ML15113A707
| ML15113A707 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/24/1999 |
| From: | Labarge D NRC (Affiliation Not Assigned) |
| To: | Mccollum W DUKE POWER CO. |
| References | |
| GL-92-01, GL-92-1, TAC-MA0557, TAC-MA0578, TAC-MA0579, TAC-MA557, TAC-MA578, TAC-MA579, NUDOCS 9906280268 | |
| Download: ML15113A707 (7) | |
Text
p t REG&Z UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 24, 1999 Mr. W. R. McCollum, Jr.
Vice President, Oconee Site Duke Energy Corporation P. O. Box 1439 Seneca, SC 29679
SUBJECT:
OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 RE: GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1, "REACTOR VESSEL STRUCTURAL INTEGRITY" (TAC NOS. MA0557, MA0578, AND MA0579)
Dear Mr. McCollum:
On May 19, 1995, the NRC issued Generic Letter 92-01, Revision 1, Supplement 1 (GL 92-01.,
Rev. 1, Supp. 1), "Reactor Vessel Structural Integrity," to holders of nuclear operating licenses.
It required addressees:
(1) to identify, collect and report any new data pertinent to the analysis of structural integrity of the reactor pressure vessels (RPVs) at their nuclear plants, and (2) to assess the impact of that data on their RPV integrity analyses relative to the requirements of Sections 50.60 and 50.61 to Part 50 of Title 10 of the Code of Federal Regulations (10 CFR 50.60 and 10 CFR 50.61), and to the requirements of Appendices G and H to Part 50 of Title 10 of the Code of Federal Regulations (Appendices G and H to 10 CFR Part 50).
On August 16, 1995, the Duke Energy Corporation responded to GL 92-01, Rev. 1, Supp. 1, and provided information relative to the structural integrity assessments for the Oconee Nuclear Station, Units 1, 2, and 3. The staff evaluated this information and provided its conclusions by letter dated Auaust 6, 1996.
Subsequently, the Babcock and Wilcox (B&W) Owners Group submitted additional data regarding the alloying chemistries of beltline welds in B&W fabricated vessels. The additional alloying data was submitted in Topical Report BAW-2325, Revision 1, for B&W fabricated RPV welds. As a result of its review of this information, the staff determined that additional information was necessary relative to the structural integrity assessments for the Oconee Nuclear Station, Units 1, 2, and 3.
Consequently, on March 27, 1998, the staff issued a request for additional information (RAI) regarding the alloying chemistries of beltline welds, your assessment of surveillance data for the pressure-temperature (P-T) limits, and pressurized thermal shock (PTS) assessments for the Oconee Nuclear Station, Units 1, 2, and 3. In this RAI, the staff requested that you provide a reassessment of the alloying chemistries for the beltline welds and RPV surveillance welds relative to the chemistries provided in the topical report, and the impact of any changes to the best-estimate chemistries for the beltline RPV welds on the structural integrity assessments relative to the requirements of 10 CFR 50.60, 10 CFR 50.61, and Appendices G and H to 10 CFR Part 50, as applicable to the licensing bases for the Oconee Nuclear Station.
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00 W. R. McCollum, Jr.
- 2 By letter dated June 25, 1998, you provided your response to the RAI. As a result of the staff's review of your response and your original response to GL 92-01, Revision 1, GL 92-01, Rev. 1, Supp. 1, the staff has revised the information for Oconee Nuclear Station, Units 1, 2, and 3 in the Reactor Vessel Integrity Database (RVID) and is releasing it as RVID Version 2. Note that this revision to the RVID includes the end-of-license neutron fluence information reported in Table 1 b of Topical Report BAW-2325, Rev. 1. This fluence information is also consistent with the fluence provided in your request to amend the technical specifications for the Oconee Nuclear Station P-T operating curves that was submitted by letter dated May 11, 1999, that is under staff review.
In addition, potential discrepancies related to the fluences assigned for the R. E. Ginna surveillance capsule data (weld wire heat 61782) in the BAW-2325, Revision 1, report were discovered in the staff's review of R. E. Ginna. The fluence values recorded for this data and the assessment of the Oconee Nuclear Station, Unit 1 weld using this information reflect what the staff believes to be the most accurate and up-to-date information submitted by R. E. Ginna.
While this information resulted in a net increase in the RTPTS value for the Oconee Nuclear Station, Unit 1 weld manufactured from weld wire heat 61782, it remains a non-limiting material.
The new database information is posted on the world-wide-web at a location that is linked to the NRC home page (http://www.nrc.gov/NRR/RVID/index.html). We request that you review this information and provide comments, if needed, by September 1, 1999. No additional information is necessary regarding the structural integrity assessments. Future submittals on P-T limits, PTS, or upper shelf energy (USE) should reference the most current information.
This completes NRC staff's action on this issue and closes TAC Nos. MA0557, MA0558, and MA0559.
