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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
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
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
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
ML20211E6871997-09-22022 September 1997
SER Accepting DPC Responses to GL-95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves
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
ML20247K2531989-09-11011 September 1989
Safety Evaluation Supporting Amends 123 & 41 to Licenses DPR-61 & NPF-49,respectively
ML20247E3761989-09-0707 September 1989
Safety Evaluation Supporting Amends 122,34,143 & 40 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively
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
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
ML20217G8101999-08-31031 August 1999
Revised Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2
ML20211B1281999-08-31031 August 1999
Dynamic Rod Worth Measurement Using Casmo/Simulate
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
ML20212B4711999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for Catawba 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
ML20211F3441999-08-17017 August 1999
Updated non-proprietary Page 2-4 of TR DPC-NE-2009
ML20211C1291999-08-17017 August 1999
ISI Rept Unit 1 Catawba 1999 RFO 11
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
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
ML20212B4871999-07-31031 July 1999
Revised Monthly Operating Rept for July 1999 for Catawba 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
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
ML20206T4771999-05-31031 May 1999
Rev 3 to UFSAR Chapter 15 Sys Transient Analysis Methodology
ML20209H4561999-05-31031 May 1999
Revised Monthly Operating Rept for May 1999 for Catawba Nuclear Station,Units 1 & 2
ML20196L1881999-05-31031 May 1999
Non-proprietary Rev 1 to DPC-NE-3004, Mass & Energy Release & Containment Response Methodology
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
ML20196A0001999-05-31031 May 1999
Monthly Operating Repts for May 1999 for Catawba 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
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
ML20196A0041999-04-30030 April 1999
Revised Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2
ML20206R1811999-04-30030 April 1999
Monthly Operating Repts for Apr 1999 for Catawba 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
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
ML20205N3651999-04-12012 April 1999
Safety Evaluation Accepting IPE of External Events Submittal
ML20205L2341999-04-0505 April 1999
SFP Criticality Analysis
ML20205P8991999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for McGuire 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
ML20206R1931999-03-31031 March 1999
Revised Monthly Operating Repts for Apr 1999 for Catawba 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
ML20204C9111999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for Catawba Nuclear Station,Units 1 & 2
1999-09-07
[Table view] |
Text
l ENCLOSURE I 3'
SAFETY EVALUATTON REPORT DOCKET N05. 50-3E9/370-MCGUIRE NUCLEAR STATION UNITS 1.?
GENERIC LETTER R3-28. ITEM 4.5.?
REACTOR TRIP SYSTEM DELIABILITY. nu-LINE TESTING INTRODUCTION AND
SUMMARY
Generic Letter R3-?R was issued by NRC on ,)uly R 1993, indicating actions to be tak'en by applicants and ifcensees based on the ceneric implications of the Salem ATUS events. Item 4.5 states a staff position which requires on-line functional testing of the reactor trip system, including independent testing of the diverse trip features of the reactor trip breakers, for all plants. Item 4.5.2 requires applicants and licensees with plants not currently designed to pemit this peri-
. odic on-line testing to justify not making modifications to pemit such tetting.
By letter dated November 4,1983, the licensee, Duke Power Company, responded to the staff position regarding item 4.5.2 of Generic Letter A3-?8 Our review of this response finds it to be acceptable.
l EVALUATION The licensee states that on-line functional testing of the Reactor Trip System is perfomed for both McGuire units. Further, staff review of the design has con-
~
firmed that the design permits independent on-line testing of the undervoltage and shunt trip attactment.
CONCLUSION The staff finds that the McGuire Nuclear Station, Units 1 and 2, are designed to pemit on-line functional testing of the reactor trip system, including independent testing of the diverse trip features of the reactor trip breakers. Thus, the licensee meets the staff position of item 4.5.7 of Generic Letter 83-28 8702030536 870120 DR ADOCK 0500 9
I* ENCLOSURE 2
/ .
SAFETY EVALUATION REPORT DOCKET NOS. 50 413/414 CATAWRA NUCLEAR STATION, UNITS 1,2 GENERIC LETTER 83 78, ITEtt 4.5.?
REACTOR TRIP SYSTEM RELIARILITY-ON-LINE TESTING ,
INTRODUCTION AND
SUMMARY
Generic Letter 83-28 was issued by NRC on .!uly 8,1983, indicatina actions to be tak'en by applicants and licensees based on the generic implications of the Salem ATWS events. Itam 4.5 states a staff position which requires on-line functional testing of the reactor trip systen, including independent testing of the diverse trip features of the reactor trip breakers, for all plants. Item d.5.? requires applicants and licensees with plants not currently designed to permit this peri-odic on-line testing to ,iustify not making nodifications to permit such testina.
By letter dated No'vember 4,1983, the licensee / applicant, Duke Power Conpany, responded to the staff position regarding item 4.5.2 of Generic letter 83 78 Our review of this response' finds it to be acceptable.
EVALUATION The licensee / applicant states that the Catawba Nuclear Station, tinits 1 and 2, designed to allow on-line testing of the Reactor Trip System which will include independent testing of the undervoltage and shunt trip attachments.
a i/ .
,l, -?-
P CONCLt!SION ,
The staff finds that the Catawba Nuclear Station, linits 1 and 2, are designed to permit on-line functional testino of the reactor trip system, including in.
dependent testing of the diverse trip features of the reactor trip breakers.
Thus, the licensee / applicant meets the staff position of item 4.5.7 of Generic letter 83-28.
9