Letter Sequence Other |
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TAC:MB6472, Missed Surveillance Requirements, Incorporate CEOG Topical Report to Eliminate Pressure Sensor Response Time Testing (Approved, Closed) |
Results
Other: LIC-03-0110, Unit No.1 TS Updated for NRC Comments on Pending Amendment Request on Pressure-Temperature Limits Report, ML021280278, ML022940186, ML030220153, ML030580351, ML030780605, ML031210545, ML031290602, ML031400506, ML031410096, ML031410107, ML031410212, ML031960625, ML032300003, ML032300305, ML032310200, ML032310213, ML032530228, ML032960189, ML040210769
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MONTHYEARML0205002282002-02-25025 February 2002
Issuance of Order for Interim Safeguards and Compensatory Security Measures
Project stage: Approval
LIC-02-0025, Response to Commission Order to Modify License for Interim Safeguards and Security Measures2002-03-15015 March 2002
Response to Commission Order to Modify License for Interim Safeguards and Security Measures
Project stage: Request
LIC-02-0064, Withdrawal of Request for Hearing on Interim Safeguards and Security Compensatory Measures Order2002-05-17017 May 2002
Withdrawal of Request for Hearing on Interim Safeguards and Security Compensatory Measures Order
Project stage: Request
ML0212802782002-05-22022 May 2002
Reply to Response to Order for Interim Safeguards and Security Compensatory Measures
Project stage: Other
LIC-02-0107, August 2002 Monthly Operating Report for Omaha Public Power District2002-09-0909 September 2002
August 2002 Monthly Operating Report for Omaha Public Power District
Project stage: Request
LIC-02-0090, License Amendment Request, Relocation of Nuclear Detector Cooling Technical Specification 2.13 to Updated Safety Analysis Report2002-10-0808 October 2002
License Amendment Request, Relocation of Nuclear Detector Cooling Technical Specification 2.13 to Updated Safety Analysis Report
Project stage: Request
ML0229401862002-10-25025 October 2002
Biweekly Notice Memo, Notice of Consideration, Testing Prestressed Concrete Containment Tendons
Project stage: Other
ML0229504532003-01-16016 January 2003
Issuance of License Amendment No. 215, Missed Surveillances & Adoption of Technical Specification Bases Control Program
Project stage: Approval
ML0302201532003-01-16016 January 2003
Technical Specification Pages for Amendment 215 Missed Surveillances and Adoption of a Technical Specification Bases Control Program
Project stage: Other
LIC-02-0105, License Amendment Request, Various Administrative and Editorial Changes2003-01-27027 January 2003
License Amendment Request, Various Administrative and Editorial Changes
Project stage: Request
ML0306307272003-02-26026 February 2003
Issuance of Amendment No. 216, Relocating TS 3.5(5), Requirements for Testing Prestressed Concrete Containment Tendons to the Updated Safety Analysis Report
Project stage: Approval
ML0305902712003-02-26026 February 2003
Technical Specifications, Relocation of TS 3.5(5), Requirements for Testing Prestressed Concrete Containment Tendons to the Updated Safety Analysis Report
Project stage: Acceptance Review
ML0305803512003-02-27027 February 2003
Correction to Amendment No. 215 to Fort Calhoun, Station No. 1. Page 5-17 of Technical Specifications Omitted Reference to SR 3.0.5. Corrected TS Page Encl
Project stage: Other
ML0307806052003-03-18018 March 2003
Pressure-Temperature Limit Report Submittal
Project stage: Other
ML0308402732003-03-24024 March 2003
RAI, Related to Integrated Leak Rate Test Surveillance Interval
Project stage: RAI
LIC-03-0042, March 2003 Monthly Operating Report for Fort Calhoun Station, Unit 12003-04-10010 April 2003
March 2003 Monthly Operating Report for Fort Calhoun Station, Unit 1
Project stage: Request
LIC-03-0052, Response to Request for Additional for Information, Pressure-Temperature Limits Report Amendment Request2003-04-10010 April 2003
Response to Request for Additional for Information, Pressure-Temperature Limits Report Amendment Request
Project stage: Request
LIC-03-0055, Response to Request for Additional Information Integrated Leak Rate Testing Surveillance Interval Amendment Request2003-04-11011 April 2003
Response to Request for Additional Information Integrated Leak Rate Testing Surveillance Interval Amendment Request
Project stage: Response to RAI
ML0312105452003-04-29029 April 2003
