Letter Sequence Other |
|---|
|
Results
Other: LIC-03-0164, Response to a RAI on Measurement Uncertainty Recapture Power Uprate, LIC-04-0006, Closure of NRC Tack Issues for Fort Calhoun Station Unit No. 1, LIC-04-0061, Notification of Technical Issues Associated with License Amendment No. 225, ML032870394, ML040210313, ML040400333, ML040490383, ML041060362, ML041310501, ML041390246, ML042120203, ML043350135, ML043370117, ML050530011, ML050600428, ML050610222, ML050750059
|
MONTHYEARLIC-03-0067, Amendment Request for License DPR-40 Measurement Uncertainty Recapture Power Uprate2003-07-18018 July 2003
Amendment Request for License DPR-40 Measurement Uncertainty Recapture Power Uprate
Project stage: Request
05000285/LER-2003-002, Regarding Inadequate Testing of Diesel Generators Due to Air Start Systems Unique Design2003-08-28028 August 2003
Regarding Inadequate Testing of Diesel Generators Due to Air Start Systems Unique Design
Project stage: Request
ML0324505182003-08-28028 August 2003
Revision of License Amendment Request, Measurement Uncertainly Recapture Power Uprate
Project stage: Request
LIC-03-0142, Completion of Recirculation Actuation Logic Channel Functional Test Circuitry Modification2003-10-14014 October 2003
Completion of Recirculation Actuation Logic Channel Functional Test Circuitry Modification
Project stage: Request
ML0328705202003-10-14014 October 2003
RAI, Measurement Uncertainty Recapture Power Uprate
Project stage: RAI
ML0328703942003-10-14014 October 2003
Withholding from Public Disclosure, Calculation Number FC-6896-P, Secondary Calorimetric Uncertainty Analysis
Project stage: Other
LIC-03-0148, Response to Request for Additional Information - Measurement Uncertainty Recapture Power Uprate2003-10-31031 October 2003
Response to Request for Additional Information - Measurement Uncertainty Recapture Power Uprate
Project stage: Response to RAI
LIC-03-0077, License Amendment Request, Addition of Diesel Generator Fuel Oil, Diesel Generating Lubrication Oil, and Diesel Generator Starting Air Requirements2003-12-0101 December 2003
License Amendment Request, Addition of Diesel Generator Fuel Oil, Diesel Generating Lubrication Oil, and Diesel Generator Starting Air Requirements
Project stage: Request
LIC-03-0159, November 2003 Monthly Operating Report for Fort Calhoun Unit 12003-12-15015 December 2003
November 2003 Monthly Operating Report for Fort Calhoun Unit 1
Project stage: Request
LIC-03-0164, Response to a RAI on Measurement Uncertainty Recapture Power Uprate2003-12-15015 December 2003
Response to a RAI on Measurement Uncertainty Recapture Power Uprate
Project stage: Other
LIC-03-0166, Response to Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate2003-12-22022 December 2003
Response to Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate
Project stage: Response to RAI
ML0402007572004-01-16016 January 2004
Issuance of License Amendment 224 Revising the Renewed Operating License and the TSs to Increase the Licensed Rated Power by 1.6 Percent from 1500 Megawatts Thermal (Mwt) to 1524 Mwt
Project stage: Approval
ML0402103132004-01-16016 January 2004
Tech Spec Pages for Amendment 224 Revising the Renewed Operating License and the TSs to Increase the Licensed Rated Power by 1.6 Percent from 1500 Megawatts Thermal (Mwt) to 1524 Mwt
Project stage: Other
LIC-04-0015, Response to RAI Regarding Fort Calhoun, Unit 1, License Amendment Request, Various Administrative and Editorial Changes2004-02-0909 February 2004
Response to RAI Regarding Fort Calhoun, Unit 1, License Amendment Request, Various Administrative and Editorial Changes
Project stage: Response to RAI
ML0404003332004-02-0909 February 2004
Public Notice of Application for Amendment to Facility Operating License
Project stage: Other
ML0404903832004-02-13013 February 2004
Amendment, Changes Implementation Date from 30 Days to 120 Days for Amendment No. 224 Issued on 01/16/2004 That Approved Measurement Uncertainty Uprate to Increase Licensed Rated Power by 1.6 Percent from 1500 Megawatts Thermal to 1524
Project stage: Other
ML0405803462004-02-18018 February 2004
