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| | issue date = 01/22/2010 | | | issue date = 01/22/2010 |
| | title = Correction to Amendment No. 263 Request to Add Steam Generator Blowdown Isolation Requirements to Technical Specifications | | | title = Correction to Amendment No. 263 Request to Add Steam Generator Blowdown Isolation Requirements to Technical Specifications |
| | author name = Wilkins L E | | | author name = Wilkins L |
| | author affiliation = NRC/NRR/DORL/LPLIV | | | author affiliation = NRC/NRR/DORL/LPLIV |
| | addressee name = Bannister D J | | | addressee name = Bannister D |
| | addressee affiliation = Omaha Public Power District | | | addressee affiliation = Omaha Public Power District |
| | docket = 05000285 | | | docket = 05000285 |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 January 22, 2010 Mr. David J. Bannister Vice President and CNO Omaha Public Power District Fort Calhoun Station 444 South 16th St. Mall Omaha, NE 68102-2247 FORT CALHOUN STATION, UNIT NO.1 -CORRECTION TO AMENDMENT NO. 263 RE: REQUEST TO ADD STEAM GENERATOR BLOWDOWN ISOLATION REQUIREMENTS TO TECHNICAL SPECIFICATIONS (TAC NO. ME0596) | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 22, 2010 Mr. David J. Bannister Vice President and CNO Omaha Public Power District Fort Calhoun Station 444 South 16th St. Mall Omaha, NE 68102-2247 |
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| | ==SUBJECT:== |
| | FORT CALHOUN STATION, UNIT NO.1 - CORRECTION TO AMENDMENT NO. 263 RE: REQUEST TO ADD STEAM GENERATOR BLOWDOWN ISOLATION REQUIREMENTS TO TECHNICAL SPECIFICATIONS (TAC NO. ME0596) |
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| ==Dear Mr. Bannister:== | | ==Dear Mr. Bannister:== |
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| On October 9, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML092540591), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 263 to Renewed Facility Operating License No. DPR-40 for the Fort Calhoun Station, Unit NO.1. The amendment consisted of changes to the Technical Specifications (TSs) in response to your application dated January 30, 2009, as supplemented by letters dated June 30 and August 28,2009 (ADAMS Accession Nos. ML090340536, ML091830041, and ML092440295, respectively). | | On October 9, 2009 (Agencywide Documents Access and Management System (ADAMS) |
| Amendment No. 263 added steam generator blowdown isolation operability and surveillance requirements to the TSs. These requirements will be needed as a result of a plant modification to add an interlock to automatically isolate steam generator blowdown following a reactor trip. In addition, the amendment modified the remedial actions for channels that currently contain a key-operated bypass switch by deleting the term "key-operated" so that channels with a bypass switch that are not key-operated may be bypassed as well. On June 30, 2008, the NRC staff issued Amendment No. 257 (ADAMS Accession No. ML081790191), which renumbered most of the pages in TS 3.1. Upon implementation of Amendment No. 257, what had been TS 3.1 -Page 13 became TS 3.1 -Page 14. Due to an administrative error, the NRC issued Amendment No. 263 which revised TS 3.1 -Page 14 improperly as TS 3.1 -Page 13 thereby creating two TS pages having the same page number, TS 3.1 -Page 13. This administrative error did not impact Amendment No. 263 for FCS. The error does not change the NRC staff conclusions regarding Amendment No. 263 for FCS. Enclosed are corrected versions of TS 3.1 -Page 13 (Amendment 257) and TS 3.1 -Page 14 (Amendment 263). Please discard the associated pages from the previous amendments and replace them with the enclosed pages. | | Accession No. ML092540591), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 263 to Renewed Facility Operating License No. DPR-40 for the Fort Calhoun Station, Unit NO.1. The amendment consisted of changes to the Technical Specifications (TSs) in response to your application dated January 30, 2009, as supplemented by letters dated June 30 and August 28,2009 (ADAMS Accession Nos. ML090340536, ML091830041, and ML092440295, respectively). |
| D. Bannister -2 If you have any questions, please contact me at 301-415-1377 or Iynnea.wilkins@nrc.gov. | | Amendment No. 263 added steam generator blowdown isolation operability and surveillance requirements to the TSs. These requirements will be needed as a result of a plant modification to add an interlock to automatically isolate steam generator blowdown following a reactor trip. |
| ?eI Y ,. tt, /' Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285 | | In addition, the amendment modified the remedial actions for channels that currently contain a key-operated bypass switch by deleting the term "key-operated" so that channels with a bypass switch that are not key-operated may be bypassed as well. |
| | On June 30, 2008, the NRC staff issued Amendment No. 257 (ADAMS Accession No. ML081790191), which renumbered most of the pages in TS 3.1. Upon implementation of Amendment No. 257, what had been TS 3.1 - Page 13 became TS 3.1 - Page 14. Due to an administrative error, the NRC issued Amendment No. 263 which revised TS 3.1 - Page 14 improperly as TS 3.1 - Page 13 thereby creating two TS pages having the same page number, TS 3.1 - Page 13. |