Tech Spec Pages for Amendment No. 217 Modifying TS 2.3.a, to Extend the Allowed Outage Time for a Single Low Pressure Safety Injection Pump from the Existing 24 Hours to 7 Days
Project stage: Other
ML0312004872003-04-29029 April 2003
Issuance of Amendment No. 217 Modifying TS 2.3.a, to Extend the Allowed Outage Time for a Single Low Pressure Safety Injection Pump from the Existing 24 Hours to 7 Days
Project stage: Approval
ML0312906022003-05-0808 May 2003
Tech Spec Pages for Amendment No. 218, Administrative and Editorial Changes to FCS TS 1.3 Basis (1); 2.7 (1)a; 2.7 (1)b; 2.7 (1)d; 2.7 (1)i; 2.7 Basis; 3.0.2; Table 3-5, Item 11; and 3.5 (3)ii
Project stage: Other
ML0312900812003-05-0808 May 2003
Issuance of Amendment No. 218, Administrative and Editorial Changes to FCS TS 1.3 Basis (1); 2.7 (1)a; 2.7 (1)b; 2.7 (1)d; 2.7 (1)i; 2.7 Basis; 3.0.2; Table 3-5, Item 11; and 3.5 (3)ii
Project stage: Approval
ML0314005062003-05-20020 May 2003
Ltr RELAP5/MOD3.3 Prediction and Model Simulation
Project stage: Other
ML0314100962003-05-20020 May 2003
Description/Model Simulation (Technical Paper - 5 Pages), Fort Calhoun, S107101
Project stage: Other
ML0314101072003-05-20020 May 2003
Listing (Report, Technical - 3 Pages), Fort Calhoun, S107102
Project stage: Other
ML0314102122003-05-20020 May 2003
Thesis (Miscellaneous Report - 134 Pages), Fort Calhoun, S107100
Project stage: Other
ML0314103762003-05-21021 May 2003
Request for Additional Information Pressure-Temperature Limit Report Submittal (Tac. MB6468)
Project stage: RAI
LIC-03-0079, Supplemental Response to Request for Additional Information, Integrated Leak Rate Testing Surveillance Interval Amendment Request2003-05-21021 May 2003
Supplemental Response to Request for Additional Information, Integrated Leak Rate Testing Surveillance Interval Amendment Request
Project stage: Supplement
LIC-03-0081, Response to Request for Additional Information, Pressure - Temperature Limits Report Amendment Request; Low Temperature Over Pressure2003-06-0404 June 2003
Response to Request for Additional Information, Pressure - Temperature Limits Report Amendment Request; Low Temperature Over Pressure
Project stage: Response to RAI
ML0316800102003-06-17017 June 2003
Request for Additional Information, Use of the Gothic (Version 7.0) Computer Program
Project stage: RAI
ML0319606252003-07-11011 July 2003
Correction to Amd. 218 for the Fort Calhoun Station, Unit No. 1 (Tac. MB7498)
Project stage: Other
ML0320202182003-07-18018 July 2003
Ltr Environmental Assessment Relating to Exemption from the Requirements of Appendix G to 10 CFR Part 50
Project stage: Approval
ML0320902422003-07-25025 July 2003
Unit 1, License Amendment 219 Modifying Technical Specification 2.1.6
Project stage: Approval
ML0321004542003-07-25025 July 2003
Unit 1, Tech Spec Pages for License Amendment 219 Modifying Technical Specification 2.1.6
Project stage: Approval
LIC-03-0110, Unit No.1 TS Updated for NRC Comments on Pending Amendment Request on Pressure-Temperature Limits Report2003-08-0505 August 2003
Unit No.1 TS Updated for NRC Comments on Pending Amendment Request on Pressure-Temperature Limits Report
Project stage: Other
ML0323000032003-08-15015 August 2003
License Amendment No. 220, Grants One-Time Five-Year Extension to Current Ten-Year Test Interval for Containment Integrated Leak Rate Testing
Project stage: Other
ML0323102002003-08-15015 August 2003
Tech Spec Pages for Amendment No. 221, Use of a Pressure Temperature Limits Report (Ptlr), Change the Minimum Boltup Temperature, Revise the Low Temperature Overpressure Protection (LTOP) Methodology and Analysis
Project stage: Other
ML0323102132003-08-15015 August 2003
Tech Spec Page to License Amendment No. 220, Grants One-Time Five-Year Extension to Current Ten-Year Test Interval for Containment Integrated Leak Rate Testing
Project stage: Other
ML0323003052003-08-15015 August 2003
License Amendment No. 221, Use of a Pressure Temperature Limits Report (Ptlr), Change the Minimum Boltup Temperature, Revise the Low Temperature Overpressure Protection (LTOP) Methodology and Analysis
Project stage: Other
ML0325302282003-09-0404 September 2003
Ft.Calhoun, Closeout Letter - Response to Order for Compensatory Measures Related to Access Authorization
Project stage: Other
ML0329601892003-10-23023 October 2003
Reply to Response to Order for Fitness-For-Duty Enhancements for Nuclear Security Force Personnel