RAI, License Amendment Request Administrative TS Changes (Tac. MC1535)
Project stage: RAI
ML0410603622004-04-14014 April 2004
Memo to File, E-mail Regarding Fort Calhoun Emergency Diesel Generating Starting Air System
Project stage: Other
LIC-04-0061, Notification of Technical Issues Associated with License Amendment No. 2252004-05-0505 May 2004
Notification of Technical Issues Associated with License Amendment No. 225
Project stage: Other
ML0413105012004-05-10010 May 2004
5/10/04, Fort Calhoun, Unit 1 - Public Notice of Application for Amendment to Facility Operating License
Project stage: Other
ML0413902462004-05-14014 May 2004
License Amendment, Amendment Restores Licensed Thermal Power from 1524 Mega Thermal
Project stage: Other
ML0413901262004-05-14014 May 2004
5/14/04, Fort Calhoun, Unit 1 - TS - Issuance of Amendment
Project stage: Approval
LIC-04-0073, Response to Request for Additional Information Regarding License Amendment Request, Addition of Diesel Generator Fuel Oil, Diesel Generator Lubricating Oil, & Diesel Generator Starting Air Requirements2004-07-0202 July 2004
Response to Request for Additional Information Regarding License Amendment Request, Addition of Diesel Generator Fuel Oil, Diesel Generator Lubricating Oil, & Diesel Generator Starting Air Requirements
Project stage: Response to RAI
ML0421202032004-07-23023 July 2004
Tech Spec Pages for Amendment 228 Various Administrative and Editorial Changes
Project stage: Other
ML0421104112004-07-23023 July 2004
Issuance of License Amendment 228 Various Administrative and Editorial Changes
Project stage: Approval
ML0424300272004-08-27027 August 2004
RAI, Modify Technical Specification 2.3.(4)
Project stage: RAI
LIC-04-0094, Supplemental Response to the Requests for Additional Information on the Fort Calhoun, Unit 1 Security Plan and Safeguards Contingency Plan2004-08-27027 August 2004
Supplemental Response to the Requests for Additional Information on the Fort Calhoun, Unit 1 Security Plan and Safeguards Contingency Plan
Project stage: Supplement
ML0433501352004-10-21021 October 2004
Tech Spec Pages for Amendment No. 229, Changing TS 2.7, TS Table 3-5 and TS 5.0 to Modify Requirements for the Diesel Generator Fuel Oil for Consistency with Improved Standard TS
Project stage: Other
ML0430205742004-10-21021 October 2004
Issuance of License Amendment No. 229, Changing TS 2.7, TS Table 3-5 and TS 5.0 to Modify Requirements for the Diesel Generator Fuel Oil for Consistency with Improved Standard TS
Project stage: Approval
LIC-04-0102, Request for Additional Information (RAI) Regarding License Amendment Request (Lar), Trisodium Phosphate (TSP) Dodecahydrate Volume2004-10-29029 October 2004
Request for Additional Information (RAI) Regarding License Amendment Request (Lar), Trisodium Phosphate (TSP) Dodecahydrate Volume
Project stage: Request
ML0433701172004-11-0808 November 2004
TS Pages for Amendment No. 230 Relocating Requirements of TS 3.3(1)a and Other Components Subject to ASME XI Boiler & Pressure Vessel Code Inspection and Testing Surveillance and TS 3.4 to Update UFSAR
Project stage: Other
ML0432705302004-11-0808 November 2004
Issuance of License Amendment No. 230 Relocating Requirements of TS 3.3(1)a and Other Components Subject to ASME XI Boiler & Pressure Vessel Code Inspection and Testing Surveillance and TS 3.4 to Update UFSAR
Project stage: Approval
LIC-04-0133, Response to NRC RAI on Trisodium Phosphate (TSP) License Amendment Request2004-12-16016 December 2004
Response to NRC RAI on Trisodium Phosphate (TSP) License Amendment Request
Project stage: Response to RAI
ML0505300112005-02-18018 February 2005
Tech Spec Page for Amendment 231 Elimination of Requirements to Provide Monthly Operating/Annual Occupational Radiation Exposure Reports
Project stage: Other
ML0505500612005-02-18018 February 2005
Issuance of License Amendment 231 Elimination of Requirements to Provide Monthly Operating/Annual Occupational Radiation Exposure Reports
Project stage: Approval
ML0506004282005-03-0101 March 2005
Amendment, Revision of TS Section 2.3(4) & TS Section 3.6(2)d.(i)
