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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20080G4721995-01-18018 January 1995 Ro:On 941223,invalid Failure Experienced on 2A DG During Normal Start of Engine to Support Transformer Maint Activities.Speed Module Which Initiates Various Control & Support Features as Function of Engine Speed Replaced ML20078L8961994-11-21021 November 1994 Ro:On 941101,DG 2A Invalid Failure Occurred.Problem Isolated to Failed 125 Volt Dc Relay on Instantaneous pre-position Circuit Board.Subj Circuit Board Will Be Replaced W/New Design During Next Unit 2 Refueling Outage ML20114C1141992-08-19019 August 1992 Special Rept:On 920407,fuel Injection Pump in Right Cylinder 7 Seized,Preventing Injection of Fuel Into Associated Cylinder.Caused by Particulate Contamination.On 920320,noise Emanated from Right Cylinder 4 ML20086F9791991-11-22022 November 1991 Special Rept:On 910920,22,27,1001 & 02,invalid Failures of Diesel Generators 1A & 1B Occurred.Redundant Diesel Generator Operable During Each Event.Diesel Generator 1B Placed on Weekly Testing Frequency ML20079P5851991-10-0909 October 1991 Ro:On 910904,09 & 16,seismic Monitoring Instrumentation (Tape Decks 1 & 2 & Sensor 5) Inoperable for More than 30 Days.Playback Tape Deck & Sensor Repaired & Restored to Operable Status ML20058A3681990-10-0101 October 1990 Deviation Investigation Rept 90-026-00:on 900815,EDG 2A Cylinder 10L Dislocated Pushrod Due to Collapsed Hydraulic Lifter ML20055G3461990-06-27027 June 1990 Ro:On 900412,engine Tripped Due to Spurious High Jacket Water Temp Trip Valve Actuation During Partial Surviellance to Verify Operability of Diesel Generator 2A.Nuclear Work Request Initiated to Repair or Replace Trip Valve ML20247C5601989-05-18018 May 1989 Special Rept:On 890224,during Local Leak Rate Surveillance Test,Overall Max Pathway Containment Leakage Failed to Meet Acceptance Criteria & Containment Isolation Valves Exhibited Excessive Leakage.Caused by Improper Valve Stroking ML20246P9061989-03-20020 March 1989 Ro:On 890214,nonvalid Test & Failure Experienced on 2B Diesel Generator.Caused by Nuclear Station Operator Inexperience & Procedural Discrepancy.Nuclear Station Operator Counseled & Procedure Change Initiated ML20236E1821989-03-10010 March 1989 Ro:On 890305,moderator Temp Coefficient Determined to Be More Positive than Allowed by Tech Spec 3.1.1.3.a & Limiting Condition for Operation Entered.Control Rods Maintained within New Withdrawal Limits Until Core Burnup Reached ML20195G5811988-06-13013 June 1988 Deviation Investigation Rept 88-076-00:on 880516,diesel Genrator 1B Uncontrollably Loaded During Monthly Operability Surveillance.Caused by 3IMX Relay Failure.Load Reduced W/ Governor Control Switch & Subj Relay Replaced ML20238D9711987-12-21021 December 1987 Ro:On 870925,during Monthly Operability Surveillance of Diesel Generator 1A,fuel Oil Leak Occurred at Connection of Fuel Pump W/Fuel Pump Discharge Line.Caused by Cracked Fitting at Cylinder Pump Discharge.Pump & Line Replaced ML20237C9051987-12-0303 December 1987 Ro:On 871105,diesel Generator 2A Inoperable for 22 H.Caused by Dirty Voltage Range & Adjustment Potentiometer (Pot) in Voltage Regulator.Pot Cleaned & Exercised Through Full Range ML20236F8351987-10-27027 October 1987 Ro:On 870814,governor Hunting Observed Following Diesel Generator Startup.Caused by Intermittent Operation of 4EX3 Relay.Diesel Generator 1B Will Remain on Monthly Testing Schedule Per Tech Spec 4.8.1.1.2 ML20236T9321987-10-27027 October 