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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20210T2161999-08-0606 August 1999 Draft SE Supporting Proposed Conversion of Current TS to ITS for Plant ML20206G7471999-05-0404 May 1999 Safety Evaluation Accepting Corrective Actions Taken by SNC to Ensure That Valves Perform Intended Safety Functions & Concluding That SNC Adequately Addressed Requested Actions in GL 95-07 ML20199D8611999-01-12012 January 1999 SER Accepting Relief Request for Inservice Insp Program for Plant,Units 1 & 2 ML20195E2281998-11-16016 November 1998 Safety Evaluation Authorizing Relief Request for Second 10-year ISI Program Relief Request 56 for Plant,Unit 1 ML20155E0271998-10-29029 October 1998 SER Approving & Denying in Part Inservice Testing Program Relief Requests for Plant.Relief Requests Q1P16-RR-V-3 & Q2P16-RR-V Denied Since Requests Do Not Meet Size Requirement of GL 89-04 ML20154B6121998-10-0101 October 1998 Safety Evaluation Granting Second 10-year ISI Requests for Relief RR-13 & RR-49 Through RR-55 for Jm Farley NPP Unit 1 ML20237C5471998-08-20020 August 1998 Suppl to SE Re Amends 137 & 129 to Licenses NPF-2 & NPF-8, Respectively.Se Being Supplemented to Incorporate Clarifications/Changes & Revise Commitment for Insp of SG U-bends in Rows 1 & 2 for Unit 2 Only ML20236U6141998-07-23023 July 1998 Safety Evaluation Authorizing Use of Alternative Alloy 690 Welds (Inco 52 & 152) as Substitute for Other Weld Metal ML20236R8671998-07-0909 July 1998 Safety Evaluation Concluding That Southern Nuclear Operating Co USI A-46 Implementation Program Has Met Purpose & Intent of Criteria in GIP-2 & Staff SSER-2 on GIP-2 for Resolution of USI A-46 ML20217D2591998-04-21021 April 1998 Safety Evaluation Accepting Licensee Proposed Alternative Re Augmented Exam of Reactor Vessel Shell Welds for Plant ML20217H3191998-03-31031 March 1998 Safety Evaluation Accepting Proposed Changes to Plant Matl Surveillance Programs ML20217D4081998-03-24024 March 1998 Safety Evaluation Accepting Proposed Changes to Maintain Calibration Info Required by ANSI N45.2.4-1972 ML20216H6731998-03-17017 March 1998 SER Accepting Quality Assurance Program Description Change for Joseph M Farley Nuclear Plant,Units 1 & 2 ML20199B0371998-01-22022 January 1998 SER Accepting Request for Relief (RR-27) for Plant,Units 1 & 2 from Certain Provisions of Section XI to ASME Boiler & Pressure Vessel Code.Relief Will Remove Insulation on ASME Code Class 1 Sys During Inservice Insp ML20198R5221997-10-29029 October 1997 Safety Evaluation Supporting Amends 132 & 124 to Licenses NPF-02 & NPF-08,respectively ML20216G9521997-09-0404 September 1997 Safety Evaluation Authorizing Request for Relief for IEEE 279-1971,Section 4.7.3 Requirements Concerning Steam Generator Water Level Control ML20236N3331997-08-21021 August 1997 SER Re Request for Interpretation of EDG TS 4.8.1.1.2.e for Farley Nuclear Plant,Units 1 & 2 ML20137E2951997-03-24024 March 1997 Safety Evaluation Supporting Amends 125 & 119 to Licenses NPF-2 & NPF-8,respectively ML20137B4371997-03-20020 March 1997 SER Accepting Request for Relief for 120-month Update of Facility Inservice Insp & Inservice Testing Programs & Code Addition & Addenda of Asme/Ansi Parts 6 & 10 ML20135E4811997-03-0404 March 1997 Safety Evaluation Accepting Implementation of 10CFR50.55a Requirements Related to Repair & Replacement Activities for Containment at Plant ML20056H1341993-08-23023 August 1993 Safety Evaluation Accepting Licensee 921217 