| | This administrative error did not impact Amendment No. 263 for FCS. The error does not change the NRC staff conclusions regarding Amendment No. 263 for FCS. Enclosed are corrected versions of TS 3.1 - Page 13 (Amendment 257) and TS 3.1 - Page 14 (Amendment 263). Please discard the associated pages from the previous amendments and replace them with the enclosed pages. |
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| | D. Bannister -2 If you have any questions, please contact me at 301-415-1377 or Iynnea.wilkins@nrc.gov. |
| | ?eI ,. Y tt, |
| | /' ~a Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285 |
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| ==Enclosures:== | | ==Enclosures:== |
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| As stated cc w/encl: Distribution via Listserv | | As stated cc w/encl: Distribution via Listserv |
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| | ENCLOSURES OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT 1 DOCKET NO. 50-285 Corrected Technical Specification Page 3.1 - Page 13 (Amendment 257) |
| | AND Corrected Technical Specification Page 3.1 - Page 14 (Amendment 263) |
| | |
| | TECHNICAL SPECIFICATIONS TABLE 3-2 (continued) |
| | MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TESTING OF ENGINEERED SAFETY FEATURES. INSTRUMENTATION AND CONTROLS |
| | ~ J Channel Description Surveillance Function Frequency Surveillance Method 0(6) |
| | : 18. SIRW Tank Temperature a. Check a. Verify that temperature is within limits. |
| | : b. Test R b. Measure temperature of SIRW tank with standard laboratory instruments. |
| | : 19. Manual Recirculation a. Test R a. CHANNEL FUNCTIONAL TEST Actuation |
| | : 20. Recirculation Actuation a. Test Q a. CHANNEL FUNCTIONAL TEST Logic R(7) |
| | : b. Test b. CHANNEL FUNCTIONAL TEST |
| | *21. 4.16 KV Emergency Bus a. Check S a. Verify voltage readings are above Low Voltage (Loss of alarm initiation on degraded voltage Voltage and Degraded level - supervisory lights "on". |
| | Voltage) Actuation Logic |
| | : b. Test Q b. CHANNEL FUNCTIONAL TEST (Undervoltage relay) |
| | : c. Calibrate R c. CHANNEL CALIBRATION |
| | : 22. Manual Emergency Off-site a. Test R a. CHANNEL FUNCTIONAL TEST Power Low Trip Actuation 3.1-Page13 Amendment No. 41.153.163.172.182.249,257 |
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| | TECHNICAL SPECIFICATIONS TABLE 3-2 (continued) |
| | MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TESTING OF ENGINEERED SAFETY FEATURES, INSTRUMENTATION AND CONTROLS Channel Description Surveillance Function Frequency Surveillance Method |
| | : 23. Auxiliary Feedwater a. Check: S a. |
| | : 1) Steam Generator 1) CHANNEL CHECK Water Level Low (Wide Range) |
| | : 2) Steam Generator 2) CHANNEL CHECK Pressure Low |
| | : b. Test: QR(7) b. |
| | : 1) Actuation Logic 1) CHANNEL FUNCTIONAL TEST |
| | : c. Calibrate: R c. |
| | : 1) Steam Generator 1) CHANNEL CALIBRATION Water Level Low (Wide Range) |
| | : 2) Steam Generator 2) CHANNEL CALIBRATION Pressure Low |
| | : 3) Steam Generator 3) CHANNEL CALIBRATION Differential Pressure High |
| | : 24. Manual Auxiliary Feedwater a. Test R a. CHANNEL FUNCTIONAL TEST Actuation |
| | : 25. Manual Steam Generator a. Test R a. CHANNEL FUNCTIONAL TEST Blowdown Isolation |
| | : 26. Automatic Steam Generator a. Test R a. CHANNEL FUNCTIONAL TEST Blowdown Isolation NOTES: (1) Not required unless pressurizer pressure is above 1700 psia. |
| | (2) CRHS monitors are the containment atmosphere gaseous radiation monitor and the Auxiliary Building Exhaust Stack gaseous radiation monitor. |
| | (3) Not required unless steam generator pressure is above 600 psia. |
| | (4) QP - Quarterly during designated modes and prior to taking the reactor critical if not completed within the previous 92 days (not applicable to a fast trip recovery). |
| | (5) Not required to be done on a SIT with inoperable level and/or pressure instrumentation. |
| | (6) Not required when outside ambient air temperature is greater than 50°F and less than 105°F. |
| | (7) Tests backup channels such as derived circuits and equipment that cannot be tested when the plant is at power. |
| | (8) SGLS is required for containment spray pump actuation only. SGLS lockout relays are not actuated for this test. |
| | 3.1 - Page 14 Amendment No. 41,54,65,122,163,171,172,182,255,257,263 |
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| OMAHA PUBLIC POWER FORT CALHOUN STATION, UNIT DOCKET NO. Corrected Technical Specification Page 3.1 -Page 13 (Amendment Corrected Technical Specification Page 3.1 -Page 14 (Amendment TECHNICAL SPECIFICATIONS TABLE 3-2 (continued)
| | D. Bannister -2 If you have any questions, please contact me at 301-415-1377 or Iynnea.wilkins@nrc.gov. |
| MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TESTING OF ENGINEERED SAFETY FEATURES.
