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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212J1891999-10-0101 October 1999 Safety Evaluation Supporting Exemption from 10CFR54.17(c)re Schedule to Apply for Renewed Operating Licenses ML20212G2671999-09-22022 September 1999 Safety Evaluation Supporting Amends 187 & 168 to Licenses NPF-9 & NPF-17,respectively ML20212G1211999-09-22022 September 1999 Safety Evaluation Supporting Amends 188 & 169 to Licenses NPF-9 & NPF-17,respectively ML20212G2511999-09-22022 September 1999 Safety Evaluation Supporting Amends 180 & 172 to Licenses NPF-35 & NPF-52,respectively ML20212D1911999-09-20020 September 1999 SER Accepting Exemption from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Closed System Isolation Valves for McGuire Nuclear Station,Units 1 & 2 ML20211P1371999-09-0808 September 1999 Safety Evaluation Supporting Amend 186 to License NPF-9 ML20211G5261999-08-24024 August 1999 SER Accepting Approval of Second 10-year Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1 ML20211A9791999-08-20020 August 1999 Safety Evaluation Granting Licensee Request for Approval of Proposed Relief from Volumetric Exam Requirements of ASME B&PV Code,Section Xi,For Plant,Unit 2 ML20210U8341999-08-13013 August 1999 Safety Evaluation Supporting Amends 179 & 171 to Licenses NPF-35 & NPF-52,respectively ML20209E4361999-07-0909 July 1999 SER Agreeing with Licensee General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196K6631999-07-0707 July 1999 Safety Evaluation Supporting Licensee 990520 Position Re Inoperable Snubbers ML20206P5201999-05-14014 May 1999 Safety Evaluation Accepting GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20206N3511999-05-11011 May 1999 Safety Evaluation Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Movs ML20205S5551999-04-21021 April 1999 Safety Evaluation Accepting Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20205N3651999-04-12012 April 1999 Safety Evaluation Accepting IPE of External Events Submittal ML20205N2381999-04-0909 April 1999 Safety Evaluation Supporting Amends 178 & 170 to Licenses NPF-35 & NPF-52,respectively ML20205B3101999-03-26026 March 1999 Safety Evaluation Supporting Amends 176 & 168 to Licenses NPF-35 & NPF-52,respectively ML20206R8381999-01-14014 January 1999 Safety Evaluation Supporting Amends 174 & 166 to Licenses NPF-35 & NPF-52,respectively ML20198A4481998-12-11011 December 1998 Safety Evaluation Concluding That for Relief Request 97-004, Parts 1 & 2,ASME Code Exam Requirements Are Impractical. Request for Relief & Alternative Imposed,Granted ML20196J8351998-12-0808 December 1998 Safety Evaluation Granting Relief Request Re Relief Valves in Diesel Generator Fuel Oil Sys ML20196C0251998-11-27027 November 1998 SER Accepting Clarification on Calibration Tolerances on Trip Setpoints for Catawba Nuclear Station ML20196A6881998-11-25025 November 1998 Safety Evaluation Granting Relief Request 98-02 Re Limited Exam for Three Welds ML20154B7991998-09-28028 September 1998 Safety Evaluation Supporting Amends 183 & 165 to Licenses NPF-09 & NPF-17,respectively ML20238F6181998-08-28028 August 1998 Safety Evaluation Supporting Amends 170 & 162 to Licenses NPF-35 & NPF-52,respectively ML20237E0691998-08-25025 August 1998 Safety Evaluation Supporting Amends 169 & 161 to Licenses NPF-35 & NPF-52,respectively ML20237E1421998-08-25025 August 1998 Safety Evaluation Supporting Amends 168 & 160 to Licenses NPF-35 & NPF-52,respectively ML20236X3611998-07-30030 July 1998 Safety Evaluation Supporting Amends 179 & 161 to Licenses NPF-9 & NPF-17,respectively ML20236M5951998-07-0909 July 1998 Safety Evaluation Supporting Amends 167 & 