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| | number = ML062690432 | | | number = ML062690432 |
| | issue date = 09/28/2006 | | | issue date = 09/28/2006 |
| | title = Fort Calhoun Station - Staff'S Review of Steam Generator Tube Integrity Technical Specification Amendment | | | title = Staff'S Review of Steam Generator Tube Integrity Technical Specification Amendment |
| | author name = Kobetz T J | | | author name = Kobetz T |
| | author affiliation = NRC/NRR/ADRO/DIRS/ITSB | | | author affiliation = NRC/NRR/ADRO/DIRS/ITSB |
| | addressee name = Terao D | | | addressee name = Terao D |
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| =Text= | | =Text= |
| {{#Wiki_filter:September 28, 2006MEMORANDUM TO:David Terao, ChiefPlant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationFROM:Timothy J. Kobetz, Chief /RA/Technical Specifications BranchDivision of Inspections and Regional Support Office of Nuclear Reactor Regulation | | {{#Wiki_filter: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 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| FORT CALHOUN STATION - STAFF'S REVIEW OF THESTEAM 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 Commission'sapproved 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 andRegional Support (DIRS) has completed its review of the LAR. The staff's review is enclosed. Docket No.: 50-285 | | 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 |
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| ==Enclosure:== | | ==Enclosure:== |
| Staff Safety Evaluation CONTACTS: Trent l. Wertz, ITSB/DIRS 301-415-1568
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| ML062690432OFFICEITSB:DIRSBC:ITSB:DIRSBC:CSGB:DCINAMETLWertzTJKobetzALHiserDATE09/11/200609/25/200609/28/2006 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONRELATED TO AMENDMENT NO. TOFACILITY OPERATING LICENSE NO. DPR-40OMAHA PUBLIC POWER DISTRICTFORT CALHOUN STATION UNIT 1DOCKET NO. 50- 28
| | Staff Safety Evaluation CONTACTS: Trent l. Wertz, ITSB/DIRS 301-415-1568 |
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| ==51.0 INTRODUCTION==
| | 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 |
| 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 applicationas originally noticed, and did not change the staff's 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 surveillanceprogram. 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 NuclearRegulatory Commission (NRC) and published in the Federal Register on March 2, 2005 (70 FR10298). 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.
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| ==2.0 REGULATORY EVALUATION== | | ==1.0 INTRODUCTION== |
| The background, description, and applicability of the proposed changes associated with theSG tube integrity issue and the applicable regulatory requirements were included in the NRCstaff's model safety evaluation (SE) published in the Federal Register on March 2, 2005(70 FR 10298). The "Notice of Availability of Model Application Concerning TechnicalSpecification Improvement To Modify Requirements Regarding Steam Generator TubeIntegrity Using the Consolidated Line Item Improvement Process" was published in the FederalRegister on May 6, 2005 (70 FR 24126), and made the model SE available for licensees toreference.
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| ==3.0 TECHNICAL EVALUATION==
| | 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. |
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| ===3.1 Overview=== | | ==2.0 REGULATORY EVALUATION== |
| In its May 30, 2006, application, and August 30, 2006, supplements, the licensee proposedchanges to the TSs that are modeled after Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-449, "Steam Generator Tube Integrity." Therewere 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 inTS 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 invalidatethe technical evaluation on TSTF-449; rather they resulted in the licensee having to slightlydeviate 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 asteam generator tube rupture assumed the contaminated secondary fluid was only brieflyreleased 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 thesedifferences 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 ofTSTF-449, the NRC staff determined they were acceptable.With respect to the differences in the format of the technical specifications, this resulted in thelicensee 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 licensee's submittal since the licensee did nothave 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 existingtechnical 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 previouslyapproved 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 plugtubes that exceed the repair criteria and plugging is an acceptable method for removing tubesfrom service.The remainder of the application was generally consistent with TSTF-449. As a result, the staffdetermined 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 ofLEAKAGE, (2) a revised TS 2.1.1 "RCS (Reactor Coolant System) Operable Components," andTS 2.1.4, "RCS Operational Leakage Limits," (3) a new TS 2.23, "Steam Generator (SG) TubeIntegrity," (4) a revised TS 3.2, "Equipment and Sampling Tests," (5) a revised TS 3.17, "SteamGenerator Tubes Integrity," (6) a new TS 5.23, "Steam Generator (SG Program)," and (7) arevised Table of Content pages to reflect the proposed changes. 3.2 ConclusionThe proposed TS changes establish a programmatic, largely performance-based regulatoryframework for ensuring SG tube integrity is maintained. The NRC staff finds that it addresseskey 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 structuralmargins 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 thatthe SGs can be operated safely without increase in risk.The revised TSs will contain limited specific details concerning how the SG Program is toachieve the required objective of maintaining tube integrity; the intent being that the licenseewill 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 theestablishment and implementation of the SG Program such as to provide reasonable assurancethat tube integrity will be maintai ned.Failure to meet the performance criteria will be reportable pursuant to the requirements in10 CFR Parts 50.72 and 50.73. The NRC reactor oversight process provides a process bywhich the NRC staff can verify that the licensee has identified any SG Program deficiencies thatmay 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 50.36and establish a TS framework that will provide reasonable assurance that SG tube integrity ismaintained without undue risk to public health and safety.The licensee included in its application the revised TS Bases to be implemented with the TSchange. The NRC staff finds that the TS Bases Control Program is the appropriate process forupdating the affected TS Bases pages and has, therefore, not included the affected Basespages with this amendment.
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| ==4.0 STATE CONSULTATION==
| | 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. |
| In accordance with the Commission's regulations, the [STATE] State official was notified of theproposed issuance of the amendments. The State official had no comments.
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| ==5.0 ENVIRONMENTAL CONSIDERATION== | | ==3.0 TECHNICAL EVALUATION== |
| The amendments change a requirement with respect to installation or use of a facilitycomponent located within the restricted area as defined in 10 CFR Part 20. The NRC staff hasdetermined that the amendments involve no significant increase in the amounts, and nosignificant change in the types, of any effluents that may be released offsite, and that there isno 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
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| ([ ] FR [ ]). Accordingly, the amendment[s] meet the eligibility criteria for categorical exclusionset 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.
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| ==6.0 CONCLUSION==
| | 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). |
| The Commission has concluded, based on the considerations discussed above that (1) there isreasonable assurance that the health and safety of the public will not be endangered byoperation in the proposed manner, (2) such activities will be conducted in compliance with theCommission'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.
| | 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. |
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| ==7.0 REFERENCES== | | ==4.0 STATE CONSULTATION== |
| A complete list of references used to complete this review can be found in the NRC's model SEpublished in the Federal Register on March 2, 2005 (70 FR 10298).Principal Contributor: Trent L. WertzDate: September 11, 2006}} | | |
| | 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== |
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| | 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. |
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| | ==6.0 CONCLUSION== |
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| | 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. |
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| | ==7.0 REFERENCES== |
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| | 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 |
| | }} |
Letter Sequence Approval |
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TAC:MD2188, Steam Generator Tube Integrity (Approved, Closed) |
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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
