029 September 2023 Special Inspection Report 05000317/2023050 and Preliminary White Finding and Apparent Violation ML23272A1032023-09-29029 September 2023 Condition Prohibited by Technical Specifications Due to Inoperable Nuclear Instrumentation at Very Low Power IR 05000317/20234012023-09-18018 September 2023 Cyber Security Inspection Report 05000317/2023401 and 05000318/2023401 ML23254A0012023-09-0505 September 2023 Registration of Use of Casks to Store Spent Fuel IR 05000317/20230052023-08-31031 August 2023 Updated Inspection Plan for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 (Report 05000317/2023005 and 05000318/2023005) ML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML23241A8412023-08-29029 August 2023 Response to Request for Additional Information - Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping ML23240A3872023-08-28028 August 2023 Senior Reactor and Reactor Operator Initial License Examinations ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration ML23219A1662023-08-16016 August 2023 Request for Additional Information Regarding Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping (EPID: L-2023-LLR-0006) - Non-proprietary ML23228A1002023-08-15015 August 2023 Notification of Readiness for NRC 95001 Inspection ML23188A0402023-08-0808 August 2023 Issuance of Amendment Nos. 346 and 324 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML23214A1572023-08-0707 August 2023 Correction to the Renewed Facility Operating License Page 3 in Amendment No 345 IR 05000317/20230022023-08-0303 August 2023 Integrated Inspection Report 05000317/2023002 ML23188A0512023-07-13013 July 2023 Correction to the Renewed Facility Operating License Pages in Amendment Nos. 336 and 314 ML23186A0372023-07-13013 July 2023 Correction to the Renewed Facility Operating License Pages in Amendment Nos. 340 and 318 IR 05000317/20233012023-07-12012 July 2023 Initial Operator Licensing Examination Report 05000317/2023301 and 05000318/2023301 IR 05000317/20230122023-07-10010 July 2023 Commercial Grade Dedication Report 05000317/2023012 and 05000318/2023012 ML23180A2362023-06-29029 June 2023 Correction of Errors on Technical Specification Pages RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators ML23156A6752023-06-20020 June 2023 Request for Withholding Information from Public Disclosure for Proposed Alternative to the Requirements for Repair/Replacement of Saltwater System Buried Piping 2024-02-01
[Table view] Category:Safety Evaluation
MONTHYEARML23304A0642024-01-0202 January 2024 Issuance of Amendment No. 349 to Modify the Long-Term Coupon Surveillance Program ML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration ML23188A0402023-08-0808 August 2023 Issuance of Amendment Nos. 346 and 324 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23086C0672023-04-24024 April 2023 Issuance of Amendment Nos. 345 and 323 Deletion of License Conditions Related to Decommissioning Trust ML22195A0252023-01-0303 January 2023 Authorization and Safety Evaluation for Alternative Request No. ISI-05-016 ML22293B8052022-11-30030 November 2022 Constellation Energy Generation, Llc_Fleet - Request to Authorize Use Honeywell Mururoa V4F1 R Supplied Air Suits ML22202A5142022-07-28028 July 2022 Authorization of Relief Request No. RR-ISI-05-20 Regarding Mitigation of Buried Saltwater System Piping Degradation ML22105A4052022-05-0202 May 2022 Authorization and Safety Evaluation for Proposed Alternative No. ISI-05-019 ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21347A8642022-01-13013 January 2022 Issuance of Amendment Nos. 342 and 320 Modifying the Licensing Basis to Allow for Full Core Offload with No Shutdown Cooling Loop Available During Certain Refueling Outages ML21299A0052021-12-14014 December 2021 Issuance of Amendments No. 340 and 318 Adoption of Technical Specifications Task Force Traveler TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML21277A2482021-11-16016 November 2021 Letter with Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (Public Version) ML21280A0782021-10-27027 October 2021 Proposed Alternative to Use of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-893 (Epids L-2020-LLR-0147 and L-2020-LLR-0148) ML21230A2062021-09-0303 