ML080920170: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
Line 3: | Line 3: | ||
| issue date = 04/09/2008 | | issue date = 04/09/2008 | ||
| title = Revision to Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedule | | title = Revision to Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedule | ||
| author name = Pickett D | | author name = Pickett D | ||
| author affiliation = NRC/NRR/ADRO/DORL/LPLI-1 | | author affiliation = NRC/NRR/ADRO/DORL/LPLI-1 | ||
| addressee name = Spina J | | addressee name = Spina J | ||
| addressee affiliation = Calvert Cliffs Nuclear Power Plant, Inc | | addressee affiliation = Calvert Cliffs Nuclear Power Plant, Inc | ||
| docket = 05000317 | | docket = 05000317 | ||
| license number = DPR-053 | | license number = DPR-053 | ||
| contact person = Pickett D | | contact person = Pickett D, NRR/DORL, 415-1364 | ||
| case reference number = TAC MD8235 | | case reference number = TAC MD8235 | ||
| document type = Letter, Safety Evaluation | | document type = Letter, Safety Evaluation | ||
Line 84: | Line 84: | ||
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). | 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 | |||
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- | 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- |
Revision as of 14:07, 12 July 2019
ML080920170 | |
Person / Time | |
---|---|
Site: | Calvert Cliffs ![]() |
Issue date: | 04/09/2008 |
From: | Pickett D NRC/NRR/ADRO/DORL/LPLI-1 |
To: | Spina J Calvert Cliffs |
Pickett D, NRR/DORL, 415-1364 | |
References | |
TAC MD8235 | |
Download: ML080920170 (5) | |
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