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At approximately 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> on February 5, 1988, with Unit 1 in Mode 3, prior to initial criticality, concurrent valve packing adjustments were performed on two (2) Main Steam Isolation Valves (MSIVs).
The work was approved by a licensed Unit Supervisor who did not believe it would render the valves inoperable.
Technical Specification Limiting Condition for Operation (LCO) 3.7.1.5 only provides action for single MSIV inoperability in Mode 3.
On Febr'2ary 6, 1988, with the unit it. Mode 4 due to an unrelated event, the duty Shift Supervisor upon learning that the packing adjustments had been performed, declared the MSIVs inoperable.
However, because of an error in judgement, the additional requirements of LCO 3.6.3 for Containment Isolation Valves were not carried out until approximately 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br /> on February 7, 1988.
The MSIVs were restored to operable status at approximately 1730 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.58265e-4 months <br /> on February 7, 1988. The primary cause of this event is insufficient familiarity with the applicable Technical Specifications.
Corsective actions to prevent recurrence include more in-depth training of operators in operability requirements for containment isolation valves and Technical Specification Requirements.
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At approximately 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> on February 5, 1988, with Unit 1 in Mode 3 prior to initial criticality and with Main Steam Isolation Valves (MSIVs) closed, an SRO-licensed Unit Supervisor approved concurrent valve packing adjustments on both "A" and "C" MSIVs to stop stearn leaks.
Prior to work start approval, the Unit Supervisvr ensured that a Post Maintenance Test would be performed to verify valve strcke time.
However, the Unit Supervisor did not believe that adjusting valve packing would rendc-MSIVs J, operable.
Therefore he did not log the MSIVs as inoperable in
.rability Tracking Log nor did he specify on the Maintenance Work Req JWR) that work be completed within the applicable Limiting Condition f' eration action statement time constraints.
At approximately 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> on February 5, 1988, craftsmen performed the packing adjustments per the approved MVR.
The packing adjustments did not stop the leakage, therefore, according to the work package ir tactions, the craftsmen returned the work package to their foreman and did x-
- 1. form the Control Room that they had completed their work.
At approximately 0258 hours0.00299 days <br />0.0717 hours <br />4.265873e-4 weeks <br />9.8169e-5 months <br /> on February 6, 1988, Unit I cooled down to Mode 4 due to an unrelated Technical Specification action requirement.
At approximately 1325 hours0.0153 days <br />0.368 hours <br />0.00219 weeks <br />5.041625e-4 months <br /> on February 6, 1988, the Shift Supervisor learned that the packings or. "A" and "C" MSIVs had been adjusted. He immediately declared the MSIVs inoperable and made the appropriate entry in the Operability Tracking Log.
The Unit 1 Operations Manager was informed.
He and the Shift Supervisor reviewed Technical Specificction 3.7.1.5 concerning MSIV operability and concluded that the valves did not require stroke timing until in Mode 3, when steam pressure was equalized across the MSIVs during Main Steam header varming.
Technical Specification 3.7.1.5 allows entry into Mode 3 prior to verifying MSIV operability provided the valves are closed. The Unit i Operations Manager also concluded that because the valves were in their fail-safe position, that the additional action requirements of Technical Specification LCO 3.6.3 for Containment Isolation Valves were not applicable for MSIVs.
At approximately 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> on February 6, 1988, the evening duty Shift Supervisor called the Unit 1 Operations Manager to discuss LCO 3.6.3 applicability.
Again they concluded that only LCO 3.7.1.5 applied.
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bouth Texas, Unit 1 o l5 l0 l0 j o l4 l 9l8 q8 0l1l5 0 l0 0l 3 0F 0l5 Ym r, w Aac w maa wim DESCRIPTION OF OCCURRENCE (Cont.)
At approximately 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> on February 7, 1980, in discussion with the resident NRC inspector, it was determined LCO 3.6.3 was applicable.
Power was removed from "A" and "C" MSIVs at approximately 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br /> to comply with Technical Specification 3.6.3 action requirements. At this time it was also determined that a 24-hour Technical Specification violation notification was required because power had not been removed from the valve actuators within four (4) hours of declaring the valves inoperable on February 6, 1988, as required by LCO 3.6.3.
