Similar Documents at Surry |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO
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[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18152A2811999-10-12012 October 1999 Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619 05000281/LER-1999-004-02, :on 981109,EDG Was Inoperable Longer than Allowed by TS Due to Governor Compensation Valve.Root Cause Evaluation Being Performed to Determine How Compensation Valve Became Closed1999-10-0101 October 1999
- on 981109,EDG Was Inoperable Longer than Allowed by TS Due to Governor Compensation Valve.Root Cause Evaluation Being Performed to Determine How Compensation Valve Became Closed
ML18152B3531999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Surry Power Station,Units 1 & 2.With ML18152B3371999-09-24024 September 1999 SER Accepting Third 10-year Interval Inservice Insp Plan Request for Relief SR-026 for Surry Power Station Unit 2 ML18152B6651999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Surry Power Station Units 1 & 2.With 05000280/LER-1999-006, :on 990802,determined That Plant Was Outside of App R Design Basis Due to Fire Barrier Deficiencies. Caused by Original Plant Design Deficiencies.Fire Watches Were Established & Mods Have Been Completed.With1999-08-27027 August 1999
- on 990802,determined That Plant Was Outside of App R Design Basis Due to Fire Barrier Deficiencies. Caused by Original Plant Design Deficiencies.Fire Watches Were Established & Mods Have Been Completed.With
05000280/LER-1999-005-01, :on 990731,effluent Radiation Monitors Were Declared Inoperable.Caused by Degraded Heat Trace Circuits for Monitors Sample Suction Line.Degraded Heat Trace Circuit Was Replaced & Addl Heat Trace Is Being Installed1999-08-27027 August 1999
- on 990731,effluent Radiation Monitors Were Declared Inoperable.Caused by Degraded Heat Trace Circuits for Monitors Sample Suction Line.Degraded Heat Trace Circuit Was Replaced & Addl Heat Trace Is Being Installed
ML18152B3841999-08-23023 August 1999 Safety Evaluation Granting Relief Request from ASME Section Xa Requirements for Containment Insp ML18152B3631999-08-23023 August 1999 Safety Evaluation Supporting Eddy Current Techniques Used by VEPCO to Determine Depth of Degradation Evident in Units SG Tubing & VEPCO Approach for Dispositioning Tubes with Avb Wear Indications ML18152B3831999-08-23023 August 1999 Safety Evaluation Granting Relief Request from ASME Section XI Requirements for Containment Insp 05000280/LER-1999-004-01, :on 990714,TS Violation Due to non-safety Related Fans Effect on CR Boundary Was Noted.Cause of Event Has Not Yet Been Determined.Cable Spreading Room Doors Were Operned to Reduce Pressure in Rooms1999-08-13013 August 1999
- on 990714,TS Violation Due to non-safety Related Fans Effect on CR Boundary Was Noted.Cause of Event Has Not Yet Been Determined.Cable Spreading Room Doors Were Operned to Reduce Pressure in Rooms
ML18151A3981999-08-13013 August 1999 SPS Unit 2 ISI Summary Rept for 1999 Refueling Outage ML18152B3791999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Surry Power Station,Units 1 & 2.With 05000281/LER-1999-003-02, :on 990705,auto Reactor Trip on Low Coolant Flow,Occurred.Caused by Loop Stop Valve Failure.Approved RCE Recommendations,Designed to Prevent Recurrence of Similar Event Will Be Implemented Through CAP1999-07-30030 July 1999
- on 990705,auto Reactor Trip on Low Coolant Flow,Occurred.Caused by Loop Stop Valve Failure.Approved RCE Recommendations,Designed to Prevent Recurrence of Similar Event Will Be Implemented Through CAP
ML20196J4781999-07-0101 July 1999 Safety Evaluation Supporting Amends 221 & 221 to Licenses DPR-32 & DPR-37,respectively ML18152B3911999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Surry Power Station,Units 1 & 2.With ML20195D3571999-06-0707 June 1999 Safety Evaluation Supporting Amends 220 & 220 to Licenses DPR-32 & DPR-37,respectively ML20195E2401999-05-31031 May 1999 Rev 2 to COLR for SPS Unit 2 Cycle 16 Pattern Ag ML18152B4341999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Surry Power Station,Units 1 & 2.With 05000281/LER-1999-002-02, :on 990425,MSSVs Tested Out of Tolerance for as Found Setpoint.Caused by Minor Setpoint Drift.No Immediate Action Required.Deviation Rept Submitted for Each Valve.With1999-05-18018 May 1999
