Deficiency Rept on 780620,0815 & 1016:potential Exists to Render Diesel Generator 1C & 1-2A Inoperable If Loss of Offsite Power or LOCA Occurs.Failure Could Leave Entire Plant W/No River Water Pumps AvailableML19276E680 |
Person / Time |
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Site: |
Farley |
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Issue date: |
11/17/1978 |
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From: |
ALABAMA POWER CO. |
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To: |
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Shared Package |
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ML19276E678 |
List: |
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References |
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NUDOCS 7903200245 |
Download: ML19276E680 (8) |
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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20211M6491997-10-0808 October 1997 Addenda 1 to Part 21 Rept Re Weldments on Opposed Piston & Coltec-Pielstick Emergency stand-by Diesel gen-set lube-oil & Jacket Water Piping Sys.Revised List of Potentially Affected Utils to Include Asterisked Utils,Submitted ML20211H7911997-09-30030 September 1997 Part 21 Rept Re Failure of Weldment Associated w/lube-oil Piping Sys on 970804 at Millstone,Unit 2.Root Cause Is Not Yet Known.Quality of Weldment Is Being Considered.Listed Util Sites Affected ML20077C2801994-11-21021 November 1994 Deficiency Rept Re Defective Yokes P/N 342849 Mfg by Copes- Vulcan,Inc.Affected Utilities Notified & Defective Yokes Will Be replaced.Copes-Vulcan Also re-inspected All Yokes in Inventory & Verified Yokes Acceptability ML18038A8971994-09-0707 September 1994 Part 21 Rept Re Defect in Latching Mechanism of Potter & Brumfield Relay on C&D High Voltage Shut Down Alarm Assembly Printed Circuit Boards.Pull Test on Relay Reset Button Incorporated Into Receiving Insp Procedures ML20059H7721994-01-17017 January 1994 Part 21 Rept Re Virginia Power Notifying Fairbands Morse Via Failure Analysis Rept NESML-Q-058 of Defective Air Start Distributor cam,16104412 ML20059F2631994-01-0707 January 1994 Part 21 Rept Re Air Start Distributor Cam Mfg by Fairbanks Morse.Mfg Suggests That Site Referenced in Encl App I Inspect Air Start Distributor Cam as Soon as Practical ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20090L8801992-03-18018 March 1992 Part 21 Re Cracked Piston Castings Received from Acme Foundry,Fairbanks Morse & General Casting.Magnetic Particle Insp of All Pistons Will Be Performed.List of Affected Plants Encl ML20058A7401990-10-19019 October 1990 Part 21 Rept Re Loose Motor Lead Connections on New Limitorque Motor Operators.List of Loose Connections Encl ML20012C1051990-03-0707 March 1990 Part 21 Rept Re Several Failures of Fairbanks Morse Engine Div Piston Pins/Bushings on Upper Pistons.Caused by Incorrect Surface Pattern on Piston Pins.Piston Pins Under Listed Purchase Orders to Be Removed & Replaced ML20151Y8141986-02-0404 February 1986 Part 21 Rept Re Colt-Pielstick Engine Tripping Out on High Speed When Started for Test Purposes at Seabrook.Caused by Source of Air Pressure Staying On.Engines Will Be Modified to Positively Vent Air from Rack Boost Cylinder ML20138B1171985-12-0202 December 1985 Supplemental Part 21 Rept Re Lower Overrun Assemblies in Robertshaw Valves Installed on Diesel Generator Sets Possibly Failing Safe to Full Cooling Position. Cotter Pins Installed ML20126C6901985-06-0505 June 1985 Part 21 Rept Re Generator Failure.Concurs W/Encl Louis Allis That Interpolar Connectors Be Removed ML20102A6721985-02-0404 February 1985 Part 21 Rept Re Failure of post-tensioned Tendon on Plant. Investigation Revealed Another Tendon Anchor Cracked But Not Failed.Anchorages Furnished to Inryco by Western Concrete of California.Further Info Forthcoming W/Util Investigation ML20101P9361984-12-20020 December 1984 Part 21 Rept Re Fatigue Cracks on Fuel Injection Pump Delivery Valve Holders of PC-2 & PC-2.3 Emergency Diesel Generators.All Valve Holders W/Improper Radius Will Be Replaced ST-HL-AE-1141, Part 21 Rept Re Capacitor Terminations Used in GE ferro- Resonant Transformers Utilized in Westinghouse Vital 7.5 Kva