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Category:Letter
MONTHYEARLIC-24-0017, ISFSI - Phase 1 Final Status Survey Report to Support Approved License Termination Plan, Revision 1; and Technical Support Document for the Ludlum 44-20 Detector Sensitivity2024-11-21021 November 2024 ISFSI - Phase 1 Final Status Survey Report to Support Approved License Termination Plan, Revision 1; and Technical Support Document for the Ludlum 44-20 Detector Sensitivity LIC-24-0015, Response to Proposed Revision to the Omaha Public Power District (OPPD) Fort Calhoun Station (FCS) Decommissioning Quality Assurance Plan (DQAP) – Clarification of Request for Additional Information Response2024-11-20020 November 2024 Response to Proposed Revision to the Omaha Public Power District (OPPD) Fort Calhoun Station (FCS) Decommissioning Quality Assurance Plan (DQAP) – Clarification of Request for Additional Information Response LIC-24-0016, Independent Spent Fuel Storage Installation - 2024 Decommissioning Funding Plan Required 72.30(c) Updated Financial Information2024-11-19019 November 2024 Independent Spent Fuel Storage Installation - 2024 Decommissioning Funding Plan Required 72.30(c) Updated Financial Information ML24318C2532024-11-18018 November 2024 Acceptance of Requested Licensing Action License Amendment Request to Revise the License Termination Plan (L-2024-LLA-0095) IR 05000285/20240032024-10-29029 October 2024 NRC Inspection Report 05000285/2024003 LIC-24-0014, Independent Spent Fuel Storage Installation - Supplement to 2021, and 2024 Nuclear Decommissioning Funding Plan Required 72.30(c) Update2024-10-10010 October 2024 Independent Spent Fuel Storage Installation - Supplement to 2021, and 2024 Nuclear Decommissioning Funding Plan Required 72.30(c) Update LIC-24-0013, Independent Spent Fuel Storage Installation - Intent to Submit a Supplement to 2021, and 2024 Nuclear Decommissioning Funding Plan Required 72.30(c) Update2024-10-10010 October 2024 Independent Spent Fuel Storage Installation - Intent to Submit a Supplement to 2021, and 2024 Nuclear Decommissioning Funding Plan Required 72.30(c) Update LIC-24-0012, Independent Spent Fuel Storage Installation - Response to Proposed Revision to Decommissioning Quality Assurance Plan (DQAP) - Request for Additional Information2024-10-0707 October 2024 Independent Spent Fuel Storage Installation - Response to Proposed Revision to Decommissioning Quality Assurance Plan (DQAP) - Request for Additional Information LIC-24-0011, Independent Spent Fuel Storage Installation - Response to Application for License Amendment Request to Revise the License Termination Plan - Supplemental Information Needed, EPID L-2024-LLA-00952024-10-0202 October 2024 Independent Spent Fuel Storage Installation - Response to Application for License Amendment Request to Revise the License Termination Plan - Supplemental Information Needed, EPID L-2024-LLA-0095 ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24255A0962024-09-12012 September 2024 License Amendment Request to Revise the License Termination Plan - Request Supplemental Information (License No. DPR-40, Docket No. 50-285) ML24243A1042024-09-12012 September 2024 Proposed Revision to the OPPD FCS DQAP - Request for Additional Information (License No. DPR-40, Docket Nos. 50-285, 72-054, and 71-0256) IR 05000285/20240022024-08-21021 August 2024 NRC Inspection Report 05000285/2024002 ML24235A0822024-08-10010 August 2024 Response to Fort Calhoun Station, Unit No. 1 - Phase 1 Final Status Survey Report to Support Approved License Termination Plan - Request for Additional Information - Request for Additional Information (EPID L-2024-DFR-0002) July 8, 2024 ML24180A2082024-07-0808 July 2024 Phase 1 Final Status Survey Reports Request for Additional Information Letter ML24183A3222024-07-0808 July 2024 Proposed Revision to the Omaha Public Power District Fort Calhoun Station Decommissioning Quality Assurance Plan - Acceptance Review LIC-24-0007, License Amendment Request (LAR) to Revise License Termination Plan (LTP)2024-06-18018 June 2024 License Amendment Request (LAR) to Revise License Termination Plan (LTP) IR 05000285/20240012024-06-0505 June 2024 NRC Inspection Report 05000285/2024001 ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities LIC-24-0008, Proposed Revision to the Omaha Public Power District (OPPD) Fort Calhoun Station (FCS) Decommissioning Quality Assurance Plan (Dqap), Unit No. 1 and ISFSI2024-05-16016 May 2024 Proposed Revision to the Omaha Public Power District (OPPD) Fort Calhoun Station (FCS) Decommissioning Quality Assurance Plan (Dqap), Unit No. 1 and ISFSI LIC-24-0003, Independent Spent Fuel Storage Installation - Radiological Effluent Release Report and Radiological Environmental Operating Report2024-04-25025 April 2024 Independent Spent Fuel Storage Installation - Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-24-0006, (Fcs), Unit 1, Independent Spent Fuel Storage