159 to Licenses NPF-35 & NPF-52,respectively ML20236K3911998-07-0606 July 1998 Safety Evaluation Accepting Relocation of TS Administrative Control Requirement to Licensee QA Program ML20249B0471998-06-17017 June 1998 Safety Evaluation Supporting Amends 166 & 158 to Licenses NPF-35 & NPF-52,respectively ML20249B6281998-06-12012 June 1998 Safety Evaluation Accepting 980303 Request to Review & Approve Proposed Change to Plant,Units 1 & 2 TS Re Relocation of Meteorological Tower ML20248B0441998-05-27027 May 1998 Safety Evaluation Authorizing Proposed Alternative Use of Current TS Section 3/4.7.8 Requirements for Snubber Visual Exam & Functional Testing,Based on Finding That Proposed Alternative Proposes Acceptable Level of Quality & Safety ML20247M0861998-05-21021 May 1998 SER Accepting 1997 Rev to Catawba UFSAR Submitted on 970925. Rev Added Analysis for Postulated Accident Involving Dropping of Sf Pool Weir Gate Onto Sf Assemblies ML20217K6961998-04-27027 April 1998 Safety Evaluation Supporting Amends 165 & 157 to Licenses NPF-35 & NPF-52,respectively ML20217K5731998-04-23023 April 1998 Safety Evaluation Supporting Amends 164 & 156 to Licenses NPF-35 & NPF-52,respectively ML20216E1771998-04-13013 April 1998 Safety Evaluation Accepting Relief Request 98-01 for Catawba Nuclear Station Units 1 & 2 from Requirements of ASME Boiler & PV Code for Second 10-year Interval Program for Inservice Testing of Pumps & Valves ML20217P7261998-04-0808 April 1998 Safety Evaluation Supporting Amends 178 & 160 to Licenses NPF-09 & NPF-17,respectively ML20217M4211998-04-0303 April 1998 Safety Evaluation Approving Request for Relief 97-04, non-code Repair Valves.Relief Granted Retroactively to Unit 1 & Expired Dec 1997.Relief for Unit 2 Will Expire at End of Cycle 9 Outage or Next Scheduled Outage Exceeding 30 Days ML20197A6551998-03-0202 March 1998 Safety Evaluation Supporting Licensee Proposed Action to Set Gwl Alarm at Higher Elevation than Current Level of El 731 Feet ML20197A6331998-03-0202 March 1998 Safety Evaluation Supporting Amends 163 & 155 to Licenses NPF-35 & NPF-52,respectively ML20203B1071998-02-0404 February 1998 Safety Evaluation Approving Proposed Alternative to Reactor Vessel Augmented Exam Requirement of Reactor Vessel Shell Welds,Per 10CFR50.55a(g)(6)(ii)(A)(5) ML20199F3361998-01-28028 January 1998 Safety Evaluation Supporting 951227 Request for NRC Approval of Proposed EALs to McGuire Nuclear Station,Units 1 & 2 ML20199A5521998-01-22022 January 1998 Safety Evaluation Re Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves, for Cns,Units 1 & 2 ML20199A6421998-01-22022 January 1998 Safety Evaluation Accepting Proposed EALs Changes for Plant, Units 1 & 2.Concludes That Changes Consistent W/Guidance in NUMARC/NESP-007,w/variations as Identified & Accepted in Review & Meets Requirements of 10CFR50.47(b)(4) ML20198P9641998-01-15015 January 1998 SE Granting Relief Request 97-03 for Second 10-yr Interval Inservice Insp Program ML20202C0001997-11-25025 November 1997 Safety Evaluation Supporting Amends 177 & 159 to Licenses NPF-9 & NPF-17,respectively ML20198R9951997-10-30030 October 1997 Safety Evaluation Authorizing Request for Approval of Alternative to Exam Requirement of Reactor Vessel Shell Weld,Per 10CFR50.55a(g)(6)(ii)(A)(5) ML20198J7651997-10-15015 October 1997 Safety Evaluation Accepting 10-yr Interval Insp Program Plan Alternatives for Listed Plants Units ML20211P4521997-10-0909 October 1997 Safety Evaluation Supporting Amend 162 to License NPF-35 ML20211F8801997-09-22022 September 1997 Safety Evaluation Supporting Second ten-year Interval Inservice Inspection Program Plan & Associated Requests for Relief for Catawba Nuclear Station Unit 1 1999-09-08
