Letter Sequence Approval |
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TAC:MD2188, Steam Generator Tube Integrity (Approved, Closed) |
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Category:Memoranda
MONTHYEARML24107B1272024-04-22022 April 2024 Ft. Calhoun Meeting Summary of March 27, 2024 Meeting with Omaha Public Power District on Submittal of Phase 1 Final Status Surveys ML22333B0922022-12-21021 December 2022 FY22 Nmss/Duwp Operating Experience Report ML21271A5992021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 8, 12, Omaha Public Power District, FCS-SAF-103, FCS Deconstruction Health and Safety Plan CAC2 ML21055A4022021-05-14014 May 2021 Memorandum: Final Environmental Assessment and Finding of No Significant Impact of Initial and Updated Decommissioning Funding Plans for the Cooper, Fort Calhoun and Virgil C. Summer Independent Spent Fuel Storage Installations ML21271A1492021-04-13013 April 2021 License Amendment Request (LAR) 21-01, Chapter 1 9 Haley & Aldrich, Inc. Memorandum to Energysolutions, File No. 0127960-006, Fort Calhoun Nuclear Power Statio~1 ML20056E4872020-02-26026 February 2020 Staff Review of Fort Calhoun Independent Spent Fuel Storage Installation Physical Security Plan, Security Training and Qualification Plan, and Safeguard Contingency Plan, Revision 0 and the Verification of Additional Security Measures (ASM) ML18173A0082018-06-20020 June 2018 Cancelling Numerous Inspection Report Numbers ML18108A1212018-04-11011 April 2018 American Nuclear Insurers - Notification of Change in the Number of Power Reactors in the Secondary Financial Protection (SFP) Program ML17275A2642017-11-21021 November 2017 Safety Evaluation Input on Fort Calhoun Station Request for Approval of Permanently Defueled Emergency Plan and Emergency Action Level Scheme, Docket No. 50-285 ML16057A1232016-02-26026 February 2016 Cy 2015 Baseline Completion ML16007A4942016-01-11011 January 2016 Review of the Updated Final Safety Analysis Report for the Period June 14, 2014 Through December 4, 2015 ML14163A0022014-06-16016 June 2014 Summary of Audit Conducted March 5-9, 2012, Request to Adopt National Fire Protection Association (NFPA) 805, Performance-Based Standard for Fire Protection for LWR Electric Generating Plants ML14129A4452014-05-12012 May 2014 5/13/2014 Notice of Forthcoming Closed Meeting to Discuss Dam Failure Analysis for Cooper Nuclear Station and Fort Calhoun Station, Unit 1 ML14114A7012014-04-24024 April 2014 Task Interface Agreement - Concurrence on Fort Calhoun Tornado Missile Protection Licensing Basis (TIA 2013-07) ML14085A1842014-03-28028 March 2014 Final Fort Calhoun Gothic TIA Response ML14016A2602014-01-28028 January 2014 Fc Final Containment Structural TIA ML13351A4762013-12-16016 December 2013 Recommendation for NRC to Close Confirmatory Action Letter EA-13-020 Supporting the Restart of Fort Calhoun Station and Recommendation to Issue Post-Restart Confirmatory Action Letter ML13346A0822013-12-12012 December 2013 Notice of Forthcoming Closed Meeting to Discuss Dam Failure Analysis for Cooper Nuclear Station and Fort Calhoun Station, Unit 1 ML13312A8522013-11-0808 November 2013 Meeting Notice with Public to Discuss Fort Calhoun Station ML13253A3542013-09-27027 September 2013 Letter to R. Morris Information Exchange Pertaining to Health Issues Related to Crow Butte Resources Uranium Mine and Ft. Calhoun Nuclear Generating Station ML13102A1892013-04-15015 April 2013 4/22/12 Notice of Closed Meeting with Omaha Public Power District to Discuss Flooding Issues Associated with Fort Calhoun, Unit 1 ML13101A2232013-04-11011 April 2013 Meeting Notice with Omaha Public Power District - Potential License Amendment Requests for Fort Calhoun, Unit 1 Related to Flood Protection for Raw Water System, Tornado Missile Protection, Piping/Code Use, and Alternate Seismic Criteria ML13066A8772013-03-0707 March 2013 Issuance of Revised U.S. Nuclear Regulatory Commission Manual Chapter 0350 Panel Fort Calhoun Station Restart Checklist Basis Document ML13046A3212013-02-19019 February 2013 Notice of Closed Meeting with Fort Calhoun to Discuss Safeguards Information, Proprietary, or Other Sensitive Information ML12345A2702012-11-30030 November 2012 Revised 12/12/2012 Notice of Forthcoming Meeting with Omaha Public Power District to Discuss Containment Internal Structures Issues to Support Restart of Fort Calhoun Station, Unit 1 