Sincerely, David E. LaBarge, Senior Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287 cc: See next page
Oconee Nuclear Station cc:
Ms. Lisa F. Vaughn Mr. J. E. Burchfield Legal Department (PBO5E)
Compliance Manager Duke Energy Corporation Duke Energy Corporation 422 South Church Street Oconee Nuclear Site Charlotte, North Carolina 28201-1006 P. 0. Box 1439 Seneca, South Carolina 29679 Anne Cottington, Esquire Winston and Strawn Ms. Karen E. Long 1400 L Street, NW.
Assistant Attorney General Washington, DC 20005 North Carolina Department of Justice Mr. Rick N. Edwards P. O. Box 629 Framatome Technologies Raleigh, North Carolina 27602 Suite 525 1700 Rockville Pike L. A. Keller Rockville, Maryland 20852-1631 Manager - Nuclear Regulatory Licensing Manager, LIS Duke Energy Corporation NUS Corporation 526 South Church Street 2650 McCormick Drive, 3rd Floor Charlotte, North Carolina 28201-1006 Clearwater, Florida 34619-1035 Mr. Richard M. Fry, Director Senior Resident Inspector Division of Radiation Protection U. S. Nuclear Regulatory North Carolina Department of Commission Environment, Health, and 7812B Rochester Highway Natural Resources Seneca, South Carolina 29672 3825 Barrett Drive Raleigh, North Carolina 27609-7721 Virgil R. Autry, Director Division of Radioactive Waste Management Mr. Steven P. Shaver Bureau of Land and Waste Management Senior Sales Engineer Department of Health and Environmental Westinghouse Electric Company Control 5929 Carnegie Blvd.
2600 Bull Street Suite 500 Columbia, South Carolina 29201-1708 Charlotte, North Carolina 28209 County Supervisor of Oconee County Walhalla, South Carolina 29621
A
~Ef-STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 205554)001 June 24, 1999 Mr. W. R. McCollum, Jr.
Vice President, Oconee Site Duke Energy Corporation P. 0. Box 1439 Seneca, SC 29679
SUBJECT:
OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 RE: GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1, "REACTOR VESSEL STRUCTURAL INTEGRITY" (TAC NOS. MA0557, MA0578, AND MA0579)
Dear Mr. McCollum:
On May 19, 1995, the NRC issued Generic Letter 92-01, Revision 1, Supplement 1 (GL 92-01, Rev. 1, Supp. 1), "Reactor Vessel Structural Integrity," to holders of nuclear operating licenses.
It required addressees:
(1) to identify, collect and report any new data pertinent to the analysis of structural integrity of the reactor pressure vessels (RPVs) at their nuclear plants, and (2) to assess the impact of that data on their RPV integrity analyses relative to the requirements of Sections 50.60 and 50.61 to Part 50 of Title 10 of the Code of Federal Regulations (10 CFR 50.60 and 10 CFR 50.61), and to the requirements of Appendices G and H to Part 50 of Title 10 of the Code of Federal Regulations (Appendices G and H to 10 CFR Part 50).
On August 16, 1995, the Duke Energy Corporation responded to GL 92-01, Rev. 1, Supp. 1, and provided information relative to the structural integrity assessments for the Oconee Nuclear Station, Units 1, 2, and 3. The staff evaluated this information and provided its conclusions by letter dated August 6, 1996.
Subsequently, the Babcock and Wilcox (B&W) Owners Group submitted additional data regarding the alloying chemistries of beltline welds in B&W fabricated vessels. The additional alloying data was submitted in Topical Report BAW-2325, Revision 1, for B&W fabricated RPV welds. As a result of its review of this information, the staff determined that additional information was necessary relative to the structural integrity assessments for the Oconee Nuclear Station, Units 1, 2, and 3.
Consequently, on March 27, 1998, the staff issued a request for additional information (RAI) regarding the alloying chemistries of beltline welds, your assessment of surveillance data for the pressure-temperature (P-T) limits, and pressurized thermal shock (PTS) assessments for the Oconee Nuclear Station, Units 1, 2, and 3. In this RAI, the staff requested that you provide a reassessment of the alloying chemistries for the beltline welds and RPV surveillance welds relative to the chemistries provided in the topical report, and the impact of any changes to the best-estimate chemistries for the beltline RPV welds on the structural integrity assessments relative to the requirements of 10 CFR 50.60, 10 CFR 50.61, and Appendices G and H to 10 CFR Part 50, as applicable to the licensing bases for the Oconee Nuclear Station.
W. R. McCollum, Jr.
- 2 By letter dated June 25, 1998, you provided your response to the RAI. As a result of the staff's review of your response and your original response to GL 92-01, Revision 1, GL 92-01, Rev. 1, Supp. 1, the staff has revised the information for Oconee Nuclear Station, Units 1, 2, and 3 in the Reactor Vessel Integrity Database (RVID) and is releasing it as RVID Version 2. Note that this revision to the RVID includes the end-of-license neutron fluence information reported in Table 1 b of Topical Report BAW-2325, Rev. 1. This fluence information is also consistent with the fluence provided in your request to amend the technical specifications for the Oconee Nuclear Station P-T operating curves that was submitted by letter dated May 11, 1999, that is under staff review.