- on 990425,MSSVs Tested Out of Tolerance for as Found Setpoint.Caused by Minor Setpoint Drift.No Immediate Action Required.Deviation Rept Submitted for Each Valve.With
ML18152B4161999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Surry Power Station Units 1 & 2.With 05000280/LER-1999-003-01, :on 990331,potential Loss of Charging Pumps Was Noted.Caused by Main CR Fire.Station Deviation Was Issued on 990331.With1999-04-28028 April 1999
- on 990331,potential Loss of Charging Pumps Was Noted.Caused by Main CR Fire.Station Deviation Was Issued on 990331.With
ML18152B6481999-04-14014 April 1999 Safety Evaluation Supporting Relief Requests IWE-2,4.5.6 & IWL-2 to Licenses DPR-32 & DPR-37 Respectively ML18152B6451999-04-13013 April 1999 SER Accepting Util Reactor Pressure Vessel Fluence Methodology for Surry Power Stations,Units 1 & 2 & North Anna Power Station,Units 1 & 2 Subject to Listed Limitations 05000281/LER-1999-001-02, :on 990301,RPS Relay Not Placed in Trip Resulted in Violation of TS 3.7.Caused by Lack of Procedural Guidance.Developed New Procedure to Provide More Explicit Instructions for Placing Stop Valve in Relay Trip1999-03-31031 March 1999
- on 990301,RPS Relay Not Placed in Trip Resulted in Violation of TS 3.7.Caused by Lack of Procedural Guidance.Developed New Procedure to Provide More Explicit Instructions for Placing Stop Valve in Relay Trip
ML18152B6511999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Surry Power Station Units 1 & 2 05000280/LER-1999-002-01, :on 990301,prematurely Released Fire Watches Resulted in Violation of TS 3.21.B.7.Caused by Inadequate Procedure.Procedure for Opening & Sealing Fire Stops Was Revised on 9902121999-03-29029 March 1999
- on 990301,prematurely Released Fire Watches Resulted in Violation of TS 3.21.B.7.Caused by Inadequate Procedure.Procedure for Opening & Sealing Fire Stops Was Revised on 990212
05000280/LER-1998-013, :on 981122,turbine/reactor Tripped on High Due to Short Circuit in Summator for MSL C Loop Channel III Flow Transmitter.Replaced 1-MS-FT1494 Summator & Module Repair Procedure Revised.With 9903190 Ltr1999-03-19019 March 1999
- on 981122,turbine/reactor Tripped on High Due to Short Circuit in Summator for MSL C Loop Channel III Flow Transmitter.Replaced 1-MS-FT1494 Summator & Module Repair Procedure Revised.With 9903190 Ltr
ML20207L8081999-03-12012 March 1999 Safety Evaluation Supporting Amends 219 & 219 to Licenses DPR-32 & DPR-37 ML18152B7331999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Surry Power Station,Units 1 & 2.With ML18152B5381999-02-16016 February 1999 SER Accepting Third 10-year Interval Inservice Insp Request for Relief for Surry Power Station,Unit 1.Staff Concludes That Licensee Proposed Alternative Will Provide Acceptable Level of Quality & Safety.Technical Ltr Rept Also Encl ML18152B5421999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Surry Power Station,Units 1 & 2.With ML18151A3031999-01-29029 January 1999 ISI Summary Rept for 1998 Refueling Outage,Including Form NIS-1, Owners Rept for ISIs & Form NIS-2, Owners Rept for Repairs & Replacements 05000280/LER-1999-001, :on 981222,auxiliary Feedwater Pipe Support Missed Surveillance.Caused by Personnel Error.Station Deviation Rept Was Submitted.Two Supports in Question Received Required Code Insp & Were Found Acceptable1999-01-21021 January 1999
- on 981222,auxiliary Feedwater Pipe Support Missed Surveillance.Caused by Personnel Error.Station Deviation Rept Was Submitted.Two Supports in Question Received Required Code Insp & Were Found Acceptable
ML18152B6011998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Surry Power Station,Units 1 & 2.With ML18152B5861998-12-18018 December 1998 SER Approving Request Relief Related to Inservice Testing Program at Surry Power Station Unit 1 ML20198F9221998-12-16016 December 1998 Safety Evaluation Supporting Amends 217 & 217 to Licenses DPR-32 & DPR-37,respectively 05000280/LER-1998-014, :on 981126,manual Reactor Trip in Response to Main Feedwater Regulating Valve Failure Occurred.Caused by Dislocation of Retaining Clip in Positioner.Control Room Operators Placed Unit in Safe,Shutdown Condition1998-12-16016 December 1998
