Revised Page 6 to LER 84-024-01,providing Corrective Actions.Relay House Emergency Lighting Improved,Operating & Maint Activities Reviewed for Potential Impact on Offsite Power & Switchyard Computer Will Be Replaced by Mar 1988| ML20205R783 |
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| Site: |
McGuire  |
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| Issue date: |
11/09/1984 |
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| From: |
DUKE POWER CO. |
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| To: |
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| Shared Package |
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| ML20205R754 |
List: |
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| References |
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| LER-84-024, LER-84-24, NUDOCS 8606050484 |
| Download: ML20205R783 (1) |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEARML20236B7361987-10-20020 October 1987
Advises That LER 369/87-20 Re RHR Pump Being Inoperable for Greater than 72 H Will Be Submitted on 871027,due to Unresolved Concerns
05000369/LER-1984-030, Suppl to LER 84-030:review Revealed Installation Error That Would Result in Failure of Upper Head Injection Accumulator Discharge Valves to Isolate on Low Level.Analysis of Safety Significance & Encl1984-12-19019 December 1984
Suppl to LER 84-030:review Revealed Installation Error That Would Result in Failure of Upper Head Injection Accumulator Discharge Valves to Isolate on Low Level.Analysis of Safety Significance & Encl
05000369/LER-1984-024, Revised Page 6 to LER 84-024-01,providing Corrective Actions.Relay House Emergency Lighting Improved,Operating & Maint Activities Reviewed for Potential Impact on Offsite Power & Switchyard Computer Will Be Replaced by Mar 19881984-11-0909 November 1984
Revised Page 6 to LER 84-024-01,providing Corrective Actions.Relay House Emergency Lighting Improved,Operating & Maint Activities Reviewed for Potential Impact on Offsite Power & Switchyard Computer Will Be Replaced by Mar 1988
ML20081M7531983-11-0707 November 1983
Ler 83-064/99T-0:on 831024,Westinghouse Notified Util of Potentially Defective Relays SA1.Relay Used in Class IE Switchgear for Diesel Generator Protection & May Cause False Trip Output to Diesel Generator.Caused by Mfg Deficiency
05000369/LER-1982-0451982-06-30030 June 1982
LER 82-045/03L-0:on 820527,HEPA & Carbon Adsorber Filters Periodic Test Revealed That Carbon Adsorber Filters on Auxiliary Bldg Ventilation Sys Failed to Pass Freon Penetration Test.Caused by Carbon Settlement
05000369/LER-1982-0441982-06-30030 June 1982
LER 82-044/03L-0:on 820526,HEPA & Carbon Adsorber Filters Periodic Test Revealed That Auxiliary Bldg Ventilation Sys Filters Failed to Pass Total DOP Penetration Test.Caused by Vibration
05000369/LER-1982-0431982-06-30030 June 1982
LER 82-043/03L-0:on 820520,HEPA & Carbon Absorber Filters Periodic Test Indicated Carbon Absorber Filter on Fuel Pool Ventilation Sys Failed to Pass Freon Penetration Test. Caused by High Humidity.Filters Replaced
05000369/LER-1982-0421982-06-30030 June 1982
LER 82-042/03L-0:on 820519,HEPA & Carbon Filters Periodic Test Revealed That HEPA after-filters on Train B of Annulus Ventilation Sys Failed to Pass Dioctyl Phthalate Penetration Test.Caused by Dirt in Filter
05000369/LER-1982-0411982-06-30030 June 1982
LER 82-041/03L-0:on 820513,HEPA & Carbon Absorber Filters Periodic Test Revealed That Carbon Absorber Filter on Train a of Annulus Ventilation Sys Failed to Pass Halogenated Hydrocarbon Penetration Test.Caused by Dirt in Filter
05000369/LER-1982-0371982-06-30030 June 1982
LER 82-037/03L-0:on 820513,while in Mode 1,performance of Nuclear Air Cleaning Sys Air Flow Measurement Periodic Test Revealed That Train a of Annulus Ventilation Sys Failed to Meet Flow Acceptance Criteria.Caused by Component Failure
05000369/LER-1982-0191982-03-30030 March 1982
LER 82-019/03L-0:on 820228,during Mode 4,performance of RCS Pressure Isolation Valve Leak Rate Test Determined That 3 Valves Failed Test.Caused by Failure of Valves to Seat Properly.Valves Disassembled & Repaired
1987-10-20
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20217G7951999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for McGuire Nuclear Station,Units 1 & 2
ML20217F3661999-09-22022 September 1999
Rev 18 to McGuire Unit 1 Cycle 14 Colr
ML20212D1911999-09-20020 September 1999
SER Accepting Exemption from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Closed System Isolation Valves for McGuire Nuclear Station,Units 1 & 2
ML20216E8851999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Units 1 & 2