In addition, potential discrepancies related to the fluences assigned for the R. E. Ginna surveillance capsule data (weld wire heat 61782) in the BAW-2325, Revision 1, report were discovered in the staff's review of R. E. Ginna. The fluence values recorded for this data and the assessment of the Oconee Nuclear Station, Unit 1 weld using this information reflect what the staff believes to be the most accurate and up-to-date information submitted by R. E. Ginna.
While this information resulted in a net increase in the RTPTS value for the Oconee Nuclear Station, Unit 1 weld manufactured from weld wire heat 61782, it remains a non-limiting material.
The new database information is posted on the world-wide-web at a location that is linked to the NRC home page (http://www.nrc.gov/NRR/RVID/index.htmi). We request that you review this information and provide comments, if needed, by September 1, 1999. No additional information is necessary regarding the structural integrity assessments. Future submittals on P-T limits, PTS, or upper shelf energy (USE) should reference the most current information.
This completes NRC staff's action on this issue and closes TAC Nos. MA0557, MA0558, and MA0559.
Sincerely, David E. LaBarge, Senior Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287 cc: See next page
Oconee Nuclear Station cc:
Ms. Lisa F. Vaughn Mr. J. E. Burchfield Legal Department (PBO5E)
Compliance Manager Duke Energy Corporation Duke Energy Corporation 422 South Church Street Oconee Nuclear Site Charlotte, North Carolina 28201-1006 P. 0. Box 1439 Seneca, South Carolina 29679 Anne Cottington, Esquire Winston and Strawn Ms. Karen E. Long 1400 L Street, NW.
Assistant Attorney General Washington, DC 20005 North Carolina Department of Justice Mr. Rick N. Edwards P. 0. Box 629 Framatome Technologies Raleigh, North Carolina 27602 Suite 525 1700 Rockville Pike L. A. Keller Rockville, Maryland 20852-1631 Manager - Nuclear Regulatory Licensing Manager, LIS Duke Energy Corporation NUS Corporation 526 South Church Street 2650 McCormick Drive, 3rd Floor Charlotte, North Carolina 28201-1006 Clearwater, Florida 34619-1035 Mr. Richard M. Fry, Director Senior Resident Inspector Division of Radiation Protection U. S. Nuclear Regulatory North Carolina Department of Commission Environment, Health, and 7812B Rochester Highway Natural Resources Seneca, South Carolina 29672 3825 Barrett Drive Raleigh, North Carolina 27609-7721 Virgil R. Autry, Director Division of Radioactive Waste Management Mr. Steven P. Shaver Bureau of Land and Waste Management Senior Sales Engineer Department of Health and Environmental Westinghouse Electric Company Control 5929 Carnegie Blvd.
2600 Bull Street Suite 500 Columbia, South Carolina 29201-1708 Charlotte, North Carolina 28209 County Supervisor of Oconee County Walhalla, South Carolina 29621
W. R. McCollum, Jr.
une 24, 1999 By letter dated June 25, 1998, you provided your response to the RAL. As a result of the staff's review of your response and your original response to GL 92-01, Revision 1, GL 92-01, Rev. 1, Supp. 1, the staff has revised the information for Oconee Nuclear Station, Units 1, 2, and 3 in the Reactor Vessel Integrity Database (RVID) and is releasing it as RVID Version 2. Note that this revision to the RVID includes the end-of-license neutron fluence information reported in Table lb of Topical Report BAW-2325, Rev. 1. This fluence information is also consistent with the fluence provided in your request to amend the technical specifications for the Oconee Nuclear Station P-T operating curves that was submitted by letter dated May 11, 1999, that is under staff review.
In addition, potential discrepancies related to the fluences assigned for the R. E. Ginna surveillance capsule data (weld wire heat 61782) in the BAW-2325, Revision 1, report were discovered in the staff's review of R. E. Ginna. The fluence values recorded for this data and the assessment of the Oconee Nuclear Station, Unit 1 weld using this information reflect what the staff believes to be the most accurate and up-to-date information submitted by R. E. Ginna.
While this information resulted in a net increase in the RTPTS value for the Oconee Nuclear Station, Unit 1 weld manufactured from weld wire heat 61782, it remains a non-limiting material.
The new database information is posted on the world-wide-web at a location that is linked to the NRC home page (http://www.nrc.gov/NRR/RVID/index.html). We request that you review this information and provide comments, if needed, by September 1, 1999. No additional information is necessary regarding the structural integrity assessments. Future submittals on P-T limits, PTS, or upper shelf energy (USE) should reference the most current information.
This completes NRC staff's action on this issue and closes TAC Nos. MA0557, MA0558, and MA0559.
Sincerely, Original signed by:
David E. LaBarge, Senior Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287 cc: See next page Distribution:
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