NL-05-2162, Results of Inspections Required by NRC Bulletin 2004-01 and First Revised NRC Order EA-03-009
| ML053470177 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 12/12/2005 |
| From: | Grissette D Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BL-04-001, EA-03-009, NL-05-2162 | |
| Download: ML053470177 (3) | |
Text
Don E. Grissette Southern Nuclear Vice President Operating Company. Inc.
40 lnverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.6474 Fax 205.992.0341 Deceniber 12, 2005 COMPANY Energy to Serve Your World Docket No.: 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-000 1 Vogtle Electric Generating Plant Results of Inspections Required by NRC Bulletin 2004-0 1 and First Revised NRC Order EA-03-009 Ladies and Gentlemen:
On February 20,2004, the NRC issued the First Revised NRC Order EA-03-009 to establish interim inspection requirements for reactor pressure vessel (RPV) heads at pressurized water reactors. On March 8, 2004, Southern Nuclear Operating Company (SNC) submitted an answer to the revised order which included a request for relaxation of the Order pursuant to the provisions of Paragraph 1V.F. SNC was granted relaxation of the Order by NRC SER dated September 13,2005. SNC completed visual inspections to identify potential boric acid leaks from pressure-retaining components above the RPV head as required by paragraph 1V.D of the Order during the recent fall 2005 refueling outage (2R11) at Unit 2 of the Vogtle Electric Generating Plant (VEGP-2). This report provides the results of the inspection as required by Paragraph 1V.E of the Order. This letter also reports the results of inspection of Alloy 8211821600 materials used in the fabrication of pressurizer nozzle penetrations as requested by NRC Bulletin 2004-01.
Examinations Required by the First Revised NRC Order EA-03-009, Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors:
As required by paragraph 1V.A of the Order, SNC calculated the Effective Degradation Year (EDY) value at the start of 2R11 for VEGP-2. The current EDY value is 2.81 years which places VEGP-2 into the Low (EDY 43) category for susceptibility to primary water stress corrosion cracking (PWSCC) established by Paragraph 1V.B. The susceptibility category determines the required examinations and timing of those examinations. As reported by SNC's June 28,2004 letter, SNC completed a bare metal visual (BMV) examination of >95% of the RPV top head surface including 360" around each RPV head penetration nozzle during the spring 2004 refueling outage (2R10) at VEGP-2. This examination satisfied the requirements of Paragraph IV.C.(3) of the Order consistent with SNC's request for relaxation. The relaxation request proposed to achieve substantial compliance with the 100% BMV examination requirement of Paragraph IV.C.(S)(a) by conducting a BMV examination of the RPV to the extent accessible. The inspection requirement of Paragraph 1V.D was required to be performed on the RPV top head during 2R11.
U. S. Nuclear Regulatory Commission NL-05-2 162 Page 2 Inspection Results:
Boron residue was observed on core exit thermal nozzle assembly at penetration 77 during the visual inspections of components above the RPV top head. The area containing the boric acid residue was cleaned and reinspected with no leakage observed.
Documentation:
The examination was documented by a written report and photographs.
Examinations Required by Bulletin 2004-01, Inspection of Alloy 8211821600 Materials Used in the Fabrication of Pressurizer Nozzle Penetrations and Steam Space Connections at Pressurized Water Reactors:
A BMV examination was performed on four 6" SafetyIRelief Nozzles (Numbers 2 1201-V6-002-W17, 18, 19, and 20) and one 4" Spray Nozzle (Number 21 20 1-V6-002-W2 1).
Inspection Results:
No evidence of material wastage or of leaking or cracked nozzles was found by BMV examinations.
Documentation:
The examinations performed were documented by a written report.
Mr. D. E. Grissette states he is a Vice President of Southern Nuclear Operating Company, is authorized to execute this oath on behalf of Southern Nuclear Operating Company and to the best of his knowledge and belief, the facts set forth in this letter are true.
This letter contains no NRC commitments. If you have any questions, please advise.
Respectfully submitted, S O T H E R N NUCLEAR OPERATING COMPANY Sworn to and subscribed before me this 12 dqy of My commisgion expires: 0 I
U. S. Nuclear Regulatory Commission NL-05-2 162 Page 3 cc: Southern Nuclear Operating Comvanv Mr. J. T. Gasser, Executive Vice President Mr. T. E. Tynan, General Manager - Plant Vogtle RType: CVC7000 U. S. Nuclear Regulatory Commission Dr. W. D. Travers, Regional Administrator Mr. C. Gratton, NRR Project Manager - Vogtle Mr. G. J. McCoy, Senior Resident Inspector - Vogtle State of Georgia Mr. L. C. Barrett, Commissioner - Department of Natural Resources
Text
Don E. Grissette Southern Nuclear Vice President Operating Company. Inc.