Project stage: Other
ML0331002902003-11-0505 November 2003
Issuance of Amendment 222, Authorizing Revisions to the Updated Safety Analysis Report to Incorporate the NRC Approval of the GOTHIC 7.0 Computer Program for Performing Containment Analysis, (Tac. MB7496)
Project stage: Approval
ML0402107692004-01-0909 January 2004
Closure of NRC TAC Issues
Project stage: Other
2003-03-24
[Table View] |
Text
October 25, 2002 MEMORANDUM TO: Biweekly Notice Coordinator FROM:
Alan B. Wang, Project Manager, Section 2
/RA/
Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation
SUBJECT:
REQUEST FOR PUBLICATION IN BIWEEKLY FR NOTICE -
NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE, PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION, AND OPPORTUNITY FOR HEARING (TAC NO. MB6472)
Omaha Public Power District, Docket No. 50-285, Fort Calhoun Station, Unit No. 1, Washington County, Nebraska Date of amendment request: October 8, 2002 Description of amendment request: The proposed amendment will relocate the requirements of Technical Specification (TS) 3.5(5), "Surveillance for Prestressing System,"
for testing prestressed concrete containment tendons to the Fort Calhoun Station (FCS)
Updated Safety Analysis Report (USAR). This proposed amendment will also add a TS requirement (TS 5.21) for a containment tendon testing program consistent with that presented in Section 5.5 of NUREG-1432, "Improved Standard Technical Specification (ITS) for Combustion Engineering Plants."
Basis for proposed no significant hazards consideration determination: As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below:
1.
The proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
Biweekly Notice Coordinator The proposed change relocates requirements for testing Prestressed Concrete Containment Tendons that do not meet the criteria for inclusion in the TS set forth in 10 CFR 50.36(c)(2)(ii). The requirements for testing Prestressed Concrete Containment Tendons are being relocated from TS to the USAR, which will be maintained pursuant to 10 CFR 50.59, thereby reducing the level of regulatory control. The level of regulatory control has no impact on the probability or consequences of an accident previously evaluated.
Therefore, the change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
2.
The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed change relocates requirements for testing Prestressed Concrete Containment Tendons that do not meet the criteria for inclusion in TS set forth in 10 CFR 50.36(c)(2)(ii). The change does not involve a physical alteration of the plant (no new or different type of equipment will be installed) or make changes in the methods governing normal plant operation. The change will not impose different requirements, and adequate control of information will be maintained. This change will not alter assumptions made in the safety analysis and licensing basis. Therefore, the change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
3.
The proposed change does not involve a significant reduction in a margin of safety.
The proposed change relocates requirements for testing Prestressed Concrete Containment Tendons that do not meet the criteria for inclusion in TS set forth in 10 CFR 50.36(c)(2)(ii). The change will not reduce a margin of safety since the location of a requirement has no impact on any safety analysis assumptions. In addition, the relocated requirements for testing Prestressed Concrete Containment Tendons remain the same as the existing TS. Since any future changes to these requirements or the surveillance procedures will be evaluated per the requirements of 10 CFR 50.59, there will be no reduction in a margin of safety.
The NRC staff has reviewed the licensees analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration.
Biweekly Notice Coordinator Attorney for licensee: James R. Curtiss, Esq., Winston & Strawn, 1400 L Street, N.W.,
Washington, DC 20005-3502 NRC Section Chief: Stephen Dembek
Biweekly Notice Coordinator Attorney for licensee: James R. Curtiss, Esq., Winston & Strawn, 1400 L Street, N.W.,
Washington, DC 20005-3502 NRC Section Chief: Stephen Dembek DISTRIBUTION:
NON-PUBLIC PDIV-2 Reading RidsNrrDlpmLpdiv (WRuland)
SDembek RidsNrrPMAWang RidsNrrLAEPeyton ACCESSION NO.: ML022940186 OFFICE PDIV-2/PM PDIV-2/LA PDIV-2/SC NAME AWang:rkb EPeyton SDembek DATE 10/23/02 10/23/02 10/24/02 OFFICIAL RECORD COPY