1987 Special Rept:On 870831,Train a Safety Injection Occurred During Performance of Bimonthly Surveillance of solid-state Protection Sys.Caused by Cognitive Personnel Error.Emergency Procedure 2BEP-0 Entered & Exited When Plant Stabilized ML20236Q1301987-10-19019 October 1987 Ro:On 870812,reactor Tripped Following Safety Injection & Main Steam Line Isolation During Power Ascension.Caused by Fully Open Governor Valve.Necessary Equipment auto-started/ Actuated Per Design ML20236E5011987-06-25025 June 1987 Ro:On 870318 & 0417,diesel Generator 1A Failed to Reach Rated Speed,Voltage & Frequency within Required Time Set by Tech Specs.Caused by Inadequate Prime in Fuel Oil Supply Line & Ruptured Diaphragm,Respectively ML20236B8871987-06-18018 June 1987 Ro:On 870428,valid Test & Failure on Diesel Generator 2B Occurred.Caused by Method Used for Determining Start Time. Diesel Generator Monthly Operability Surveillance Procedures Revised ML20207T2771987-03-0606 March 1987 Ro:On 870210,diesel Generator 1A Experienced Valid Test Failure.Caused by Failure of Check Valve to Supply Day Tank in Event That Check Valve Fails to Seat.Addl Soft Seat Check Valve Installed Between Engine & Supply Day Tank ML20212K9321987-02-27027 February 1987 Special Rept;On 870215,wide-range Noble Gas Monitor Taken Out of Svc for Mod to Demonstrate Capability to Test for Radioiodine,Per TMI Action Plan Item II.F.1.Mod Scheduled for Completion by mid-Mar 1987 ML20198S1011986-05-29029 May 1986 Special Rept:On 860505,diesel Generator 2A Declared Incapable Due to Contaminated Fuel & Broken Rocker Arms on Seven Left Cylinder.Caused by Bent Retaining Rings & Insufficient Generator Crosshead Procedure.Parts Replaced ML20195D1001986-05-19019 May 1986 Ro:On 860430,Unit 2 Diesel Generator 1B Required 12.5 to Reach Rated Conditions.Caused by Inadequate Prime in Fuel Oil Supply Line.Union Lightened ML20203F6021986-03-20020 March 1986 Special Rept:On 860223 & 0313,diesel Generator 1B Experienced Two Nonvalid Tests & Failures Due to Isochronous Relay Failure.Caused by Intermittent Continuity Between Contacts in Isochronous Relay While in Test Mode ML20203K9371986-03-11011 March 1986 Special Rept:On 860212 & 17,Cooper Bessemer Diesel Generator 2A Failures Occurred Due to Rocker Arm Failure.Caused by Liner Misalignment W/Subsequent Head Alignment.Heads Realigned or Replaced ML20135F8431985-09-0303 September 1985 Ro:On 850813,30- & 250-ft Wind Direction Recorders & 30-ft Air Temp Recorder in Main Control Room Reported Inoperable. Caused by Damaged Fuses in Communication Line Between Meteorological Tower & Control Room.Fuses Replaced ML20127J2541985-06-13013 June 1985 Ro:On 850527,control Room Indication of 30-ft Wind Speed Lost.Caused by Problems W/Communication Links Between Tower Instrumentation & Control Room Readouts.Work in Progress to Restore Operability ML20126M8411985-06-0303 June 1985 Correction to 850523 Special Rept:Second & Third Sentences of Second Paragraph Should Read ...On One of Sys Five Sensor Signal Cables.This Signal Cable Is for Free Field Sensor ML20127E1111985-05-23023 May 1985 Special Rept:On 850419,seismic Instrumentation Sys Began Alarming Continuously.Troubleshooting Indicated 120 Mv Peak to Peak 60 Cycle Signal on Sys Fire Sensor Signal Cables. Problem Under Investigation ML20107D5151985-02-0808 February 1985 Updated Special Rept Re Diesel Generator Failures. Reevaluation Reduced Failures of Diesel Generator 1A to One Common Failure,Decreasing Total to Two Failures Out of 58 Valid Tests ML20106A1761985-01-12012 January 1985 Special Rept:On 841228,suction Relief Valve 1RH8708A & on 841230,RHR Sys Lifted on High Pressure Transient During Restoration of Loop Following Performance of Surveillance Procedure Bvs 0.5-2.SI.3 ML20076K7771983-07-0808 July 1983 Ro:On 830630,during Insp of Spent Fuel Rack,Five Propane Gas Cylinders Found in Spent Fuel Pool Area.Caused by Personnel Error.Cylinders Will Be Stored Outside Fuel Handling Bldg.Signs Re Combustible Matl Will Be Posted 1995-01-18
