Letter Sequence Other |
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TAC:MB5839, 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
February 27, 2003 Mr. R. T. Ridenoure Division Manager - Nuclear Operations Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
P.O. Box 550 Fort Calhoun, NE 68023-0550
SUBJECT:
FORT CALHOUN STATION NO. 1 - CORRECTION TO AMENDMENT NO. 215 (TAC NO. MB5839)
Dear Mr. Ridenoure:
On January 16, 2003, the Commission issued Amendment No. 215 to Facility Operating License No. DPR-40 for the Fort Calhoun Station, Unit No. 1 (FCS). The amendment requested changes to the technical specifications (TS) in response to your application dated October 8, 2002. The amendment revised Surveillance Requirement (SR) 3.0.4, TS 5.19, and added TS 5.20 [Technical Specification (TS) Bases Control Program] and SR 3.0.5 to extend the delay period before entering a Limiting Condition for Operation following a missed surveillance. The delay period is extended from the current limit of "... up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />..." to
"...up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified surveillance interval, whichever is greater."
In addition, SR 3.0.5 was modified to include the following statement: "A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the risk impact shall be managed."
Page 5-17 of the TSs omitted a reference to SR 3.0.5. This reference was included in your October 8, 2002, request and was addressed on page 12 of the NRCs safety evaluation.
Enclosed is the corrected page. Please replace this page in your copy of the TS. We apologize for any inconvenience this may have caused.
Sincerely,
/RA/
Alan B. Wang, Project Manager, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-285
Enclosure:
Page 5-17 of the Technical Specifications cc w/encl: See next page
ML030580351 NRR-106 OFFICE PDIV-2/PM PDIV-2/LA OGC PDIV-2/SC NAME AWang EPeyton AFernandez SDembek DATE 2/3/03 2/3/03 2/24/03 2/25/03 DOCUMENT NAME: G:\\PDIV-2\\Fort Calhoun\\mb5839correction.wpd Ft. Calhoun Station, Unit 1 cc:
Winston & Strawn ATTN: James R. Curtiss, Esq.
1400 L Street, N.W.
Washington, DC 20005-3502 Chairman Washington County Board of Supervisors P.O. Box 466 Blair, NE 68008 Mr. John Kramer, Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 310 Fort Calhoun, NE 68023 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 Ms. Sue Semerera, Section Administrator Nebraska Health and Human Services Systems Division of Public Health Assurance Consumer Services Section 301 Cententiall Mall, South P.O. Box 95007 Lincoln, Nebraska 68509-5007 Mr. David J. Bannister Manager - Fort Calhoun Station Omaha Public Power District Fort Calhoun Station FC-1-1 Plant P.O. Box 550 Fort Calhoun, NE 68023-0550 Mr. John B. Herman Manager - Nuclear Licensing Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
P.O. Box 550 Fort Calhoun, NE 68023-0550 Mr. Richard P. Clemens Division Manager - Nuclear Assessments Omaha Public Power District Fort Calhoun Station P.O. Box 550 Fort Calhoun, Nebraska 68023-0550 Mr. Daniel K. McGhee Bureau of Radiological Health Iowa Department of Public Health 401 SW 7th Street Suite D Des Moines, IA 50309
5.0 ADMINISTRATIVE CONTROLS 5.19 Containment Leakage Rate Testing Program (Continued)
The maximum allowable primary containment leakage rate, La, at Pa, shall be 0.1% of containment air weight per day.
Leakage Rate acceptance criteria are:
a.
Containment leakage rate acceptance criterion is 1.0 La. During unit startup following testing in accordance with this program, the leakage rate acceptance criteria are 0.60 La Maximum Pathway Leakage Rate (MXPLR) for Type B and C tests and 0.75 La for Type A tests.
b.
Personnel Air Lock testing acceptance criteria are:
(1)
Overall Personnel Air Lock leakage is 0.1 La when tested at Pa.
(2)
For each PAL door, seal leakage rate is 0.01 La when pressurized to
5.0 psig.
c.
Containment Purge Valve (PCV-742A/B/C/D) testing acceptance criterion is:
For each Containment Purge Valve, leakage rate is < 18.000 SCCM when tested at Pa.
d.
If at any time when containment integrity is required and the total Type B and C measured leakage rate exceeds 0.60 La Minimum Pathway Leakage Rate (MNLPR), repairs shall be initiated immediately. If repairs and retesting fail to demonstrate conformance to this acceptance criteria within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, then containment shall be declared inoperable.
The provisions of Specification 3.0.1 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.
The provisions of Specifications 3.0.4 and 3.0.5 are applicable to the Containment l
Leakage Rate Testing Program.
5.20 Technical Specifications (TS) Bases Control Program l
This program provides a means for processing changes to the Bases of these l
Technical Specifications.
l a.
Changes to the Bases of the TS shall be made under appropriate administrative l
controls and reviews.
l b.
Licensees may make changes to Bases without prior NRC approval provided l
the changes do not require either of the following:
l 5-17 Amendment No. 185, 202,215