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20212J1891999-10-0101 October 1999 Safety Evaluation Supporting Exemption from 10CFR54.17(c)re Schedule to Apply for Renewed Operating Licenses ML20217G7951999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for McGuire Nuclear Station,Units 1 & 2 ML20217H0201999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Catawba Nuclear Station,Units 1 & 2 ML20212A6271999-09-30030 September 1999 Rev 0 to WCAP-15243, Anaylsis of Capsule V & Capsule Y Dosimeters from Duke Energy Catawba Unit 2 Reactor Vessel Radiation Surveillance Program 05000414/LER-1999-004-01, :on 980906,error During Tagout Caused de-energization of Vital Bus & Actuation of Ltop.Caused by Inadequate Work Practices.Individuals Involved Were Counseled1999-09-27027 September 1999
- on 980906,error During Tagout Caused de-energization of Vital Bus & Actuation of Ltop.Caused by Inadequate Work Practices.Individuals Involved Were Counseled
05000413/LER-1999-015, :on 990616,discovered That Auxiliary Bldg Filtered Ventilation Exhaust Sys Was Inoperable.Caused by Improperly Positioned Vortex Damper.Damper Was Repositioned Correctly & Sys Was Retested Successfully1999-09-27027 September 1999
- on 990616,discovered That Auxiliary Bldg Filtered Ventilation Exhaust Sys Was Inoperable.Caused by Improperly Positioned Vortex Damper.Damper Was Repositioned Correctly & Sys Was Retested Successfully
ML20217F3661999-09-22022 September 1999 Rev 18 to McGuire Unit 1 Cycle 14 Colr ML20212G2671999-09-22022 September 1999 Safety Evaluation Supporting Amends 187 & 168 to Licenses NPF-9 & NPF-17,respectively ML20212G1211999-09-22022 September 1999 Safety Evaluation Supporting Amends 188 & 169 to Licenses NPF-9 & NPF-17,respectively ML20212G2511999-09-22022 September 1999 Safety Evaluation Supporting Amends 180 & 172 to Licenses NPF-35 & NPF-52,respectively 05000413/LER-1999-008, :on 990610,operations Prohibited by TS 3.5.2, Was Violated.Caused by Inoperable Centrifugal Charging Pump. Operators Swapped to CCP 1A & Sys Parameters Were Returned to Normal.With1999-09-21021 September 1999
- on 990610,operations Prohibited by TS 3.5.2, Was Violated.Caused by Inoperable Centrifugal Charging Pump. Operators Swapped to CCP 1A & Sys Parameters Were Returned to Normal.With
05000414/LER-1999-005-02, :on 990727,missed Emergency DG TS Surveillance Concerning Verification of Availability of Offsite Power Sources,Was Declared.Caused by Defective Procedure.Revised Affected Procedure1999-09-20020 September 1999
- on 990727,missed Emergency DG TS Surveillance Concerning Verification of Availability of Offsite Power Sources,Was Declared.Caused by Defective Procedure.Revised Affected Procedure
ML20212D1911999-09-20020 September 1999 SER Accepting Exemption from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Closed System Isolation Valves for McGuire Nuclear Station,Units 1 & 2 05000413/LER-1999-009, :on 990518,inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits Was Noted. Caused by Inadequate Retest Following Surveillance Test Failure.Valve Was Retested & Returned to Service1999-09-15015 September 1999
- on 990518,inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits Was Noted. Caused by Inadequate Retest Following Surveillance Test Failure.Valve Was Retested & Returned to Service
ML20211P1371999-09-0808 September 1999 Safety Evaluation Supporting Amend 186 to License NPF-9 ML20216E5401999-09-0707 September 1999 Special Rept:On 990826,discovered That Meteorological Sys Upper Wind Speed Cup Set Broken,Causing Upper Wind Channel to Be Inoperable.Cup Set Replaced & Channel Restored to Operable Status on 990826 05000414/LER-1999-004, :on 990616,CIV 2NM-221A Was Returned to Svc Without Testing,As Required by TS 3.6.3.Caused by Programmatic Deficiency.Test Procedure Has Been Revised & Subject Valve Was Successfully Tested & Returned to Svc1999-09-0101 September 1999