| | Sincerely, IRA! |
| INSTRUMENTATION AND CONTROLS J Channel Description Surveillance Function Frequency Surveillance Method 18. SIRW Tank Temperature
| | Lynnea Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285 |
| : a. Check 0(6) a. Verify that temperature is within limits. b. Test R b. Measure temperature of SIRW tank with standard laboratory instruments.
| |
| : 19. Manual Recirculation
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| : a. Test R a. CHANNEL FUNCTIONAL TEST Actuation
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| : 20. Recirculation Actuation
| |
| : a. Test Q a. CHANNEL FUNCTIONAL TEST Logic b. Test R(7) b. CHANNEL FUNCTIONAL TEST *21. 4.16 KV Emergency Bus a. Check S a. Verify voltage readings are above Low Voltage (Loss of alarm initiation on degraded voltage Voltage and Degraded level -supervisory lights "on". Voltage) Actuation Logic b. Test Q b. CHANNEL FUNCTIONAL TEST (Undervoltage relay) c. Calibrate R c. CHANNEL CALIBRATION
| |
| : 22. Manual Emergency Off-site a. Test R a. CHANNEL FUNCTIONAL TEST Power Low Trip Actuation 3.1-Page13 Amendment No. 41.153.163.172.182.249,257 TECHNICAL SPECIFICATIONS TABLE 3-2 (continued)
| |
| MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TESTING ENGINEERED SAFETY FEATURES, INSTRUMENTATION AND Channel Description Surveillance Function Frequency Surveillance Method Auxiliary Feedwater
| |
| : a. Check: S a. Steam Generator
| |
| : 1) CHANNEL CHECK Water Level Low (Wide Range) Steam Generator
| |
| : 2) CHANNEL CHECK Pressure Low QR(7)Test: b. 1) Actuation Logic 1) CHANNEL FUNCTIONAL TEST Calibrate:
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| R c. 1) Steam Generator
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| : 1) CHANNEL CALIBRATION Water Level Low (Wide Range) 2) Steam Generator
| |
| : 2) CHANNEL CALIBRATION Pressure Low Steam Generator
| |
| : 3) CHANNEL CALIBRATION Differential Pressure High Manual Auxiliary Feedwater
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| : a. Test R a. CHANNEL FUNCTIONAL TEST Actuation Manual Steam Generator
| |
| : a. Test R a. CHANNEL FUNCTIONAL TEST Blowdown Isolation Automatic Steam Generator
| |
| : a. Test R a. CHANNEL FUNCTIONAL TEST Blowdown Isolation NOTES: (1) Not required unless pressurizer pressure is above 1700 psia. (2) CRHS monitors are the containment atmosphere gaseous radiation monitor and the Auxiliary Building Exhaust Stack gaseous radiation monitor. (3) Not required unless steam generator pressure is above 600 psia. (4) QP -Quarterly during designated modes and prior to taking the reactor critical if not completed within the previous 92 days (not applicable to a fast trip recovery).
| |
| (5) Not required to be done on a SIT with inoperable level and/or pressure instrumentation.
| |
| (6) Not required when outside ambient air temperature is greater than 50°F and less than 105°F. (7) Tests backup channels such as derived circuits and equipment that cannot be tested when the plant is at power. (8) SGLS is required for containment spray pump actuation only. SGLS lockout relays are not actuated for this test. -Page 14 Amendment No. 41,54,65,122,163,171,172,182,255,257,263 D. Bannister -2 If you have any questions, please contact me at 301-415-1377 or Iynnea.wilkins@nrc.gov.
