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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212D1911999-09-20020 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 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 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 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 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 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 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 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 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) 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 ML20198P9641998-01-15015 January 1998 SE Granting Relief Request 97-03 for Second 10-yr Interval Inservice Insp Program 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 ML20211E6871997-09-22022 September 1997 SER Accepting DPC Responses to GL-95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves 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 ML20149K8281997-07-29029 July 1997 SER Granting Request for Exemption from Requirements of 10CFR70.24 for Units 1 & 2 ML20148S2231997-07-0202 July 1997 Safety Evaluation Accepting Supplemental Test Program for Relief Request 1.4.2 for Units 1 & 2 ML20141E1121997-06-16016 June 1997 Safety Evaluation Approving Licensee Position That UFSAR Table 6-77 Be Revised to Identify SA-1 & SA-4 Instead of SA-3 & SA-6 as Containment Isolation Valves ML20148H2501997-06-0505 June 1997 Safety Evaluation Accepting Proposed Restructuring of Util Through Acquisition Of,& Merger W/Panenergy Corp ML20141G6701997-05-20020 May 1997 Safety Evaluation Accepting Proposed Alternative Use of TS Requirement for Code Class Snubbers ML20135B3051997-02-27027 February 1997 Safety Evaluation Granting Second 10 Yr ISI Program Plan & Associated Requests for Relief ML20134P2421997-02-20020 February 1997 Safety Evaluation Accepting TR BAW-10199P for Ref in Plants Licensing Documentation & Use in Licensing Applications ML20134L4081996-11-19019 November 1996 SER Accepting Performance of Plant Standby Nuclear Svc Water Pond ML20134G5551996-11-0707 November 1996 Safety Evaluation Accepting Proposed Application of BWU-Z CHF Correlation for Plants Mark-BW 17x17 Type Fuel ML20129E4851996-10-0101 October 1996 Safety Evaluation Recommending That Relief Request 96-02 Be Granted,Per 10CFR50.55a(g)(6)(i),per Request ML20059G8601993-10-29029 October 1993 SE Granting 921130 Request for Relief from Requirements of 1986 Edition of ASME Boiler & Pressure Vessel Code,Section XI Re Inservice Insp of safety-related Snubbers During Second 10-yr Interval ML20057F4121993-10-12012 October 1993 Safety Evaluation Re Inservice Testing Program Requests for Relief.Alternatives Authorized Per 10CFR50.55a(a)(3) or Relief Granted Per 10CFR50.55a(f)(6)(i) ML20057A0361993-08-26026 August 1993 Safety Evaluation Supporting Amends 138 & 120 to Licenses NPF-9 & NPF-17,respectively ML20056H3191993-08-24024 August 1993 SER Accepting Proposed TS Changes Re RWST & Cla Boron Concentrations ML20056D9611993-07-30030 July 1993 SER Accepting Licensee 930325-0429 Submittals of Technical Info to Support Continued Operation of Facility for Remainder of Fuel Cycle 7 ML20126H3171992-12-28028 December 1992 Safety Evaluation Granting Extension of First 10-yr ISI Interval to Coincide W/Start of end-of-cycle 8 Refueling Outage ML20058N7961990-08-0909 August 1990 Safety Evaluation Approving Relief Request 89-01 Re ASME Code Test Requirements for Nuclear Svc Water Sys ML20055H9151990-07-27027 July 1990 Safety Evaluation Accepting Actions Taken to Resolve NRC Bulletin 88-002, Rapidly Propagating Fatigue Cracks in Steam Generators Tubes ML20248C0731989-08-0303 August 1989 Sser Accepting 880601,0909 & 890602 Changes to ATWS Mitigation Sys Actuation Circuitry for Plants ML20247H7611989-07-18018 July 1989 Safety Evaluation Supporting Amends 100 & 82 to Licenses NPF-9 & NPF-17,respectively ML20246C4621989-06-29029 June 1989 Safety Evaluation Granting Request for Relief from Hydrostatic Testing Requirements of Section XI of ASME Code ML20247C0171989-05-18018 May 1989 Safety Evaluation Supporting Util Actions to Recover from 890307-08 Unit 1 Steam Generator Tube Rupture Event 1999-09-20
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G7951999-09-30030 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 ML20217F3661999-09-22022 September 1999 Rev 18 to McGuire Unit 1 Cycle 14 Colr 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 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 ML20212B4711999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 ML20217G8101999-08-31031 August 1999 Revised Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2 ML20217H0321999-08-31031 August 1999 Revised Monthly Operating Rept for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 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 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 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 ML20210S2371999-07-31031 July 1999 Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2 ML20216E8951999-07-31031 July 1999 Revised Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2 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 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 ML20209H1631999-06-30030 June 1999 Monthly Operating Repts for June 1999 for McGuire Nuclear Station,Units 1 & 2 ML20210S2491999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for McGuire Nuclear Station,Units 1 & 2 ML20196A0001999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Catawba Nuclear Station,Units 1 & 2 ML20209H4561999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Catawba Nuclear Station,Units 1 & 2 ML20206T4771999-05-31031 May 1999 Rev 3 to UFSAR Chapter 15 Sys Transient Analysis Methodology ML20195K3691999-05-31031 May 1999 Monthly Operating Repts for May 1999 for McGuire Nuclear Station,Units 1 & 2 ML20196L1881999-05-31031 May 1999 Non-proprietary Rev 1 to DPC-NE-3004, Mass & Energy Release & Containment Response Methodology ML20209H1731999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for McGuire Nuclear Station,Units 1 & 2 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 ML20206N8391999-05-0404 May 1999 Rev 16 to CNEI-0400-24, Catawba Unit 1 Cycle 12 Colr ML20206R1811999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20196A0041999-04-30030 April 1999 Revised Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20206R0891999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 ML20195K3761999-04-30030 April 1999 Revised MORs for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 ML20206N8261999-04-22022 April 1999 Rev 15 to CNEI-0400-24, Catawba Unit 1 Cycle 12 Colr. Page 145 of 270 of Incoming Submittal Not Included 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 ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML20205L2341999-04-0505 April 1999 SFP Criticality Analysis ML20206R1931999-03-31031 March 1999 Revised Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20206R0931999-03-31031 March 1999 Revised Monthly Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205P9521999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Catawba Nuclear Station,Units 1 & 2 ML20205P8991999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205C4171999-03-25025 March 1999 Special Rept 99-02:on 801027,Commission Approved for publication,10CFR50.48 & 10CFR50 App R Delineating Certain Fire Protection Provisions for Nuclear Power Plants Licensed to Operate Prior to 790101.Team Draft Findings Reviewed ML20207K2051999-03-0505 March 1999 Special Rept 99-01:on 990128,DG Tripped After 2 H of Operation During Loaded Operation for Monthly Test.Caused by Several Components That Were Degraded or Had Intermittent Problems.Parts Were Replaced & Initial Run Was Performed ML20205P9561999-02-28028 February 1999 Revised Monthly Operating Repts for Feb 1999 for Catawba Nuclear Station,Units 1 & 2 1999-09-07
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p i UNITED STATE 8 l
g j 2
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30006 4001 1
4 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION i
j RELATED TO REFERENCE OF THE BWU-Z CRITICAL HEAT FLUX CORRELATION j IN LICENSING DOCUMENTATION AND USE IN LICENSING APPLICATIONS j DUKE POWER COMPANY
} CATAWBA NUCLEAR STATION. UNITS 1 AND 2 l l
MCGUIRE NUCLEAR STATION. UNITS 1 AND 2 DOCKET NOS. 50-413. 50-414. 50-369. AND 50-370
1.0 INTRODUCTION
In a letter of October 22, 1996, Duke Power Company (DPC), requested approval i to reference the BWU-Z critical heat flux (CHF) correlation included in the !
descriptions contained in the topical report BAW-10199P-A, "The BWU Critical !
Heat Flux Correlations" (approved by letter, R. Jones to J. Taylor, April 5, 1996) in licensing documentation for its Catawba and McGuire Nuclear Stations, and incorporate that correlation in its licensing analytical models for those plants. DPC also requested to incorporate the statement "Other CHF correlations that have been reviewed and approved by the NRC may also be used to perform DNBR analyses," currently found in the approved DFC report DPC-NE-3000, Revision 1, into its reports DPC-NE-3001, DPC-NE-2004, and DPC-NE-2007.
2.0 EVALUATION 2.1 BWU-Z Applicability to Catawba and McGuire In its review, the staff considered the acceptability of the BWU-Z CHF correlation for reference in Catawba and McGuire licensing documentation and use in Catawba and McGuire licensing analyses. The staff also referred to BAW-10199P-A and the staff's safety evaluation report (SER) of April 5,1996, which discuss the BWU-Z correlation and its applicability considerations.
From such review, the staff concludes that the BWU-Z correlation covers the ranges of thermal / hydraulic conditions expected in Catawba and McGuire licensing analyses and therefore is suitable for inclusion in versions of the VIPRE code approved for use in Catawba and McGuire licensing analyses.
Therefore, the staff also concludes that BAW-10199P-A (August 1996) is acceptable for reference in Catawba and McGuire licensing documentation, including plant technical specifications and core operating limits reports (COLRs).
970225'0228 970220 DR ADOCK 050003 9 n, , - ~ rw- - . + --
I i
i l
j 2.2 Topical Reports Wording Change i In its October 22, 1996, letter, DPC also requested to incorporate the I statement "Other CHF correlations that have been reviewed and approved by the
- NRC may also be used to perform DNBR analyses," currently found in the
- approved DPC topical report DPC-NE-3000, Revision 1, into its reports DPC-NE-
, 3001, DPC-NE-2004, and DPC-NE-2007. In the staff's reading of the request, it
- appears that the wording would permit DPC to reference and use other approved
- correlations in licensing analyses without prior NRC approval. Such reference and use would be contrary to the operating license and COLR change process, which requires that any change to a methodology referenced in plant technical i specifications or COLR (e.g., VIPRE) be reviewed and approved by the staff for i
that reference prior to doing so. Therefore, the staff concludes that the
! proposed wording change is unacceptable. The staff's understanding of the l wording is that it is to indicate which correlations might be candidates for technical specifications or COLR inclusion, with only an applicability review i
! by the staff. It is only with this understanding that the s'taff previously i
, approved the wording to stand in DPC-NE-3000, Revision 1. l
~
3.0 CONCLUSION
S The staff concludes that BAW-10199P-A (August 1996) is acceptable for l reference in Catawba and McGuire licensing documentation, including plant i i technical specifications and COLRs, and for use in versions of the VIPRE code
- approved for use in Catawba and McGuire licensing analyses.
t l The staff does not approve the requested topical report wording changes. ;
i Principal Contributor: Frank R. Orr Date: February 20, 1997
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