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MONTHYEARML0515201562005-06-0303 June 2005 Fort Calhoun, RAI, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors Project stage: RAI ML0517506252005-06-27027 June 2005 Forthcoming Meeting with Omaha Public Power District, Fort Calhoun Station, Unit 1 to Discuss Pilot Plant for the NRC Staff Resolution of Generic Letter 2004-02. Project stage: Meeting LIC-05-0090, Response to Request for Additional Information Related to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2005-08-0101 August 2005 Response to Request for Additional Information Related to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Response to RAI ML0603804072006-02-0909 February 2006 RAI Re Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors. Project stage: RAI LIC-06-0070, Supplement to Revised Request for an Extension to the Completion Date for Corrective Actions Taken in Response to Generic Letter 2004-022006-06-28028 June 2006 Supplement to Revised Request for an Extension to the Completion Date for Corrective Actions Taken in Response to Generic Letter 2004-02 Project stage: Supplement LIC-08-0021, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2008-02-29029 February 2008 Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request LIC-08-0098, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, Change of Commitment for Close-out Letter Submittal2008-09-0505 September 2008 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, Change of Commitment for Close-out Letter Submittal Project stage: Other ML0825906662008-09-12012 September 2008 E-mail from M. Lalor, GE to A. Wang, NRR/DORL/LPL4 Re Trip Report for Observation of GL-2004-2 Sump Testing Project stage: Other ML1001500722010-02-12012 February 2010 Request for Additional Information, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: RAI ML1004302742010-02-12012 February 2010 Notice of Forthcoming Teleconference with Omaha Public Power District to Discuss NRC Staff Request for Additional Information on Generic Letter 2004-02 for Fort Calhoun Station, Unit 1 Project stage: RAI ML1006200722010-03-23023 March 2010 Summary of Category 1, Teleconference with Omaha Public Power District to Discuss NRC Staff Request for Additional Information on Generic Letter 2004-02 for Fort Calhoun Station, Unit 1 Project stage: RAI ML1016205062010-06-14014 June 2010 Notice of Forthcoming Teleconference Meeting with Omaha Public Power District to Discuss NRC Staff Request for Additional Information Dated 2/12/2010 on Generic Letter 2004-02 for Fort Calhoun Station, Unit 1 Project stage: RAI ML1019403012010-07-29029 July 2010 6/30/2010 Summary of Teleconference Meeting with Omaha Public Power District to Discuss NRC Staff Request for Additional Information Dated 2/12/2010 on Generic Letter 2004-02 for Fort Calhoun Station, Unit 1 Project stage: RAI 2008-02-29
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Category:Letter type:LIC
MONTHYEARLIC-23-0007, Response to Fort Calhoun, Unit 1 & Independent Spent Fuel Storage Installation Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements Request for Additional Information2023-12-0606 December 2023 Response to Fort Calhoun, Unit 1 & Independent Spent Fuel Storage Installation Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements Request for Additional Information LIC-23-0005, Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 20232023-08-24024 August 2023 Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 2023 LIC-23-0004, (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report2023-04-20020 April 2023 (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-23-0003, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2023-03-15015 March 2023 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-23-0001, Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - Request for Additional Information2023-02-27027 February 2023 Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - Request for Additional Information LIC-23-0002, Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report2023-02-20020 February 2023 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report LIC-22-0010, Response to Fort Calhoun Station, Unit No. 1 - Review of License Termination Plan Requirements - Request for Additional Information2022-06-15015 June 2022 Response to Fort Calhoun Station, Unit No. 1 - Review of License Termination Plan Requirements - Request for Additional Information LIC-22-0005, (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report2022-04-20020 April 2022 (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-22-0009, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2022-03-30030 March 2022 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-22-0006, Reactor Head Disposition Project Overview2022-03-17017 March 2022 Reactor Head Disposition Project Overview LIC-22-0004, Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report2022-02-17017 February 2022 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report LIC-21-0008, Organizational and Management Change2021-10-28028 