| |
| Sincerely, IRA! Lynnea Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285 | |
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| ==Enclosures:== | | ==Enclosures:== |
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| As stated cc w/encl: Distribution via Listserv DISTRIBUTION PUBLIC LPLIV Reading RidsAcrsAcnw_MailCTR Resource RidsNrrDorlLpl4 Resource RidsNrrPMFortCalhoun Resource RidsNrrLAJBurkhardt Resource RidsOgcRp Resource RidsRgn4MailCenter Resource GHill,OIS RecordsAmend Resource ADAMS Accession No. ML093561119 OFFICE NRR/LPL4/PM NRR/LPL4/PM NRR/LPL4/LA NRR/LPL4/BC NRR/LPL4/PM NAME LWilkins AWang JBurkhardt MMarkley LWilkins DATE 1/19/10 1/20/10 1/19/10 1/22/10 1/22/10 OFFICIAL AGENCY}} | | As stated cc w/encl: Distribution via Listserv DISTRIBUTION PUBLIC LPLIV Reading RidsAcrsAcnw_MailCTR Resource RidsNrrDorlLpl4 Resource RidsNrrPMFortCalhoun Resource RidsNrrLAJBurkhardt Resource RidsOgcRp Resource RidsRgn4MailCenter Resource GHill,OIS RecordsAmend Resource ADAMS Accession No. ML093561119 OFFICE NRR/LPL4/PM NRR/LPL4/PM NRR/LPL4/LA NRR/LPL4/BC NRR/LPL4/PM NAME LWilkins AWang JBurkhardt MMarkley LWilkins DATE 1/19/10 1/20/10 1/19/10 1/22/10 1/22/10 OFFICIAL AGENCY RECORD}} |
Letter Sequence Other |
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MONTHYEARLIC-09-0004, License Amendment Request (LAR) 09-01, Steam Generator Blowdown Isolation Operability and Testing Requirements2009-01-30030 January 2009
License Amendment Request (LAR) 09-01, Steam Generator Blowdown Isolation Operability and Testing Requirements
Project stage: Request
ML0905407952009-02-23023 February 2009
Acceptance Review Email, License Amendment Request, Modify Technical Specifications to Add Operability and Testing Requirements for Steam .Generator Blowdown Isolation on a Reactor Trip
Project stage: Acceptance Review
ML0916805892009-06-17017 June 2009
Request for Additional Information, License Amendment Request, Modify Technical Specifications to Add Operability and Testing Requirements for Steam Generator Blowdown Isolation on a Reactor Trip
Project stage: RAI
ML0916805862009-06-17017 June 2009
Email, Request for Additional Information, License Amendment Request, Modify Technical Specifications to Add Operability and Testing Requirements for Steam Generator Blowdown Isolation on a Reactor Trip
Project stage: RAI
LIC-09-0043, Response to Request for Additional Information Concerning License Amendment Request (LAR) 09-01, Steam Generator Blowdown Isolation Operability and Testing Requirements2009-06-30030 June 2009
Response to Request for Additional Information Concerning License Amendment Request (LAR) 09-01, Steam Generator Blowdown Isolation Operability and Testing Requirements
Project stage: Response to RAI
LIC-09-0068, Response to Revision to License Amendment Request (LAR) 09-01, Steam Generator Blowdown Isolation Operability and Testing Requirements.2009-08-28028 August 2009
Response to Revision to License Amendment Request (LAR) 09-01, Steam Generator Blowdown Isolation Operability and Testing Requirements.
