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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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BAffTY EYAlilAT1DN BY THE OFFICE OF NUCLEAR REACTOR REGULATION R1Quf.AI FOR RKTEAPAf TAT 10N OF EMERGENCY DIEREL GFMEBAIDE TECHNICAL SPECIFICATION 4_R.1.1.22.
FARLEY NUCLEAR PLANT. UNfTS 1 AND 2 DOCKET NOR. 60448 AND 50- 344 MCEDhDIBG h as tener of May 22,19g7. Sowhern Ncioar Operahng Comparty (boensee) requested an enorpretaban of the >chncal Mm (78) concomme the load repcbon testeg for the two throd energency deoel generssors (EDGs).12A and IC. at Farley Nuclear Plant (Farley).
Unas 1 ml 2 Portners portone of each ins TS Survesence Requrement (SR) 4.8.1.1.2.e reeers moee shared EDGs to menstand a 1200 2400 kW load repcbon every Ave years. The teenmee hee been performme me edycs SR by shgrung one of the shared EDGs (EDG 12A) to uns 1. mi anyung me amor EDO (EDO 1C) to Und 2 Sm me leed repocton lost a pertermed to verdy the operetzer:y of the EDG voltage regulator WW governor. me teel does not depend on the loads to whch these unas are connected. The I aconeee careends mat toesn0 com EDGs 12A and 1C on a per und TS basis would represent seepers and eassessee noseng of the EDGs and a not necessary. Thus, the beansee r archmed shat as curvors noseng memod sabshes the TS SR 4 8.1.1.2 e provtsson for the anaos EDGs at Fartey However, me resadent nspector reviewed the bconsee's evaluation and Gearood men me teensee's conctusaon, and requested NRR to interpret l TS$448112e E.
OfALM&IElf There are 6,e eeeef generosors tot ewo unas at Farley. Tram 8 of the two unas has one large (4015 kW) em EDO tot each uru (desagnated as 18 and 28) As the rest of the desel
} ponerators. one type 4015 kW (12A) and two smas 2450 kW (1C and 2C), are shared by both anos are are provided men yterlocks to prevert them Irom suppfying power to Unit 1 and Unrt 2
! esumAansoimfy Tee EDGs (12A and IC) among de three shared chesels are serving Train A
- of eeer urus, artes deoef 2C a mM for stahon tdackcut everta and suppies power to the F
B ran of eeer urns Sence she 8 ram has no shared EDGs the interpretation of TS SR 4 81 12 e apphoe to the shared EDGs e the A trari.
Currere 54 4 81 12 e of me TS at Fartey for Unas 1 and 2 requres that:
At Isaat once per 5 years, on a staggered base, by ventyng that the emergency eseef generator can repoca a load of 1200 2400 kW without tnoping. The ernergency eeeef generseer output treakarts) must remam closed such that the
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9807150092 980624 PDR FOIA UNNERST98 ,155 PDR
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RAFETY EVALUATION RY TNf OFFICE OF NUCLEAM REACTOR R*O_QLATION REQUE.Af 7QM INTEAMtf TAT)ON OF EMERGENCY Dif SEL .GENEAATOR TECHNICAL RPECiflCATION LR111e .
FAALEY NUCLEAR PLANT. UNITR 1 AND 2 DOCKETNOLA0448AND50344 M
Wi es tueer of May 22.1997. So Ahom Nudear Operaeng Company (hcensee) requested an ensrpresamen of me Mcfrucat apardem (TS) concenung the load resecuon testeg for the two enwed emergency seeef generasors (EDGs).12A and IC, at Farley Nucaser Plant (Fariey).