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217H5221999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Byron Station, Units 1 & 2.With ML20217P6351999-09-29029 September 1999 Non-proprietary Rev 6 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20212B9261999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Byron Station,Units 1 & 2.With ML20210R3431999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Byron Station, Units 1 & 2.With ML20210E2251999-07-21021 July 1999 B1R09 ISI Summary Rept Spring 1999 Outage, 980309-990424 ML20209G1751999-07-0808 July 1999 SG Eddy Current Insp Rept,Cycle 9 Refueling Outage (B1R09) ML20207H7941999-06-30030 June 1999 Rev 0 to WCAP-15180, Commonwealth Edison Co Byron,Unit 2 Surveillance Program Credibility Evaluation ML20207H8071999-06-30030 June 1999 Rev 0 to WCAP-15178, Byron Unit 2 Heatup & Cooldowm Limit Curves for Normal Operations ML20207H7851999-06-30030 June 1999 Rev 0 to WCAP-15183, Commonwealth Edison Co Byron,Unit 1 Surveillance Program Credibility Evaluation ML20207H7771999-06-30030 June 1999 Rev 0 to WCAP-15177, Evaluation of Pressurized Thermal Shock for Byron,Unit 2 ML20209H3711999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Byron Station, Units 1 & 2.With ML20207H7561999-06-28028 June 1999 Pressure Temp Limits Rept (Ptlr) ML20207H7621999-06-28028 June 1999 Pressure Temp Limits Rept (Ptlr) ML20195J8001999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Byron Station,Units 1 & 2.With ML20207B6481999-05-25025 May 1999 SER Accepting Revised SGTR Analysis for Byron & Braidwood Stations.Revised Analysis Was Submitted to Support SG Replacement at Unit 1 of Each Station ML20195B2591999-05-19019 May 1999 Rev 66a to CE-1-A,consisting of Proposed Changes to QAP for Dnps,Qcs,Znps,Lcs,Byron & Braidwood Stations ML20206R6991999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Byron Station Units 1 & 2.With ML20195C7961999-04-28028 April 1999 Rev 2 to NFM9800233, Byron Station Unit 2 COLR for Cycle 8A (BY2C8A) M980023, Rev 2 to NFM9800233, Byron Station Unit 2 COLR for Cycle 8A (BY2C8A)1999-04-28028 April 1999 Rev 2 to NFM9800233, Byron Station Unit 2 COLR for Cycle 8A (BY2C8A) ML20205P7001999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Byron Station,Units 1 & 2.With ML20205B5091999-03-26026 March 1999 SER Accepting Relief Requests 12R-24,Rev 0 & 12R-34,Rev 0, Related to Second 10-year Interval Inservice Insp for Byron Station,Units 1 & 2 ML20205C5101999-03-21021 March 1999 Revised Safety Evaluation Supporting Improved TS Amends Issued by NRC on 981222 to FOLs NPF-37,NPF-66,NPF-72 & NPF-77.Revised Pages Include Editorial Corrections ML20204G3831999-03-19019 March 1999 Safety Evaluation Accepting Second 10-yr Interval ISI Request for Relief 12R-11 M990004, Rev 0 to NFM9900043, Byron Unit 1,Cycle 10 COLR in ITS Format W(Z) Function1999-03-17017 March 1999 Rev 0 to NFM9900043, Byron Unit 1,Cycle 10 COLR in ITS Format W(Z) Function ML20206A8831999-03-17017 March 1999 Rev 0 to NFM9900043, Byron Unit 1,Cycle 10 COLR in ITS