RC-09-0060, Response to Request for Additional Information for Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.

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Response to Request for Additional Information for Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
ML091270196
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 05/01/2009
From: Archie J
South Carolina Electric & Gas Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
GL-04-002, RC-09-0060, TAC MC4721
Download: ML091270196 (2)


Text

Jeffrey B. Archie Vice President,Nuclear Operations 803.345.4214 May 1, 2009 A SCANA COMPANY RC-09-0060 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555

Dear Sir / Madam:

Subject:

VIRGIL C. SUMMER NUCLEAR STATION (VCSNS)

DOCKET NO. 50/395 OPERATING LICENSE NO. NPF-12 REQUEST FOR ADDITIONAL INFORMATION FOR GENERIC LETTER 2004-02 RESPONSE DUE DATE EXTENSION

Reference:

NRC Letter (ADAMS Accession No. ML090270927) to Mr. Jeffery B. Archie Dated February 3, 2009, "V. C. Summer Nuclear Station Request for Additional Information for Generic Letter 2004-02 (TAC NO. MC4721)"

The referenced letter identified 26 Request for Additional Information (RAI) items regarding the supplemental response provided by South Carolina Electric & Gas Company (SCE&G) to Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized-Water Reactors". The referenced letter requested that a response be provided in 90 days to all the RAIs except No. 23 and that only one response letter be provided. It was also identified that if the licensee concludes that more than 90 days is needed to respond to the RAIs, the licensee should request additional time, including a basis for why such time is needed.

SCE&G hereby requests additional time to complete development of the responses to the RAIs.

During in-house development of the responses, it has been determined that additional external resources will be required. We have responses to some of the RAIs, but many require additional support from our three consultants who were initially involved in the analysis and design effort to respond to Generic Letter 2004-02. This additional support effort will involve calculation revisions, review of test data and records, and additional SEM (scanning electron microscope) analysis of test debris. Based on the level of effort required by our consultants and allowing for internal reviews, we anticipate a full response to the RAIs, except for No. 23, by September 30, 2009.

As identified in RAI No. 23, the SCE&G supplemental response refers to WCAP-16406-P to address in-vessel downstream effects. This WCAP is not recognized by the NRC. SCE&G plans to demonstrate that the in-vessel downstream effects are addressed by the application of WCAP-16793-NP, "Evaluation of Long-Term Cooling Considering Particulate, Fibrous, and Chemical Debris in Recirculating Fluid" after the final version is accepted and the NRC Safety Evaluation (SE) is issued. Therefore, within 90 days of issuance of the final NRC staff SE on WCAP-16793-NP, SCE&G will respond to RAI No. 23 to demonstrate that the in-vessel downstream effects are bounded by this WCAP and the corresponding final NRC staff SE, and by addressing the conditions and limitations in the final SE.

SCE&G I Virgil C.Summer Nuclear Station

  • T(803) 345.5209
  • www.scana.com

Document Control Desk CR-04-02911 RC-09-0060 Page 2 of 2 Should you have questions, please call Mr. Bruce Thompson at (803) 931-5042.

I certify under penalty of perjury that the foregoing is true and correct.

1 tl,ý 7 Executed on Jeffrey B./A4,,Ihie

/ýýi/eP resident, Nuclear Operations GAR/JBA/dr K. B. Marsh S. A. Byrne N. S. Carns J. H. Hamilton R. J. White K. J. Browne L. A. Reyes R. E. Martin NRC Resident Inspector K. M. Sutton NSRC RTS (CR-04-0291 1)

File (815.14)

PRSF (RC-09-0060)

Text

Jeffrey B. Archie Vice President,Nuclear Operations 803.345.4214 May 1, 2009 A SCANA COMPANY RC-09-0060 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555

Dear Sir / Madam:

Subject:

VIRGIL C. SUMMER NUCLEAR STATION (VCSNS)

DOCKET NO. 50/395 OPERATING LICENSE NO. NPF-12 REQUEST FOR ADDITIONAL INFORMATION FOR GENERIC LETTER 2004-02 RESPONSE DUE DATE EXTENSION

Reference:

NRC Letter (ADAMS Accession No. ML090270927) to Mr. Jeffery B. Archie Dated February 3, 2009, "V. C. Summer Nuclear Station Request for Additional Information for Generic Letter 2004-02 (TAC NO. MC4721)"

The referenced letter identified 26 Request for Additional Information (RAI) items regarding the supplemental response provided by South Carolina Electric & Gas Company (SCE&G) to Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized-Water Reactors". The referenced letter requested that a response be provided in 90 days to all the RAIs except No. 23 and that only one response letter be provided. It was also identified that if the licensee concludes that more than 90 days is needed to respond to the RAIs, the licensee should request additional time, including a basis for why such time is needed.

SCE&G hereby requests additional time to complete development of the responses to the RAIs.

During in-house development of the responses, it has been determined that additional external resources will be required. We have responses to some of the RAIs, but many require additional support from our three consultants who were initially involved in the analysis and design effort to respond to Generic Letter 2004-02. This additional support effort will involve calculation revisions, review of test data and records, and additional SEM (scanning electron microscope) analysis of test debris. Based on the level of effort required by our consultants and allowing for internal reviews, we anticipate a full response to the RAIs, except for No. 23, by September 30, 2009.

As identified in RAI No. 23, the SCE&G supplemental response refers to WCAP-16406-P to address in-vessel downstream effects. This WCAP is not recognized by the NRC. SCE&G plans to demonstrate that the in-vessel downstream effects are addressed by the application of WCAP-16793-NP, "Evaluation of Long-Term Cooling Considering Particulate, Fibrous, and Chemical Debris in Recirculating Fluid" after the final version is accepted and the NRC Safety Evaluation (SE) is issued. Therefore, within 90 days of issuance of the final NRC staff SE on WCAP-16793-NP, SCE&G will respond to RAI No. 23 to demonstrate that the in-vessel downstream effects are bounded by this WCAP and the corresponding final NRC staff SE, and by addressing the conditions and limitations in the final SE.

SCE&G I Virgil C.Summer Nuclear Station

  • T(803) 345.5209
  • www.scana.com

Document Control Desk CR-04-02911 RC-09-0060 Page 2 of 2 Should you have questions, please call Mr. Bruce Thompson at (803) 931-5042.

I certify under penalty of perjury that the foregoing is true and correct.

1 tl,ý 7 Executed on Jeffrey B./A4,,Ihie

/ýýi/eP resident, Nuclear Operations GAR/JBA/dr K. B. Marsh S. A. Byrne N. S. Carns J. H. Hamilton R. J. White K. J. Browne L. A. Reyes R. E. Martin NRC Resident Inspector K. M. Sutton NSRC RTS (CR-04-0291 1)

File (815.14)

PRSF (RC-09-0060)