Inverters.Initially Reported on 840913.Technical Bulletin Issued W/Instructions for Proper Connection of Capacitors1984-09-14014 September 1984 Part 21 Rept Re Capacitor Terminations Used in GE ferro- Resonant Transformers Utilized in Westinghouse Vital 7.5 Kva Inverters.Initially Reported on 840913.Technical Bulletin Issued W/Instructions for Proper Connection of Capacitors ML20092D9711984-06-15015 June 1984 Part 21 Rept Re Thermal Nonrepeatability & Other Calibr Errors in Barton Lot 1 Transmitters.Initially Reported on 840615.Transmitter Defects Identified & Expected Error Deviations Calculated.Utils Notified ML20010C6111981-08-14014 August 1981 Part 21 Rept Re Potential for Stress Corrosion Cracking of Anchor Bolts,Originally Reported on 810813.Utils That Have Plants for Which Vendor Has Supports & Restraints Design Responsibility Will Be Notified of Problem ML20010E2211981-05-26026 May 1981 Interim Deficiency Rept Re Vol Control Tank Level Instrumentation Control Sys Interaction W/Protection Sys, Initially Reported 810522.Plant Procedures Being Reviewed to Assure Operator Alert.Rept to Follow ML19345D4951980-12-0808 December 1980 Initial Deficiency Rept Re 800814 Hydrogen Dilution Fan 2B Trip.Caused by Blade Mounting Bolt Fracture.Fan Hubs & Blades Returned to Joy Mfg Co for Testing ML19332A0151980-08-20020 August 1980 Deficiency Evaluation Rept Re Westinghouse Centrifugal Charging Pump Operation Following Secondary Side High Energy Line Rupture.Design Change Implemented to Remove Safety Injection Initiation Closure Signal from Isolation Valves ML19330B7961980-07-22022 July 1980 Part 21 Rept Re GE Medium Voltage Penetrations.On 800620,air Inside Containment Found Escaping Through Three Penetration Modules Into Auxiliary Bldg.Testing Revealed Leakage Problem in All Six Medium Voltage Penetrations ML19318A0791980-06-13013 June 1980 Interim Deficiency Rept Re Unreacted Lime in Waste Settling Pond Causing Ph to Exceed Upper Limit.Caused by Discharge of Clarified Water Which Dissolved Calcium Sulfate Layer Over Lime.Discharge Terminated & Acid Will Be Added ML19320C4561980-06-13013 June 1980 Part 21 Rept Re Westinghouse Review of Safety Injection Termination Criteria Following Secondary Side High Energy Line Rupture W/Potential for Damage to Centrifugal Charging Pumps.Concerns Are Applicable to Facility ML19296C2941980-02-0505 February 1980 Deficiency Rept Re Undetectable Failures in Engineered Safety Features Actuation Sys.Util Will Incorporate Test Sequence Using Recommended Westinghouse Test Sequence. Design Change Will Permit Monitoring of Breaker Position ML19260D5581980-01-11011 January 1980 Deficiency Rept Re Discrepancies in ASME Code Sys.Cause Unstated.Valves Will Be Replaced or Upgraded to Class 2 by Obtaining Proper Documentation from Manufacturer ML19276E6801978-11-17017 November 1978 Deficiency Rept on 780620,0815 & 1016:potential Exists to Render Diesel Generator 1C & 1-2A Inoperable If Loss of Offsite Power or LOCA Occurs.Failure Could Leave Entire Plant W/No River Water Pumps Available 1997-09-30
[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
[Table view] |
Text
. i A .
JOSEPH M. FARLEY NUCLEAR PLANT-UNIT 2 ALABAMA POWER COMPANY REPORT OF 10CFR50.55(e) DEFICIENCY A design condition has been detected which can render Diesel Generator lC and 1-2A inoperable when both Farley units are in operation and loss-of-offsite power (LOSP) on both units or LOSP on both units and LOCA on one unit occur.
Presently, as shown in , Figure 1, Diesel Generator 1C has its auxiliaries powered from emergency Motor Control Center (MCC) IN. MCC IN gets its power supply from emergency 600V Load Center 1R. The 600V Load Center 1R is a shared load center capable of being energized from either unit. When it is energized from Unit 1 it is supplied from the 4KV Bus lH through Station Service Transformer 1R. When it is energized from Unit 2 it is supplied from the Unit 2 4 KV Cus 2H through Station Service Transformer 2R. The two 600V incoming breakers of 600V Load Center 1R are key interlocked so that only one can be closed at any time. The alignment of Load Center 1R to Unit 1 er Unit 2 can be performed manually only, from the local control panel located in the diesel building.