40 lnverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.6474 Fax 205.992.0341 Deceniber 12, 2005 COMPANY Energy to Serve Your World Docket No.: 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-000 1 Vogtle Electric Generating Plant Results of Inspections Required by NRC Bulletin 2004-0 1 and First Revised NRC Order EA-03-009 Ladies and Gentlemen:
On February 20,2004, the NRC issued the First Revised NRC Order EA-03-009 to establish interim inspection requirements for reactor pressure vessel (RPV) heads at pressurized water reactors. On March 8, 2004, Southern Nuclear Operating Company (SNC) submitted an answer to the revised order which included a request for relaxation of the Order pursuant to the provisions of Paragraph 1V.F. SNC was granted relaxation of the Order by NRC SER dated September 13,2005. SNC completed visual inspections to identify potential boric acid leaks from pressure-retaining components above the RPV head as required by paragraph 1V.D of the Order during the recent fall 2005 refueling outage (2R11) at Unit 2 of the Vogtle Electric Generating Plant (VEGP-2). This report provides the results of the inspection as required by Paragraph 1V.E of the Order. This letter also reports the results of inspection of Alloy 8211821600 materials used in the fabrication of pressurizer nozzle penetrations as requested by NRC Bulletin 2004-01.
Examinations Required by the First Revised NRC Order EA-03-009, Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors:
As required by paragraph 1V.A of the Order, SNC calculated the Effective Degradation Year (EDY) value at the start of 2R11 for VEGP-2. The current EDY value is 2.81 years which places VEGP-2 into the Low (EDY 43) category for susceptibility to primary water stress corrosion cracking (PWSCC) established by Paragraph 1V.B. The susceptibility category determines the required examinations and timing of those examinations. As reported by SNC's June 28,2004 letter, SNC completed a bare metal visual (BMV) examination of >95% of the RPV top head surface including 360" around each RPV head penetration nozzle during the spring 2004 refueling outage (2R10) at VEGP-2. This examination satisfied the requirements of Paragraph IV.C.(3) of the Order consistent with SNC's request for relaxation. The relaxation request proposed to achieve substantial compliance with the 100% BMV examination requirement of Paragraph IV.C.(S)(a) by conducting a BMV examination of the RPV to the extent accessible. The inspection requirement of Paragraph 1V.D was required to be performed on the RPV top head during 2R11.
U. S. Nuclear Regulatory Commission NL-05-2 162 Page 2 Inspection Results:
Boron residue was observed on core exit thermal nozzle assembly at penetration 77 during the visual inspections of components above the RPV top head. The area containing the boric acid residue was cleaned and reinspected with no leakage observed.
Documentation:
The examination was documented by a written report and photographs.
Examinations Required by Bulletin 2004-01, Inspection of Alloy 8211821600 Materials Used in the Fabrication of Pressurizer Nozzle Penetrations and Steam Space Connections at Pressurized Water Reactors:
A BMV examination was performed on four 6" SafetyIRelief Nozzles (Numbers 2 1201-V6-002-W17, 18, 19, and 20) and one 4" Spray Nozzle (Number 21 20 1-V6-002-W2 1).
Inspection Results:
No evidence of material wastage or of leaking or cracked nozzles was found by BMV examinations.
Documentation:
The examinations performed were documented by a written report.
Mr. D. E. Grissette states he is a Vice President of Southern Nuclear Operating Company, is authorized to execute this oath on behalf of Southern Nuclear Operating Company and to the best of his knowledge and belief, the facts set forth in this letter are true.
This letter contains no NRC commitments. If you have any questions, please advise.
Respectfully submitted, S O T H E R N NUCLEAR OPERATING COMPANY Sworn to and subscribed before me this 12 dqy of My commisgion expires: 0 I
U. S. Nuclear Regulatory Commission NL-05-2 162 Page 3 cc: Southern Nuclear Operating Comvanv Mr. J. T. Gasser, Executive Vice President Mr. T. E. Tynan, General Manager - Plant Vogtle RType: CVC7000 U. S. Nuclear Regulatory Commission Dr. W. D. Travers, Regional Administrator Mr. C. Gratton, NRR Project Manager - Vogtle Mr. G. J. McCoy, Senior Resident Inspector - Vogtle State of Georgia Mr. L. C. Barrett, Commissioner - Department of Natural Resources