Forwards LER 96-003-01 Re Concurrent Inoperability of Edgs. Rev Submitted to Provide Addl Info Re Troubleshooting of Components Removed from EDG 1A
Person / Time
ML20134K654
Site:	McGuire
Issue date:	11/07/1996
From:	Mcmeekin T DUKE POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20134K656	List: 05000369/LER-1996-003, :on 960618,during Scheduled Operability Test of EDG 1A,EDG Declared Inoperable.Caused by Equipment Failure/ Malfuction of EDG 1A & Equipment Failure & Mfg Process Deficiency of EDG 1B.EDGs SD & Failed Components Replaced 05000369/LER-1996-003-01, Forwards LER 96-003-01 Re Concurrent Inoperability of Edgs. Rev Submitted to Provide Addl Info Re Troubleshooting of Components Removed from EDG 1A
References
NUDOCS 9611190261
Download: ML20134K654 (2)
v • d • e

LER-1996-003, Forwards LER 96-003-01 Re Concurrent Inoperability of Edgs. Rev Submitted to Provide Addl Info Re Troubleshooting of Components Removed from EDG 1A

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(v), Loss of Safety Function
3691996003R01 - NRC Website
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ll l

Duke keer Cornpany T. C Mchirms AkCuire Nudear Genemtion Deparonen!

Vice President 12700Hagers FerryRoad(MG0lVP)

(704)8754800

- Huntersville NC280784985

('704)8754809 Fax DUKEPOWER

[

DATE:

November 7, 1996 l.

1 I

U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.. 20555

Subject:

McGuire Nuclear Station, Unit 1 Docket No.'50-369 Licensee Event Report 369/96-03, Revision 1 l

Problem Investigation Process No.:

0-M96-1753 Gentlemen:

Pursuant to 10 CFR 50.73 Sections (a) (1) and (d), attached is Licensee Event Report 369/96-03, Revision 1, concerning concurrent inoperability l

of both Unit 1 Emergency Diesel Generators.

This report is being subenitted in accordance with 10 CFR 50.73 (a) (2) (v).

This report also

. satisfies the Special Reporting requirements of Technical-Specification 3.8.1.1.

This revision is being submitted to provide additional information with regard to troubleshooting of the components removed from Emergency Diesel Generator 1A.

Also, it has now been determined that the failure of components associated with Emergency Diesel Generator 1A in this event is not Nuclear Plant Reliability Data System (NPRDS) reportable.

This event is considered to be of no significance with respect to the health and safety of the public.

Very truly yours, NJi

. c. Nc

.un JWP/bcb l

Attachment cca Mr.

S.D. Ebneter INPO Records Center Administrator, Region II Suite 1500 U.S. Nuclear Regulatory Commission 1100 circle 75 PrArkway 101 Marietta St., NW, Suite 2900 Atlanta, GA 30?39 Atlanta, GA 30323 Mr. Victor Norses Mr. Scott Schaeffer U.S. Nuclear Regulatory Commissic,n NRC Resident Inspector Office of Nuclear Reactor Regulation McGuire Nuclear Station Washington, D.C.. 20555 I

9611190261 961107 PDR ADOCK 05000369.

8 PDR

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bxc

3. L. Walch (EC11C)

E. L. T ylor (CNS)

Q. A. Copp (EC050)

J. I. Glenn (MG02ME)

P. R. Herran (MG01VP)

C. B. Davis (MG01CP)

J.-E. Burchfield (ONS Reg Compliance)

G. H.

Savage (EC06E)

G. B. Swindlehurst (EC11-0842)

C. M. Misenheimer (EC08I)

R. F. Cole (EC05N)

J. M. Frye (EC05N)

T. G. Becker (PB02L) i P. M. Abraham (EC08I)

R. B. White (MG01VP)

L. V. Wilkie (ONO3SR)

D. P. Kimball (CNOSSR) l K.

L. Crane (MG01RC)

N. Casler (EC05N)

NSRB Support Staff (EC05N)

Licensee Event Report

McGuire

70 | 71 | 72 | 73 | 74 | 75 | 76 | 77 | 78 | 79 | 80 | 81 | 82 | 83 | 84 | 85 | 86 | 87 | 88 | 89 |

90 | 91 | 92 | 93 | 94 | 95 | 96 | 97 | 98 | 99 | 00 | 01 | 02 | 03 | 04 | 05 | 06 | 07 | 08 | 09 |