Format W(Z) Function ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results ML20204H9941999-03-0303 March 1999 Non-proprietary Rev 4 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations ML20204C7671999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Byron Station,Units 1 & 2.With ML20199G8271998-12-31031 December 1998 Rev 1 Comm Ed Byron Nuclear Power Station,Unit 1 Cycle 9 Startup Rept ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with ML20202F6181998-12-31031 December 1998 Cycle 8 COLR in ITS Format & W(Z) Function ML20206B4001998-12-31031 December 1998 Annual & 30-Day Rept of ECCS Evaluation Model Changes & Errors for Byron & Braidwood Stations ML20199E6371998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Byron Station,Units 1 & 2.With ML20202F6021998-12-31031 December 1998 Cycle 9 COLR in ITS Format & W(Z) Function ML20196K6731998-12-31031 December 1998 10CFR50.59 Summary Rept for 1998 ML20207H7731998-11-30030 November 1998 Rev 0 to WCAP-15125, Evaluation of Pressurized Thermal Shock for Byron,Unit 1 ML20207H8011998-11-30030 November 1998 Rev 0 to WCAP-15124, Byron Unit 1 Heatup & Cooldown Limit Curves for Normal Operation ML20198D1501998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Byron Nuclear Power Station,Units 1 & 2.With ML20196A4191998-11-19019 November 1998 Safety Evaluation Accepting QA TR CE-1-A,Rev 66 Re Changes in Independent & Onsite Review Organization by Creating NSRB ML20195F8321998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Byron Nuclear Power Station,Units 1 & 2.With 05000454/LER-1998-018, Corrected LER 98-018-00:on 980912,inoperable Unit 1 DG Was Noted.Caused by Low Lube Oil Pressure Condition.Immediately Entered Into Lcoar for AC Sources TS 3.8.1.1,Action a1998-10-0909 October 1998 Corrected LER 98-018-00:on 980912,inoperable Unit 1 DG Was Noted.Caused by Low Lube Oil Pressure Condition.Immediately Entered Into Lcoar for AC Sources TS 3.8.1.1,Action a ML20207H7671998-10-0505 October 1998 Rv Weld Chemistry & Initial Rt Ndt ML20154L5501998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Byron Nuclear Power Station,Units 1 & 2.With ML20197C9051998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Byron Nuclear Power Station,Units 1 & 2.With ML20151Z9651998-08-31031 August 1998 Revised MOR for Aug 1998 for Byron Nuclear Power Station. Rept Now Includes Page 9 Which Was Omitted from Previously Issued Rept ML20238F6551998-08-28028 August 1998 SE Authorizing Licensee Request for Relief NR-20,Rev 1 & NR-25,Rev 0 Re Relief from Examination Requirement of Applicable ASME BPV Code,Section XI for First ISI Interval Exams ML20237E2331998-08-21021 August 1998 Revised Pages of Section 20 of Rev 66 to CE-1-A, QA Topical Rept ML20237B3361998-08-14014 August 1998 B2R07 ISI Summary Rept,Spring 1998 Outage, 961005-980518 ML20237B4841998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Byron Nuclear Power Station Units 1 & 2 1999-09-30
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^ 8:]/18-rN Commonwealth Edison Byr:n Nuciar St: tion
/ 4450 North GIrrnIn Church Rold FMCMTY EfJilNG
( 1 Byron, Illinois 61010 f
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O(' a May 29,1986 PA FILS LTR: BYRON 86-0541 FILE: 2.7.400 Mr. James G. Kcppler Regional Administrator '
Region Ill U. S. Nuclear Regulatory Commission Glen Ellyn, Illinois 60137
Dear Sir,
This Special Report is submitted in accordance with Byron litdtion License ,
NPF-37 Appendix A, Technical Specification 4.8.1.1.3, reporting of Diesel Generator Failures.