Response to NRC 920917 SE Re Inservice Testing Program Relief Request ML20062D7001990-11-0909 November 1990 Safety Evaluation Supporting Util 881123 & 900917 Responses to Generic Ltr 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Matls & Its Effect on Plant Operations. Submittals Acceptable.Beltline Welds Discussed ML20245A8601989-06-13013 June 1989 Safety Evaluation Supporting Util 831104 & 850422 Responses to Generic Ltr 83-28,Item 4.5.3, Reactor Trip Sys Reliability for All Domestic Operating Reactors ML20195D5391988-10-31031 October 1988 Safety Evaluation Supporting ATWS Rule,10CFR50.62 ML20154C9651988-05-12012 May 1988 Safety Evaluation Re Flaw Indications in Reactor Pressure Vessel ML20147E2621987-11-16016 November 1987 Corrected Page 2 of Safety Evaluation Re Amends 74 & 66 to Licenses NPF-2 & NPF-8,respectively,deleting Ref to Quarterly Surveillance Testing on Staggered Test Basis ML20235K4441987-07-0808 July 1987 Safety Evaluation Supporting Granting Licensee Relief from Volumetric Exam of Steam Generator Primary Side Noozles Inside Radiused Sections ML20212E2241987-02-27027 February 1987 Safety Evaluation Accepting Util 831104 Response to Item 4.5.2 of Generic Ltr 83-28 Re on-line Functional Testing of Reactor Trip Sys,Including Independent Testing of Diverse Trip Features of Reactor Trip Breakers ML20212F5101987-01-0707 January 1987 Safety Evaluation Accepting Licensee 831104 Response to Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification (Reactor Trip Sys Components) ML20211D5341987-01-0707 January 1987 Safety Evaluation Re Rev 1 to EGG-EA-6794, Conformance to Reg Guide 1.97,Joseph M Farley Nuclear Plant,Units 1 & 2 & Licensee Submittals.Response Acceptable ML20207C2671986-12-15015 December 1986 Safety Evaluation Accepting Licensee Responses to Generic Ltr 83-28,Item 2.1 (Part 2) & Item 2.2.2 Re Vendor Interface Programs for Reactor Trip Sys & All Other Site safety- Related Components ML20214Q1891986-11-17017 November 1986 Safety Evaluation Granting Relief Re Inservice Evaluation Criteria for Disposition of Linear Indication in Reactor Coolant pipe-to-safe End Weld on Cold Leg Pipe of Loop C ML20211H9811986-06-19019 June 1986 Safety Evaluation Supporting Util Request for Relief from Inservice Testing/Insp Requirements Re pressure-retaining Valve Body Welds & Internal Pressure Boundary Surfaces of Valves Exceeding 4 Inches Nominal Pipe Size ML20198C7851986-05-16016 May 1986 Safety Evaluation Concluding That Util Pressurized Thermal Shock Screening Criteria for Reactor Pressure Vessels Complies w/10CFR50.61 ML20140C9901986-03-19019 March 1986 Suppl 1 to Safety Evaluation Supporting Util 851114 Response to Generic Ltr 83-28,Item 3.2.2 Re Test & Maint Procedures ML20136H6821985-12-27027 December 1985 Safety Evaluation Granting Relief from Certain Inservice Testing/Insp Requirements Re Reactor Vessel Flange Ligaments,Reactor Coolant Pump Casing Internal Surfaces & Flange Bolts ML20136C4251985-11-12012 November 1985 Safety Evaluation Accepting Util 831104 & 850215 Responses to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Re post-maint Testing Requirements in Existing Tech Specs for Reactor Trip Sys Components ML20209J1941985-10-24024 October 1985 SER Accepting Licensee 831104 & 850422 Responses to Items 4.2.1 & 4.2.2 of Generic Ltr 83-28 Concerning Preventative Maint Program & Trending Parameters for DS-416 Type Reactor Trip Breakers,Respectively ML20135H3891985-09-12012 September 1985 Safety Evaluation Re Compliance W/License Condition 2.C.