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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML18096A6491992-04-23023 April 1992 Special Rept 92-4:on 920318,two Fire Barrier Penetrations Were Impaired to Support Turbine/Generator Design Change Work for Greater than Seven Days.Caused by Outage Related Activities.Penetrations Were Resealed on 920326 ML18094B3871990-04-0404 April 1990 Supplemental Special Rept 88-3-20:from 880720-900314 Addl Fire Penetration Seal Impairments Not Restored to Functional Status within 7 Days.Hourly Fire Watch Will Continue Until All Fire Protection Concerns Resolved ML18094A6541989-08-28028 August 1989 Special Rept:On 890805,06 & 08,sea Turtles Impinged on Circulating Water Sys Intake Trash Bars.Caused by Summer Migration of Turtles & Boating & Commercial Fishing Operations.Bars Cleaned Once Per Day ML18094A5551989-07-0505 July 1989 Special Rept 89-4:on 890622,automatic Actuation Feature for Fire Pumps Deactivated & Sensing Line for Pressure Transmitter Isolated.Caused by Inadequate Administrative Control.Second Pressure Sensing Tap to Be Installed ML18094A5481989-06-22022 June 1989 Ro:On 890622,automatic Actuation Feature for Fire Pumps Found Deactivated.Caused by Sensing Line Between Fire Pump Cross 1FP10 & 2FP10 Being Isolated & Precluding Automatic Initiation.Jockey Pump & Isolation Valves Replaced ML18093B1991988-10-0404 October 1988 Supplemental Special Rept 88-3-2:on 880713,25,28 & Between 0802-30 & 31-0930,impairment of Fire Barriers Discovered. Cause Could Not Be Positively Determined.Fire Watches Will Continue Until All Fire Protection Concerns Resolved ML18093B0621988-09-0606 September 1988 Special Rept 88-5:on 880817,several Fire Barrier Penetrations in Support of Design Mods During Current Refueling Outage Impaired for Greater than 7 Days.Hourly Fire Watches Will Continue Until Concerns Resolved ML18093A9691988-07-21021 July 1988 Ro:On 880715,two Loggerhead Sea Turtles Stranded on Circulating Water Sys Intake Trash Bars.Caused by Summer Migration Patterns.Trash Bar Observation Increased to at Least Once Per 2 H ML18093A8151988-04-21021 April 1988 Ro:On 880409,steam Generator Tube Plugged Due to Primary to Secondary Side Leakage & Leaking Explosive Plug Discovered on Hot Leg Side.Leaking Plug Drilled Out & Verified Intact 1992-04-23
[Table view] Category:LER)
MONTHYEARML18096A6491992-04-23023 April 1992 Special Rept 92-4:on 920318,two Fire Barrier Penetrations Were Impaired to Support Turbine/Generator Design Change Work for Greater than Seven Days.Caused by Outage Related Activities.Penetrations Were Resealed on 920326 ML18094B3871990-04-0404 April 1990 Supplemental Special Rept 88-3-20:from 880720-900314 Addl Fire Penetration Seal Impairments Not Restored to Functional Status within 7 Days.Hourly Fire Watch Will Continue Until All Fire Protection Concerns Resolved ML18094A6541989-08-28028 August 1989 Special Rept:On 890805,06 & 08,sea Turtles Impinged on Circulating Water Sys Intake Trash Bars.Caused by Summer Migration of Turtles & Boating & Commercial Fishing Operations.Bars Cleaned Once Per Day ML18094A5551989-07-0505 July 1989 Special Rept 89-4:on 890622,automatic Actuation Feature for Fire Pumps Deactivated & Sensing Line for Pressure Transmitter Isolated.Caused by Inadequate Administrative Control.Second Pressure Sensing Tap to Be Installed ML18094A5481989-06-22022 June 1989 Ro:On 890622,automatic Actuation Feature for Fire Pumps Found Deactivated.Caused by Sensing Line Between Fire Pump Cross 1FP10 & 2FP10 Being Isolated & Precluding Automatic Initiation.Jockey Pump & Isolation Valves Replaced ML18093B1991988-10-0404 October 1988 Supplemental Special Rept 88-3-2:on 880713,25,28 & Between 0802-30 & 31-0930,impairment of Fire Barriers Discovered. Cause Could Not Be Positively Determined.Fire Watches Will Continue Until All Fire Protection Concerns Resolved ML18093B0621988-09-0606 September 1988 Special Rept 88-5:on 880817,several Fire Barrier Penetrations in Support of Design Mods During Current Refueling Outage Impaired for Greater than 7 Days.Hourly Fire Watches Will Continue Until Concerns Resolved ML18093A9691988-07-21021 July 1988 Ro:On 880715,two Loggerhead Sea Turtles Stranded on Circulating Water Sys Intake Trash Bars.Caused by Summer Migration Patterns.Trash Bar Observation Increased to at Least Once Per 2 H ML18093A8151988-04-21021 April 1988 Ro:On 880409,steam Generator Tube Plugged Due to Primary to Secondary Side Leakage & Leaking Explosive Plug Discovered on Hot Leg Side.Leaking Plug Drilled Out & Verified Intact 1992-04-23