As shown in Figure 1, Diesel Generator 1-2A has its auxiliaries powered from emergency MCC 1S. MCC 15 is a shared MCC capable of being energized from either unit. When it is energized from Unit 1 it is supplied from the Unit 1600V Load Center 10, which in turn is powered from Unit 14KV Bus IF through Station Service Trans former ID. When it is energized frcm Unit 2 it is supplied from the Unit 2 600V Load Center 2D, which in turn is powered from Unit 2 4 KV Bus 2F thrcugh Station Service Transformer 2D. The alignment of MCC 15 to Unit 1 or Unit 2 can be performed manually only from the MCC 1S located in the diesel building.
Under LOSP on both units or LOSP on both units and LOCA on Unit 1, Diesel IC is a source of power for Unit 2 Train A hot shutdown loads, while Diesel 1-2A is a source of power for Unit 1 LOCA loads. If, at the accident occurrence, 600V Load Center 1R is aligned te Unit 1, it will be deenergized since 4 KV Bus lH is deenergized, and Diesel Generator 1C loses its auxiliaries. At this time, MCC IN 7 903 2 0 0 g2e/di
.p_
has a be connected to Station Service Transformer 2R by the manual operation of the key interlocked incoming breakers of 600V Load Center 1R. Diesel genera tor manu-facturer has specified that diesel genera tor can run without its auxiliaries for one minute if the engine is at operating tempera ture, or for three minutes from cold start. If the manual changeover of power source to llCC 1R cannot be accomplished in the specified time, Diesel b nerator 1C could be automatically tripped bec.use of low lube oil pressure, or damaged beca':se of loss of cooling water. The high cooling water temperature is alarmed, but does not trip the diesel generator auto-mati ally under accident conditions.
If Diesel Generator IC is disabled, no source of power for Unit 2 Train A safeguard loads will be availchle, and a single failure on Unit 2 Train B can render Unit 2 incapable of being shutdown. (4 KV Bus lH is deenergized under the postulated conditions since the tie breaker between 4 KV Bus IF and 4 KV Bus lH is open.)
If, under the above conditions f4CC 1S is aligned to Unit 2, it will be deenergized and Diesel Generator 1-2A loses its auxiliaries. If Diesel Generator 1-2A is disabled, no source of power for Unit 1 Train A LOCA loads will be available.
In this case, if we apply the single failure criterion to Unit 1 Train B instead of Unit 2 Train B, Unit 2 will meet the hot shutdown requirements, while Unit I cannot neet the LOCA requirements.
Under LOSP on both units and LOCA on Unit 2, Diesel Generator 1C is the source of power for Unit 1 Train A hot shutdown loads, while Diesel Generator 1-2A is the source of power for Unit 2 LOCA loads. If, at the accident occurrence 600V Load Center 1R is aligned to Unit 2, it will be deenergized since 4 KV Bus 2H is deenergized, and Diesel Generator 1C loses its auxiliaries. Diesel Generator 1C will be disabled, no source of power for Unit 1 Train A safeguard loads will be '
available, and a single failure on Unit 1 Train B can render Unit 1 incapable of being .
shutdown. (4 KV Bus 2H is deenergized under the postulated conditions since the tie breaker between 4KV Bus 2F and 4 KV Bus 2H is open.)
/
.=
If, under the above conditions fiCC 15 is aligned to Unit 1, it will be deenergized, Diesel Generator 1-2A disabled, and no source of power for Unit 2 Train A LOCA loads will be available. In this case, if we hpply the single failure criterion to linit 2 Train B instead of Unit 1 Train B, Unit 1 will meet the hot shutdown requirements, while Unit 2 cannot meet the LOCA requirements.
Thus, under the criteria of 10CFRCO.55(e) the referenced problem constitutes a significant deficiency. Note that the referenced problem is only a safety pro-blem when Unit I and Unit 2 are operated simultaneously.
A second problem identified concerning the diesel generator relates to the following. The Farley Nuclear Plant is intended to'be designed to accommodate the Loss of Pond Dam along with Loss-of-Offsite Power and a single failure. Under this event, the river water systems will be automatically diverted to the wet pit which supplies suction to service water pumps.
For this event, for Unit 1 operation alone, a minimum of 2 river water pumps will be required. Therefore, to accommodate single failure, 4 river water pumps
~
are powered from the diesel generator system.
For Unit 1 and Unit 2 operation, a minimum of 4 river water pumps are required ar,d to accommodate single failure, 8 river water pumps are to be sequenced onto the diesel generator system.