October 2021 Organizational and Management Change LIC-21-0007, ISFSI Only Emergency Plan Update2021-09-0808 September 2021 ISFSI Only Emergency Plan Update LIC-21-0004, Radiological Effluent Release Report and Radiological Environmental Operating Report2021-04-29029 April 2021 Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-21-0003, Independent Spent Fuel Storage Installation - 2021 Annual Decommissioning Funding / Irradiated Fuel Management Status Report2021-03-30030 March 2021 Independent Spent Fuel Storage Installation - 2021 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-21-0002, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2021-02-22022 February 2021 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report LIC-20-0015, Correction to Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report 2019 (ML20121A092)2020-07-29029 July 2020 Correction to Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report 2019 (ML20121A092) LIC-20-0014, Submittal of Revision 8 to the Fort Calhoun Station (Fcs), Physical Security Plan (PSP)2020-07-15015 July 2020 Submittal of Revision 8 to the Fort Calhoun Station (Fcs), Physical Security Plan (PSP) LIC-20-0012, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration and Certification of Permanent Removal of All Spent Fuel Assemblies from the Spent Fuel Pool2020-05-18018 May 2020 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration and Certification of Permanent Removal of All Spent Fuel Assemblies from the Spent Fuel Pool LIC-20-0011, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2020-05-0707 May 2020 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration LIC-20-0009, (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report2020-04-30030 April 2020 (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-20-0008, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2020-04-13013 April 2020 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration LIC-20-0006, (Fcs), Unit 1, Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E2020-03-26026 March 2020 (Fcs), Unit 1, Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E LIC-20-0004, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2020-03-10010 March 2020 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration LIC-20-0003, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2020-02-27027 February 2020 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report LIC-20-0002, Independent Spent Fuel Storage Installation - Submittal of Revision 7 to Physical Security Plan2020-02-27027 February 2020 Independent Spent Fuel Storage Installation - Submittal of Revision 7 to Physical Security Plan LIC-20-0001, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2020-02-0606 February 2020 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration LIC-19-0025, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2019-12-19019 December 2019 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration LIC-19-0007, Post-Shutdown Decommissioning Activities Report2019-12-16016 December 2019 Post-Shutdown Decommissioning Activities Report LIC-19-0021, Independent Spent Fuel Storage Installation - Response to Request for Additional Information License Amendment for ISFSI-only EP and EAL Scheme2019-11-20020 November 2019 Independent Spent Fuel Storage Installation - Response to Request for Additional Information License Amendment for ISFSI-only EP and EAL Scheme LIC-19-0022, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2019-11-18018 November 2019 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration LIC-19-0018, Submittal of Revision 6 to the Fort Calhoun Station (Fcs), Physical Security Plan (PSP)2019-11-14014 November 2019 Submittal of Revision 6 to the Fort Calhoun Station (Fcs), Physical Security Plan (PSP) LIC-19-0020, Independent Spent Fuel Storage Installation - Updated Information Submittal and Revision 1 of the Blast Analysis2019-10-17017 October 2019 Independent Spent Fuel Storage Installation - Updated Information Submittal and Revision 1 of the Blast Analysis LIC-19-0017, Clarification to Revised Response to Orders for Interim Safeguards and Security Compensatory Measures and Implementation of Additional Security Measures Associated with Access Authorization for Fort Calhoun Station Dated 9 November, 20042019-08-0808 August 2019 Clarification to Revised Response to Orders for Interim Safeguards and Security Compensatory Measures and Implementation of Additional Security Measures Associated with Access Authorization for Fort Calhoun Station Dated 9 November, 2004 An LIC-19-0010, License Amendment Request (LAR) 19-03; Revised Fort Calhoun Station License in Support of the Revised Response to Orders for Interim Safeguards and Security Compensatory Measures and Implementation of Additional Security Measures Associa2019-05-20020 May 2019 License Amendment Request (LAR) 19-03; Revised Fort Calhoun Station License in Support of the Revised Response to Orders for Interim Safeguards and Security Compensatory Measures and Implementation of Additional Security Measures Associated LIC-19-0008, Submittal