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARLR-N99-0449, Monthly Operating Rept for Sept 1999 for Salem,Unit 2.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 2.With LR-N99-0448, Monthly Operating Rept for Sept 1999 for Salem,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 1.With ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20212B7221999-09-14014 September 1999 Safety Evaluation Supporting Amends 224 & 205 to Licenses DPR-70 & DPR-75,respectively LR-N99-0415, Monthly Operating Rept for Aug 1999 for Salem,Unit 1.With 9909131999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 1.With 990913 LR-N99-0416, Monthly Operating Rept for Aug 1999 for Salem,Unit 2.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 2.With ML18107A5311999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 1.With 990913 05000272/LER-1999-006-02, :on 990729,determined That SG Blowdown RMs Setpoint Was non-conservative.Caused by Inadequate ACs for Incorporating Original Plant Licensing Data Into Plant Procedures.Blowdown Will Be Restricted.With1999-08-26026 August 1999
- on 990729,determined That SG Blowdown RMs Setpoint Was non-conservative.Caused by Inadequate ACs for Incorporating Original Plant Licensing Data Into Plant Procedures.Blowdown Will Be Restricted.With
ML18107A5201999-08-12012 August 1999 Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO 9) Second Interval,Second Period, First Outage (96RF) LR-N99-0380, Monthly Operating Rept for July 1999 for Salem,Unit 2.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 2.With ML18107A4811999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 1.With 990813 Ltr LR-N99-0379, Monthly Operating Rept for July 1999 for Salem,Unit 1.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 1.With 05000311/LER-1999-008, :on 990714,determined That Limit Switch Cables Were Subject to Multiple Hot Shorts in Same Fire Area.Caused by Inadequate Original Post Fire Safe Shutdown Analysis.All Limit Switch Cables for MOVs Were Reviewed.With1999-07-28028 July 1999
- on 990714,determined That Limit Switch Cables Were Subject to Multiple Hot Shorts in Same Fire Area.Caused by Inadequate Original Post Fire Safe Shutdown Analysis.All Limit Switch Cables for MOVs Were Reviewed.With
ML20210B7371999-07-21021 July 1999 Safety Evaluation Supporting Amends 223 & 204 to Licenses DPR-70 & DPR-75,respectively ML18107A4411999-07-0909 July 1999 SER Denying Licensee 980730 & 990222 Requests to Revise TS 3/4.7.6, Control Room Emergency Air Conditioning Sys, & Associated Bases to Change Acceptable Criteria for Control Room Emergency Air Conditioning System 05000311/LER-1999-007, :on 990605,surveillance for Quadrant Power Tilt Ratio (QPTR) Was Missed.Caused by Human Error.Qptr Calculation Was Performed & Personnel Involved Have Been Held Accountable IAW Pse&G Policies.With1999-07-0606 July 1999
- on 990605,surveillance for Quadrant Power Tilt Ratio (QPTR) Was Missed.Caused by Human Error.Qptr Calculation Was Performed & Personnel Involved Have Been Held Accountable IAW Pse&G Policies.With
05000272/LER-1999-005-02, :on 990605,11 Containment Declared Inoperable. Caused by Valves 11SW72 & 11SW223 Both Leaking.Procedure S1.OP-ST.SW-0010(Q) Was Enhanced to Provide Specific Instructions to Ensure Proper Sequencing.With1999-07-0202 July 1999
- on 990605,11 Containment Declared Inoperable. Caused by Valves 11SW72 & 11SW223 Both Leaking.Procedure S1.OP-ST.SW-0010(Q) Was Enhanced to Provide Specific Instructions to Ensure Proper Sequencing.With
05000311/LER-1999-002, :on 990405,determined That 2SA118 Failed as Found Leakrate Test.Caused by Foreign Matl Found in 2SA118 valve.2SA118 Valve Was Cycled Several Times & Seat Area Was Air Blown in Order to Displace Foreign Matl.With1999-07-0101 July 1999
- on 990405,determined That 2SA118 Failed as Found Leakrate Test.Caused by Foreign Matl Found in 2SA118 valve.2SA118 Valve Was Cycled Several Times & Seat Area Was Air Blown in Order to Displace Foreign Matl.With
