LER-1997-001, Forwards LER 97-001-00 Concerning DG Load Sequencer Inadvertent Esfa |
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| Reporting criterion: |
10 CFR 50.73(a)(2)(iv), System Actuation |
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| 3701997001R00 - NRC Website |
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e Duke Power A Dcke Energy Comymy McGuire Nuclear Generation Department 12700 flogers Ferry Road (MGolVP) lluntersville, NC 28078-9340 DATE: June 26, 1997 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.
20555
Subject:
McGuire Nuclear Station, Unit 2 Docket No. 50-369 Licensee Event Report 370/97-01, Revision 0 Problem Investigation Process No.: PIP 2-M97-2175 Gentlemen:
Pursuant to 10 CFR 50.73 Sections (a) (1) and (d), attached is Licensee Event Report 370/97-01, Revision 0, concerning a Diesel Generator Load Sequencer Inadvertent Engineered Safety Feature Actuation.
This report is being submitted in accordance with 10 CFR 50.73 (a) (2) (iv).
This event is considered to be of no significance with respect to the health and safety of the public.
l Very truly yours, 4
H.
B.
Barron, Jr.
JWP/bcb i
Attachment cca Mr.
L.
A.
Reyes INPO Records Center U.S. Nuclear Regulatory Commission 700 Galleria Parkway Region II Atlanta, GA 30339 Atlanta Federal Center 61 Forsyth St.,
SW, Duite 23T85 Atlanta, GA 30323 Mr. Victor Nerses Mr. Scott Shaeffer U.S. Nuclear Regulatory Commission NRC Resident Inspector Office of Nuclear Reactor Regulation McGuire Nuclear Station Washington, D.C.
20555 9707010312 970626 PDR ADOCK 05000370 g
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bxc: D. L. Walch (EC11C)
M. S. Kitlan (CNS)
G. A.
Copp (EC050)
J' I. Glenn (MG02ME)
P.
R. Herran (MG01VP)
L. S. Davis (MG05BE)
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
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P. M. Abraham (EC08I) l R. B. White (MG01VP) i R.
T. Bond (ONO3SR) l D.
P. Kimball (CN05SR)
K. L. Crane (MG01RC)
R. N. Casler (EC05N)
NSRB Support Staff (EC05N) i l
I i
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| | | Reporting criterion |
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| 05000369/LER-1997-001-01, :on 970318,failure to Comply W/Ts 3.6.3 Following Valve 1CF-26AB Inoperability,Occurred.Caused by Misinterpretation of Reference Documents Re Applicability. Correct Application of TS Clarified |
- on 970318,failure to Comply W/Ts 3.6.3 Following Valve 1CF-26AB Inoperability,Occurred.Caused by Misinterpretation of Reference Documents Re Applicability. Correct Application of TS Clarified
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)
10 CFR 50.73(t)(2) | | 05000369/LER-1997-001-03, :on 970318,failure to Comply W/Ts 3.6.3 Requirements Following Valve 1CF-26AB Inoperability Was Identified,Due to Misinterpretation of Reference Documents. Application of TS to Valve Was Clarified |
- on 970318,failure to Comply W/Ts 3.6.3 Requirements Following Valve 1CF-26AB Inoperability Was Identified,Due to Misinterpretation of Reference Documents. Application of TS to Valve Was Clarified
| 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)
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-1997-002, :on 970313,FWIVs Were Declared Inoperable Due to Hydraulic Oil Degradation.Solenoid Coils & Plungers Were Replaced or Cleaned |
- on 970313,FWIVs Were Declared Inoperable Due to Hydraulic Oil Degradation.Solenoid Coils & Plungers Were Replaced or Cleaned
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
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-1997-002-03, :on 970313,inoperability of FW Isolation Valves Discovered Due to Hydraulic Oil Degradation.Replaced Unit FWIV Solenoid Coils |
- on 970313,inoperability of FW Isolation Valves Discovered Due to Hydraulic Oil Degradation.Replaced Unit FWIV Solenoid Coils
| 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)(viii)(A) | | 05000369/LER-1997-003-02, :on 970326,both Trains of Control Room Ventilation Sys Inoperable Due to Isolated Air Intake Valves.Radiation Monitor Will Be Evaluated to Determine If Changes Are Needed in Design or Maint |
- on 970326,both Trains of Control Room Ventilation Sys Inoperable Due to Isolated Air Intake Valves.Radiation Monitor Will Be Evaluated to Determine If Changes Are Needed in Design or Maint
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(viii)(B) | | 05000369/LER-1997-004, :on 970320,main Steam Safety Valve TS Inaccuracies Were Discovered.Caused by Incorrect vendor-supplied Algorithm.Engineering Guidelines for Plant Operation Are in Place & TS Has Been Revised |
- on 970320,main Steam Safety Valve TS Inaccuracies Were Discovered.Caused by Incorrect vendor-supplied Algorithm.Engineering Guidelines for Plant Operation Are in Place & TS Has Been Revised
| 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)
10 CFR 50.73(a)(2)(1) | | 05000369/LER-1997-006, :on 970512,Unit 1 Esfa Occurred Due to Tripping of MFW Pumps.Enhanced Procedural Guidance Re Functional Verification of Equipment After Maint |
- on 970512,Unit 1 Esfa Occurred Due to Tripping of MFW Pumps.Enhanced Procedural Guidance Re Functional Verification of Equipment After Maint
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)(i)
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) | | 05000369/LER-1997-007, :on 970514,Unit 1 RT Occurred During Power Range Nuclear Instrumentation Testing.Caused by Personnel Utilizing Inappropriate Procedure for Existing Plant Conditions.Reviewed Subject & Associated Procedures |
- on 970514,Unit 1 RT Occurred During Power Range Nuclear Instrumentation Testing.Caused by Personnel Utilizing Inappropriate Procedure for Existing Plant Conditions.Reviewed Subject & Associated Procedures
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)(i)
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(e)(2)(vii) | | 05000369/LER-1997-008-01, Has Been Cancelled Per 10CFR50.73 | Has Been Cancelled Per 10CFR50.73 | | | 05000369/LER-1997-009, :on 970906,reactor Trip Occurred on Both Units Due to Loss of non-vital Power to Plant components.Re-closed Breaker MKA-1B,restored Kxa to Svc,Replaced Breaker MKA-1B & Repaiared Cable Connection |
- on 970906,reactor Trip Occurred on Both Units Due to Loss of non-vital Power to Plant components.Re-closed Breaker MKA-1B,restored Kxa to Svc,Replaced Breaker MKA-1B & Repaiared Cable Connection
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
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-1997-010, :on 971023,determined That Potential Existed for Inadequate Margin to Be Maintained W/Regard to RCS Flow Rate Due to Analysis Deficiency.Ts Change Will Be Submitted to Eliminate Potential non-conservatism |
- on 971023,determined That Potential Existed for Inadequate Margin to Be Maintained W/Regard to RCS Flow Rate Due to Analysis Deficiency.Ts Change Will Be Submitted to Eliminate Potential non-conservatism
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2) | | 05000369/LER-1997-011, :on 971111,SSPS Surveillance Testing Was Noted to Be Inadequate.Caused by Inadequate Test Design Supplied by Vendor.Sps for Ssps Trains Were Revised |
- on 971111,SSPS Surveillance Testing Was Noted to Be Inadequate.Caused by Inadequate Test Design Supplied by Vendor.Sps for Ssps Trains Were Revised
| 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)
10 CFR 50.73(a)(2)(1) |
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