Project stage: Request
ML0925405912009-10-0909 October 2009
License Amendment, Issuance of Amendment No. 263 Modify Technical Specifications to Add Operability and Testing Requirements for Steam Generator Blowdown Isolation on a Reactor Trip
Project stage: Approval
ML0935611192010-01-22022 January 2010
Correction to Amendment No. 263 Request to Add Steam Generator Blowdown Isolation Requirements to Technical Specifications
Project stage: Other
2009-06-17
[Table View] |
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Category:Letter
MONTHYEARIR 05000285/20240032024-10-29029 October 2024
NRC Inspection Report 05000285/2024003
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
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)
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)
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
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
IR 05000285/20230022023-06-0505 June 2023
NRC Inspection Report 05000285/2023002
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
ML22265A0262022-09-26026 September 2022
U.S. Nuclear Regulatory Commissions Analysis of Omaha Public Power Districts Decommissioning Status Report (License No. DPR-40, Docket No. 50-285)
IR 05000285/20220042022-09-14014 September 2022
NRC Inspection Report 05000285/2022004
ML22138A1252022-08-0303 August 2022
Letter to Mr. Timothy Rhodd, Chairperson, Iowa Tribe of Kansas and Nebraska, Re., Ft Calhoun LTP Section 106
ML22138A1222022-08-0303 August 2022
Letter to Mr. John Shotton, Chairman, Otoe-Missouria Tribe of Indians, Oklahoma, Re., Ft Calhoun LTP Section 106
ML22138A1302022-08-0303 August 2022
Letter to Justin Wood, Principal Chief, Sac and Fox Nation, Oklahoma, Re., Ft Calhoun LTP Section 106
ML22214A0922022-08-0303 August 2022
Letter to Stacy Laravie, Thpo, Ponca Tribe of Nebraska, Re., Ft Calhoun LTP Section 106
2024-09-18
[Table view]
Category:Technical Specifications
MONTHYEARML24019A1672024-01-31031 January 2024
Issuance of Amendment to Renewed Facility License to Add License Condition to Include License Termination Plan Requirements
ML17123A3482017-07-27027 July 2017
Issuance of Amendment No. 291, Revise the Radiological Emergency Response Plan for Permanently Defueled Condition
ML16084A7552016-04-0505 April 2016
Issuance of Amendment No. 287, Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours/Month, Using CLIIP
ML15307A0132016-02-23023 February 2016
Issuance of Amendment No. 286, Request to Make Administrative Changes to the Technical Specifications to Update Titles, Delete Obsolete Actions in Appendix B, and Relocate a Definition
ML15288A0052015-12-15015 December 2015
Issuance of Amendment No. 285, Adopt Emergency Action Level Scheme Pursuant to Nuclear Energy Institute (NEI) 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors
LIC-15-0076, License Amendment Request 15-06; Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control.2015-09-11011 September 2015
License Amendment Request 15-06; Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control.
LIC-15-0085, License Amendment Request 15-05; Application to Revise Technical Specification to Adopt TSTF-426, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiative 6B & 6C, Using the Consolidated Line Item.2015-09-11011 September 2015
License Amendment Request 15-05; Application to Revise Technical Specification to Adopt TSTF-426, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiative 6B & 6C, Using the Consolidated Line Item.
LIC-15-0053, License Amendment Request (LAR) 15-04; Application to Revise Technical Specification for Administrative Changes2015-08-20020 August 2015
License Amendment Request (LAR) 15-04; Application to Revise Technical Specification for Administrative Changes
ML15209A8022015-08-10010 August 2015
Issuance of Amendment No. 283, Revise Updated Safety Analysis Report to Allow Pipe Stress Analysis to Be Performed in Accordance with ASME Code Section III
ML15111A3992015-06-30030 June 2015
Issuance of Amendment No. 282, Revise Updated Safety Analysis Report for Controlling Raw Water Pump Operation and Safety Classification of Components During a Flood
ML15035A2032015-03-27027 March 2015
Issuance of Amendment No. 281, Revise Technical Specification 3.1, Table 3-3 to Correct Administrative Error in Surveillance Method for Containment Wide Range Radiation Monitors
ML15015A4132015-02-20020 February 2015
Issuance of Amendment No. 280, Revise Technical Specification 3.2, Table 3-5 to Add New Surveillance Requirement
ML14356A0122014-12-29029 December 2014
Issuance of Amendment No. 279, Revise Technical Specification Surveillance Requirements for One-Time Extension from Refueling Frequency of Once Per 18 Months to Maximum of 28 Months
ML14328A8142014-12-22022 December 2014
Issuance of Amendment No. 278, Revise Technical Specification 2.5, Auxiliary Feedwater (AFW) System to Allow 7-Day Completion Time for Turbine-Driven AFW Pump Based on TSTF-340, Revision 3
LIC-14-0128, License Amendment Request (LAR) 14-10; One- Time Extension of Technical Specification Surveillance Requirements2014-11-0707 November 2014
License Amendment Request (LAR) 14-10; One- Time Extension of Technical Specification Surveillance Requirements
ML14279A2752014-11-0606 November 2014