ML18107A5211999-07-0101 July 1999 Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO 10) Second Interval,Second Period,Second Outage (99RF) 05000311/LER-1999-006, :on 990501,determined That There Was No Flow in One of Four Injection Legs.Caused by Sticking of Valve in Safety Injection Discharge Line to 21 Cold Leg.Valve Was Cut Out of Sys & Replaced.With1999-07-0101 July 1999
- on 990501,determined That There Was No Flow in One of Four Injection Legs.Caused by Sticking of Valve in Safety Injection Discharge Line to 21 Cold Leg.Valve Was Cut Out of Sys & Replaced.With
ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept LR-N99-0325, Monthly Operating Rept for June 1999 for Salem,Unit 2.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 2.With LR-N99-0324, Monthly Operating Rept for June 1999 for Salem,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 1.With ML18107A4341999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 2.With 990713 Ltr ML18107A4161999-06-23023 June 1999 Safety Evaluation Accepting Licensee Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions 05000272/LER-1999-004-02, :on 990520,reactor Tripped from 100% Power,Due to Negative Flux Trip Signal from Nuclear Instrumentation. Cause Has Not Been Determined.Discoloration Was Identified on One of Penetrations.With1999-06-17017 June 1999
- on 990520,reactor Tripped from 100% Power,Due to Negative Flux Trip Signal from Nuclear Instrumentation. Cause Has Not Been Determined.Discoloration Was Identified on One of Penetrations.With
ML18107A3751999-06-15015 June 1999 Safety Evaluation Accepting Licensee Request for Approval of Proposed Changes to Nuclear Business Unit EP for Hope Creek & Salem Generating Stations,Iaw 10CFR50.54(q) 05000272/LER-1999-003-02, :on 990513,unplanned Entry Into TS 3.0.3 Was Made.Caused by Human error.Re-positioned Creacs Supply Fan Selector Switches & Revised Procedures S1 & S2.OP-ST.SSP-0001(Q).With1999-06-0909 June 1999
- on 990513,unplanned Entry Into TS 3.0.3 Was Made.Caused by Human error.Re-positioned Creacs Supply Fan Selector Switches & Revised Procedures S1 & S2.OP-ST.SSP-0001(Q).With
05000311/LER-1999-005-01, :on 990504,failure to Meet TS Action Statement Requirements for High Oxygen Concentration in Waste Gas Holdup Sys Occurred.Caused by Inability of Operators. Existing Procedures Will Be Evaluated.With1999-06-0202 June 1999
- on 990504,failure to Meet TS Action Statement Requirements for High Oxygen Concentration in Waste Gas Holdup Sys Occurred.Caused by Inability of Operators. Existing Procedures Will Be Evaluated.With
ML18107A3441999-06-0101 June 1999 Interim Part 21 Rept Re Premature Over Voltage Protection Actuation in Circuit Specific Application in Dc Power Supply.Testing & Evaluation Activities Will Be Completed on 990716 LR-N99-0278, Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 2.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 2.With LR-N99-0275, Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 1.With ML18107A3111999-05-21021 May 1999 SER Accepting GL-88-20,suppl 4, IPEEEs for Severe Accident Vulnerabilities, for Plant,Units 1 & 2 05000272/LER-1999-002-02, :on 990413,determined That Number 12 Auxiliary Bldg Exhaust Fan Was Rotating Backwards.Caused by mis-wiring of Motor Due to Human Error by Maint technician.Mis-wiring Was Corrected & Fan Was Returned to Svc.With1999-05-12012 May 1999
- on 990413,determined That Number 12 Auxiliary Bldg Exhaust Fan Was Rotating Backwards.Caused by mis-wiring of Motor Due to Human Error by Maint technician.Mis-wiring Was Corrected & Fan Was Returned to Svc.With
05000311/LER-1999-004-01, :on 990411,automatic Actuation of ESF Occurred During Reactor Vessel Head Removal in Support of Refueling Operations.Caused by High Radiation Condition.Containment Atmosphere Was Monitored.With1999-05-10010 May 1999
- on 990411,automatic Actuation of ESF Occurred During Reactor Vessel Head Removal in Support of Refueling Operations.Caused by High Radiation Condition.Containment Atmosphere Was Monitored.With
ML20206H2631999-05-0404 May 1999 Safety Evaluation Supporting Amend 222 to License DPR-70 05000311/LER-1999-003-01, :on 990406,all Salem Unit 2 Chillers Rendered Inoperable.Caused by Human Error.Lessons Learned from Event Were Communicated to All Operators by Including Them in Night Orders.With1999-05-0404 May 1999
