LIC-15-0129, Addendum to Response to Request for Information Regarding Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident - Flood Hazard Reevaluation Report

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Addendum to Response to Request for Information Regarding Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident - Flood Hazard Reevaluation Report
ML15310A018
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 11/04/2015
From: Dean E
Omaha Public Power District
To:
Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML15310A010 List:
References
LIC-15-0129
Download: ML15310A018 (3)
v • d • e


Text

Withhold from Public Disclosure Under 10 CFR 2.390.

Enclosure Co_ntains Security-Related Information.

Upon Removal of Enclosure, This Letter and its Attachmentare Decontrolled.

'\

Omaha

- - Public Power 111!11/!/J Oistlict-

___ 444 South 1r:fh Street Mall Omaha, NE 68102-2247 10 CFR 50.54(f)

_Ll_C-15-0129 November 4, 2015 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Fort Calhoun Station, Unit No. 1 Renewed Facility Operating -ucense No. DPR-40 NRC Docket No. 50-285

Subject:

Addendum to Response to Request for Information Regarding Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident- Fort Calhoun Station Flood Hazard Reevaluation Report

References:

1. Letter from OPPD (L. P. Cortopassi) to NRC (Document Control Desk),

"Response to Request for Information Regarding Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident- Fort Calhoun Station Flood Hazard Reevaluation Report," dated February 4, 2015 (LIC-15-0015) (ML15042A127)

2. Email from NRC (Tekia Govan) to NPPD (Brenda Kirkpatrick) and OPPD (Michael Edwards), "Ft Calhoun/Cooper Audit Status," dated July 8, 2015 The purpose of this letter is to provide the dam failure 2D TUFLOW model results. As such, Enclosure 1 provides Addendum 1 to the Flood Hazard Reevaluation Report (FHRR) submitted by the Omaha Public Power District (OPPD) in February 2015 (Reference 1).

As noted in Reference 2, during _the Nuclear Regulatory Commission (NRG) FHRR joint audit of OPPD and the Nebraska Public Power District (NPPD), the staff was informed that a dam failure scenario utilizing the 20 TUFLOW model would be developed for both Cooper Nuclear Station (CNS) and FCS. This analysis provides a more explicit representation of flow velocities, water depths, and channel/overbank velocity distributions. -

During the development of the 2D TUFLOW Model, OPPD was asked to conduct a sensitivity analysis on extending the upstream boundary to a point above the Soldier River. The results of that sensitivity analysis presented during the audit show that there are negligible differences in water surface elevation (WSEL) and flow distributions between the original and extended upstream boundary 2D TUFLOW models.

Withhold from Public Disclosure Under 10 CFR 2.390.

Enclosure Contains Security-Related Information.

Upon Removal of Enclosure, This Letter and its Attachment are Decontrolled.

Employment with Equal Opportunity

Withhold from Public Disclosure Under 1o CFR 2.390.

Enclosure Contains Security-Related Information.

Upon Removal of Enclosure, This Letter and its Attachment are Decontrolled.

U. S. Nuclear Regulatory Commission LIC-15-0015 Page2 The enclosed Addendum supersedes Section 2.3.2.3 (Water Levels and Time to Peak Water Levels) and 2.3.2.4 (Velocities) of the Reference 1 FHRR and the figures and tables referenced in those sections.

  • Please note that results from Sections 2.3.2.3 and 2.3.2.4 are used in Section 2.3.3 (Combined Effects), Section 2.3.4 (Associated Flooding Impacts) and Section 3.3 (Dam Breaches and Failures), which have not been updated. OPPD will update FHRR Sections 2.3.3, 2.3.4, and 3.3 and submit a full revision to the FHRR including incorporation of the enclosed Addendum, by September 30, 2016.

The Enclosure contains security-related information and OPPD requests that it be withheld from public disclosure in accordance with 10 CFR 2.390.

I declare under penalty of perjury that the foregoing is true and correct. Executed on November 4, 2015.

EDD/JKG/mle

Attachment:

Summary of Regulatory Commitments

Enclosure:

Fort Calhoun Station, Flood Hazard Reevaluation Report, Addendum 1 (SL-013016) Revision 2 c: W. M. Dean, Director of Office of Nuclear Reactor Regulation (w/o Enclosure)

M. L. Dapas, NRG Regional Administrator, Region IV (w/o Enclosure)

C. F. Lyon, NRG Senior Project Manager T. V. Govan, NRG Project Manager S. M. Schneider, NRG Senior Resident Inspector (w/o Enclosure)

Withhold from Public Disclosure Under 10 CFR 2.390.

Enclosure Contains Security-Related Information.

Upon Removal of Enclosure, This Letter and its Attachment are Decontrolled.

Withhold from Public Disclosure Under 10 CFR 2.390.

Enclosure Contains Security-Related Information.

Upon Removal of Enclosure, This Letter and its Attachment are Decontrolled.

LIC-15-0129 Attachment

--Page 1 --

Summary of Regulatory Commitments The following table identifies commitments made in this document. (Any other actions discussed in the submittal represent intended or planned actions. They are describeq to the NRC for the NRC's information and are not regulatory commitments.)

Commitment - Committed " Commitment Type Date or One-Time Programmatic Outage Action (Yes/No)

(Yes/No)

OPPD will update FHRR Sections 2.3.3, 2.3.4, and 3.3 September Yes No and submit a full revision to the FHRR including 30,2016 incorooration of the enclosed addendum.