- on 990616,CIV 2NM-221A Was Returned to Svc Without Testing,As Required by TS 3.6.3.Caused by Programmatic Deficiency.Test Procedure Has Been Revised & Subject Valve Was Successfully Tested & Returned to Svc
05000413/LER-1999-014, :on 990816,missed Surveillances & Operation Prohibited by TS Was Noted.Caused by Defective Procedures or Programs Inappropriate TS Requirements.Affected Procedures/ Programs Were Revised & Testing Was Performed1999-09-0101 September 1999
- on 990816,missed Surveillances & Operation Prohibited by TS Was Noted.Caused by Defective Procedures or Programs Inappropriate TS Requirements.Affected Procedures/ Programs Were Revised & Testing Was Performed
05000414/LER-1999-003, :on 990612,unplanned Actuation of ESFAS Occurred Due to a SG High Level.Caused by Inadequate Procedural Guidance.Msiv 2SM-7 Was Closed & SG 2A Level Was Returned to Normal1999-08-31031 August 1999
- on 990612,unplanned Actuation of ESFAS Occurred Due to a SG High Level.Caused by Inadequate Procedural Guidance.Msiv 2SM-7 Was Closed & SG 2A Level Was Returned to Normal
ML20216E8851999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Units 1 & 2 ML20211B1281999-08-31031 August 1999 Dynamic Rod Worth Measurement Using Casmo/Simulate ML20217G8101999-08-31031 August 1999 Revised Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2 ML20212B4711999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 ML20217H0321999-08-31031 August 1999 Revised Monthly Operating Rept for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 05000413/LER-1999-012, :on 990727,adverse Sys Interaction Between Annulus Ventilation Sys & Auxiliary Building Ventilation Sys Was Discovered.Caused by Inadequate Design.Compensatory Actions Developed & Implemented.With1999-08-26026 August 1999
- on 990727,adverse Sys Interaction Between Annulus Ventilation Sys & Auxiliary Building Ventilation Sys Was Discovered.Caused by Inadequate Design.Compensatory Actions Developed & Implemented.With
ML20211G5261999-08-24024 August 1999 SER Accepting Approval of Second 10-year Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1 ML20211A9791999-08-20020 August 1999 Safety Evaluation Granting Licensee Request for Approval of Proposed Relief from Volumetric Exam Requirements of ASME B&PV Code,Section Xi,For Plant,Unit 2 ML20211C1291999-08-17017 August 1999 ISI Rept Unit 1 Catawba 1999 RFO 11 ML20211F3441999-08-17017 August 1999 Updated non-proprietary Page 2-4 of TR DPC-NE-2009 ML20210U8341999-08-13013 August 1999 Safety Evaluation Supporting Amends 179 & 171 to Licenses NPF-35 & NPF-52,respectively ML20210R1051999-08-0606 August 1999 Special Rept:On 990628,cathodic Protection Sys Was Declared Inoperable After Sys Did Not Pass Acceptance Criteria of Bimonthly Surveillance.Work Request 98085802 Was Initiated & Connections on Well Anode Were Cleaned or Replaced ML20212B4871999-07-31031 July 1999 Revised Monthly Operating Rept for July 1999 for Catawba Nuclear Station,Units 1 & 2 ML20210S2891999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Catawba Nuclear Station,Units 1 & 2 ML20216E8951999-07-31031 July 1999 Revised Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2 ML20210S2371999-07-31031 July 1999 Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2 05000413/LER-1999-009, :on 990518,inoperability of Containment Valve Injection Water Sys Valve Was Noted in Excess of TS Limits. Caused by Inadequate Testing Following Surveillance Test Failure.Valve Was Retested & Restored to Service1999-07-19019 July 1999