10 | 11 | 12 | 13 | 14 | 15 | 16 | 17 | 18 | 19 | 20 | 21 | 22 | 23 | 24 | 25 |

		Reporting criterion
05000369/LER-1996-001-01, Forwards LER 96-001-01 Re Manual Reactor Trip.Rev Due to Determination That Event Not NPRDS Reportable & Not Considered Significant Re Public Health & Safety	Forwards LER 96-001-01 Re Manual Reactor Trip.Rev Due to Determination That Event Not NPRDS Reportable & Not Considered Significant Re Public Health & Safety	10 CFR 50.73(a)(2)(iv), System Actuation
05000369/LER-1996-001, :on 960203,manual Reactor Tripped When 1A RCP Upper Thrust Bearing Reached Administrative Limit of 195 Degrees.Caused by Unknown Equipment Failure.Associated Sys & Components Evaluated/Tested.Unit Returned to Svc on 960205	on 960203,manual Reactor Tripped When 1A RCP Upper Thrust Bearing Reached Administrative Limit of 195 Degrees.Caused by Unknown Equipment Failure.Associated Sys & Components Evaluated/Tested.Unit Returned to Svc on 960205	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000369/LER-1996-002-01, :on 960204,inadvertent Manual Initiation of Unit 1 FW Isolation Occurred Due to Inappropriate Action. OPS Mgt Evaluated Depressing & Holding Train a & B CF Isolation	on 960204,inadvertent Manual Initiation of Unit 1 FW Isolation Occurred Due to Inappropriate Action. OPS Mgt Evaluated Depressing & Holding Train a & B CF Isolation	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B)
05000369/LER-1996-003-01, Forwards LER 96-003-01 Re Concurrent Inoperability of Edgs. Rev Submitted to Provide Addl Info Re Troubleshooting of Components Removed from EDG 1A	Forwards LER 96-003-01 Re Concurrent Inoperability of Edgs. Rev Submitted to Provide Addl Info Re Troubleshooting of Components Removed from EDG 1A	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000369/LER-1996-003-03, :on 960618,concurrent Inoperability of Both Unit 1 Emergency Diesel Generators.Caused by Possible Equipment Failure/Malfunction.Shutdown of EDGs & Replaced Failed Components	on 960618,concurrent Inoperability of Both Unit 1 Emergency Diesel Generators.Caused by Possible Equipment Failure/Malfunction.Shutdown of EDGs & Replaced Failed Components
05000369/LER-1996-003, :on 960618,during Scheduled Operability Test of EDG 1A,EDG Declared Inoperable.Caused by Equipment Failure/ Malfuction of EDG 1A & Equipment Failure & Mfg Process Deficiency of EDG 1B.EDGs SD & Failed Components Replaced	on 960618,during Scheduled Operability Test of EDG 1A,EDG Declared Inoperable.Caused by Equipment Failure/ Malfuction of EDG 1A & Equipment Failure & Mfg Process Deficiency of EDG 1B.EDGs SD & Failed Components Replaced	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000369/LER-1996-004, :on 961010,incorrectly Calibrated Rcl Loss of Flow Reactor Trip Bistables Identified.Caused by Procedural/ Technical Inaccuracy.All Affected Procedures Were Changed & Instruments Calibrated within TS Limits	on 961010,incorrectly Calibrated Rcl Loss of Flow Reactor Trip Bistables Identified.Caused by Procedural/ Technical Inaccuracy.All Affected Procedures Were Changed & Instruments Calibrated within TS Limits	10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A)
05000369/LER-1996-004-05, :on 961010,incorrectly Calibrated Reactor Coolant Loop Loss of Flow Reactor Trip Bistables Identified. Caused by Procedure Technical Inaccuracy.All Affected Procedures Were Changed	on 961010,incorrectly Calibrated Reactor Coolant Loop Loss of Flow Reactor Trip Bistables Identified. Caused by Procedure Technical Inaccuracy.All Affected Procedures Were Changed	10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1)
05000369/LER-1996-005-01, :on 961101,TS Required Shutdown of Both Units Due to Failed Surveillance Test of Vital Battery Evcc.Caused Is Unknown.Replaced & Retested Vital Battery Bank Evcc	on 961101,TS Required Shutdown of Both Units Due to Failed Surveillance Test of Vital Battery Evcc.Caused Is Unknown.Replaced & Retested Vital Battery Bank Evcc	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(1)
05000369/LER-1996-005, Forwards Suppl Info Re LER 96-005,rev 1 Re TS Required Shutdown of Both Units Due to Failed Surveillance Test of Vital Battery Bank Evcc.Rev Changes Commitment Re Vital Battery Vank Evcc	Forwards Suppl Info Re LER 96-005,rev 1 Re TS Required Shutdown of Both Units Due to Failed Surveillance Test of Vital Battery Bank Evcc.Rev Changes Commitment Re Vital Battery Vank Evcc
05000369/LER-1996-005-04, :on 961101,TS Required Shutdown of Both Units Occurred Due to Failed Surveillance Test of Vital Battery Evcc.All Vital Battery Banks Will Be Replaced with Conventional Batteries by End of 2EOC11 Outage	on 961101,TS Required Shutdown of Both Units Occurred Due to Failed Surveillance Test of Vital Battery Evcc.All Vital Battery Banks Will Be Replaced with Conventional Batteries by End of 2EOC11 Outage	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1)
05000369/LER-1996-006, :on 961109,actuation of Both Unit 1 Motor Driven Feedwater Pumps Were Manually Initiated Due to Loss of Auxiliary Steam Supply to Main Feedwater Pump Turbine. Pump Has Been Repaired	on 961109,actuation of Both Unit 1 Motor Driven Feedwater Pumps Were Manually Initiated Due to Loss of Auxiliary Steam Supply to Main Feedwater Pump Turbine. Pump Has Been Repaired	10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1)
05000369/LER-1996-006-03, :on 961109,manually Initiated Actuation of Unit 1 Driven AFW Pumps Occurred Due to Loss of as Supply to MFW Pump Turbine.Caused by Insufficient Lubrication.No Corrective Actions Right Now	on 961109,manually Initiated Actuation of Unit 1 Driven AFW Pumps Occurred Due to Loss of as Supply to MFW Pump Turbine.Caused by Insufficient Lubrication.No Corrective Actions Right Now	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000369/LER-1996-007-02, :on 961107,mode Related Missed TS Surveillance on Containment Integrity Discovered Due to Technical Inaccuracy.Pm/Pt Database Corrected & TS Surveillance Quality Improvement Team Formed	on 961107,mode Related Missed TS Surveillance on Containment Integrity Discovered Due to Technical Inaccuracy.Pm/Pt Database Corrected & TS Surveillance Quality Improvement Team Formed	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1)

05000369/LER-1996-003-01, Forwards LER 96-003-01 Re Concurrent Inoperability of Edgs. Rev Submitted to Provide Addl Info Re Troubleshooting of Components Removed from EDG 1A

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