- on 981126,manual Reactor Trip in Response to Main Feedwater Regulating Valve Failure Occurred.Caused by Dislocation of Retaining Clip in Positioner.Control Room Operators Placed Unit in Safe,Shutdown Condition
ML18152B5901998-12-16016 December 1998 Safety Evaluation Authorizing Request to Use Code Case N-577 as Alternative to Requirements of ASME Code Section XI for Surry Power Station,Unit 1 ML18152B7121998-12-0404 December 1998 LER 98-S01-00:on 981105,noted Failure to Deactivate Station Access Badge.Caused by Human Error.Licensee Will Now Deactivate Station Badges Before Clearance Is Revoked & Process for Badge Deactivations Have Been Strengthened 05000280/LER-1998-012, :on 981102,noted That EDGs Were Concurrently Inoperable.Caused by Required Testing Per TS 3.16.B.1.a.2. Redundant EDG Was Returned to Svc within Two Hour Period, Following Satisfactory Testing.With1998-12-0101 December 1998
- on 981102,noted That EDGs Were Concurrently Inoperable.Caused by Required Testing Per TS 3.16.B.1.a.2. Redundant EDG Was Returned to Svc within Two Hour Period, Following Satisfactory Testing.With
ML18152B7081998-11-30030 November 1998 Rev 0 to COLR for Surry 1 Cycle 16,Pattern Un ML18152B5721998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Surry Power Station,Units 1 & 2.With ML18152B6241998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Surry Power Station Units 1 & 2.With ML18152B6881998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Surry Power Station Units 1 & 2.With ML20151U7261998-09-0303 September 1998 Safety Evaluation Approving Exemption from Certain 10CFR20 Requirements Re Use of self-contained Breathing Apparatus with Enriched Oxygen in Subatmospheric Containments at SPS ML18153A3271998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Surry Power Station,Units 1 & 2 ML20237E9721998-08-26026 August 1998 Safety Evaluation Supporting Amends 216 & 216 to Licenses DPR-32 & DPR-37,respectively ML18153A3161998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Surry Power Station Units 1 & 2 05000280/LER-1998-010, :on 980715,low Intake Canal Level Instrument Channel I Was Declared Inoperable to Allow Testing of Intake Canal Level Probe 1-CW-LE-102.Subject Probe Was Cleaned by Diver,Tested & Channel I Was Returned to Operable Status1998-07-31031 July 1998
- on 980715,low Intake Canal Level Instrument Channel I Was Declared Inoperable to Allow Testing of Intake Canal Level Probe 1-CW-LE-102.Subject Probe Was Cleaned by Diver,Tested & Channel I Was Returned to Operable Status
1999-09-30
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NRC Form 3M 19-831 LICENSEE EVENT REPORT (LER) POW 28-06-01-01 U.S. NUCLEAR REGULATORY COMMIS&IOII!
APPROVED 0MB NO. 31LI0-01Ge EXPIRES: 1/31/111 FACILITY NAME 111 !DOCKET NUMIIER 121 T PAGE 131 Surry Power Station, Unit 2 o 15 I o 1.0 I o I 2 18 11 1 OF O 13 TITLE 141 Control/Relay Room Chiller Inoperable Due to Fouled Filter-Dryer Element IVINT DATE 1111 LEA NUMBER 1111 REPORT DATE 171 OTHER FACILITIES INVOLVED Ill MONTH DAY YEAR YEAR .}{ SE~~~~;~AL
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- -:-::-:-:::::,:: I I I I I I I EXPECTED SUPPLEMENTAL REPORT EXPECTED 1141 MONTH DAY YEAR SUBMISSION n YES (If y1r, comp/Ill EXPECTEO SUBMISSION DA TE) NO DATE {151 I I I ABSTRACT (Limir ro 1400 1P1ce,, i.e .* 1pproximer,/y fif?Hn 1ingl**11>>C*
rvpewrirr,n Hnel} (11) NRC Form 31111 19-831 On April 23, 1988 at 2316 hours0.0268 days <br />0.643 hours <br />0.00383 weeks <br />8.81238e-4 months <br />, with Unit 1 in cold shutdown and Unit 2 at 100% power, it was necessary to remove from service one of the three control room/relay room chillers, 1-VS-E-4A (EIIS-CHU), to perform minor maintenance.
The refrigerant filter-dryer was becoming clogged and the unit was secured to prevent the unit from tripping.
The "B" chiller unit (l-VS-E-4B) had previously been removed from service for a major overhaul, leaving only one chiller (l-VS-E-4C) operating.
This is contrary to Technical Specification 3 .14 which requ-ires one control room/relay room chiller to be operating and another to be operable.
The refrigerant filter-dryer elements of 1-VS-E-4A were becoming fouled with debris and required replacement.