- on 990518,inoperability of Containment Valve Injection Water Sys Valve Was Noted in Excess of TS Limits. Caused by Inadequate Testing Following Surveillance Test Failure.Valve Was Retested & Restored to Service
05000414/LER-1999-004-02, :on 990610,violation of TS 3.6.3 Was Noted Due to CIV 2NM-221A Being Returned to Service Without Testing. Caused by Procedure Deficiency.Civ 2NM-221A Was Tested & Returned to Operable Status1999-07-15015 July 1999
- on 990610,violation of TS 3.6.3 Was Noted Due to CIV 2NM-221A Being Returned to Service Without Testing. Caused by Procedure Deficiency.Civ 2NM-221A Was Tested & Returned to Operable Status
ML20209E4361999-07-0909 July 1999 SER Agreeing with Licensee General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation 05000414/LER-1999-003-02, :on 990612,unplanned Actuation of Esfa Sys Due to a SG High Level Was Noted.Caused by Inadequate Procedural Guidance.Long Term Corrective Actions to Prevent Recurrence of Event Are Being Developed1999-07-0808 July 1999
- on 990612,unplanned Actuation of Esfa Sys Due to a SG High Level Was Noted.Caused by Inadequate Procedural Guidance.Long Term Corrective Actions to Prevent Recurrence of Event Are Being Developed
ML20196K6631999-07-0707 July 1999 Safety Evaluation Supporting Licensee 990520 Position Re Inoperable Snubbers ML20210S2491999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for McGuire Nuclear Station,Units 1 & 2 ML20209H1631999-06-30030 June 1999 Monthly Operating Repts for June 1999 for McGuire Nuclear Station,Units 1 & 2 ML20209H4501999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Catawba Nuclear Station,Units 1 & 2 ML20210S2951999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Catawba Nuclear Station,Units 1 & 2 05000414/LER-1999-002-03, :on 990504,plant Was Forced to Shutdown as Result of Flow Restriction Caused by Corrosion of Afs Assured Suction Source Piping Due to Inadequate Testing. Affected Piping Was Cleaned & Flow Tested1999-06-0303 June 1999
- on 990504,plant Was Forced to Shutdown as Result of Flow Restriction Caused by Corrosion of Afs Assured Suction Source Piping Due to Inadequate Testing. Affected Piping Was Cleaned & Flow Tested
ML20195K3691999-05-31031 May 1999 Monthly Operating Repts for May 1999 for McGuire Nuclear Station,Units 1 & 2 ML20209H1731999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for McGuire Nuclear Station,Units 1 & 2 ML20206T4771999-05-31031 May 1999 Rev 3 to UFSAR Chapter 15 Sys Transient Analysis Methodology ML20196L1881999-05-31031 May 1999 Non-proprietary Rev 1 to DPC-NE-3004, Mass & Energy Release & Containment Response Methodology ML20209H4561999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Catawba Nuclear Station,Units 1 & 2 1999-09-08
[Table view] |
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-s UNITED STATES s
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.c. 20666-0001
.....,o SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION EXEMPTION FROM 10 CFR 54.17(c)
REGARDING SCHEDULE TO APPLY FOR A RENEWED OPERATING LICENSE CATAWBA NUCLEAR STATION. UNITS 1 AND 2 DOCKET NOS. 50-413 AND 50-414 MCGUIRE NUCLEAR STATION. UNIT 2
)
i DOCKET NO. 50-370
1.0 INTRODUCTION
Requirements for filing applications for renewed operating licenses are contained in the license renewal rule, Title 10 of the Code of FederalRegulations (10 CFR), Part 54, Section 54.17(c),
which states: "An application for a renewed license may not be submitted to the Commission earlier than 20 years before the expiration of the operating license currently in effect."