of 2018 Annual Report2019-04-0404 April 2019 Submittal of 2018 Annual Report LIC-19-0004, Independent Spent Fuel Storage Installation - Submittal of Revision 4 to Physical Security Plan (PSP)2019-03-28028 March 2019 Independent Spent Fuel Storage Installation - Submittal of Revision 4 to Physical Security Plan (PSP) LIC-19-0005, 2019 Annual Decommissioning Funding I Irradiated Fuel Management Status Report2019-03-28028 March 2019 2019 Annual Decommissioning Funding I Irradiated Fuel Management Status Report LIC-19-0001, License Amendment Request (LAR) 19-01: Independent Spent Fuel Storage Installation (ISFSI) Emergency Plan and Emergency Action Level Scheme2019-02-28028 February 2019 License Amendment Request (LAR) 19-01: Independent Spent Fuel Storage Installation (ISFSI) Emergency Plan and Emergency Action Level Scheme LIC-19-0003, Revised Response to Orders for Interim Safeguards and Security Compensatory Measures and Implementation of Additional Security Measures Associated with Access Authorization for Fort Calhoun Station Dated 9 November, 2004 and Relaxation R2019-02-28028 February 2019 Revised Response to Orders for Interim Safeguards and Security Compensatory Measures and Implementation of Additional Security Measures Associated with Access Authorization for Fort Calhoun Station Dated 9 November, 2004 and Relaxation Requ LIC-19-0002, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2019-01-0303 January 2019 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report LIC-18-0031, Independent Spent Fuel Storage Installation - Transmittal of Emergency Plan Update2018-12-17017 December 2018 Independent Spent Fuel Storage Installation - Transmittal of Emergency Plan Update LIC-18-0030, Request for Partial Site Release Phase 22018-11-12012 November 2018 Request for Partial Site Release Phase 2 LIC-18-0028, Letter of Intent to Submit Request for Additional Partial Site Release2018-10-18018 October 2018 Letter of Intent to Submit Request for Additional Partial Site Release LIC-18-0027, Submittal of Foreign Ownership, Control or Influence Five-Year Renewal Filing and NRC Facility Clearance Update2018-10-0303 October 2018 Submittal of Foreign Ownership, Control or Influence Five-Year Renewal Filing and NRC Facility Clearance Update LIC-18-0003, License Amendment Request (LAR) 18-01; Revised Fort Calhoun Station Permanently Defueled Technical Specifications to Align to Those Requirements for Permanent Removal of Spent Fuel from Spent Fuel Pool2018-09-28028 September 2018 License Amendment Request (LAR) 18-01; Revised Fort Calhoun Station Permanently Defueled Technical Specifications to Align to Those Requirements for Permanent Removal of Spent Fuel from Spent Fuel Pool LIC-18-0025, Guarantee of Payment of Deferred Premiums for the Period of July 1, 2018 to June 30, 20192018-07-19019 July 2018 Guarantee of Payment of Deferred Premiums for the Period of July 1, 2018 to June 30, 2019 LIC-18-0023, Fort Calhoun Station, Unit 1 Request for Partial Site Release2018-06-29029 June 2018 Fort Calhoun Station, Unit 1 Request for Partial Site Release LIC-18-0021, Transmittal of Revision 3 to the Physical Security Plan (PSP) and Revision 4 to the FCS Protective Strategy (Safeguards Contingency Plan)2018-06-0606 June 2018 Transmittal of Revision 3 to the Physical Security Plan (PSP) and Revision 4 to the FCS Protective Strategy (Safeguards Contingency Plan) LIC-18-0017, Submittal of Revision 2 to the Fort Calhoun Station (Fcs), Physical Security Plan (PSP) and Revision 3 of the FCS Protective Strategy2018-04-26026 April 2018 Submittal of Revision 2 to the Fort Calhoun Station (Fcs), Physical Security Plan (PSP) and Revision 3 of the FCS Protective Strategy 2023-08-24
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444 South 16th Street Mall Omaha NE 68102-2247 August 1,2005 LIC-05-0090 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001
References:
- 1. Docket No. 50-285
- 2. Letter from Bruce A. Boger (NRC) to Ross Ridenoure (OPPD) dated September 13,2004, NRC Generic Letter 2004-02: Potential Impact Of Debris Blockage On Emergency Recirculation During Design Basis Accidents At Pressurized-Water Reactors (NRC-04-0115)
- 3. Letter from Ralph L. Phelps (OPPD) to Document Control Desk (NRC) dated March 4,2005,90 Day Response to Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors" (LIC-05-0017)
- 4. Letter from Alan B. Wang (NRC) to Ross Ridenoure (OPPD) dated June 3, 2005, Request for Additional Information (RAI) Related to Generic Letter 2004-02, Potential Impact Of Debris Blockage On Emergency Recirculation During Design Basis Accidents At Pressurized-Water Reactors (TAC No. MC4686) (NRC-05-077)
SUBJECT:
Fort Calhoun Station Unit No. 1, Response to Request for Additional Information Related to Generic Letter 2004-02, Potential Impact Of Debris Blockage On Emergency Recirculation During Design Basis Accidents At Pressurized-Water Reactors In Reference 3, the Omaha Public Power District (OPPD) provided information in response to Reference 2. In Reference 4, the NRC requested additional information concerning Reference 3.