This report addresses one valid test and failure experienced on the 2A Diesel Generator. The criteria used to determine valid tests and failures is in eccordance .
with Section C.2.e of Regulatory Guide 1.108.
t During an extended run of the 2A Diesel Generator to support Unit 2 System Auxiliary Transformer switching, an increase in crankcase oil level was observed.
Sampling indicated that diesel fuel oil had contaminated the crankcase oil.
All other operating parameters!were normal. The Unit 2A Diesel Generator was declared incapable at 0415 on May 5,1986, and Limiting Condition for Operation Action Requirement (LCOAR) 8.1.3-la was initiated. Investigation into the fuel oil leak identified a loose fitting on the fuel oil return line connection on the eight right cylinder. In addition, on May 7,1986 broken rocker arms were discovered on the seven left cylinder. It is believed that the rocker arm failure occurred during the May 5th run.
On February 12,1986 and February 17,1986 similar failures were experienced on the five left and seven left cylinders respectively. Cooper Bessemer, the diesel engine vendor, concluded that the root cause for these failures was a misalignment of the cylinder head and the cylinder liner. This misalignment in turn caused abnormal side loading and deformation of the crosshead guide which eventually lead to the rocker arm failure. Allindications from the May 5th failure show that the root cause for this failure is not the same as the root cause for the February 12th and 17th failures. Following the repairs for the February 12th and 17th failures, and prior to the May 5th failure, the 2A Diesel Generator ran for 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br />.
8606100328 860529 4 DR ADOCK 0500 g g 5 0
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BYRON 86-0541 Page 2 Cooper Bessemer was brought on site to assist in the investigation of the current failure. The following actions were taken.
- 1. The seven left cylinder head was removed and inspected for physical deformation. Special emphasis was placed on correct clearances between the crosshead (camfollower) and its guide due to the previous failures of this kind. In addition the cylinder liner was checked for proper alignment. Three abnormal conditions were detected.
- 1) One lifter on the exhaust rocker arm was found collapsed.
- 2) Indentations were found on the connection of the intake crosshead and its pushrod.
- 3) Bent retaining rings were found on both the intake and exhaust rocker arms.
- 2. The five left and ten right cylinder heads were removed due to similar failures experienced in February,1986. A similar inspection to that of the seven left cylinder was excecuted. Again, bent retaining rings were discovered on the intake and exhaust rocker arms.
- 3. Cam shaft covers for all twenty cylinders were removed to verify proper clearance between all crossheads and their respective guides.
In addition, all rocker arm assembly covers were removed to inspect the rocker arm assemblies. Bent retaining rings were discovered on 14 of 20 rocker arm assemblies.
- 4. A Commonwealth Edison Systems Material Analysis Department (SMAD) representative was brought on site to investigate a possible material defect. Initialindications revealed that the exhaust rocker arm, manufactured by JG Corp. had a lower Brinell hardness than the intake rocker arm, manufactured by Cooper Bessemer. This condition was also noted in the two previous rocker arm failures dated 2/12/86 and 2/17/86.
Byron Station, in conjunction with Cooper Bessemer, identified four possible root causes for the failure root cause. The four possible root causes include;
- 1) collapsed lifter
- 2) crosshead indentations
- 3) weak rocker arms, and
- 4) bent retaining rings.
Cooper Bessemer indicated that one collapsed lifter could not have independently caused the rocker arms to fail. The indentations at the union of the pushrod and the crosshead were proven to have taken place after the failure of the rocker arms. Additionally these indentations had no effect on the clearance between the crosshead and its guide. Although SMAD did identify a lower Brinell hardness in the exhaust rocker arm, the minimum safety factor for the weaker rocker arms was in excess of 10.
BYRON 86-0541 Page 3 The intermediate root cause for this event is the bent retaining rings. The function of a rocker arm retaining ring is to hold the tappet inside the rocker arm during disassembly of the rocker arms. The tappet is the intermediate piece between the valve stem and its respective rocker arm. The lifter, which provides a dampening effect during valve operation, is housed by the tappet.