With Unit 1 in operation alone two (2) emergency power sources (diesel generator 1C-Train A and diesel generator 2C-Train B) are dedicated to the River Ma ter Sys tem. Four river water pumps with automatic starting capability are
'available so that in the event of single failure at least 2 river water pumps will Therefore, start, meeting the minimum requirements for safe shutdown of the unit.
k there is no deficiency for Unit 1 operation.
t t However, af ter two units go into operation, only one emergency power source (diesel generator 2C-Train B) is dedicated to the River Water System, hence only
i -c-4 river water pumps with automatic capability would be available. The failure of diesel generator 2C could leave the entire plant with no river water pumps available. This deviates from our commitment in the FSAR and does not ccet the minimum River Water System availability requirements for safe shutdown of both Uni ts . R'edesign to provide a minitrum of four river water pumps on Loss of Offsi te Power is undentay.
To correct the first problem the following corrective action will be taken (refer to Figure 2):
(1) The key interlock feature of breakers ER02 and ER05 on Load Center IP. will be removed and replaced by an electrical interlock, so that only one of the two breakers could be closed at any time.
The electrical circuitry of these breakers 1.ill be changed to accomplish the following: (a) automatically connect Locd Center 1R to Bus IH (ER02 closed and ER05 open) when Diesel Gnerator 1C is aligned to Unit 1 (DH07 on Bus lH closed); (b) automatically connect Load Center 1R to Bus 2H (ER05 closed and ER02 open) when Diesel Generator 1C is aligned to Unit 2 (DH07 on Bus 2H closed).
(2) !!anual transfer switch on f:CC 1S will be removed and the incoming feeders from Load Centers ID and 2D will be solidly connected to the !!CC.
. Breakers EDl3 on Load Center ID and ED13 on Load Center 20 will be electricaily interlocked, so that only one of the two breakers could be closed at any time. The electrical circuitry of these breakers will be changed to accomplish the following: (a) automatically connect fiCC IS to Load Center 10 (E013 on Load Center ID closed and EDl3 on Load Center 2D open) when Diesel Generator 1-2A is alignet to Unit 1 (DF08 on Bus IF closed), (b) automatically connect f4CC IS to Load Center 2D (E013 on Load Center 20 closed and EDl3 on Load Center 10 open) when Diesel Generator 1-2A is aligned to Uni t 2 (DF08 on Bus 2F closed).
In order to correct the second problem, the following changes to the logic, schematic, and wiring concerning the diesel generator are proposed (see figures 1, 2 and 3):
/
_5_
(1) Af ter the sequencer has added the LOSP loads to Bus IF, the 4 KV Bus IF will furnish power to the 4 KV Bus 1H. Three Unit 1 Train A river water pumps (Numbers 8, 9, and 10) will be started on Bus lH in sequence.
(2) The LOSP sequencer on Bus 2F will be modified to eliminate containment cooler 2B from being added automatically. As in the pas t, containment cooler 2A will be automatically applied to Bus 2F. Af ter LOSP sequencer has added LOSP loads to Bus 2F, the river water pumps sequencer on Bus 2H will be unblocked to enable one river water pump (Number 6) to automatically be applied to Bus 2H.
(3) Should diesel generator 2C fail, diesel generator 1B will furnish power to Bus lJ and diesel generator 2B will furnish power to Bus 2J after the sequencers on Buses 1G and 2G have had LOSP loads added. Two river water pumps (Numbers 4 and 5) will start on Bus lJ and two river water pumps (Numbers 1 and 2) will start on Bus 2J.
(4) The existing feature of the diesel generator 2C working like a backup for diesel generator 18 or 2B if ei ther fails to furnish power to the hot shutdown load will be removed. This feature is not required to meet single failure criteria.
In the design event discussed, the river water system will be automatically diverted to the pond wet pit which supplies suction to the service water pumps.
Additional stop logs will be addert to the pond wet pit to ensure that adequate wet pit level is maintained.
The above changes will ensure that the plant has adequate river water supply with both units operating. Both problems will be corrected prior to the issuance of the Unit 2 Operating License.
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/
MCC IP ] eel 4 MCC iT ,
MCC 2T
___._m.__
ab b g)b_.i '
- 2 E k
Diesel 1B Auxiliaries Diese; 2C Auxiliaries
._bb.6 b Q i h
Diesel 28 Auxiliaries FIGURE 3 PRESENT CONFIGURATION -TRAIN B
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(The corrective action necessitates no change to this figure.)