ML20211B1281999-08-31031 August 1999
Dynamic Rod Worth Measurement Using Casmo/Simulate
ML20217G8101999-08-31031 August 1999
Revised Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2
ML20211G5261999-08-24024 August 1999
SER Accepting Approval of Second 10-year Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1
ML20211F3441999-08-17017 August 1999
Updated non-proprietary Page 2-4 of TR DPC-NE-2009
ML20210S2371999-07-31031 July 1999
Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2
ML20216E8951999-07-31031 July 1999
Revised Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2
ML20209E4361999-07-0909 July 1999
SER Agreeing with Licensee General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation
ML20196K6631999-07-0707 July 1999
Safety Evaluation Supporting Licensee 990520 Position Re Inoperable Snubbers
ML20209H1631999-06-30030 June 1999
Monthly Operating Repts for June 1999 for McGuire Nuclear Station,Units 1 & 2
ML20210S2491999-06-30030 June 1999
Revised Monthly Operating Rept for June 1999 for McGuire Nuclear Station,Units 1 & 2
ML20209H1731999-05-31031 May 1999
Revised Monthly Operating Rept for May 1999 for McGuire Nuclear Station,Units 1 & 2
ML20206T4771999-05-31031 May 1999
Rev 3 to UFSAR Chapter 15 Sys Transient Analysis Methodology
ML20196L1881999-05-31031 May 1999
Non-proprietary Rev 1 to DPC-NE-3004, Mass & Energy Release & Containment Response Methodology
ML20195K3691999-05-31031 May 1999
Monthly Operating Repts for May 1999 for McGuire Nuclear Station,Units 1 & 2
ML20206N3511999-05-11011 May 1999
Safety Evaluation Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Movs
ML20195K3761999-04-30030 April 1999
Revised MORs for Apr 1999 for McGuire Nuclear Station,Units 1 & 2
ML20206R0891999-04-30030 April 1999
Monthly Operating Repts for Apr 1999 for McGuire Nuclear Station,Units 1 & 2
ML20205L2341999-04-0505 April 1999
SFP Criticality Analysis
ML20206R0931999-03-31031 March 1999
Revised Monthly Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2
ML20205P8991999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2
ML20205C4171999-03-25025 March 1999
Special Rept 99-02:on 801027,Commission Approved for publication,10CFR50.48 & 10CFR50 App R Delineating Certain Fire Protection Provisions for Nuclear Power Plants Licensed to Operate Prior to 790101.Team Draft Findings Reviewed
ML20207K2051999-03-0505 March 1999
Special Rept 99-01:on 990128,DG Tripped After 2 H of Operation During Loaded Operation for Monthly Test.Caused by Several Components That Were Degraded or Had Intermittent Problems.Parts Were Replaced & Initial Run Was Performed
ML20204C8911999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for McGuire Nuclear Station,Units 1 & 2
ML20205P9021999-02-28028 February 1999
Revised Monthly Operating Repts for Feb 1999 for McGuire Nuclear Station,Units 1 & 2
ML20204C8961999-01-31031 January 1999
Revised Monthly Operating Repts for Jan 1999 for McGuire Nuclear Station,Units 1 & 2
ML20199E0301998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for McGuire Nuclear Station,Units 1 & 2
ML20216F9931998-12-31031 December 1998
Piedmont Municipal Power Agency 1998 Annual Rept
ML20198A4481998-12-11011 December 1998
Safety Evaluation Concluding That for Relief Request 97-004, Parts 1 & 2,ASME Code Exam Requirements Are Impractical. Request for Relief & Alternative Imposed,Granted
ML20198D7561998-11-30030 November 1998
Monthly Operating Repts for Nov 1998 for McGuire Nuclear Station,Units 1 & 2
ML20199E0491998-11-30030 November 1998
Revised Monthly Operating Rept for Nov 1998 for McGuire Nuclear Station,Units 1 & 2 Re Personnel Exposure
ML20199E9651998-11-24024 November 1998
Rev 1 to ATI-98-012-T005, DPC Evaluation of McGuire Unit 1 Surveillance Weld Data Credibility
ML20196D4171998-11-24024 November 1998
Special Rept 98-02:on 981112,failure to Implement Fire Watches in Rooms Containing Inoperable Fire Barrier Penetrations,Was Determined.Repair of Affected Fire Barriers in Progress
ML20196G0581998-11-0606 November 1998
Rev 17 to COLR Cycle 13 for McGuire Unit 1
ML20196G0761998-11-0606 November 1998
Rev 15 to COLR Cycle 12 for McGuire Unit 2
ML20198D7771998-10-31031 October 1998
Revised Monthly Operating Rept for Oct 1998 for McGuire Nuclear Station,Units 1 & 2
ML20195E5961998-10-31031 October 1998
Monthly Operating Repts for Oct 1998 for McGuire Nuclear Station,Units 1 & 2
ML20154L6251998-09-30030 September 1998
Monthly Operating Repts for Sept 1998 for McGuire Nuclear Station,Units 1 & 2
ML20195E6021998-09-30030 September 1998
Revised Monthly Operating Rept for Sept 1998 for McGuire Nuclear Station,Units 1 & 2