Although a normal retaining ring has no operational function, the bent rings obstructed the pathway for the tappet during valve adjustment. This in turn created a gap between the valve stem and the rocker arm. In addition, the collapsed lifter on the seven left cylinder increased the gap between the valve stem and the rocker arm. This gap caused the failure through either constant impact loading, or by allowing a pushrod to travel out of its normal position.
With the pushrod out of position, the rocker arm can over extend, creating high stresses within the rocker arm.
The root cause for this event is the lack of detailed procedure for the inspection of the Diesel Generator crossheads. Following the corrective action for the February 12 and 17 failures, the crossheads were inspected. During the inspection the valve adjusting screws, which position the tappet in the correct position, were backed out of their taps. The crankshaft was then rolled using the turning gear. This was done to check the crossheads for full freedom of movement.
Ilowever, by using this method, the tappets were forced against the retaining rings causing deformation of the rings. This deformation, as explained in the previous paragraphs, led to the failure of the seven left cylinder rocker arms.
It must be noted that failure of one rocker arm, on a given head, willinevitably cause the failure of the other rocker arm. Therefore, finding two failed rocker arms on a given head is expected.
The root cause for the contaminated lube oilis the broken rocker arms. When the rocker arms break, combustion no longer takes place in the cylinder. Ilowever, fuel oil is stillinjected into the cylinder. When the piston strokes, the fuel oil is compressed between the cylinder head and the piston. The fuel oil eventually leaks by the piston rings and enters the crankcase. Although a smallleak was found on a fuel drain line, this leak was minimal in comparision to the fuel leak by the piston rings.
The following corrective actions were taken to return the 2A Diesel Generator to capable status. A Cooper Bessemer Representative assisted in all reassembly procedures.
- 1) The loose fitting on the fuel oil return line was tightened to prevent lube oil contamination. In addition all 20 fuel oil injectors were replaced to isolate any undetected leakage.
- 2) The retaining rings on all 20 cylinders were removed and replaced.
- 3) The broken rocker arms and the collapsed lifter on the seven left cylinder were removed and replaced.
- 4) At 0302 on May lith,1986, the 2A Diesel Generator was started for an operational surveillance. At 0445, after successful completion ,
of the one hour run, LCOAR 8.1.3-la was exited.
. (
BYRON 86-0541 Paga 4
- 5) At 1013 on May lith, the 2A Diesel Generator began a 99 hour0.00115 days <br />0.0275 hours <br />1.636905e-4 weeks <br />3.76695e-5 months <br /> fullload run. At 1300 on May 14th the 99 hour0.00115 days <br />0.0275 hours <br />1.636905e-4 weeks <br />3.76695e-5 months <br /> run was successfully completed. All previous rocker arm failures Imve occurred in less than 68 hours7.87037e-4 days <br />0.0189 hours <br />1.124339e-4 weeks <br />2.5874e-5 months <br />, therefore this test verified rocker arm integrity.
- 6) The Diesel Generator Operational Procedures have been temporarily changed to alert the operator on how to detect rocker arm failure, and the proper actions to take if failure occurs.
- 7) Cooper Bessemer is currently working on detailed procedures for crosshead inspection. Crosshead Inspections will not be performed until the procedure is received.
The 2A Diesel Generator was unavailable for 6 days following the May 5th failure. This failure will have no effect on the testing frequency of the 2A Diesel Generator. Currently Technical Specification 3/4.1.8.3 applies to the 2A Diesel Generator. This specification has no requirement for altering testing frequencies due to valid tests and failures, therefore Section C.2.d of Regulatory Guide 1.108 is not applicable. This failure will be recorded for future use in determining the testing frequency upon acquisition of the Unit 2 Operating 6 License, blVS k R. E. Querio Station Manager Byron Nuc! car Power Station REQ /MMR/bf ec: J. Ilinds, NRC Resident inspector U. S. NRC Document Control Desk, Washington, D.C.
INPO Record Center CECO Distribution List M. Robert J. Cook
- 03/059
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