OPPD is providing the requested information as Attachment 1 to this letter.
This letter contains the following commitment:
The chemical effect evaluation approach will be summarized in our September 1, 2005, response to Reference 2.
I declare under penalty of perjury that the forgoing is true and correct. (Executed on August 1, 2005 .)
Employment with Equal Opportunity 4171
U. S. Nuclear Regulatory Commission LIC-05-0090 Page 2 If you have any questions or require additional information, please contact Thomas R. Byrne at (402) 533-7368.
Sincerely, Manager - Fort Calhoun Station - Response to Request for Additional Information Related to Generic Letter 2004-02, Potential Impact Of Debris Blockage On Emergency Recirculation During Design Basis Accidents At Pressurized-Water Reactors
LIC-05-0090 Page 1 Attachment 1 Response to Request for Additional Information Related to Generic Letter 2004-02, Potential Impact Of Debris Blockage On Emergency Recirculation During Design Basis Accidents At Pressurized-Water Reactors
LIC-05-0090 Page 2 Attachment 1 Response to Request for Additional Information Related to Generic Letter 2004-02, Potential Impact Of Debris Blockage On Emergency Recirculation During Design Basis Accidents At Pressurized-Water Reactors NRC Question 1:
In your 90-day response to [Generic Letter] GL 2004-02, you indicated that you intend to use future test results, industry guidance, and NRC guidance to account for chemical precipitants in your evaluation and their availability will impact the schedule for performing an evaluation. The cooperative NRC-Electric Power Research Institute tests in progress at the University of New Mexico are designed to determine if chemical effects occur, but are not designed to measure head loss associated with any chemical effects. The staff notes that some chemical effects have been observed in the initial three tests.
For addressing chemical effects, you state the evaluation may occur after the September 1, 2005, response due date, depending on the schedule for testing and the availability of industry guidance. This is contrary to the information request in GL 2004-02, which requests that chemical effects be addressed in the September 1,2005, response.
This delay is also contrary to the staffs position that there are sufficient bases to address sump vulnerability to chemical effects and that the September response will be incomplete if the evaluation is incomplete, the design is not complete, or there is no schedule for upgrades. In this light, please discuss your plans and schedule for evaluating chemical effects. In addition, please discuss any plans for performing testing to support your evaluation of this effect.
OPPD Response:
OPPD provided the required 90-day response to GL 2004-02 based on information available at that time. Subsequent to submitting the 90-day response, additional information has become available pertaining to chemical effects.
Recent cooperative NRC-EPRI Integrated Chemical Effects Testing (ICET) indicates that precipitant could be formed during long term post-LOCA recirculation operation. The effects of this precipitant on screen head loss have not been quantified nor has a methodology been formulated for determining this component of the total head loss. The Omaha Public Power District (OPPD) has initiated the chemical effects evaluation task to address sump screen head loss during post-LOCA recirculation. The evaluation will determine if the NRC-EPRI tests bound site-specific post-LOCA parameters, and ensure sufficient head loss margin exists to accommodate chemical effects. The initial approach will utilize margin allocated for chemical effects (bump-up factor). The bump up factor will be validated by testing andlor evaluation data and adjusted as necessary. The chemical effect evaluation approach will be summarized in our September 1, 2005, response to GL 2004-02.
