NL-05-0923, Results of Inspections Required by NRC BL-04-001 and First Revised NRC Order EA-03-009

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Results of Inspections Required by NRC BL-04-001 and First Revised NRC Order EA-03-009
ML051590444
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 06/06/2005
From: Grissette D
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BL-04-001, EA-03-009, NL-05-0923
Download: ML051590444 (3)
v • d • e


Text

Don E.Grissette Southern Nuclear Vice President Operating Company, Inc.

40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.6474 Fax 205.992.0341 SOUTHERN NA June 6, 2005 COMPANY Energy to Serve Your World' Docket No.: 50-424 NL-05-0923 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Vogtle Electric Generating Plant Results of Inspections Required by NRC Bulletin 2004-01 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 IV.F. SNC completed visual inspections to identify potential boric acid leaks from pressure-retaining components above the RPV head as required by paragraph IV.D of the Order during the recent spring 2005 refueling outage (IR12) at Unit 1 of the Vogtle Electric Generating Plant (VEGP-l).

This report provides the results of the inspection as required by Paragraph IV.E of the Order. This letter also reports the results of inspection of Alloy 82/182/600 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 IV.A of the Order, SNC calculated the Effective Degradation Year (EDY) value at the start of IR12 for VEGP-1. The current EDY value is 3.01 years which places VEGP-I into the Low (EDY <8) category for susceptibility to primary water stress corrosion cracking (PWSCC) established by Paragraph IV.B. The susceptibility category determines the required examinations and timing of those examinations. As reported by SNC's December 19, 2003 letter, SNC completed a bare metal visual (BMV) examination of >99% of the RPV top head surface including 3600 around each RPV head penetration nozzle during the fall 2003 refueling outage (IRI I) at VEGP- 1. 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.(5)(a) by conducting a BMV examination of the RPV to the extent accessible. The inspection requirement of Paragraph IV.D was required to be performed on the RPV top head during IR12. 6i10

U. S. Nuclear Regulatory Commission NL-05-0923 Page 2 Inspection Results:

Boron residue was observed during the visual inspections on the RPV top head and a "general" visual inspection was performed with insulation panels removed from the closure head. No evidence of head material wastage or of leaking or cracked nozzles was found. The boron residue was determined to be associated with previous cleaning/decontamination efforts of conoseals and not associated with new "active" leakage. The areas below the conoseals were cleaned and reinspected during Mode 3 startup with no leakage observed.

Documentation:

The examination was documented by a written report.

Examinations Required by Bulletin 2004-01, Inspection of Alloy 82/182/600 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" SafetylRelief Nozzles (Numbers 11201-V6-002-W17, 18, 19, and 20) and one 4" Spray Nozzle (Number 1 201-V6-002-W21).

In addition, an Appendix VIII volumetric examination was performed on the 4" Spray Nozzle (Number 11201-V6-002-W21).

Inspection Results:

No evidence of material wastage or of leaking or cracked nozzles was found by BMV examinations.

Examination coverage of 100% was achieved in the performance of the volumetric examination of the 4" Spray Nozzle with no recordable indications.

Documentation:

The examinations performed were documented by a written report.

U. S. Nuclear Regulatory Commission NL-05-0923 Page 3 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, SOUTHERN NUCLEAR OPERATING COMPANY Don E. Grissette Sworn to and subscribedbefore me this /day of ,

(- +/- . 2005.

Notary Public My commission expires:

DEG/DRG/daj cc: Southern Nuclear Operating Companv Mr. J. T. Gasser, Executive Vice President Mr. W. F. Kitchens, General Manager - Plant Vogtle RType: CVC7000 U. S. Nuclear Regulatorv 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 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.6474 Fax 205.992.0341 SOUTHERN NA June 6, 2005 COMPANY Energy to Serve Your World' Docket No.: 50-424 NL-05-0923 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Vogtle Electric Generating Plant Results of Inspections Required by NRC Bulletin 2004-01 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 IV.F. SNC completed visual inspections to identify potential boric acid leaks from pressure-retaining components above the RPV head as required by paragraph IV.D of the Order during the recent spring 2005 refueling outage (IR12) at Unit 1 of the Vogtle Electric Generating Plant (VEGP-l).

This report provides the results of the inspection as required by Paragraph IV.E of the Order. This letter also reports the results of inspection of Alloy 82/182/600 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 IV.A of the Order, SNC calculated the Effective Degradation Year (EDY) value at the start of IR12 for VEGP-1. The current EDY value is 3.01 years which places VEGP-I into the Low (EDY <8) category for susceptibility to primary water stress corrosion cracking (PWSCC) established by Paragraph IV.B. The susceptibility category determines the required examinations and timing of those examinations. As reported by SNC's December 19, 2003 letter, SNC completed a bare metal visual (BMV) examination of >99% of the RPV top head surface including 3600 around each RPV head penetration nozzle during the fall 2003 refueling outage (IRI I) at VEGP- 1. 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.(5)(a) by conducting a BMV examination of the RPV to the extent accessible. The inspection requirement of Paragraph IV.D was required to be performed on the RPV top head during IR12. 6i10

U. S. Nuclear Regulatory Commission NL-05-0923 Page 2 Inspection Results:

Boron residue was observed during the visual inspections on the RPV top head and a "general" visual inspection was performed with insulation panels removed from the closure head. No evidence of head material wastage or of leaking or cracked nozzles was found. The boron residue was determined to be associated with previous cleaning/decontamination efforts of conoseals and not associated with new "active" leakage. The areas below the conoseals were cleaned and reinspected during Mode 3 startup with no leakage observed.

Documentation:

The examination was documented by a written report.

Examinations Required by Bulletin 2004-01, Inspection of Alloy 82/182/600 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" SafetylRelief Nozzles (Numbers 11201-V6-002-W17, 18, 19, and 20) and one 4" Spray Nozzle (Number 1 201-V6-002-W21).

In addition, an Appendix VIII volumetric examination was performed on the 4" Spray Nozzle (Number 11201-V6-002-W21).

Inspection Results:

No evidence of material wastage or of leaking or cracked nozzles was found by BMV examinations.

Examination coverage of 100% was achieved in the performance of the volumetric examination of the 4" Spray Nozzle with no recordable indications.

Documentation:

The examinations performed were documented by a written report.

U. S. Nuclear Regulatory Commission NL-05-0923 Page 3 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, SOUTHERN NUCLEAR OPERATING COMPANY Don E. Grissette Sworn to and subscribedbefore me this /day of ,

(- +/- . 2005.

Notary Public My commission expires:

DEG/DRG/daj cc: Southern Nuclear Operating Companv Mr. J. T. Gasser, Executive Vice President Mr. W. F. Kitchens, General Manager - Plant Vogtle RType: CVC7000 U. S. Nuclear Regulatorv 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

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