- on 990406,all Salem Unit 2 Chillers Rendered Inoperable.Caused by Human Error.Lessons Learned from Event Were Communicated to All Operators by Including Them in Night Orders.With
05000311/LER-1999-002-01, :on 990405,determined That Containment Isolation Valve Failed as Found Leakrate Test.Caused by Foreign Matl Blocking Valves from Closing.Check Valve Mechanically Agitated.With1999-05-0303 May 1999
- on 990405,determined That Containment Isolation Valve Failed as Found Leakrate Test.Caused by Foreign Matl Blocking Valves from Closing.Check Valve Mechanically Agitated.With
LR-N99-0226, Monthly Operating Rept for Apr 1999 for Salem Unit 2.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Salem Unit 2.With LR-N99-0225, Monthly Operating Rept for Apr 1999 for Salem Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Salem Unit 1.With ML18107A3711999-04-30030 April 1999 Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1 ML18107A3151999-04-30030 April 1999 Submittal-Only Screening Review of Salem Generating Station Individual Plant Exam for External Events (Seismic Portion), Rev 1 ML20206B4761999-04-26026 April 1999 Safety Evaluation Supporting Amends 220 & 202 to Licenses DPR-70 & DPR-75,respectively 05000311/LER-1999-001-03, :on 990330,MSSV Failed Lift Set Test.Caused by Setpoint Variance Which Is Result of Aging.Valves Were Adjusted & Retested to Ensure TS Tolerance.With1999-04-23023 April 1999
- on 990330,MSSV Failed Lift Set Test.Caused by Setpoint Variance Which Is Result of Aging.Valves Were Adjusted & Retested to Ensure TS Tolerance.With
ML18107A1791999-04-15015 April 1999 Safety Evaluation Supporting Changes to QA Program in That QA Program Continues to Meet Requirements of App B to 10CFR50 ML18107A1601999-04-0707 April 1999 Safety Evaluation Accepting Request for Exemption from Update Requirements of 10CFR50.71(e)(4) ML18107A2881999-04-0707 April 1999 Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11 LR-N99-0176, Monthly Operating Rept for Mar 1999 for Salem,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Salem,Unit 1.With LR-N99-0177, Monthly Operating Rept for Mar 1999 for Salem,Unit 2.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Salem,Unit 2.With 05000272/LER-1999-001-02, :on 990228,reactor Scram Was Noted as Result of Turbine Trip.Caused by Operator Error.Lesson Plans Revised to Explicitly Demonstrate Manner in Which Valve Functions. with1999-03-29029 March 1999
- on 990228,reactor Scram Was Noted as Result of Turbine Trip.Caused by Operator Error.Lesson Plans Revised to Explicitly Demonstrate Manner in Which Valve Functions. with
1999-09-30
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e CPS~G Public Service Electric arc Gas ~~Mpary ?.O. Box 236 Har.coci<.s Bridge. Ne-,*, Je~sey 08038-0236 Nuclear Business Unit NOV ;:; 1 .:' .J l LR-N970729 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 SPECIAL REPORT 311/97-015-00 SALEM GENERATING STATION - UNIT 2 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Gentlemen:
This Special Report regarding a valid failure of the 2A Emergency Diesel Generator is being submitted pursuant to the requirements of Technical Specification 4.8.1.1.4.
Sincerely,
~~
A. C. Bakken Ill General Manager Salem Operations Attachment I- I.
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SPECIAL REPORT 3111-015 LR-N970729 PLANT IDENTIFICATION Salem Generating Station - Unit 2 Facility Operating License No. DPR-75 Docket No. 50-311 DESCRIPTION OF OCCURRENCE On 10/22/97 2.'\ Emergency Diesel Generator (EOG), an ALCO 251 engine, was being started in accordance with monthly surveillance test S2. OP-ST. DG-0001.
Approximately 6 seconds into the start sequence the operators decided that the start did not sound like a normal start sequence. At this point the operators manually interrupted the start sequence of the diesel. The engin~ was stopped before the over crank circuit of 10 seconds stopped the engine. The diesel was then declared inoperable.
PLANT CONDITIONS:
Unit 2 was operating in Mode 1 at approximately 100 % power. 28 and 2C ED G's were operable at the time of 2A EDG's failure to start.
REPORTING REQUIREMENT:
This failure is being reported as required by Technical Specification 4.8.1.1.4 which states:
"All diesel generator failures, valid or non-valid, shall be reported to the Commission in a Special Report pursuant to Specification 6.9.2 within 30 days.