September 2021 Proposed Alternative to Use ASME OM Code Case OMN-28 ML21190A0042021-09-0202 September 2021 Proposed Alternative to the Requirements of the ASME Section XI, Subsection Iwl Concerning Unbound Post-Tensioning Systems ML21216A2202021-08-0505 August 2021 Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting ML21166A1682021-06-25025 June 2021 ML21039A6362021-02-17017 February 2021 R. E. Ginna - Proposed Alternative to Use the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-885 ML21028A6732021-02-0303 February 2021 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L-2020-LLR-011 ML20363A2422021-01-26026 January 2021 Issuance of Amendment Nos. 339 and 317 Regarding Accident Tolerant Fuel Lead Test Assemblies (EPID L-2019-LLA-0282) - (Non-Proprietary) ML20356A1212021-01-15015 January 2021 Relief from the Requirements of the ASME Code ML20273A0882020-11-0909 November 2020 Issuance of Amendment Nos. 338 and 316 Revise Emergency Diesel Generator Surveillance Requirements for Frequency and Voltage Tolerances ML20287A1302020-11-0505 November 2020 Review of Quality Assurance Program Changes ML20275A1022020-11-0404 November 2020 Proposed Alternative I4r-07 to the Requirements of the American Society of Mechanical Engineers Code ML20269A2002020-09-30030 September 2020 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117 ML20232A1712020-09-0101 September 2020 Request to Use Alternative Code Case OMN-26 ML20182A1942020-08-13013 August 2020 Issuance of Amendment Nos. 336 and 314 Concerning Reactor Coolant Pump Flywheel Inspection Program ML20134H9402020-07-0808 July 2020 Issuance of Amendments Revising the High Radiation Area Administrative Controls ML20113F0412020-04-30030 April 2020 Proposed Alternative to the Submittal Schedule for Certain Reports (COVID-19) ML20021A0702020-04-0606 April 2020 Issuance of Amendments to Delete License Conditions for Decommissioning Trusts ML19330D9092020-02-28028 February 2020 Issuance of Amendment Nos. 332 and 310 Risk-Informed Categorization and Treatment of Systems, Structures, and Components ML19337D0352020-02-28028 February 2020 Issuance of Amendment Nos. 333 and 311 Deletion of E-Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specifications ML20028E3992020-02-0404 February 2020 Proposed Alternative to Use ASME Code Case N-879 ML19298C9722019-10-31031 October 2019 50.69 Apla SE Input L-2018-LLA-0482 ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19165A2472019-08-26026 August 2019 Issuance of Amendment Nos 330 and 308 Relocation and Consolidation the Emergency Operations Facility and Joint Information Center for the Calvert Cliffs Nuclear Power Plant ML19168A1172019-07-29029 July 2019 Issuance of Relief Request 15R-03 Use of ASME Code N-513-4 ML19196A1232019-07-19019 July 2019 Issuance of Relief Request 15R-04 Use of Encoded Phased Array Ultrasonic Examination Techniques ML19192A2442019-07-18018 July 2019 Proposed Alternative to Use ASME Code Cases N-878 and N-880 ML19134A3732019-05-30030 May 2019 Issuance of Relief Request I5R-05 Relief from the Requirements of the ASME Code ML19136A2162019-05-30030 May 2019 Use of a Provision in a Later Edition of the ASME Code ML19053A5882019-04-19019 April 2019 Plants, Units 1 and 2 - Issuance of Amendment Nos. 329 and 307 Removal of an Exception to the Minimum Education Requirements for Shift Technical Advisors ML19046A0432019-02-25025 February 2019 Plants, Units 1 and 2 - Revision to the Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedule ML18365A3732019-01-22022 January 2019 Issuance of Amendment Nos. 328 and 306 to Extend Completion Time of Required Action D.3 of Technical Specification 3.8.1 to 14 Days ML18318A0142018-11-30030 November 2018 Correction to Amendment Nos. 326 and 304 Add Risk-Informed Completion Time Program ML18309A3012018-11-15015 November 2018 R. E. Ginna - Issuance of Amendment Nos. 327, 305, 232, 173, and 133, Respectively, Eliminating the Nuclear Advisory Committee Requirements ML18270A1302018-10-30030 October 2018 Issuance of Amendment Nos. 326 and 304 to Add Risk-Informed Completion Time Program 2024-01-02
[Table view] |
Text
April 9, 2008
Mr. James A. Spina, Vice President Calvert Cliffs Nuclear Power Plant, Inc.
Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702
SUBJECT:
CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NO. 1 - REVISION TO REACTOR PRESSURE VESSEL SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE (TAC NO. MD8235)
Dear Mr. Spina:
By letter dated March 5, 2008, Calvert Cliffs Nuclear Power Plant, Inc. submitted for Nuclear Regulatory Commission (NRC) staff review a request for revising the withdrawal schedule for the reactor pressure vessel (RPV) surveillance capsule at the 104° location for Calvert Cliffs Nuclear Power Plant (CCNPP), Unit No. 1. The purpose of the licensee's submittal was to provide a surveillance capsule withdrawal schedule for CCNPP, Unit No. 1 that is consistent with the most recent projected extended end-of-license fluence at one-quarter of the RPV wall thickness.
The NRC staff has completed its review and concludes that the proposed withdrawal schedule for the CCNPP, Unit No. 1 capsule mentioned above meets the requirements of the American Society for Testing and Materials Standard E185-82, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels," and Appendix H to Title 10 of the Code of Federal Regulations Part 50, "Reactor Vessel Material Surveillance Program Requirements." The staff's safety evaluation is enclosed.
Please contact me at 301-415-1364 if you have any questions.
Sincerely, /RA/
Douglas V. Pickett, S enior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Docket No. 50-317
Enclosure:
Safety Evaluation
cc w/encl: See next page
ML080920170 OFFICE LPLI-1/PM LPLI-1/LA CVIB/BC LPLI-1/BC
NAME DPickett SLittle MMitchell as signed on MKowal DATE 4 /4/ 08 4 / 8/ 08 3 / 20 / 08 4 /9/ 08 Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2
cc:
Mr. Michael J. Wallace, President Constellation Energy Nuclear Group, LLC 750 East Pratt Street, 18 th Floor Baltimore, MD 21202
Mr. John M. Heffley, Senior Vice President and Chief Nuclear Officer Constellation Energy Nuclear Generation Group 111 Market Place Baltimore, MD 21202
President Calvert County Board of Commissioners 175 Main Street Prince Frederick, MD 20678
Mr. Carey Fleming, Esquire Sr. Counsel - Nuclear Generation Constellation Energy Nuclear Group, LLC 750 East Pratt Street, 17 th floor Baltimore, MD 21202
Mr. Jay S. Gaines Director, Licensing Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702
Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 287 St. Leonard, MD 20685
Ms. Susan T. Gray, Program Manager Power Plant Assessment Program Maryland Department of Natural Resources Tawes State Office Building B-3 580 Taylor Avenue Annapolis, MD 21401
Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406
Ms. Kristen A. Burger, Esquire Maryland People's Counsel 6 St. Paul Centre Suite 2102 Baltimore, MD 21202-1631
Ms. Patricia T. Birnie, Esquire Co-Director Maryland Safe Energy Coalition P.O. Box 33111 Baltimore, MD 21218
Mr. Roy Hickok NRC Technical Training Center 5700 Brainerd Road Chattanooga, TN 37411-4017
Mr. Louis S. Larragoite Manager - Nuclear Licensing Constellation Energy Nuclear Generation Group 111 Market Place, 2 nd Floor Baltimore, MD 21202
Enclosure
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REACTOR VESSEL SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE REVISION CALVERT CLIFFS NUCLEAR POWER PLANT, INC.
CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-317
1.0 INTRODUCTION
By letter dated March 5, 2008 (Agencywide Documents Access Management Systems Accession No. ML080660110), Calvert Cliffs Nuclear Power Plant, Inc. submitted for staff review a request for revising the withdrawal schedule for the reactor pressure vessel (RPV) surveillance capsule at the 104° location for Calvert Cliffs Nuclear Power Plant (CCNPP), Unit No. 1. The purpose of the licensee's submittal was to provide an RPV surveillance capsule withdrawal schedule for CCNPP, Unit No. 1, that is consistent with the recently projected 60-year end-of-license (EOL) fluence at one-quarter of the RPV wall thickness (1/4T).