ML12335A1652012-11-30030 November 2012 Forthcoming Meeting with Omaha Public Power District to Discuss Containment Internal Structures Issues to Support Restart of Fort Calhoun Station, Unit 1 ML12318A3192012-11-13013 November 2012 Issuance of U.S. Nuclear Regulatory Commission Manual Chapter 0350 Panel Fort Calhoun Station Restart Checklist Basis Document ML12251A3172012-09-0707 September 2012 Manual Chapter 0350 Oversight Panel Charter - Revision ML12066A0302012-03-29029 March 2012 Closure Memorandum: Issue for Resolution 2011-001 Fort Calhoun - Failure to Maintain External Flooding Procedures. ML12229A1842012-03-0606 March 2012 Backfit Panel Regarding Fort Calhoun Flooding ML1134707162011-12-13013 December 2011 Memo to M.S.Virgilio Notification of Change to Regulatory Oversight of Fort Calhoun Station ML11293A1982011-10-19019 October 2011 Charter for Backfit Panel on Postulated Failure of Upstream Dams Affecting Fort Calhoun Station ML1118811312011-07-0707 July 2011 Docketing of Nonproprietary Information Provided by Omaha Public Power District (OPPD) Personnel Following the June 2, 2011, Regulatory Conference ML13106A1702011-07-0101 July 2011 Proposed Adequate Protection Backfit Exception ML11174A2322011-06-21021 June 2011 for the Record-06-21-2011: NRC Ensures Public Safety Through Rigorous Oversight of Nuclear Power Plant Safety Standards ML1113807322011-05-18018 May 2011 Regulatory Conference with Omaha Public Power ML1113306432011-05-16016 May 2011 Notice of Forthcoming Prelicensing Teleconference on 5/26/11 with Omaha Public Power District Related to Fort Calhoun Station, Unit 1's License Amendment Submittal Related to Transition to Risk-Informed NFPA-805 ML1109103272011-04-0505 April 2011 Verbal Authorization, Request for Relief from Code Case N-722 Visual Examination of the Reactor Vessel Hot-Leg Nozzle-to-Safe-End Dissimilar Metal Welds, 4th 10-Year Inservice Inspection Interval ML1108106952011-03-23023 March 2011 Notice of Forthcoming Pre-Licensing Meeting with Omaha Public Power District to Discuss Its Plans to Submit an Extended Power Uprate for Fort Calhoun Station and Issues Related to Equipment Environmental Qualification ML1104808672011-02-18018 February 2011 03/2/2011 Notice of Forthcoming Closed Pre-Licensing Teleconference with Omaha Public Power District to Discuss Its Plans to Submit an Extended Power Uprate for Fort Calhoun Station and Issues Related to Control Rod Withdrawal at Power ML1035605482010-12-23023 December 2010 Notice of Forthcoming Pre-Licensing Meeting with Omaha Public Power District to Discuss Fort Calhoun Station'S Extended Power Uprate, Spent Fuel Pool Criticality, and Proposed License Amendment Request Modeled After TSTF-493 ML1020701262010-08-30030 August 2010 the Nuclear Regulatory Commission Staff Spot-Check Review of Fort Calhoun Station Unit 1, June 30, 2010 - Finding of No Potential Issues in Bank Statements ML1016205062010-06-14014 June 2010 Notice of Forthcoming Teleconference Meeting with Omaha Public Power District to Discuss NRC Staff Request for Additional Information Dated 2/12/2010 on Generic Letter 2004-02 for Fort Calhoun Station, Unit 1 ML1006010322010-03-0101 March 2010 Cy 2009 Baseline Inspection Completion ML1004302742010-02-12012 February 2010 Notice of Forthcoming Teleconference with Omaha Public Power District to Discuss NRC Staff Request for Additional Information on Generic Letter 2004-02 for Fort Calhoun Station, Unit 1 ML0909607752009-04-0606 April 2009 Notice of End-of-Cycle Meeting with Omaha Public Power District - Fort Calhoun Station to Present and Discuss the Performance Results for the Fort Calhoun Station for the Period of January 1 Though December 31, 2008 ML0901504382009-01-16016 January 2009 Notice of Forthcoming Meeting with Omaha Public Power District, to Discuss Oppd'S Plans to Submit an Extended Power Uprate Request for the Fort Calhoun Station, Unit 1 ML0901603362009-01-16016 January 2009 Notice of Forthcoming Meeting with Omaha Public Power District, to Discuss the Fort Calhoun Station'S Transition to National Fire Protection Association (NFPA) 805 ML0814100052008-06-0303 June 2008 Summary of Conference Call with Omaha Public Power District (OPPD) Regarding OPPD Emergency Relief Request Submitted May 15, 2008 for Fort Calhoun Station (Tac No. MD8722) ML0809404512008-04-18018 April 2008 Summary of 12/6/2006 Meeting with Omaha Public Power District, Regarding Water Management Strategies for Resolution of GSI-191 (Tac No MD5780) 2024-04-22