Issuance of Amendment No. 277, Revise Technical Specification Surveillance Requirement 3.2, Table 3-5, Item 3, for One-Time Extension of Frequency to Maximum of 28 Months
ML14209A0272014-08-0707 August 2014
Issuance of Amendment No. 276, Request to Revise Updated Safety Analysis Report for Westinghouse Plant-Specific Leak-Before-Break Analysis
ML14098A0922014-06-16016 June 2014
Issuance of Amendment No. 275, Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition)
ML14115A2972014-04-10010 April 2014
Enclosure 1: Fort Calhoun Station, Unit 1 - Supplement to License Amendment Request 10-07, Proposed Changes to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants
ML14041A4082014-02-10010 February 2014
License Amendment Request (LAR) 14-01, One-Time Extension of Technical Specification Surveillance Requirement 3.2, Table 3-5, Item 3
ML14108A0442013-12-31031 December 2013
Omaha Public Power District Fort Calhoun Station Unit Radiological Environmental Operating Report for Technical Specification Section 5.94.b January 1, 2013 to December 31, 2013
ML14108A0422013-12-31031 December 2013
Omaha Public Power District Fort Calhoun Station Unit No. 1 - Annual Report for Technical Specification Section 5.94.a January 1, 2013 to December 31, 2013
ML12128A1702012-04-12012 April 2012
Technical Specification (TS) Basis Change Index, Page 2 of 2 and TS 2.10 - Page 18
LIC-12-0006, License Amendment Request (LAR) 12-01, Proposed Change to Establish the Reactor Protective System (RPS) Actuation Circuits Limiting Condition for Operation (LCO)2012-02-10010 February 2012
License Amendment Request (LAR) 12-01, Proposed Change to Establish the Reactor Protective System (RPS) Actuation Circuits Limiting Condition for Operation (LCO)
LIC-12-0052, Annual Report for Technical Specification Section 5.9.4a2011-12-31031 December 2011
Annual Report for Technical Specification Section 5.9.4a
LIC-10-0034, License Amendment Request (LAR) Revision to Technical Specification (TS) 2.15, Table 2-5, Item 1 and TS 3.1, Table 3-3, Items 1, 2 and 4 Control Element Assembly Position Indication and Correction of TS 2.10.2(7)c.2010-07-12012 July 2010
License Amendment Request (LAR) Revision to Technical Specification (TS) 2.15, Table 2-5, Item 1 and TS 3.1, Table 3-3, Items 1, 2 and 4 Control Element Assembly Position Indication and Correction of TS 2.10.2(7)c.
LIC-10-0043, Supplement to Emergency License Amendment Request Revision to Technical Specification 2.15, Table 2-5 Note (C) for Safety Valve Acoustic Position Indication2010-06-0101 June 2010
Supplement to Emergency License Amendment Request Revision to Technical Specification 2.15, Table 2-5 Note (C) for Safety Valve Acoustic Position Indication
ML0935611192010-01-22022 January 2010
Correction to Amendment No. 263 Request to Add Steam Generator Blowdown Isolation Requirements to Technical Specifications
ML0925405912009-10-0909 October 2009
License Amendment, Issuance of Amendment No. 263 Modify Technical Specifications to Add Operability and Testing Requirements for Steam Generator Blowdown Isolation on a Reactor Trip
ML0912502752009-05-0505 May 2009
Replacement Page TS 2.1 - Page 8, License Amendment Request for Administrative Revisions
ML0907108912009-03-27027 March 2009
License Amendment, Issuance of Amendment No. 258, Revise Limiting Condition for Operation 2.7(2)j in TS 2.7, Electrical Systems, to Clarify Allowed Outage Time for Emergency Diesel Generators
ML0911703682009-02-18018 February 2009
Updated Tech Spec Pages, from Licensee, License Amendment Request Lic 08-0078, Administrative Revisions to the Technical Specifications to Correct Typographical Errors and Provide Clarification
LIC-09-0008, License Amendment Request for Adoption of TSTF-511, Rev 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26.2009-01-30030 January 2009
License Amendment Request for Adoption of TSTF-511, Rev 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26.
LIC-08-0074, License Amendment Request (LAR) 08-03, Clarify Technical Specification 2.7(2) Regarding Preferred Offsite Power Source, Transformer Allowed Outage Time (AOT)2008-07-31031 July 2008
License Amendment Request (LAR) 08-03, Clarify Technical Specification 2.7(2) Regarding Preferred Offsite Power Source, Transformer Allowed Outage Time (AOT)
LIC-08-0049, License Amendment Request (LAR) Clarification of Technical Specification (TS) 2.7(2)j, Regarding Emergency Diesel Generators Allowed Outage Time2008-04-22022 April 2008
License Amendment Request (LAR) Clarification of Technical Specification (TS) 2.7(2)j, Regarding Emergency Diesel Generators Allowed Outage Time
LIC-08-0008, License Amendment Request (LAR) Revision to Technical Specification (TS) 2.5(1)A, Auxiliary Feedwater (AFW) System.2008-02-0505 February 2008
License Amendment Request (LAR) Revision to Technical Specification (TS) 2.5(1)A, Auxiliary Feedwater (AFW) System.
LIC-07-0084, License Amendment Request, Change to Diesel Generator Surveillance Testing.2007-10-0505 October 2007
License Amendment Request, Change to Diesel Generator Surveillance Testing.
LIC-07-0082, License Amendment Request (LAR) Permanent Use of Sodium Tetraborate as the Containment Building Sump Buffering Agent.2007-09-11011 September 2007
License Amendment Request (LAR) Permanent Use of Sodium Tetraborate as the Containment Building Sump Buffering Agent.