2.0 REGULATORY
REQUIREMENTS
The surveillance program for CCNPP, Unit No. 1, was implemented to monitor the radiation-induced changes in the mechanical and impact properties of the RPV materials. The surveillance program was established in accordance with Appendix H to Title 10 of the Code of Federal Regulations Part 50 (10 CFR Part 50), "Reactor Vessel Material Surveillance Program Requirements." Appendix H to 10 CFR Part 50 requires licensees to monitor changes in the fracture toughness properties of ferritic materials in the RPV beltline region of light water nuclear power reactors. Appendix H to 10 CFR Part 50 states that the design of the surveillance program and the withdrawal schedule must meet the requirements of the edition of the American Society for Testing and Materials (ASTM) Standard E185, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels," that is current on the issue date of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) to which the reactor vessel was purchased. Later editions of ASTM E185 may be used including those editions through 1982 (ASTM E 185-82). The RPV surveillance program for CCNPP, Unit No. 1, was initially established per ASTM E 185-70, which was the edition of the ASTM standard that was current on the issue date of the ASME Code to which the CCNPP, Unit No. 1 RPV was designed. However, its current surveillance capsule withdrawal schedule has been developed in accordance with ASTM E 185-
- 82.
3.0 TECHNICAL EVALUATION
The licensee's RPV surveillance program for CCNPP, Unit No. 1, is in accordance with the ASTM E185-82 standard and has a five-capsule withdrawal schedule (the sixth capsule is
considered standby). This surveillance program, which was approved on November 8, 2000, was revised to satisfy the commitments stated in the NRC "Safety Evaluation Report Related to the License Renewal of Calvert Cliffs Nuclear Power Plant, Units 1 and 2 (NUREG-1705)" for properly monitoring changes in the fracture toughness properties of RPV beltline materials during the extended period of operation. Currently, the first two capsules have been withdrawn and analyzed. The third capsule, the capsule at the 104° location, was scheduled to be withdrawn during the CCNPP, Unit No. 1 spring 2008 refueling outage. This schedule was based on the projected 60-year EOL 1/4T fluence of 2.96 X 10 19 n/cm 2 (E > 1.0 MeV) and the same projected fluence in 2008 for the third capsule. As reported in the submittal, these projected values have been revised to 3.06 X 10 19 n/cm 2 (E > 1.0 MeV) for the 60-year EOL 1/4T fluence and 3.12 X 10 19 n/cm 2 (E > 1.0 MeV) for the 2010 capsule fluence. Based on this, the licensee proposed to withdraw the third capsule during the unit's spring 2010 refueling outage.
ASTM E185-82 recommends that in a five capsule surveillance program the third capsule be withdrawn and tested at the time when the accumulated neutron fluence of the capsule corresponds to approximately the EOL 1/4T fluence. As discussed above, it is evident that the newly projected 2010 fluence for the third capsule is closer to the EOL 1/4T fluence than the previously projected fluence for the third capsule in 2008. Therefore, the NRC staff determined that withdrawing the third capsule during the unit's spring 2010 refueling outage meets the ASTM E185-82 recommendation for the third capsule. Table 2 of the submittal showed that the withdrawal schedule for all other capsules (Capsules 4, 5, and standby) remained unchanged. This is reasonable considering the minor change in the projected 60-year EOL 1/4T fluence. Based on this, the staff determined that Capsules 4 and 5 still meet the ASTM E185-82 recommendation and the NUREG-1705 commitments. When better fluence predictions become available after the Capsule 3 data are analyzed, the licensee will perform additional evaluations to adjust, if necessary, the remaining capsule withdrawal schedules in accordance with 10 CFR Part 50, Appendix H, as stated in the submittal.
4.0 CONCLUSION
Based on the NRC staff's review of the submittal, the staff found that the revised withdrawal schedule for CCNPP, Unit No. 1, RPV satisfy the requirements of ASTM E185-82 and Appendix H to 10 CFR Part 50. In addition, the staff found that the revised withdrawal schedules for CCNPP still fulfills the commitment associated with Item 69 in Appendix E of NUREG-1705 for the renewed license period of 60 years. Therefore, the staff concludes that the licensee's modified withdrawal schedule for CCNPP, Unit No. 1 is acceptable. Principal Contributor: S. Sheng
Date: April 9, 2008