[Table view] Category:Safety Evaluation
MONTHYEARML24019A1682024-01-31031 January 2024 Safety Evaluation Report for Approval of License Termination Plan ML21271A5992021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 8, 12, Omaha Public Power District, FCS-SAF-103, FCS Deconstruction Health and Safety Plan CAC2 ML20056E4872020-02-26026 February 2020 Staff Review of Fort Calhoun Independent Spent Fuel Storage Installation Physical Security Plan, Security Training and Qualification Plan, and Safeguard Contingency Plan, Revision 0 and the Verification of Additional Security Measures (ASM) ML19297D6742019-12-0909 December 2019 FCS ISFSI Only Tech Specs SER ML18017B0052018-03-30030 March 2018 Review of the Irradiated Fuel Management Plan (CAC No. MF9553; EPID L-2017-LLL-0009) ML18047A6612018-03-28028 March 2018 Issuance of Amendment No. 298, Request to Modify License Condition 3.C to Delete Requirement for Commission-Approved Cyber Security Plan (CAC No. MF9850; EPID L-2017-LLA-0236) ML18010A0872018-03-0606 March 2018 Issuance of Amendment No. 297, Request for Technical Specification Changes to Align to Those Requirements for Decommissioning (CAC No. MF9567; EPID L-2017-LLA-0192) ML17338A1722018-01-19019 January 2018 Issuance of Amendment No. 296, Revise Technical Specifications (TS) to Delete Dry Spent Fuel Cask Loading Limits from TS 3.8.3(6), Figure 2-11, Table 3-4, Table 3-5, and TS 4.3.1.3 (CAC No. MF9831; EPID L-2017-LLA-0235) ML17276B2862017-12-12012 December 2017 Issuance of Amendment No. 295, Revise the Emergency Plan and Emergency Action Level Scheme for the Permanently Defueled Condition (CAC No. MF8951; EPID L-2016-LLA-0036) ML17263B1982017-12-11011 December 2017 Letter and Safety Evaluation, Request for Exemption from 10 CFR 50.47 and 10 CFR 50 Appendix E to Reduce Emergency Planning Requirements for Permanently Defueled Condition (CAC MF9067; EPID L-2016-LLE-0003) ML17289A0602017-11-22022 November 2017 Issuance of Amendment No. 294, Revise Cyber Security Plan Implementation Schedule for Milestone 8 and Associated License Condition (CAC No. MF9559; EPID L-2017-LLA-0184) ML17275A2642017-11-21021 November 2017 Safety Evaluation Input on Fort Calhoun Station Request for Approval of Permanently Defueled Emergency Plan and Emergency Action Level Scheme, Docket No. 50-285 ML17278A6072017-11-17017 November 2017 Issuance of Amendment No. 293, Request to Revise Current Licensing Basis for the Auxiliary Building to Use American Concrete Institute Ultimate Strength Requirements (CAC No. MF8525; EPID L-2016-LLA-0013) ML17165A4652017-07-28028 July 2017 Fort Calhoun Station, Unit 1 - Issuance of Amendment No. 292, Revise Technical Specifications to Align Staffing Requirements to Those Required for Decommissioning (CAC No. MF8437) ML17123A3482017-07-27027 July 2017 Issuance of Amendment No. 291, Revise the Radiological Emergency Response Plan for Permanently Defueled Condition ML17144A2462017-06-21021 June 2017 Approval of Certified Fuel Handler Training and Retraining Program to Facilitate Activities Associated with Decommissioning and Irradiated Fuel Handling Management ML17053A0992017-04-0707 April 2017 Issuance of Amendment No. 290, Request to Delete License Condition 3.D., Fire Protection Program, No Longer Needed for Permanently Shutdown and Defueled Condition ML16141A7392016-05-27027 May 2016 Safety Evaluation, Review of Aging Management Program of Reactor Vessel Internals Based on MRP-227-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines ML16104A0742016-04-15015 April 2016 Relief Request, Request to Use a Portion of a Later Edition of the ASME B&PV Code, Section XI, Fourth 10-Year Inservice Inspection Interval 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 ML16041A3082016-02-19019 February 2016 Relief Requests P-1 - LPSI and CS Pumps; P-2 - Adjusting Hydraulic Parameters Consistent W/Code Case OMN-21; G-1 - Test Frequency Consistent W/Code Case OMN-20, Fifth 10-Year Inservice Testing Interval 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 ML15294A2792015-11-19019 November 2015 Issuance of Amendment No. 284, Request to Revise License Condition Related to Cyber Security Plan Milestone 8 Full Implementation Date ML15232A0032015-08-21021 August 2015 Relief Request RR-14, Relief from ASME Code Case N-729-1 Requirements for Reactor Vessel Head Penetration