Duke Energy Corporation (licensee / Duke) requested, in a letter dated June 22,1999, an emmption from the 20-year restriction in Section 54.17(c) to allow it to submit renewal e tcativ i foi McGuire, Unit 2, and Catawba, Units 1 and 2, earlier than 20 years before expiratio U their operating licenses. Such an exemption would allow Duke to submit applications for renewal of the operating licenses of McGuire, Units 1 and 2, and Catawbt, Units 1 and 2, on the same or similar schedules with the goal of obtaining efficiencies f f j
preparation and review of the applications. Duke has indicated that the McGuire aru Gatawba applications would not be submitted until June 2001 when McGuire, Unit 1, achieves 20 years of operating experience. Duke stated that the exemptions were requested at this time because it needs to know, by the fall of 1999, the regulatory conditions under which license renewal applications for McGuire and Catawba can be prepared to support submittal of the applications to the Nuclear Regulatory Commission (NRC) in June 2001.
The current operating license for McGuire, Unit 1, expires on June 12,2021, and for McGuire, Unit 2, on March 3,2023. The current operating license for Catawba, Unit 1, expires on December 6,2024, and for Catawba, Unit 2, on February 24,2026. If Duke submits the renewal applications on the earliest possible date, June 13,2001, when McGuire, Unit 1, meets the 20-year limit contained in Section 54.17(c), McGuire, Unit 2, will have approximately 18.3 years of operating experience and Catawba, Units 1 and 2, approximately 16.5 years and 15.3 years operating experience, respectively.
In its request, Duke stated that business considerations dictate preparation and submittal of concurrent license renewal applications for McGuire and Catawba. Further, Duke stated that submittal of such renewal applications in 2001, as oppost;d to some time thereafter, is 9910050063 991001 E
PDR ADOCK 05000369 P
PDR
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. necessary to obtain the full amount of the potential cost savings. To support preparation of the July 1998 Oconee Nuclear Station renewal applications, Duke assembled a team of individuals with relevant experience in necessary disciplines to prepare the applications and to remain dedicated to the renewal effort throughout the period of NRC staff review. According to Duke, granting the exemption request would allow it to use this same team of qualified and experienced professionals to prepare its McGuire and Catawba renewal applications. Thus, Duke states that it can avoid redeployment costs that would arise if it were unab!e to proceed promptly with preparation of additional renewal applications, Duke indicated that it would also be able to avoid the costs that would arise if it were forced to reassemble and train a new team to prepare McGuire and Catawba applications in the future.
2.0 EVALUATION Section 54.15 states that exemptions from the requirements of Part 54 may be granted by the Commission in accordance with Section 50.12. An exemption may be granted under Section 50.12 if the exemption is authorized by law, will not present an undue risk to the public health and safety, and is consistent with the common defense and security. However, an exemption will not be granted tnless special circumstances are present as defined in Section 50.12(a)(2).
2.1 Authorized by Law The Commission's basis for establishing the 20-year limit contained in Section 54.17(c) is discussed in the 1991 Statements of Consideration for Part 54 (56 FR 64963). The limit was established to ensure that substantial operating experience was accumulated by a licensee before a renewal application is submitted such that any plant-specific concerns regarding aging would be disclosed. In amending the rule in 1995, the Commissica sought public comment on whether the 20-year limit should be reduced. The Commission determined that sufficient basis did not exist to generically reduce the 20-year limit. However, the Commission did indicate in the Statements of Consideration for the amended rule (60 FR 22488), that it was willing to consider plant-specific exemption requests by applicants who believe that sufficient information is available to justify applying for license renewal prior to 20 years from expiation of the current license. Duke's exemption requests are consistent with the Commission's intent to consider plant-specific requests.