ML20154B4131998-09-22022 September 1998
Rev 0 to ISI Rept for McGuire Nuclear Unit 1 Twelfth Refueling Outage
ML20151W3521998-09-0808 September 1998
Special Rept 98-01:on 980819,maint Could Not Be Performed on FPS Due to Isolation Boundary Leakage.Caused by Inadequate Info Provided in Fire Impairment Plan.Isolated Portion of FPS Was Returned to Svc
ML20154L6321998-08-31031 August 1998
Rev 1 to MOR for Aug 1998 for McGuire Nuclear Station,Unit 1
ML20153B3741998-08-31031 August 1998
Monthly Operating Repts for Aug 1998 for McGuire Nuclear Station,Units 1 & 2
ML20236U1601998-07-31031 July 1998
Non-proprietary DPC-NE-2009, DPC W Fuel Transition Rept
ML20237B2381998-07-31031 July 1998
Monthly Operating Repts for July 1998 for McGuire Nuclear Station,Units 1 & 2
ML20153B3931998-07-31031 July 1998
Revised Monthly Operating Repts for Jul 1998 for McGuire Nuclear Station,Units 1 & 2
ML20236P0451998-07-0808 July 1998
Part 21 Rept Re non-conformance & Potential Defect in Component of Nordberg Model FS1316HSC Standby Dg.Caused by Outer Spring Valves Mfg from Matl That Did Not Meet Specifications.Will Furnish Written Rept within 60 Days
1999-09-30
[Table view] |
LER-2084-024, Revised Page 6 to LER 84-024-01,providing Corrective Actions.Relay House Emergency Lighting Improved,Operating & Maint Activities Reviewed for Potential Impact on Offsite Power & Switchyard Computer Will Be Replaced by Mar 1988 |
| Event date: |
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| 3692084024R00 - NRC Website |
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text
s I
m4 Form 364A U S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER) TEXT CONTINUATION AarRovEo ove No siso-oto4 E xPIRES 8/3111$
FACILIT Y NAME (H COCK kT NUMBER (2) LER NUMBER 16) PAGE(31 VIA" vega vs McGuire Nuclear Station, Unit 1 0 l5 l 0 j o l 0 l 3l 6l 9 8l4 _
0l 2 l4 _ 01 0l 6 or 0l6 1En w n-. .n. . <.wr.< . .emc ur- unm n
~10 seconds later. Flow came on full when the pumps were restarted as the valves were already open. The operators secured the Turbine Driven Auxiliary Feedwater pump at 12:57: 39 as levels were above their no-load target of 38%. The operators then adjusted auxiliary feedwater flow to maintain steam generator level with the higher than normal stean demand.
The levels smoothed out once main steam was isolated. Ac 30 minates after the trip all 4 steam generators were within 4% of the no-load target level.
At 21:49:48 the 2 out of 3 undervoltage logic for ETA and ETB was satisfied. The blackout logic initiated properly fcr both trains, and both diesel generators started. Once the 8 second time delay and voltage test were completed, the two sequencers load shed and loaded the blackout load groups on the diesels. All loads were on the diesel within 15 seconds of the blackout logic actuation, as expected by the accelerated sequence.
Containment ventilation was isolated at 21:49:34 when the circuit breaker for EMF's 38, 39, 40 opened.
No Safety Injection actuation occurred. The pressurizer PORV's and code safety valves were not challenged. Indicated pressurizer and steam generator levels remained on-scale. The primary temperature decrease was within the 100 degrees F/ hour Technical Specification limit. There was no abnormal release of radioactivity during this event, and no abnormal coolant leakage.
CORRECTIVE ACTION: Corrective actions have been initiated to prevent recurrence of this event. These actions include addition of a control output relay test circuit to provide computer maintenance and operating personnel with confirmation that all control output relays are open prior to re-enabling control outputs. Also, the computer's initialization software has been modified to reset all control output relays to the "open" position on re-initialization (manual and auto-restart).
Relay settings on the Craighead White and Mecklenburg Black lines, which tripped on overcurrent during the event, have been increased to allow these two lines to carry full Unit 1 output.
Other related corrective actions included:
- 1) Relay house emergency lighting was improved. Low-level emergency lighting in the switchyard relay house hampered restoration of power to the switchyard.
- 2) Operating and maintenance activities were reviewed for potential impact on off-site power.
- 3) Consideration is being given to the replacement of existing " latching" type control outputs with " momentary" type outputs.
- 4) Independent of this incident, plans had been made to replace the existing switchyard computer by March 1988.
8606050484 860530 PDR ADOCK 05000369
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