Chiller.l-VS-E-4A had recently been replaced with a new unit. This type of debris is not unusual when a new chiller/unit is placed in service. Chiller 1-VS-E-4A was secured, the filter-dryer elements were replaced, and the chiller was returne*d to service at 2334 hours0.027 days <br />0.648 hours <br />0.00386 weeks <br />8.88087e-4 months <br /> on April 23, 1988. A major upgrade of the chiller units has been completed to improve the capacity and reliability of these units. 8806010092 880520 PDR ADOCK 05000281 S PDR NRC Farm 366A (9-831 FACILITY NAME (11 . LICENSEE EVENT REPORT (LERI TEXT CONTINUATION DOCKET NUMBER (2) POW 28-06-01-01 U.S. NUCLEAR REGULATORY COMMISSION APPROVED 0MB NO. 3150-0104 EXPIRES: 8/31 /88 LER NUMBER (61 PAGE (31 Surry Power Station, Unit 2 o Is I o I o I o I 2 I 8 I 1 8 I 8 -OI 11 1 -O I O O I 2 OF O I 3 TEXT /ff more ,poco i8 required, U/ltJ 11ddition11/
NRC Form 366A'8J (17) NRC FORM 366A (9-831 1.0 Description of the Event On April 23, 1988 at 2316 hours0.0268 days <br />0.643 hours <br />0.00383 weeks <br />8.81238e-4 months <br />, with Unit 1 in cold shutdown and Unit 2 at 100% power, it was necessary to remove from service one of.the three control room/relay room chillers, l-VS-E-4A (EIIS-CHU), to perform minor maintenance.
The refrigerant dryer was becoming clogged and the unit was secured to prevent the unit from tripping.
The "B" chiller unit (l-VS-E-4B) had previously been removed from service for a major overhaul, leaving only one chiller (1-VS-E-4C) operating.
This is contrary to Technical Specification 3.14 which requires one control room/relay room chiller to be operating and another to be operable.
Maintenance was pleted and 1-VS-E-4A was returned to service at 2334 hours0.027 days <br />0.648 hours <br />0.00386 weeks <br />8.88087e-4 months <br /> on April 23, 1988. The chiller was out of service for a period of mately 18 minutes. 2.0 Safety Consequences and Implications The control room/relay room air conditioning system consists of three 100% capacity air conditioning chiller units. The design temperature of the control and relay room spaces is from 40 degrees Fahrenheit to 100 degrees Fahrenheit, and the electrical equipment has been qualified to 120 degree$ Fahrenheit ambient temperature.
During this event, the control room/relay room air handling units, which receive chilled water from the chiller units, remained operable or operating.
In addition, there was no noticeable crease in ambient temperature of the affected.
areas. Therefore, the health and safety of the public were not affected.
3.0 Cause T.he refrigerant filter-dryer elements of 1-VS-E-4A were coming fouled with debris and required replacement.
Chiller l-VS-E-4A had recently been replaced with a new unit. This type of debris is not unusual when a new chiller unit is placed in service. 4.0 Immediate Corrective Action(s)
Chiller 1-VS-E-4A was secured, the filter-dryer elements were replaced, and the chiller was returned to service.
NRC Form 366A (9-83)
- ll'ACILITY NAME (1) LICENSEE E POW 28-06-01-01 T REPORT (LER) TEXT CONTINUAT N U.S. NUCLEAR *REGULATORY COMMISSION APPROVED 0MB NO. 3150..:.0104 EXPIRES: 8/31 /88 DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) :,:,:,:,:,:
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REVISION YEAR :;:;:;:;:;:
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NUMBER Surry Power Station; Unit 2 o Is I o I o I o 1 21 s 11 s I s -o 1 11 1 -o Io o 13 oF o p TEXT (ff mom_,,,, is required, u.,, additional NRC Farm 366A'sl (17) NRC FORM 366A (9-831 5.0 Additional Corrective Action(s)
A major upgrade of the chiller units has been completed to improve the capacity and reliability of these units. 6.0 Action(s)
Taken to Prevent Recurrence Replacement of the filter-dryers is considered normal maintenance.
No additional actions are required at this time. 7.0 Similar Events None. 8.0 Manufacturer/Model Number McQuay, Model KB086
. ' (' ----------~ May 20. 1988 U.S. Nuclear Regulatory Commission Document Control Desk 016 Phillips Building Washington, D.C. 20555 Gentlemen:
Vl,.Gl'NIA
!L(CT .. IC ANO POWER COMl',iNv Surry ,owe, Station ,. O. lo* 31& Surrv, Vlrglnl1 23883 Serial Hoa: Docket Ro.: Licensee Moo : 88-022 50-281 DPR-37 Pursuant to Surry Power Station Technical Specifications.
Virginia Electric and Power Company hereby submits the following Licensee Event Report for Surry Unit 2. REPORT NUMBER 88-011-00 This report has been reviewed by the Station Nuclear Safety and Operating Committee and will be reviewed by Safety Evaluation and Controlc Very truly yours~ David L. Benson Station Manager Enclosure cc: Dro J. Nelson Grace Regional Administrator Suite 2900 101 Marietta Street, RW Atlanta. Georgia 30323