The current operating licenses for McGuire and Catawba are issued in accordance with Section 103 of the Atomic Energy Act, as amended (AEA). Section 103 and 10 CFR 50.51 limit the duration for an operating license to a maximum of 40 years. In accordance with Section 54.31, the renewed license will be of the same class as the operating license currently in effect and cannot exceed a term of 40 years. Therefore, the term of the renewed licenses for McGuire and Catawba are limited both by law and the Commission's regulations to 40 years.
Additionally, Section 54.31(b) states that:
A renewed license will be issued for a fixed period of time, which is the sum of the additional amount of time beyond the expiration of the operating license (not to exceed 2 s years) that is requested in a renewal application plus the remaining number of years on the operating license currently in effect. The term of any renewed license may not exceed 40 years.
?
! In its requer' Duke stated that it is not seeking exemption from the forty-year limit imposed on the term u ' AcGuire and Catawba's renewed operating licenses. Duke indicated that it expects the NRC tu adjust the terms of the renewed licenses accordingly. Therefore, should the Commission determine to renew the McGuire or Catawba licenses, granting of Duke's exemption requests will not result in violation of the AEA and the Commission's regulations with respect to the duration of any renewed license.
Because of Duke's decision to apply early for license renewal for McGuire, Unit 2, and Catawba, Units 1 and 2, Duke may not obtain the maximum 20-year period of extended operation permitted by Section 54.31(b). Any actual reduction will depend on the date the renewed licenses are issued. If Duke desires further extension of McGuire and Catawba's operating licenses in the future, additional renewal applications can be submitted in accordance with Part 54.
2.2 No Undue Risk to Public Health and Safety Duke's exemption requests seek only scheduler relief regarding the date of submittal, and not substantive relief from the requirements of Parts 51 or 54. Duke must still conduct all environmental reviews required by Part 51 and all safety reviews and evaluations required by Part 54 when preparing the applications for McGuire and Catawba. The staff's review will verify that all applicable Commission regulations have been met before issuing the renewed licenses.
Therefore, the staff finds that granting these scheduler exemptions will not represent an undue risk to public health and safety.
2.3 Consistent with the Common Defense and Security As discussed previously, the exemptions requested are only scheduler exemptions. The NRC staff will rev'ew any renewal applications Duke submits pursuant to the requested exemption to determine whether all applicable requirements are fully met. Accordingly, granting the requested exemptions will not adversely affect the common defense and security.
2.4 Special Circumstances Supporting Issuance of the Exempions An exemption will not be granted unless special circumstances are present as defined in Section 50.12(a)(2). Specifically, Section 50.12(a)(2)(ii) states that a special circumstance exists when " application of the regulation in the particular circumstances... is not necessary to achieve the underlying purpose of the rule." In initially promulgating Section 54.17(c)in 1991, the Commission stated that the purpose of the timc limit was "to ensure that substantial operating experience is accumulated by a licensee before it submits a renewal application."
(56 FR 64963). A' hat time, the Commissbn found that twenty years of operating experience provided a sufficier, basis for renewal applications. However, in issuing the amended Part 54 j
in 1995, the Commission indicated it would consider an exemption to this requirement if sufficient information was available on a plant-specific basis to justify submission of an application to renew a license before completion of 20 years of operation (60 FR 22488).
[
The 20-year limit was imposed by the Commission to ensure that sufficient operating experience was accumulated to identify any plant-specific aging concerns. As set forth below, McGuire, Unit 2, and both Catawba units are sufficiently similar to McGuire, Unit 1, such that the operating experience for McGuire, Unit 1, should apply to the other three units. In addition,
. the other three units have accumulated significant operating experience. Accordingly, under the requested exemption, sufficient operating experience will have been accumulated to identify any plant-specific aging concerns for all four units.