Nozzle Welds, Fourth 10-Year Inservice Inspection Interval 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 ML14323A5992014-12-0202 December 2014 Relief Request RR-13, Relief from Inservice Testing Requirements to Perform Testing of 4 Valves During the April 2015 Refueling Outage ML14316A1672014-11-19019 November 2014 Relief Request RR-14, Proposed Alternative for Temporary Acceptance of a Pin Hole Leak in Raw Water System 20-Inch Elbow Located in Room 19 of Auxiliary Building 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) ML14003A0032014-01-28028 January 2014 Issuance of Amendment No. 274, Revise Technical Specification 2.16, River Level, and Establish EAL Classification Criteria for External Flooding Events Under Radiological Emergency Response Plan ML13296A5842013-10-25025 October 2013 Issuance of Amendment No. 273, Revise Current Licensing Basis of Pipe Break Criteria for High Energy Line Breaks (Exigent Circumstances) ML13203A0702013-07-26026 July 2013 Issuance of Amendment No. 272 - Revise Current Licensing Basis to Adopt Revised Design Basis/Methodology for Addressing Design-Basis Tornado/Tornado Missile Impact (Exigent Circumstances) ML13141A6082013-06-25025 June 2013 Safety Assessment in Response to Request for Information Pursuant to 10 CFR 50.54(f) - Recommendation 9.3 Communications Assessment ML13070A0422013-03-29029 March 2013 Issuance of Amendment No. 271, Relocate Technical Specification LCO 2.17, Miscellaneous Radioactive Material Sources, and Surveillance Requirement 3.13 to Updated Safety Analysis Report ML13043A6612013-02-28028 February 2013 Issuance of Amendment No. 270 to Revise Technical Specification 2.15 to Establish Limiting Condition for Operation Requirements for Reactor Protective System Actuation Circuits ML13017A4672013-01-31031 January 2013 Approval of Request for Change to the Reactor Vessel Surveillance Capsule Removal Schedule ML12333A1192012-12-31031 December 2012 Issuance of Amendment No. 269, Incorporate New Radial Peaking Factor Definition and Clarify Limiting Condition for Operation (LCO) 2.10.2(6) ML1126204022011-09-30030 September 2011 Issuance of Amendment No. 268, Revise Updated Safety Analysis Report to Relocate Acoustic Position and Tail Pipe Temperature Indication Surveillance Requirements from Technical Specifications ML1118615712011-08-31031 August 2011 Issuance of Amendment No. 267, Revise Technical Specification (TS) 2.15 and TS 3.1 Related to Operability of Secondary Control Element Assembly Position Indication System Channels; Correction to TS 2.10.2(7)c ML1122702902011-08-18018 August 2011 Relief Request RR-12 from Code Case N-722, Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 600/82/182 Materials, Fourth 10-Year Inservice Inspection Interval ML1118010942011-07-27027 July 2011 Issuance of Amendment No. 266, Revise License Condition and Approve Cyber Security Plan and Associated Implementation Schedule ML1022101332010-08-20020 August 2010 Request for Use of Alternative to Depth-Sizing Qualification for Volumetric Examinations of Reactor Pressure Vessel Welds for 4th 10-year Inservice Inspection Interval ML1009100772010-05-14014 May 2010 License Amendment, 264, Revision of Tech Spec Sections 2.0.1 and 2.7 for Inoperable System, Subsystem, or Component Due to Inoperable Power Source and Deletion of Diesel Generator Surveillance Requirement 3.7(1)e 2024-01-31
[Table view] |
Text
September 28, 2006 MEMORANDUM TO: David Terao, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Timothy J. Kobetz, Chief /RA/
Technical Specifications Branch Division of Inspections and Regional Support Office of Nuclear Reactor Regulation
SUBJECT:
FORT CALHOUN STATION - STAFFS REVIEW OF THE STEAM GENERATOR TUBE INTEGRITY TECHNICAL SPECIFICATION AMENDMENT (TAC NO. MD2188)
By letter dated May 30, 2006 (ML061510203) as supplemented by two letters dated August 30, 2006 (ML062430402 and ML062480074), Omaha Public Power District (the licensee) submitted a license amendment request (LAR) regarding Fort Calhoun Station steam generator (SG) tube integrity technical specifications (TSs). The proposed amendment would revise the existing SG tube surveillance program to be consistent with the U.S. Nuclear Regulatory Commissions approved Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-449, Steam Generator Tube Integrity, Revision 4. TSTF-449 is part of the consolidated line item improvement process (CLIIP).