At approximately 1730 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.58265e-4 months <br /> on February 7, 1988, with the unit in Mode 4, the "A"
and "C" MSIVs were stroked and timed satisfactory per the approved surveillance procedure. The MSIVs were declared operable at this time and Technical Specifications 3.6.3 and 3.7.1.5 satisfied.
At approximately 1734 hours0.0201 days <br />0.482 hours <br />0.00287 weeks <br />6.59787e-4 months <br /> on February 7, 1988, the NRC was notified via the ENS of Technical Specification non-compliance pursuant to the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> reportability requirements.
The "A" and "C" MSIVs were inoperable for approximately 56 hours6.481481e-4 days <br />0.0156 hours <br />9.259259e-5 weeks <br />2.1308e-5 months <br />. However, they remained closed thrce2ghout this time until stroked for surveillance testing.
At approximately 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> on February 8, 1988, the resident NRC inspector dicussed Technical Specification 3.0.3 applicability to this event with the Unit 1 Operations Manager, and it was decided the 2 nit had not complied with Technical Specifications in that two (2) MSIVs were inoperable while the unit in Mode 3, contrary to the action statement requirements of LCO 3.7.1.5.
was A second notification to the NRC was made pursuant to this violation at approximately 1128 hours0.0131 days <br />0.313 hours <br />0.00187 weeks <br />4.29204e-4 months <br /> on February 9, 198U, via the ENS.
_CAUSE OF OCCURRENCE:
The root causes for their event are:
(1) Failure of the Unit Supervisor to recognize that the MSIV's were inoperable due to insufficient familiarity with Technical Specifications 3.6.3 and 3.7.1.5.
(2) Failure of the Unit Supervisor to involve his supervisors in deciding the operability of the valves.
(3) The Te:hnical Specifications do not clearly identify that Section 3.6.3 applies to the MSIV's and it does not clearly specify tho action requirements for this type of containment isolation if the specification is applied.
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U S. NUCLEfJ KE1ULtTZY COMMI58 TON NRC 7erm 364A LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Areaoveo ous No. siso-oio4 EXPIRE S. 8/31/55 P ACILITY NAME II)
DOCK ET NUMBER GI LER NUM8t R 85)
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CORRECTIVE ACTIONS
The following corrective actions have been or will be taken to prevent recurrence of this event:
1.
The Unit 1 Operations Manager has issued a memo to the Shift Jupervisors which discusses this event and the applicability of Technical Specification LCO 3.6.3 to all containment isolation valves listed in FSAR table 3.6.2.4-2.
2.
Intermediate corrective action for this event will be to review the operability requirements for containment isolation valves with Licensed Operators between March 28 and April 29, 1988 during requalification training.
3.
Long Term corrective action will be the evaluation and revision as necessary to the Licensed Operator Training Program to ensure that Technical Specifications are taught with emphasis on practical applications.
This will be completed by August 31, 1988.
4.
Nuclear Plant Operations has implemented a procedure which requires a three party review by the Shift Supervisor, Unit Supervisor and Shift Technical Advisor of all LCO actions.
ANALYSIS OF EVENT
This event had no impact on the health and safety of the public because the Main Steam Isolation Valves were closed for the duration of the event and the unit had not achieved criticality by this time.
The MSIVs were to have been stroke tested immediately after opening to prove operability as detailed in the Post-Maintenance Instructions of the MWR.
However, this event is reportable as a Licensee Event Report under 10CFR50.73(a)(2)(1)(B) because the unit was operating in a mode prohibited by Technical Specifications.
Additionally, because this event was the result of a single cause which allowed independent trains to become inoperable, this event is also reportable pursuant to 10CFR50.73(a)(2)(vii).
NL,LER88015 104r33
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ADDITIONAL INFORMATION
There has been one other reportable event due to a misinterpretation of the Technical Specifications.
This has been reported to the NRC as LER 86-019.