Lhes I rd 2 Portners portons of each ure TS Survesence Requrement (SR) 4.8.1.1.2.e reeers moes enered EDGs to wehetand a 1200 2400 kWload rerecuon every Ave years. The tsensee has boon perlormng me subpect SR by shgnng one of the shared EDGs (EDG 12A) to tw 1. rd asynng me omer EDO (EDO 1C) to Una 2 Sece me teed repecten test a periormed to verWy the opersbesty of the EDG vonage regulator ww govemer. me test does not depend on the loads to wtuch these unas are connected. The aseeee cornenes that tesang bom EDGE 12A and 1C on a per und TS basis would represent sothedere rid secesaw locang of she EDGs and a not necesswy Thus, the beensee caractuesd that as cwrert beseng method satsnes the TS SR 4 8.1.1.2 e provisen for the shared EDGs at Fartey However, she rewdent repector reviewed the beensee's evaluation and esarsed man she aconsee's condusen, and requested NRR to interpret TS SR 4 8112 e EX&LM&ICid There we eve seeef ponerasors for two unas at Farley. Tram B of the two units has one large (4075 kW) em EDO for each una (desagnated as 18 and 28) As the rest of the desel ponerammL one large 4075 kW (12A) and two smas 2850 kW (1C and 2C), are shared by both wies and we provided weh stortocks to prevent them from supplyng power to Unit 1 and Unrt 2 asnumaneoussy Too EDGs (12A and 1C) among We three shared desels are serving Train A of emer wut. utdo esmei 2C e -M for stauon War *rd events and supphes power to the 5 ten of esher wit Sece the 8 tan has no shared EDGs the interpretation of TS SR 4 81 12 e appees to she shared EDGs a the A traet Cwrort SR 4 81 12 e of she 78 at Farley for Unas 1 and 2 requres that:
At Isaet oas per 5 years, on a staggered bass, by wentyng that the emergency eseef genersect can repect a load of 1200-2400 kW unthout tnoping. The emergency e***l genersoor output breaker (s) must remam c$osed such that the ATTACHMENT 9807150092 980624 PDR FOIA UNNERST98 ,155 PDR
.. . j l
emergency diesel generator is connected to at least one emergency bus. Verify that all fuses and breakers on the energized emergency bus (es) are not tripped.
The generator voltage shall remain within 3330 and 4990 volts during and following the load rejection.
Each EDG is provided with an engine overspeed trip to prevent damage to the engine.
Recovery from the transient caused by the loss of a large load could cause the diesel engine to overspeed, which,if the overspeed is excessive, might result in a trip of the engine. Therefore.
TS SR 4.8.1.12.e'(i.e., the load rejection test)is prescribed to verify the ability of the EDG voltage regulator and govemor to respond such that voltage and frequency transients continue to remain within acceptable limits and the EDG does not trip during a load rejection.
Although EDGs 12A and 1C are designed to be shared between two units and each unit maintains a separate TS at Farley, the licensee has been performing the subject SR once per five years by stigning EDG 12A to a Unit 1 emergency bus and aligning EDG 1C to a Unit 2 emergency bus. The NRC inspector reviewed the above mentioned SR provision and questioned whether the shared EDGs should be tested for each unit twice in five years.
The licensee took the position that it is not necessary for each shared EDG to be aligned to each unit for testing for the following reasons:
- 1) The load rejection test is conducted to validate the EDG function by verifying the ability of the voltage regulator or govemor to maintain the load within acceptable limits during a load rejection. Thus, the test results depend on the equipment within the EDGs themselves, not on the EDG loads used for the test, if there is a problem with the EDG voltage regulator or govemor, it would be evident regardless of the loads that are connected to it or which unit the load came from.
- 2) When the staff granted the load rejection testing frequency from every 18 months to every five years as shown in the current TS SR 4.8.1.1.2.e. the testing was intended for each EDG on an EDG by EDG basis, not on a unit by unit basis.
- 3) If the shared EDGs are required to be tested on a per unit basis, the (shared) EDGs in i the A train would be performing the load rejection test twice as often as the (dedicated)
EDGs in the B train.
- 4) Having five diesel generators that have either an automatic or manual capability to load one of the two safety traias represents much greater flexibility than having four dedicated EDGs installed in a two trains as shown in the NRC's Standard TS. Thus, in j terms of reduced surveillance and testing requirements for EDGs, credit can be given to
! the Farley TS in order to avoid redundant testings.
l l Since the purpose of this surveillance is to demonstrate that the voltags regulator and govemor l In each EDG are performing correctly, TS SR 4.8.1.1.2.e for Units 1 and 2 at Farley tests the EDG themselves, not the EDG loads. Therefore, the staff concurs with ths licensee's interpretation that the testing requirement for the shared EDGs (12A and 10) in TS 4.8.1.1.2.e is satisfied by aligning these EDGs to either Unit 1 or Unit 2 independently, as long as tneir operability is confirmed once per five years. Subsequently, the licensee has submitted a TS amendment request to clanfy SR 4.8.1.1.2.e for the shared EDGs, which the staff is currently reviewing.
2-