The staff of the Technical Specifications Branch (ITSB) of the Division of Inspections and Regional Support (DIRS) has completed its review of the LAR. The staffs review is enclosed.
Docket No.: 50-285
Enclosure:
Staff Safety Evaluation CONTACTS: Trent l. Wertz, ITSB/DIRS 301-415-1568
ML062690432 OFFICE ITSB:DIRS BC:ITSB:DIRS BC:CSGB:DCI NAME TLWertz TJKobetz ALHiser DATE 09/11/2006 09/25/2006 09/28/2006 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. TO FACILITY OPERATING LICENSE NO. DPR-40 OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION UNIT 1 DOCKET NO. 50- 285
1.0 INTRODUCTION
By letter dated May 30, 2006 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML061510203), as supplemented by two letters dated August 30, 2006 (ADAMS Accession No. ML062430402 and ML062480074), Omaho Public Power District (OPPD, (the licensee) requested changes to the Technical Specifications (TSs) for the Fort Calhoun Station Unit No. 1 (Fort Calhoun). The supplements dated August 30, 2006, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staffs original proposed no significant hazards consideration determination as published in the Federal Register on [DATE] ([ ] FR [ ]).]
The proposed changes would revise the existing steam generator (SG) tube surveillance program. The changes are modeled after TS Task Force (TSTF) traveler TSTF-449, Revision 4, Steam Generator Tube Integrity, and the model safety evaluation prepared by the Nuclear Regulatory Commission (NRC) and published in the Federal Register on March 2, 2005 (70 FR 10298). In this regard, the scope of the application includes changes to the definition of leakage, changes to the primary-to-secondary leakage requirements, changes to the SG tube surveillance program (SG tube integrity), changes to the SG reporting requirements, and associated changes to the TS Bases.
2.0 REGULATORY EVALUATION
The background, description, and applicability of the proposed changes associated with the SG tube integrity issue and the applicable regulatory requirements were included in the NRC staffs model safety evaluation (SE) published in the Federal Register on March 2, 2005 (70 FR 10298). The Notice of Availability of Model Application Concerning Technical Specification Improvement To Modify Requirements Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process was published in the Federal Register on May 6, 2005 (70 FR 24126), and made the model SE available for licensees to reference.
3.0 TECHNICAL EVALUATION
3.1 Overview In its May 30, 2006, application, and August 30, 2006, supplements, the licensee proposed changes to the TSs that are modeled after Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-449, Steam Generator Tube Integrity. There were minor differences between TSTF-449 and the licensee's application. These included differences in the facility licensing basis (than that discussed in TSTF-449) and differences in TS numbering and format, since the licensee has a different TS format (than that assumed in TSTF-449).