McGuire and Catawba are two-unit plants comprised of four-loop Westinghouse pressurized water reactors with ice-condenser containments and a rated power of 3411 megawatts. Duke states that it will use the combined experience it has gained by operation of the McGuire and Catawba units to perform the evaluations required to support the license renewal applications.
Duke also states that the two McGuire units and the two Catawba units are similar in design, operation, and maintenance. This statement is supported by a review of the McGuire and Catawba Updated Final Safety Analysis Reports (UFSARs). In particular, Section 1.3 of the Catawba UFSAR describes the similarities in design between McGuire and Catawba. Table 1-2 of the Catawba UFSAR lists significant similarities between systems, structures, and components installed at Catawba and McGuire, including elements of the reactor system, the reactor coolant system, the engineered safety features, and the auxiliary systems. Additionally, Duke indicates that the current aging management programs and activities are similar at each of the four units.
Duke also stated that there are " regular and systematic exchanges of information on plant-specific operating experience among all three Duke nuclear stations" (McGuire, Catawba, and Oconee). An example provided was peer communications that occur on an ongoing basis during the normal course of operation and maintenance of the units. A v Mly, during certain infrequent occurrences at any one station, peer observers from the other.
, plants participate to gain firsthand experience and to provide input based on their own experiences.
These communications provide the means to continually improve plant programs. Additionally, peer group meetings are held regularly throughout the year to discuss topics of mutualinterest.
The effectiveness of programs and activities is reviewed, and program changes are often discussed. This sharing of plant-specific operating experience among the Duke nuclear stations is part of Duke's normal process to maintain the effectiveness of plant programs and activities and to continually improve the performance of Duke's nuclear stations.
Given these similarities, the operating experience at McGuire, Unit 1, should be applicable to McGuire, Unit 2, and also to the Catawba units for purposes of the license renewal review. At the time of application, McGuire, Unit 1, will have achieved the required 20 years of operation and its operating experience will be applicable to Unit 2 which will have almost met the 20-year requirement with 18.3 years of operating experience. Because of the similarity of design, operation, and maintenance between McGuire and Catawba, the McGuire operating experience should be applicable to Catawba. Additionally, the Catawba units will have operated for a substantial period of time (approximately 16.5 years for Unit 1 and 15.3 years for Unit 2) which provides additional plant-specific operating experience to supplement the McGuire operating experience. The actual twenty years of operating experience of McGuire Unit 1,in conjunction with the substantial number of years of operation of the other three units, should be sufficient to identify any aging concerns applicable to the four units.
Therefore, sufficient combined operating experience should exist at the earliest possible date for submittal to satisfy the intent of Section 54.17(c), and application of the regulation in this case is not necessary to achieve the underlying purpose of the rule. The staff finds that Duke's request meets the requirement in Section 50.12(a)(2) that special circumstances exist to grant the exemption.
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3.0 CONCLUSION
The staff finds that based on the similarity between the McGuire and Catawba units and the operating experience that will be available at the earliest possible date for submittal of concurrent applications (June 13,2001), there is sufficient basis to find that the Commission's
. Intent in Section 54.17(c) regarding the timing for submittal of a renewal application can be met to justify granting the exemptions for McGuire, Unit 2, and Catawba, Units 1 and 2. Should Duke submit applications to renew the licenses for McGuire and Catawba, those applications must demonstrate full compliance with Parts 51 and 54 for each of the units and include information addressing the similarity in design, operation and maintenance to support the l
submittal of concurrent applications. In the course of its review of any application to renew the licenses for the McGuire and Catawba units, the NRC staff wi!) examine how the actual operating experience available from all the units applies to the particular systems, structures, and components at those plants.
' Principal Contributor: Stephen Hoffman j
Date:
October 1, 1999 i
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