LIC-07-0046, Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process2007-05-16016 May 2007
Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process
ML0707100982007-04-0303 April 2007
Technical Specifications, Editorial Changes to Apply Certain Limiting Conditions for Operation Requirements
ML0705905082007-02-28028 February 2007
License and Technical Specification Pages - Amendment No. 248 to Facility Operating License Relocation of T.S. 2.22, Toxic Gas Monitors, and T.S. Table 3-3, Item 29 to Updated Safety Analysis Report
LIC-06-0146, License Amendment Request, Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Purge System Using the Consolidated Line Item Improvement Process.2006-12-20020 December 2006
License Amendment Request, Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Purge System Using the Consolidated Line Item Improvement Process.
LIC-06-0147, License Amendment Request for Administrative Revisions to Fort Calhoun Station, Unit No. 1 Technical Specifications2006-12-20020 December 2006
License Amendment Request for Administrative Revisions to Fort Calhoun Station, Unit No. 1 Technical Specifications
ML0631105582006-11-0707 November 2006
Technical Specifications, Revising TS Steam Generator Tube Suveillance Program
ML0631202592006-10-27027 October 2006
Tech Spec Pages for Amendment 244 Modifications to Technical Specification 2.4, Containment Cooling to Reduce Operable Containment Spray Pumps
ML0628604282006-10-10010 October 2006
Response to Request for Additional Information (RAI) Related to the Replacement of Trisodium Phosphate
ML0624304022006-08-30030 August 2006
Revised License Amendment Request, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process and Deletion of Sleeving as a Steam Generator..
ML0624201602006-08-30030 August 2006
Tech Spec Pages for Amendment 241 Regarding Use of M5 Fuel Cladding
ML0624301302006-06-27027 June 2006
Tech Spec Pages for Amendment 240 Deletion of Design Features in Technical Specifications 4.3.1.2b and 4.3.1.2c
LIC-06-0063, Exigent LAR, Deletion of Design Features Technical Specifications Redundant to 10 CFR 50.68, Criticality Accident Requirements.2006-06-0202 June 2006
Exigent LAR, Deletion of Design Features Technical Specifications Redundant to 10 CFR 50.68, Criticality Accident Requirements.
2024-01-31
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 22, 2010 Mr. David J. Bannister Vice President and CNO Omaha Public Power District Fort Calhoun Station 444 South 16th St. Mall Omaha, NE 68102-2247
SUBJECT:
FORT CALHOUN STATION, UNIT NO.1 - CORRECTION TO AMENDMENT NO. 263 RE: REQUEST TO ADD STEAM GENERATOR BLOWDOWN ISOLATION REQUIREMENTS TO TECHNICAL SPECIFICATIONS (TAC NO. ME0596)
Dear Mr. Bannister:
On October 9, 2009 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML092540591), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 263 to Renewed Facility Operating License No. DPR-40 for the Fort Calhoun Station, Unit NO.1. The amendment consisted of changes to the Technical Specifications (TSs) in response to your application dated January 30, 2009, as supplemented by letters dated June 30 and August 28,2009 (ADAMS Accession Nos. ML090340536, ML091830041, and ML092440295, respectively).
Amendment No. 263 added steam generator blowdown isolation operability and surveillance requirements to the TSs. These requirements will be needed as a result of a plant modification to add an interlock to automatically isolate steam generator blowdown following a reactor trip.
In addition, the amendment modified the remedial actions for channels that currently contain a key-operated bypass switch by deleting the term "key-operated" so that channels with a bypass switch that are not key-operated may be bypassed as well.
On June 30, 2008, the NRC staff issued Amendment No. 257 (ADAMS Accession No. ML081790191), which renumbered most of the pages in TS 3.1. Upon implementation of Amendment No. 257, what had been TS 3.1 - Page 13 became TS 3.1 - Page 14. Due to an administrative error, the NRC issued Amendment No. 263 which revised TS 3.1 - Page 14 improperly as TS 3.1 - Page 13 thereby creating two TS pages having the same page number, TS 3.1 - Page 13.
This administrative error did not impact Amendment No. 263 for FCS. The error does not change the NRC staff conclusions regarding Amendment No. 263 for FCS. Enclosed are corrected versions of TS 3.1 - Page 13 (Amendment 257) and TS 3.1 - Page 14 (Amendment 263). Please discard the associated pages from the previous amendments and replace them with the enclosed pages.