Reports of diesel failures shall include the information recommended in Regulatory Position C.3.b of Regulatory Guide 1.108, Revision 1,. August 1977.
If the number of failures in the last 100 valid. tests (on a per nuclear unit basis) is greater than or equal to 7, the report shall be supplemented to include additional information recommended in Regulatory Position C.3.b of Regulatory Guide 1.108, Revision 1, August 1977."
SPECIAL REPORT 311,-015 LR-N970729 REPORT DETAILS:
The following information is provided as specified in Regulatory Position C.3.b of regulatory Guide 1.108, Revision 1, August 1977:
- 1. Diesel Generator Unit Involved: 2A
- 2. Number of Failures in the Last 100 tests:
a) This was the fourth failure of the 2A EDG in the last 100 valid tests of the 2A EOG.
b) This was the first failure of a Unit 2 EOG in the last 100 valid tests of the 2A, 28, and 2C EDG's in total. .
- 3. Cause of the Failure:
The cause of the unusual starting sequence could not be determined by testing and/or inspections. The diesel restarted properly on three subsequent attempts.
The most likely causes of the abnormal noise during the start sequence were: (1) moisture build up in the starting air headers; and/or (2) improper operation of the #3 air start motor. The moisture was probably due to operation of the air compressors to overcome leak-by of the fuel rack booster pressure regulators. This moisture could have caused sluggish operation of the fuel rack boosters and/or the air start solenoid valves with possible resultant improper air start motor operation. The improper air start motor operation may have been caused by grease on the bendix gear screw.
- 4. Corrective Measures Taken:
Note: Corrective actions were performed in the sequence listed below.
a) The 2A EDG equipment was inspected just subsequent to the aborted start . Fuel rack position, air start motor condition, fuel supply isolation valve position, speed recorder indication and annunciation received were all as expected. The floor under the air start motors .showed some sign of "liquid splash" although none of the people involved with the post trip inspection noted the floor as wet.
b) The fuel rack boosters were tested and operated properly, although there was some moisture noted when one side was operated.
c) The air start motors were tested. # 1, #2 & #4 motors operated properly on the first try, while# 3 motor required two attempts to engage. Lack of engagement of one air start motor will not prevent a successful start. The most likely cause for the failure of
SPECIAL REPORT 311.-015 LR-N970729
- 3 air start motor to engage*was grease on the bendix drive. The air start motors on the other five EDG's were inspected and deposits of grease were not evident.
d) Approximately 1/2 ounce of water was drained from each fuel rack booster pressure regulator. While 1/2 ounce of water is not significant, it is an indication that moisture was present in the system.
e) The 2A EOG was re-tested satisfactorily as was expected, given the findings of a through c.
f) The 2A EOG fuel rack booster pressure regulators were replaced, thus eliminating the continuous air leak-by and resultant moisture.
g) The other two Unit 2 EDG's were tested satisfactorily to ensure their operability.
- h) The rack booster regulators on the other five Salem EDG's were checked for accumulated water. None was noted. Also none of the other regulators exhibited leak-by.
i) As a preventative measure, the rack booster pressure regulators on Unit 1, 18 and 1C EDG's will be replaced with a newer designed pressure regulator.
j) As a preventative measure, the rack booster pressure regulators on Unit 2, 28 and 2C EDG's will be replaced with a newer designed pressure regulator.
k) The fuel rack lubrication procedure will be revised to include draining of the booster pressure regulators during rack lubrication. Fuel rack lubrication is performed monthly.
I) The 2A EOG will be started weekly four times to assure no repeat failures. At the submittal of this report three of these "weekly" starts have been successful.
m) The 2A EOG air start motor bendix drives were cleaned and lubricated. A procedure revision will be made to clarify the cleaning, inspection and lubrication of the air start motor bendix drive.
n) The event will be evaluated for training impact.
- 5. Length of Time the Emergency Diesel Generator Was Cut of Service:
a) The 2A EOG was out of service for investigation of the 10/22/97 failure to start for 10.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SPECIAL REPORT 311,015 LR-N970729
- 6. Define the Current Surveillance Test Interval:
a) The 2A EOG is in a 31 day surveillance test frequency as required by TS 4.8.1.1.2a.
This interval is required following one failure or less in the last twenty valid tests on a per diesel generator basis. This is the normal test frequency.
SAFETY CONSEQUENCES AND IMPLICATIONS At the time of the 2A EOG failure to start, the other two EDG's were operable. With one diesel inoperable, the two remaining diesels are capable of providing power to the minimum safeguards equipment required for analyzed .accident and transient
- conditions. Therefore, this event did not impact the health and safety of the general public.