Installation, Phase 1 Final Status Survey Report to Support Approved License Termination Plan2024-04-17017 April 2024 (Fcs), Unit 1, Independent Spent Fuel Storage Installation, Phase 1 Final Status Survey Report to Support Approved License Termination Plan ML24079A1702024-03-10010 March 2024 ISFSI, Unit 1 - 10 CFR 50.59 Report, Quality Assurance (QA) Program Changes, Technical Specification Basis Changes, 10 CFR 71.106 Quality Assurance Program Approval, Aging Management Review, Commitment Revisions and Revision of Updated Safe LIC-24-0005, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2024-03-0101 March 2024 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-24-0002, Independent Spent Fuel Storage Installation - Submittal of Annual Radioactive Effluent Release Report2024-02-27027 February 2024 Independent Spent Fuel Storage Installation - Submittal of Annual Radioactive Effluent Release Report ML24019A1672024-01-31031 January 2024 Issuance of Amendment to Renewed Facility License to Add License Condition to Include License Termination Plan Requirements IR 05000285/20230062023-12-21021 December 2023 NRC Inspection Report 05000285/2023006 LIC-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 IR 05000285/20230052023-11-0202 November 2023 NRC Inspection Room 05000285/2023005 ML23276A0042023-09-28028 September 2023 U.S. EPA Response Letter to NRC Letter on Consultation and Finality on Decommissioning and Decontamination of Contaminated Sites MOU - Fort Calhoun Station, Unit 1 – (License No. DPR-40, Docket No. 50-285) IR 05000285/20230042023-09-13013 September 2023 NRC Inspection Report 05000285/2023-004 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 ML23234A2412023-08-18018 August 2023 Email - Letter to M Porath Re Ft Calhoun Unit 1 LTP EA Section 7 Informal Consultation Request ML23234A2392023-08-18018 August 2023 Letter to B Harisis Re Ft Calhoun Unit 1 LTP EA State of Nebraska Comment Request.Pdf IR 05000285/20230032023-07-10010 July 2023 – NRC Inspection Report 05000285/2023003 ML23082A2202023-06-26026 June 2023 Consultation on the Decommissioning of the Fort Calhoun Station Unit 1 Pressurized Water Reactor in Fort Calhoun, Nebraska IR 05000285/20230022023-06-0505 June 2023 NRC Inspection Report 05000285/2023002 ML23151A0032023-06-0505 June 2023 – 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 ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities IR 05000285/20230012023-02-24024 February 2023 NRC Inspection Report 05000285/2023001 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 ML23020A0462023-01-19019 January 2023 Threatened and Endangered Species List: Nebraska Ecological Services Field Office IR 05000285/20220062023-01-0505 January 2023 NRC Inspection Report 05000285/2022-006 ML22357A0662022-12-30030 December 2022 Technical RAI Submittal Letter on License Amendment Request for Approval of License Termination Plan IR 05000285/20220052022-10-26026 October 2022 NRC Inspection Report 05000285/2022-005 ML22276A1052022-09-30030 September 2022 Conclusion of Consultation Under Section 106 NHPA for Ft. Calhoun Station LTP ML22258A2732022-09-29029 September 2022 Letter to John Swigart, SHPO; Re., Conclusion of Consultation Under Section 106 Hnpa Fort Calhoun Station Unit 1 2024-09-18
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ilppB Omaha Public Power District 444 South 1ffh Street Mall Omaha, NE 68102-2247 January 31, 2014 U C-14-0008 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555
References:
- 1. Docket No. 50-285
- 2. NRC Letter, "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated March 12,2012 (ML12073A348) (NRC-12-0021)
- 3. NRC Letter to Nuclear Energy Institute, Endorsement of Nuclear Energy Institute (NEI) 12-07, "Guidelines for Performing Verification Walkdowns of Plant Flood Protection Features," dated May 31, 2012, (ML12144A142)
- 4. Letter from OPPD (L. P. Cortopassi) to NRC (Document Control Desk), "OPPD 180-day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident,"
dated November 27,2012 (ML12334A449) (UC-12-0170)
- 5. Letter from OPPD (L. P. Cortopassi) to NRC (Document Control Desk), "OPPD Supplemental Response to NRC Request for Information Pursuant to 1 0 CFR 50.54(f) Regarding the Flooding Aspects of Recommendations 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident,"
dated August 15, 2013 (ML13228A098) (UC-13-01 02)
- 6. NRC Letter to OPPD, Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Flooding Walkdowns; dated December 23, 2013 (ML13325A891) (NRC-13-0157)
Subject:
OPPD Response to NRC 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.3, Flooding - Review of Available Physical Margin (APM) Assessments On March 12, 2012, the NRC staff issued Reference 2 requesting information pursuant to Title 10 of the Code of Federal Regulations 50.54(f). of that letter contains specific requested Information associated with Near-Term Task Force Recommendation 2.3 for Flooding.