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The Light company P.O. Ilox 1700 llouston, Texas 77001 (713) 228 9211 llouston Lighting & Power March 22, 1988 ST-HL-AE-2527 File No.:
G26 10CFR50.73 U.
S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, DC 20555 South Texas Project Electric Generating Station Unit 1 Docket No. STN 50-498 License Event Report 88-015 Regarding Two MSIVs Being Inoperable Resulting in a Technical Specification Violation On February 7, 1988, Houston Lighting & Power Company (HL&P) notified the NRC pursuant to 10CFR50.72 of a reportable event regarding two (2) Main Steam Isolation Valves (MSIVs) being inoperable at the same time resulting in a violation of the Technical Specifications.
The event did not have any adverse impact on the health and safety of the public.
In accordance with 10CFR50.73, HL&P submits the attached Licensee Event Report (LER 88-015).
If you should have any questions on this matter, please contact Mr. C.A. Ayala at (512) 972-8628.
G. E. Vaughn Vice President Nuclear Plant Operations GEV/MEP/eg
Attachment:
Licensee Event Report 88-015 Regarding Two MSIVs Being Inoperable Resulting in a Technical Specification Violation Ob A Subsidiary of Ilouston Industries Incorporated NL.LER88015
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Ilouston Lighting & Power Company
- - ST-HL-AE-2550 File No.: G26 Page 2 cc Regional Administrator, Region IV Rufus S. Scott Nuclear Regulatory Commissien Associate General Counsel' 611 Ryan Plaza Drive, Suite 1000 Houston Lighting & Power Company Arlington, TX 76011 P. O. Box 1700 Houston, TX 77001 N. Prasad Kadambi, Project Manager U. S. Nuclear Regulatory Commission INPO 1 White Flint North Records Center 11555 Rockville Pike 1100 Circle 75 Parkway Rockville, MD 20859 Atlanta, Ga. 30339-3064 Dan R. Carpenter Dr. Joseph M. Hendrie Senior Resident Inspector / Operations 50 Bellport Lane e/o U. S.-Nuclear Regulatory Commission Bellport, NY 11713 P. O.. Box 910 Bay City, TX 77414 Don L. Garrison Resident Inspector / Construction c/o U. S. Nuclear Regulatory Commission P. O. Box 910 Bay City, TX 77414 J. R. Newman, Esquire Newman & Holtzinger, P.C.
1615 L Street, N.W.
Washington, DC 20036 R. L. Range /R. P. Verret Central Power & Light Company P. O. Box 2121 Corpus Christi, TX 78403 R. John Miner (2 copies)
Chief Operating Officer City of Austin Electric Utility 721 Barton Springs Road Austin, TX 78704 R. J. Costello/M. T. Hardt City Public Service Board P. O. Box 1771 San Antonio, TX 78296 Revised 03/18/88 NL.LER. DISTR.1
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| 05000498/LER-1988-002, :on 880105,discovered Failure to Perform Local Leakage Rate Testing on Containment Isolation Valves.Caused by Lack of Training Re Required post-maintenance Testing. Valves Retested & Personnel Counseled |
- on 880105,discovered Failure to Perform Local Leakage Rate Testing on Containment Isolation Valves.Caused by Lack of Training Re Required post-maintenance Testing. Valves Retested & Personnel Counseled
| 10 CFR 50.73(a)(2)(1) | | 05000498/LER-1988-003, :on 880106,automatic Actuation of Control Room Ventilation Sys to Recirculation Mode Occurred.Caused by Improper Operator Action When Transferring Distribution Panel Back to Preferred Power Supply |
- on 880106,automatic Actuation of Control Room Ventilation Sys to Recirculation Mode Occurred.Caused by Improper Operator Action When Transferring Distribution Panel Back to Preferred Power Supply