Text
444 South 16th Street Mall Omaha NE 68102-2247 August 1,2005 LIC-05-0090 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001
References:
- 1. Docket No. 50-285
- 2. Letter from Bruce A. Boger (NRC) to Ross Ridenoure (OPPD) dated September 13,2004, NRC Generic Letter 2004-02: Potential Impact Of Debris Blockage On Emergency Recirculation During Design Basis Accidents At Pressurized-Water Reactors (NRC-04-0115)
- 3. Letter from Ralph L. Phelps (OPPD) to Document Control Desk (NRC) dated March 4,2005,90 Day Response to Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors" (LIC-05-0017)
- 4. Letter from Alan B. Wang (NRC) to Ross Ridenoure (OPPD) dated June 3, 2005, Request for Additional Information (RAI) Related to Generic Letter 2004-02, Potential Impact Of Debris Blockage On Emergency Recirculation During Design Basis Accidents At Pressurized-Water Reactors (TAC No. MC4686) (NRC-05-077)
SUBJECT:
Fort Calhoun Station Unit No. 1, Response to Request for Additional Information Related to Generic Letter 2004-02, Potential Impact Of Debris Blockage On Emergency Recirculation During Design Basis Accidents At Pressurized-Water Reactors In Reference 3, the Omaha Public Power District (OPPD) provided information in response to Reference 2. In Reference 4, the NRC requested additional information concerning Reference 3.
OPPD is providing the requested information as Attachment 1 to this letter.
This letter contains the following commitment:
The chemical effect evaluation approach will be summarized in our September 1, 2005, response to Reference 2.
I declare under penalty of perjury that the forgoing is true and correct. (Executed on August 1, 2005 .)
Employment with Equal Opportunity 4171
U. S. Nuclear Regulatory Commission LIC-05-0090 Page 2 If you have any questions or require additional information, please contact Thomas R. Byrne at (402) 533-7368.
Sincerely, Manager - Fort Calhoun Station - Response to Request for Additional Information Related to Generic Letter 2004-02, Potential Impact Of Debris Blockage On Emergency Recirculation During Design Basis Accidents At Pressurized-Water Reactors
LIC-05-0090 Page 1 Attachment 1 Response to Request for Additional Information Related to Generic Letter 2004-02, Potential Impact Of Debris Blockage On Emergency Recirculation During Design Basis Accidents At Pressurized-Water Reactors
LIC-05-0090 Page 2 Attachment 1 Response to Request for Additional Information Related to Generic Letter 2004-02, Potential Impact Of Debris Blockage On Emergency Recirculation During Design Basis Accidents At Pressurized-Water Reactors NRC Question 1:
In your 90-day response to [Generic Letter] GL 2004-02, you indicated that you intend to use future test results, industry guidance, and NRC guidance to account for chemical precipitants in your evaluation and their availability will impact the schedule for performing an evaluation. The cooperative NRC-Electric Power Research Institute tests in progress at the University of New Mexico are designed to determine if chemical effects occur, but are not designed to measure head loss associated with any chemical effects. The staff notes that some chemical effects have been observed in the initial three tests.
For addressing chemical effects, you state the evaluation may occur after the September 1, 2005, response due date, depending on the schedule for testing and the availability of industry guidance. This is contrary to the information request in GL 2004-02, which requests that chemical effects be addressed in the September 1,2005, response.
This delay is also contrary to the staffs position that there are sufficient bases to address sump vulnerability to chemical effects and that the September response will be incomplete if the evaluation is incomplete, the design is not complete, or there is no schedule for upgrades. In this light, please discuss your plans and schedule for evaluating chemical effects. In addition, please discuss any plans for performing testing to support your evaluation of this effect.
OPPD Response:
OPPD provided the required 90-day response to GL 2004-02 based on information available at that time. Subsequent to submitting the 90-day response, additional information has become available pertaining to chemical effects.
Recent cooperative NRC-EPRI Integrated Chemical Effects Testing (ICET) indicates that precipitant could be formed during long term post-LOCA recirculation operation. The effects of this precipitant on screen head loss have not been quantified nor has a methodology been formulated for determining this component of the total head loss. The Omaha Public Power District (OPPD) has initiated the chemical effects evaluation task to address sump screen head loss during post-LOCA recirculation. The evaluation will determine if the NRC-EPRI tests bound site-specific post-LOCA parameters, and ensure sufficient head loss margin exists to accommodate chemical effects. The initial approach will utilize margin allocated for chemical effects (bump-up factor). The bump up factor will be validated by testing andlor evaluation data and adjusted as necessary. The chemical effect evaluation approach will be summarized in our September 1, 2005, response to GL 2004-02.