(12)(b),requiring Provisions to Assure That safety-grade Backup Means of RCS Depressurization Meets Requirements of Rev 1 to Branch Technical Position Rsb 5-1.Addl Info Needed ML20209G9691985-09-10010 September 1985 Safety Evaluation Re Generic Ltr 83-28,Items 3.1.1,3.1.2, 3.2.1,3.2.2,4.1 & 4.5.1.Addl Info Required for Item 3.2.2 Re Check of Vendor & Engineering Recommendations for Testing & Maint ML20127N3131985-06-12012 June 1985 SER Re Util 831104 Response to Generic Ltr 83-28,Item 1.2, Post-Trip Review (Data & Info Capability). Licensee post-trip Review Data & Info Capabilities Acceptable ML20129D5451985-05-21021 May 1985 SER Re Util 831104 Response to Generic Ltr 83-28,Item 1.1 Re post-trip Review Program & Procedures.Program & Procedures Acceptable Subj to Implementation of Listed Recommendations 1999-08-06
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217P0761999-10-0606 October 1999 Non-proprietary, Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs ML20217G0361999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20212E7451999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Hcgs,Unit 1.With Summary of Changes,Tests & Experiments Implemented During Aug 1999.With ML20216E4941999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Jmfnp.With ML20210T2161999-08-0606 August 1999 Draft SE Supporting Proposed Conversion of Current TS to ITS for Plant ML20211B2011999-08-0404 August 1999 Informs Commission About Results of NRC Staff Review of Kaowool Fire Barriers at Farley Nuclear Plant,Units 1 & 2 & Staff Plans to Address Technical Issues with Kaowool & FP-60 Barriers ML20210R6031999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20196J3791999-06-30030 June 1999 Safety Evaluation of TR WCAP-14750, RCS Flow Verification Using Elbow Taps at Westinghouse 3-Loop Pwrs. Rept Acceptable ML20209G0661999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With L-99-267, Monthly Operating Repts for June 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With L-99-023, Monthly Operating Repts for May 1999 for Jfnp Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Jfnp Units 1 & 2. with ML20206G7471999-05-0404 May 1999 Safety Evaluation Accepting Corrective Actions Taken by SNC to Ensure That Valves Perform Intended Safety Functions & Concluding That SNC Adequately Addressed Requested Actions in GL 95-07 L-99-020, Monthly Operating Repts for Apr 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20206C9461999-04-30030 April 1999 1:Final Cycle 16 Freespan ODSCC Operational Assessment L-99-161, Monthly Operating Repts for Mar 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20205N0961999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20204D7271999-03-15015 March 1999 ISI Refueling 15,Interval 2,Period 3,Outage 3 for Jm Farley Nuclear Generating Plant,Unit 1 ML20207M6421999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20203A2651999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20199D8611999-01-12012 January 1999 SER Accepting Relief Request for Inservice Insp Program for Plant,Units 1 & 2 ML20199E6591998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20206C8081998-12-31031 December 1998 Alabama Power 1998 Annual Rept ML20198K4091998-12-18018 December 1998 COLR for Jm Farley,Unit 1 Cycle 16 ML20198B2561998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20195E2281998-11-16016 November 1998 Safety Evaluation Authorizing Relief Request for Second 10-year ISI Program Relief Request 56 for