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000498/LER-1988-004, Forwards LER 88-004-00 Re 880110 ESF Actuation Due to Loose or Corroded Toxic Gas Monitor Computer Board Electrical Connection.Suppl to LER Will Be Submitted Upon Completion of Evaluation of Root Cause by 880309 | Forwards LER 88-004-00 Re 880110 ESF Actuation Due to Loose or Corroded Toxic Gas Monitor Computer Board Electrical Connection.Suppl to LER Will Be Submitted Upon Completion of Evaluation of Root Cause by 880309 | | | 05000498/LER-1988-005, :on 880110,inadequate Surveillance Performed on Control Room Intake Air Radioactivity Monitor.Caused by Procedure & Operator Errors.Procedures Will Be Revised & Addl Guidance Will Be Given to Operators |
- on 880110,inadequate Surveillance Performed on Control Room Intake Air Radioactivity Monitor.Caused by Procedure & Operator Errors.Procedures Will Be Revised & Addl Guidance Will Be Given to Operators
| 10 CFR 50.73(a)(2)(1) | | 05000498/LER-1988-006, :on 880112,inadequate Surveillance of Master Relays Determined.Caused by Inadequate Technical Development of Surveillance Procedure.Surveillance Procedures Corrected |
- on 880112,inadequate Surveillance of Master Relays Determined.Caused by Inadequate Technical Development of Surveillance Procedure.Surveillance Procedures Corrected
| | | 05000498/LER-1988-007, :on 880115,surveillance Procedure Review Identified Incorrectly Applied Air Density Correction Factors Used in Airflow Calculations.Caused by Weakness in Review of HVAC Filter Test Procedures |
- on 880115,surveillance Procedure Review Identified Incorrectly Applied Air Density Correction Factors Used in Airflow Calculations.Caused by Weakness in Review of HVAC Filter Test Procedures
| 10 CFR 50.73(a)(2)(1) | | 05000498/LER-1988-008, :on 880120,safety-related Electrical Cable Splices Incorrectly Installed.Caused by Personnel Not Following Correct Cable Splice Detail Sheet.Procedures Revised W/Detailed Instructions |
- on 880120,safety-related Electrical Cable Splices Incorrectly Installed.Caused by Personnel Not Following Correct Cable Splice Detail Sheet.Procedures Revised W/Detailed Instructions
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability | | 05000498/LER-1988-009, :on 880123,unanticipated Safety Injection Signal Occurred from Solid State Protection Sys Actuation Train A.Caused by Inadequate Surveillance Procedure.Train a & B Master Relay Test Procedures Revised |
- on 880123,unanticipated Safety Injection Signal Occurred from Solid State Protection Sys Actuation Train A.Caused by Inadequate Surveillance Procedure.Train a & B Master Relay Test Procedures Revised
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000498/LER-1988-010, :on 870923,maint Work Request Prepared Stating That Charging Header Pressure Indicator Reading 1,000 Psi More than Local Process Pressure Gauge.Caused by Lack of Identification in Tech Spec Re Subj Loop |
- on 870923,maint Work Request Prepared Stating That Charging Header Pressure Indicator Reading 1,000 Psi More than Local Process Pressure Gauge.Caused by Lack of Identification in Tech Spec Re Subj Loop
| 10 CFR 50.73(a)(2)(1) | | 05000498/LER-1988-011, :on 880127,nonperformance of Scheduled Surveillance Test on Essential Chilled Water Pump 11B Discovered.Caused by Inadequate Control of Test Packages. Procedure Rev Underway |
- on 880127,nonperformance of Scheduled Surveillance Test on Essential Chilled Water Pump 11B Discovered.Caused by Inadequate Control of Test Packages. Procedure Rev Underway
| 10 CFR 50.73(a)(2)(1) | | 05000498/LER-1988-012, :on 880129,limiting Value for Stroke Time on Valve CV-FCV-0205 Found Omitted from Inservice Test Plan. Caused by Inadequate Administrative Control.Temporary Procedure ITSP03-CV-0001 Corrected Deficiency |
- on 880129,limiting Value for Stroke Time on Valve CV-FCV-0205 Found Omitted from Inservice Test Plan. Caused by Inadequate Administrative Control.Temporary Procedure ITSP03-CV-0001 Corrected Deficiency