Withhold from Public Disclosure Under 10 CFR 2.390.

Enclosure Contains Security-Related Information.

Upon Removal of Enclosure, This Letter and its Attachment are Decontrolled.

Withhold from Public Disclosure Under 10 CFR 2.390.

Enclosure Co_ntains Security-Related Information.

Upon Removal of Enclosure, This Letter and its Attachmentare Decontrolled.

'\

Omaha

- - Public Power 111!11/!/J Oistlict-

___ 444 South 1r:fh Street Mall Omaha, NE 68102-2247 10 CFR 50.54(f)

_Ll_C-15-0129 November 4, 2015 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Fort Calhoun Station, Unit No. 1 Renewed Facility Operating -ucense No. DPR-40 NRC Docket No. 50-285

Subject:

Addendum to Response to Request for Information Regarding Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident- Fort Calhoun Station Flood Hazard Reevaluation Report

References:

1. Letter from OPPD (L. P. Cortopassi) to NRC (Document Control Desk),

"Response to Request for Information Regarding Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident- Fort Calhoun Station Flood Hazard Reevaluation Report," dated February 4, 2015 (LIC-15-0015) (ML15042A127)

2. Email from NRC (Tekia Govan) to NPPD (Brenda Kirkpatrick) and OPPD (Michael Edwards), "Ft Calhoun/Cooper Audit Status," dated July 8, 2015 The purpose of this letter is to provide the dam failure 2D TUFLOW model results. As such, Enclosure 1 provides Addendum 1 to the Flood Hazard Reevaluation Report (FHRR) submitted by the Omaha Public Power District (OPPD) in February 2015 (Reference 1).

As noted in Reference 2, during _the Nuclear Regulatory Commission (NRG) FHRR joint audit of OPPD and the Nebraska Public Power District (NPPD), the staff was informed that a dam failure scenario utilizing the 20 TUFLOW model would be developed for both Cooper Nuclear Station (CNS) and FCS. This analysis provides a more explicit representation of flow velocities, water depths, and channel/overbank velocity distributions. -

During the development of the 2D TUFLOW Model, OPPD was asked to conduct a sensitivity analysis on extending the upstream boundary to a point above the Soldier River. The results of that sensitivity analysis presented during the audit show that there are negligible differences in water surface elevation (WSEL) and flow distributions between the original and extended upstream boundary 2D TUFLOW models.

Withhold from Public Disclosure Under 10 CFR 2.390.

Enclosure Contains Security-Related Information.

Upon Removal of Enclosure, This Letter and its Attachment are Decontrolled.

Employment with Equal Opportunity

Withhold from Public Disclosure Under 1o CFR 2.390.

Enclosure Contains Security-Related Information.

Upon Removal of Enclosure, This Letter and its Attachment are Decontrolled.

U. S. Nuclear Regulatory Commission LIC-15-0015 Page2 The enclosed Addendum supersedes Section 2.3.2.3 (Water Levels and Time to Peak Water Levels) and 2.3.2.4 (Velocities) of the Reference 1 FHRR and the figures and tables referenced in those sections.

  • Please note that results from Sections 2.3.2.3 and 2.3.2.4 are used in Section 2.3.3 (Combined Effects), Section 2.3.4 (Associated Flooding Impacts) and Section 3.3 (Dam Breaches and Failures), which have not been updated. OPPD will update FHRR Sections 2.3.3, 2.3.4, and 3.3 and submit a full revision to the FHRR including incorporation of the enclosed Addendum, by September 30, 2016.

The Enclosure contains security-related information and OPPD requests that it be withheld from public disclosure in accordance with 10 CFR 2.390.

I declare under penalty of perjury that the foregoing is true and correct. Executed on November 4, 2015.

EDD/JKG/mle

Attachment:

Summary of Regulatory Commitments

Enclosure:

Fort Calhoun Station, Flood Hazard Reevaluation Report, Addendum 1 (SL-013016) Revision 2 c: W. M. Dean, Director of Office of Nuclear Reactor Regulation (w/o Enclosure)

M. L. Dapas, NRG Regional Administrator, Region IV (w/o Enclosure)

C. F. Lyon, NRG Senior Project Manager T. V. Govan, NRG Project Manager S. M. Schneider, NRG Senior Resident Inspector (w/o Enclosure)

Withhold from Public Disclosure Under 10 CFR 2.390.

Enclosure Contains Security-Related Information.

Upon Removal of Enclosure, This Letter and its Attachment are Decontrolled.

Withhold from Public Disclosure Under 10 CFR 2.390.

Enclosure Contains Security-Related Information.

Upon Removal of Enclosure, This Letter and its Attachment are Decontrolled.

LIC-15-0129 Attachment

--Page 1 --

Summary of Regulatory Commitments The following table identifies commitments made in this document. (Any other actions discussed in the submittal represent intended or planned actions. They are describeq to the NRC for the NRC's information and are not regulatory commitments.)

Commitment - Committed " Commitment Type Date or One-Time Programmatic Outage Action (Yes/No)

(Yes/No)

OPPD will update FHRR Sections 2.3.3, 2.3.4, and 3.3 September Yes No and submit a full revision to the FHRR including 30,2016 incorooration of the enclosed addendum.

Withhold from Public Disclosure Under 10 CFR 2.390.

Enclosure Contains Security-Related Information.

Upon Removal of Enclosure, This Letter and its Attachment are Decontrolled.

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