With respect to the differences in the facility licensing basis, the differences did not invalidate the technical evaluation on TSTF-449; rather they resulted in the licensee having to slightly deviate from some of the modifications discussed in TSTF-449. For example, in the Bases section for Steam Generator Tube Integrity, TSTF-449 indicated that the accident analysis for a steam generator tube rupture assumed the contaminated secondary fluid was only briefly released to the atmosphere via safety valves and the majority is discharged to the main condenser. Since the licensee has a different licensing basis than the one described in the standard technical specifications (i.e., TSTF-449), they modified the TSTF-449 wording to accommodate their existing licensing Bases. Another example is that TSTF-449 has specific definitions for the modes of operation. For example, in TSTF-449, Mode 5 is referred to as cold shutdown and the average reactor coolant temperature during this mode must be less than 200-degrees Fahrenheit. For Fort Calhoun, the comparable mode is termed cold shutdown condition, is referred to as Operating Mode 4" and the cold-leg temperature must be less than 210-degrees Fahrenheit. These differences in Modes required the licensee to deviate from the changes discussed in TSTF-449 to remain consistent with the intent of TSTF-449. Since these differences were minor in nature, they were consistent with the plant's licensing basis (e.g., in the level of detail incorporated into the TS Bases), and they were consistent with the intent of TSTF-449, the NRC staff determined they were acceptable.
With respect to the differences in the format of the technical specifications, this resulted in the licensee having to relocate many of the TSTF-449 requirements into the appropriate sections of their technical specifications. In addition, there were some changes in the Bases Section of TSTF-449 that were not incorporated into the licensees submittal since the licensee did not have the corresponding paragraphs in their version of the Bases. For example, the licensee did not have several references to their steam generator tube surveillance program in their existing technical specifications so they did not need to delete these changes in order to adopt TSTF-449. Since these differences were administrative in nature and did not affect the technical adequacy of the submittal, the NRC staff determined they were acceptable.
In addition to these minor changes, the licensee proposed to delete reference to a previously approved sleeving (i.e., repair) method since this repair method would no longer be applicable to their replacement steam generators (which were being installed in 2006). Removal of the sleeving method as a repair method is acceptable since the licensee will be required to plug tubes that exceed the repair criteria and plugging is an acceptable method for removing tubes from service.
The remainder of the application was generally consistent with TSTF-449. As a result, the staff determined that the model SE is applicable to this review and finds the proposed changes acceptable.
Consistent with TSTF-449, the proposed TS changes include: (1) a revised definition of LEAKAGE, (2) a revised TS 2.1.1 RCS (Reactor Coolant System) Operable Components, and TS 2.1.4, "RCS Operational Leakage Limits," (3) a new TS 2.23, "Steam Generator (SG) Tube Integrity," (4) a revised TS 3.2, "Equipment and Sampling Tests," (5) a revised TS 3.17, "Steam Generator Tubes Integrity," (6) a new TS 5.23, Steam Generator (SG Program), and (7) a revised Table of Content pages to reflect the proposed changes.
3.2 Conclusion The proposed TS changes establish a programmatic, largely performance-based regulatory framework for ensuring SG tube integrity is maintained. The NRC staff finds that it addresses key shortcomings of the current framework by ensuring that SG programs are focused on accomplishing the overall objective of maintaining tube integrity. It incorporates performance criteria for evaluating tube integrity that the NRC staff finds consistent with the structural margins and the degree of leak tightness assumed in the current plant licensing basis. The NRC staff finds that maintaining these performance criteria provides reasonable assurance that the SGs can be operated safely without increase in risk.
The revised TSs will contain limited specific details concerning how the SG Program is to achieve the required objective of maintaining tube integrity; the intent being that the licensee will have the flexibility to determine the specific strategy for meeting this objective. However, the NRC staff finds that the revised TSs include sufficient regulatory constraints on the establishment and implementation of the SG Program such as to provide reasonable assurance that tube integrity will be maintained.
Failure to meet the performance criteria will be reportable pursuant to the requirements in 10 CFR Parts 50.72 and 50.73. The NRC reactor oversight process provides a process by which the NRC staff can verify that the licensee has identified any SG Program deficiencies that may have contributed to such an occurrence and that appropriate corrective actions have been implemented.
In conclusion, the NRC staff finds that the TS changes proposed by the licensee in its May 30, 2006, application August 30, 2006 supplement conform to the requirements of 10 CFR 50.36 and establish a TS framework that will provide reasonable assurance that SG tube integrity is maintained without undue risk to public health and safety.
The licensee included in its application the revised TS Bases to be implemented with the TS change. The NRC staff finds that the TS Bases Control Program is the appropriate process for updating the affected TS Bases pages and has, therefore, not included the affected Bases pages with this amendment.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the [STATE] State official was notified of the proposed issuance of the amendments. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding
([ ] FR [ ]). Accordingly, the amendment[s] meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
7.0 REFERENCES
A complete list of references used to complete this review can be found in the NRCs model SE published in the Federal Register on March 2, 2005 (70 FR 10298).
Principal Contributor: Trent L. Wertz Date: September 11, 2006