Per Reference 3, the NRC endorsed Nuclear Energy Institute (NEI) 12-07, "Guidelines for Performing Verification Walkdowns of Plant Flood Protection Features," dated May 31, 2012. In References 4 and 5, OPPD submitted responses to Reference 2.
U. S. Nuclear Regulatory Commission LlC-14-0008 Page 2 One of the requirements of NEI 12-07 is to identify the available physical margin (APM) associated with each applicable flood protection feature, determine if the margin provided is small, and evaluate any small margins that have potentially significant consequences through the corrective action process. The results of this effort were to be maintained on site for future NRC audits.
Following the NRC staff's initial review of the walkdown reports, regulatory site audits were conducted at a sampling of plants. Based on the walkdown reports, reviews, and site audits, the staff identified additional information necessary to allow them to complete their assessments.
Accordingly, in Reference 6, the NRC issued a request for addition information (RAI) to a number of licensees including OPPD. OPPD's response is attached.
If you should you have questions, please contact Mr. Bill Hansher at (402) 533-6894.
No commitments to the NRC are contained in this letter.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on January 31,2014.
Sincerely.
Louis P. Cortopassi Site Vice President and CNO
Attachment:
Request for Additional Information Flooding Walkdowns LPC/JKG/mle c:
M. L. Dapas, NRC Regional Administrator, Region IV J. M. Sebrosky, NRC Senior Project Manager J. C. Kirkland, NRC Senior Resident Inspector
LI C-14-0008 Attachment Page 1 Request for Additional Information Flooding Walkdowns Please provide the following:
- 1. Confirmation that the process for evaluating APM was reviewed; OPPD Response OPPD has completed a review of the process used at Fort Calhoun Station to evaluate the APM.
- 2. Confirmation that the APM process is now or was always consistent with the guidance in NEI 12-07 and discussed in this RAI; OPPD Response The APM process was always consistent with the guidance in FAQ-030 and NEI 12-07, and discussed in this RAI.
- 3. If changes are necessary, a general description of any process changes to establish this consistency; OPPD Response No changes were necessary
- 4. As a result of the audits and subsequent interactions with industry during public meetings, NRC staff recognized that evaluation of APM for seals (e.g., flood doors, penetrations, flood gates, etc.) was challenging for some licensees.
Generally, licensees were expected to use either Approach A or Approach B (described below) to determine the APM for seals:
a) If seal pressure ratings were known, the seal ratings were used to determine APM (similar to example 2 in Section 3.13 of NEI12-07). A numerical value for APM was documented. No further action was performed if the APM value was greater than the pre-established small-margin threshold value. If the APM value was small, an assessment of "significant consequences" was performed and the guidance in NEI 12-07 Section 5.8 was followed.
b) If the seal pressure rating was not known, the APM for seals in a flood barrier is assumed to be greater than the pre-established small-margin threshold value if the following conditions were met: (1) the APM for the barrier in which the seal is located is greater than the small-margin threshold value and there is evidence that the seals were designed/procured, installed, and controlled as flooding seals in accordance with the flooding licensing basis. Note that in order to determine that
LI C-14-000S Attachment Page 2 the seal has been controlled as a flooding seal, it was only necessary to determine that the seal configuration has been governed by the plant's design control process since installation. In this case, the APM for the seal could have been documented as "not small".
As part of the RAI response, state if either Approach A or Approach B was used as part of the initial walkdowns or as part of actions taken in response to this RAI.
No additional actions are necessary if either Approach A or B was used.
If neither Approach A or B was used to determine the APM values for seals (either as part of the walkdowns or as part of actions taken in response to this RAI), then perform the following two actions:
Enter the condition into the CAP (note: it is acceptable to utilize a single CAP entry to capture this issue for multiple seals).
CAP disposition of "undetermined" APM values for seals should consider the guidance provided in NEI 12-07, Section 5.8.
The CAP disposition should confirm all seals can perform their intended safety function against floods up to the current licensing basis flood height. Disposition may occur as part of the Integrated Assessment.
If an Integrated Assessment is not performed, determine whether there are significant consequences associated with exceeding the capacity of the seals and take interim action(s), if necessary, via the CAP processes. These actions do not need to be complete prior to the RAI response.
Report the APM as "undetermined" and provide the CAP reference in the RAI response.
OPPD Response The approach used to determine APM for Fort Calhoun Station most closely matches Approach A as described above. Seal pressure ratings were determined to be in accordance with the design basis and provide flood protection to 1,014 feet. As noted in Updated Safety Analysis Report (USAR), Section 2.7.1.2, flooding protection is provided by removable flood barriers that extend to 1,014 feet. USAR Section 2.7.1.2 also states:
The Corps of Engineers estimate of the flood level that might result from the failure of Oahe or Fort Randall dams coincident with the probable maximum flood that produces the 1,009.3 foot flood is 1,014 feet.
The numeric value of the difference between the height of the flood barriers and the height of the probable maximum flood was used. The APM value was small, an assessment of "significant consequences" was performed, and the guidance in NEI 12-07 Section 5.S was followed.