Project stage: Other
ML0506102222005-03-0101 March 2005
Technical Specifications, Revision of TS Section 2.3(4) & TS Section 3.6(2)d.(i)
Project stage: Other
ML0507500592005-03-11011 March 2005
Tech Spec Pages for Amendment 233 Revising TS 5.9.5 to Be Consistent with Specification 5.6.5 of NUREG-1432
Project stage: Other
ML0507505342005-03-11011 March 2005
Issuance of License Amendment 233 Revising TS 5.9.5 to Be Consistent with Specification 5.6.5 of NUREG-1432
Project stage: Approval
LIC-04-0006, Closure of NRC Tack Issues for Fort Calhoun Station Unit No. 12005-07-0101 July 2005
Closure of NRC Tack Issues for Fort Calhoun Station Unit No. 1
Project stage: Other
2004-02-13
[Table View] |
Text
TECHNICAL SPECIFICATIONS 5.0 ADMINISTRATIVE CONTROLS 5.9 Reporting Requirements (Continued) 5.9.4 Unique Reporting Requirements
- a. Annual Radioactive Effluent Release Report The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous calendar year of operation shall be submitted before May I of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be
- 1) consistent with the objectives outlined in the ODCM and PCP, and 2) in conformance with 10 CFR 50.36a. and Section IV.B.1 of Appendix I to 10 CFR 50.
- b. Annual Radiological Environmental Operating Report The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May I of each year.
The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (I) the ODCM and (2)Section IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR 50.
- c. Not Used 5.9.5 CORE OPERATING LIMITS REPORT (COLR)
- a. Core Operating Limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:
1.3(4) Thermal Margin/Low Pressure Trip 1.3(8) Axial Power Distribution 2.2.7 Borated Water Sources - Shutdown 2.2.8 Borated Water Sources - Operating 2.10.2 Reactivity Control Systems and Core Physics Parameters Limits 2.10.4 Power Distribution Limits
- b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
5.0 - Page 8 Amendment No. 9,24,35,38,46,75,86, 99,1 10,113,119,133,141,144,117, 152,157,160,161,178,185,196, S2O 22, 233
TECHNICAL SPECIFICATIONS 5.0 ADMINISTRATIVE CONTROLS 5.9 Reporting Requirements (Continued)
- 1. OPPD-NA-8301, "Reload Core Analysis Methodology Overview" approved version as specified in the COLR.
- 2. OPPD-NA-8302, "Neufronics Design Methods and Verification", approved version as specified in the COLR.
- 3. OPPD-NA-8303, "Transient and Accident Methods and Verification", approved version as specified in the COLR.
- 4. WCAP-12610-P-A, "VANTAGE + Fuel Assembly Report," April 1995 (Westinghouse Proprietary) as approved in the Safety Evaluation by the Office of Nuclear Reactor Regulation Related to Amendment No. 178 to Facility Operating License No. DPR-40, Omaha Public Power District, Fort Calhoun Station Unit No. 1, Docket No. 50-285, dated October 25, 1996.
- 5. XN-75-32(P)(A) Supplements 1,2, 3, & 4, "Computational Procedure for Evaluating Fuel Rod Bowing," approved version as specified in the COLR.
- 6. XN-NF-82-06(P)(A) and Supplements 2,4, and 5, "Qualification of Exxon Nuclear Fuel for Extended Bumup," approved version as specified in the COLR.
- 7. XN-NF-85-92(P)(A), "Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results," approved version as specified in the COLR.
- 8. ANF-88-133(P)(A) and Supplement 1, "Qualification of Advanced Nuclear Fuels PWR Design Methodology for Rod Burnups of 62 GWd/MTU," approved version as specified in the COLR.
- 9. EMF-92-116(P)(A), "Generic Mechanical Design Criteria for PWR Fuel Designs," approved version as specified in the COLR.
- c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulics limits, Emergency Core Cooling System (ECCS) limits, nuclear limits such as shutdown margin (SDM), transient analysis limits, and accident analysis limits) of the safety analysis are met.
- d. The COLR, including any mid-cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.
5.0 - Page 9 Amendment No.
141,144,157,178,196,202, 233
TECHNICAL SPECIFICATIONS 5.0 ADMINISTRATIVE CONTROLS Not Used Order 07121480 5.0 - Page 10 Amendment No. 59,75,86,93,99,105, 152,155,176,181,196, 202, 20) 233