D. Bannister -2 If you have any questions, please contact me at 301-415-1377 or Iynnea.wilkins@nrc.gov.
?eI ,. Y tt,
/' ~a Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285
Enclosures:
As stated cc w/encl: Distribution via Listserv
ENCLOSURES OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT 1 DOCKET NO. 50-285 Corrected Technical Specification Page 3.1 - Page 13 (Amendment 257)
AND Corrected Technical Specification Page 3.1 - Page 14 (Amendment 263)
TECHNICAL SPECIFICATIONS TABLE 3-2 (continued)
MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TESTING OF ENGINEERED SAFETY FEATURES. INSTRUMENTATION AND CONTROLS
~ J Channel Description Surveillance Function Frequency Surveillance Method 0(6)
- 18. SIRW Tank Temperature a. Check a. Verify that temperature is within limits.
- b. Test R b. Measure temperature of SIRW tank with standard laboratory instruments.
- 19. Manual Recirculation a. Test R a. CHANNEL FUNCTIONAL TEST Actuation
- 20. Recirculation Actuation a. Test Q a. CHANNEL FUNCTIONAL TEST Logic R(7)
- b. Test b. CHANNEL FUNCTIONAL TEST
- 21. 4.16 KV Emergency Bus a. Check S a. Verify voltage readings are above Low Voltage (Loss of alarm initiation on degraded voltage Voltage and Degraded level - supervisory lights "on".
Voltage) Actuation Logic
- b. Test Q b. CHANNEL FUNCTIONAL TEST (Undervoltage relay)
- c. Calibrate R c. CHANNEL CALIBRATION
- 22. Manual Emergency Off-site a. Test R a. CHANNEL FUNCTIONAL TEST Power Low Trip Actuation 3.1-Page13 Amendment No. 41.153.163.172.182.249,257
TECHNICAL SPECIFICATIONS TABLE 3-2 (continued)
MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TESTING OF ENGINEERED SAFETY FEATURES, INSTRUMENTATION AND CONTROLS Channel Description Surveillance Function Frequency Surveillance Method
- 23. Auxiliary Feedwater a. Check: S a.
- 1) Steam Generator 1) CHANNEL CHECK Water Level Low (Wide Range)
- 2) Steam Generator 2) CHANNEL CHECK Pressure Low
- b. Test: QR(7) b.
- 1) Actuation Logic 1) CHANNEL FUNCTIONAL TEST
- c. Calibrate: R c.
- 1) Steam Generator 1) CHANNEL CALIBRATION Water Level Low (Wide Range)
- 2) Steam Generator 2) CHANNEL CALIBRATION Pressure Low
- 3) Steam Generator 3) CHANNEL CALIBRATION Differential Pressure High
- 24. Manual Auxiliary Feedwater a. Test R a. CHANNEL FUNCTIONAL TEST Actuation
- 25. Manual Steam Generator a. Test R a. CHANNEL FUNCTIONAL TEST Blowdown Isolation
- 26. Automatic Steam Generator a. Test R a. CHANNEL FUNCTIONAL TEST Blowdown Isolation NOTES: (1) Not required unless pressurizer pressure is above 1700 psia.
(2) CRHS monitors are the containment atmosphere gaseous radiation monitor and the Auxiliary Building Exhaust Stack gaseous radiation monitor.
(3) Not required unless steam generator pressure is above 600 psia.
(4) QP - Quarterly during designated modes and prior to taking the reactor critical if not completed within the previous 92 days (not applicable to a fast trip recovery).
(5) Not required to be done on a SIT with inoperable level and/or pressure instrumentation.
(6) Not required when outside ambient air temperature is greater than 50°F and less than 105°F.
(7) Tests backup channels such as derived circuits and equipment that cannot be tested when the plant is at power.
(8) SGLS is required for containment spray pump actuation only. SGLS lockout relays are not actuated for this test.
3.1 - Page 14 Amendment No. 41,54,65,122,163,171,172,182,255,257,263
D. Bannister -2 If you have any questions, please contact me at 301-415-1377 or Iynnea.wilkins@nrc.gov.
Sincerely, IRA!
Lynnea Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285
Enclosures:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION PUBLIC LPLIV Reading RidsAcrsAcnw_MailCTR Resource RidsNrrDorlLpl4 Resource RidsNrrPMFortCalhoun Resource RidsNrrLAJBurkhardt Resource RidsOgcRp Resource RidsRgn4MailCenter Resource GHill,OIS RecordsAmend Resource ADAMS Accession No. ML093561119 OFFICE NRR/LPL4/PM NRR/LPL4/PM NRR/LPL4/LA NRR/LPL4/BC NRR/LPL4/PM NAME LWilkins AWang JBurkhardt MMarkley LWilkins DATE 1/19/10 1/20/10 1/19/10 1/22/10 1/22/10 OFFICIAL AGENCY RECORD