Plant,Unit 1 ML20195C9681998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20155E0271998-10-29029 October 1998 SER Approving & Denying in Part Inservice Testing Program Relief Requests for Plant.Relief Requests Q1P16-RR-V-3 & Q2P16-RR-V Denied Since Requests Do Not Meet Size Requirement of GL 89-04 ML20154B6121998-10-0101 October 1998 Safety Evaluation Granting Second 10-year ISI Requests for Relief RR-13 & RR-49 Through RR-55 for Jm Farley NPP Unit 1 ML20151V8341998-09-30030 September 1998 Non-proprietary Rev 2 to NSA-SSO-96-525, Jm Farley Nuclear Plant Safety Analysis IR Neutron Flux Reactor Trip Setpoint Change ML20154H6001998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20154H0121998-09-30030 September 1998 Submittal-Only Screening Review of Farley Nuclear Plant IPEEE (Seismic Portion) ML20197C8991998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20237C5471998-08-20020 August 1998 Suppl to SE Re Amends 137 & 129 to Licenses NPF-2 & NPF-8, Respectively.Se Being Supplemented to Incorporate Clarifications/Changes & Revise Commitment for Insp of SG U-bends in Rows 1 & 2 for Unit 2 Only ML20236Y1121998-07-31031 July 1998 Voltage-Based Repair Criteria 90-Day Rept ML20237B1891998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Jm Farley Nuclear Plant,Units 1 & 2 ML20237A2181998-07-24024 July 1998 Jm Farley Unit 2 ISI Rept Interval 2,Period 3 Outage 1, Refueling Outage 12 ML20236U6141998-07-23023 July 1998 Safety Evaluation Authorizing Use of Alternative Alloy 690 Welds (Inco 52 & 152) as Substitute for Other Weld Metal ML20236R8671998-07-0909 July 1998 Safety Evaluation Concluding That Southern Nuclear Operating Co USI A-46 Implementation Program Has Met Purpose & Intent of Criteria in GIP-2 & Staff SSER-2 on GIP-2 for Resolution of USI A-46 ML20236M5981998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Jm Farley Nuclear Plant,Units 1 & 2 ML20154H0461998-06-30030 June 1998 Technical Evaluation Rept on Review of Farley Nuclear Plant IPEEE Submittal on High Winds,Flood & Other External Events (Hfo) ML20248M3121998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Jm Farley Nuclear Plant,Units 1 & 2 ML20247F3631998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Jm Farley Nuclear Plant,Units 1 & 2 ML20217D2591998-04-21021 April 1998 Safety Evaluation Accepting Licensee Proposed Alternative Re Augmented Exam of Reactor Vessel Shell Welds for Plant ML20247E8851998-03-31031 March 1998 FNP Unit 2 Cycle 13 Colr ML20217H3191998-03-31031 March 1998 Safety Evaluation Accepting Proposed Changes to Plant Matl Surveillance Programs ML20216D5941998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Joseph M Farley Nuclear Plant,Units 1 & 2 ML20217D4081998-03-24024 March 1998 Safety Evaluation Accepting Proposed Changes to Maintain Calibration Info Required by ANSI N45.2.4-1972 ML20216H6731998-03-17017 March 1998 SER Accepting Quality Assurance Program Description Change for Joseph M Farley Nuclear Plant,Units 1 & 2 ML20216J6851998-03-16016 March 1998 Revised Pages 58 & 59 to Fnp,Units 1 & 2,Power Uprate Project BOP Licensing Rept ML20216D9811998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Jm Farley Nuclear Plant,Units 1 & 2 1999-09-30
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p C*%q\ UNITED STATES g j NUCLEAR REGULATORY COMMISSION o WASHINGTON. D.C. 30006 4001 SAFETY EVALUATION BY THE OFFICE OF NUCI FAR REACTOR REGULATION QUALITY ASSURANCE PROGRAM DESCRIPTION CHANGE SOUTHERN NUCI FAR OPERATING COMPANY. INC.. ET AL.
JOSEPH M. FARI FY NUCI FAR PLANT. UNITS 1 AND 2 DOCKET NOS. 50-348 AND 50-384
1.0 INTRODUCTION
By letter dated November 18,1997, as supplemented by letter dated February 23,1998, Southem Nuclear Operating Company, Inc. (SNC) requested a change to the Farley Nuclear Plant (FNP) Final Safety Analysis Report (FSAR) Quality Assurance (QA) Program Description pursuant to 10 CFR 50.54(a)(3). SNC proposed an altemative to the requirement to attach labels or tags to installed process instruments. The proposed attemative is to maintain a log or data base that includes calibration information specified by ANSI N45.2.4-1972 for each installed process instrument requiring calibration in lieu of the presently used calibration stickers. This change was requested because the existing practice of affixing calibration stickers directly to the instruments tends to obscure portions of the meters and the stickers are difficult to remove, in addition, occasional problems with stickers becoming detached or illegible have occurred.
2.0 EVALUATION SNC is committed to Regulatory Guide 1.30, " Quality Assurance Requirements for the Installation, inspection, and Testing of instrumeritation and Electric Equipment," dated August 11,1972, which in tum, references ANSI N45.2.4-1972 " Installation, inspection and Testing Requirements for Instrumentation and Electric Equipment During the Conttruction of Nuclear Power Generating Stations." Section 6.2.1 for tests of installed equipment specifies, in i part, *ltems requiring calibration shall be tagged or labeled on completion indicating date of l calibration and identity of person that performed the calibration." The requested change to the i FNP QA Program Description is:
With the exceptions listed below, Southem Nuclear Operating Company complies with Regulatory Guide 1.30 as addressed in FSAR, section 17.2.
Exception is taken to ANSI N45.2.4 (1972) " Installation, inspection, and Testing Requirements for instrumentation and Electric Equipment During the Construction Phase of Nuclear Power Generating Stations", section 6.2.1, which states, in part: " Items requiring calibration shall be tagged or labeled on completion indicating date of calibration and identity of person that performed the calibration." installed process instruments at Plant Farley are identified by 9803300011 980324 PDR ADOCK 05000348 P PDR
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unique instrument numbers which are readable at the instrument. These j instrument numbers are traceable to calibration schedules and records. These calibration schedules or records contain the same information as required by ANSI N45.2.4(1972). These schedules or records are readily accessible to !
personnel who are required to check calibration status as required by goveming I procedures. These instruments are not tagged or labeled with calibration data. i Section ll, " Acceptance Criteria," of Standard Review Plan (SRP) Section 17.2, " Quality i Assurance During the Operational Phase," contains provisions for the use of attematives to the acceptance criteria contained in SRP 17.2 provided they are evaluated by the staff and are considered to be in compliance with pertinent NRC regulations. Criterion 12.5 of ERP 17.1, which is referenced in SRP 17.2, requires that measuring and test equipment be labeled or tagged or "othenese controlled" to indicate the due date of the next calibration. Based on the staffs review, it was determined that SNC's proposed change is an acceptable altemative to tagging installed process instruments with calibration data in that:
- 1. unique instrument numbers are readable at the instrument,
- 2. the instrument numbers are traceable to calibration schedules and records,
- 3. the calibration schedules and records contain the same information as required by ANSI j N45.2.4-1972,
- 4. these schedules and records are readily accessible to personnel who are required to check calibration status as required by goveming procedures, and
- 5. the above altemative to tagging or labeling installed process instruments with calibration data is "otherwise controlled" by its description in the requested change to the FNP QA Program Description.
3.0 CONCLUSION
The staff finds that the requested change to maintain the calibration information required by !
I ANSI N45.2.4-1972 for the installed process instruments requiring calibration in a log / data base represents an acceptable attemative to the acceptance criterion contained in SRP Section 17.2.
The proposed changes are acceptable and continue to meet the pertinent requirements of 10 CFR Part 50 Appendix B.
PrincipalContributor: R. Smith Date: March 24, 1998 T*
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