| 10 CFR 50.73(a)(2)(1) | | 05000498/LER-1988-013, :on 880204,two Time Delay Relays in solid-state Protection Sys Not Tested During Surveillance.Caused by Inadequate Review of Vendor Technical Manual & Actuation Logic Schematics.Procedure Revised |
- on 880204,two Time Delay Relays in solid-state Protection Sys Not Tested During Surveillance.Caused by Inadequate Review of Vendor Technical Manual & Actuation Logic Schematics.Procedure Revised
| 10 CFR 50.73(a)(2)(1) | | 05000498/LER-1988-014, :on 880204,reactor Protection Sys Actuation Occurred.Caused by Software Design Error in Qualified Display Processing Sys (Qdps) Temp Averaging Sys.Qdps Modified to Prevent Recurrence |
- on 880204,reactor Protection Sys Actuation Occurred.Caused by Software Design Error in Qualified Display Processing Sys (Qdps) Temp Averaging Sys.Qdps Modified to Prevent Recurrence
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000498/LER-1988-015, :on 880206,two MSIVs Declared Inoperable When Duty Shift Supervisor Learned That Packing Adjustments Performed.Addl Requirements for Containment Isolation Valves Not Carried Out Until 880207 |
- on 880206,two MSIVs Declared Inoperable When Duty Shift Supervisor Learned That Packing Adjustments Performed.Addl Requirements for Containment Isolation Valves Not Carried Out Until 880207
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(1) | | 05000498/LER-1988-016, Forwards LER 88-016-00 in Response to NRC Re Violations Noted in Insp Rept 50-498/88-01 Concerning Feedwater Flow Transmitters.Violation Fully Addressed as LER Subj.Corrective Actions Completed & Reviewed by NRC | Forwards LER 88-016-00 in Response to NRC Re Violations Noted in Insp Rept 50-498/88-01 Concerning Feedwater Flow Transmitters.Violation Fully Addressed as LER Subj.Corrective Actions Completed & Reviewed by NRC | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(1) | | 05000498/LER-1988-017, :on 880211,operations Personnel Notified That Personnel Air Lock Sealing Air Sys Containment Isolation Valves Did Not Meet Requirements of GDC 57.Caused by Design Error.Mod Implemented to Meet Requirement |
- on 880211,operations Personnel Notified That Personnel Air Lock Sealing Air Sys Containment Isolation Valves Did Not Meet Requirements of GDC 57.Caused by Design Error.Mod Implemented to Meet Requirement
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000498/LER-1988-018, :on 880212,safety Injection Actuation Initiated by Excessive Cooldown Protection Logic Following RCS Flow Coastdown Measurement Test.Caused by Formation of Slug of Cool Water in Coolant Loop.Test to Be Revised |
- on 880212,safety Injection Actuation Initiated by Excessive Cooldown Protection Logic Following RCS Flow Coastdown Measurement Test.Caused by Formation of Slug of Cool Water in Coolant Loop.Test to Be Revised
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000498/LER-1988-019, :on 880212 & 13 Unit Cooldown to Satisfy Tech Spec 3.0.3 Prematurely Terminated.Caused by Personnel Error. Addl Guidance for Determining Equipment Operability & Special Training Held |
- on 880212 & 13 Unit Cooldown to Satisfy Tech Spec 3.0.3 Prematurely Terminated.Caused by Personnel Error. Addl Guidance for Determining Equipment Operability & Special Training Held
| 10 CFR 50.73(a)(2)(1) | | 05000498/LER-1988-020, :on 880215,review of Inservice Test on Essential Cooling Water Screen Wash Booster Pump 1A Revealed That Pump Test Data Outside Acceptable Range.Caused by Personnel Error.Special Training Initiated |
- on 880215,review of Inservice Test on Essential Cooling Water Screen Wash Booster Pump 1A Revealed That Pump Test Data Outside Acceptable Range.Caused by Personnel Error.Special Training Initiated
| 10 CFR 50.73(a)(2)(1) | | 05000498/LER-1988-021, :on 880224,ESF Actuation Due to Inverter Failure.Caused by Dc to Dc Converter Assembly Failure.Plant Engineering Dept Reviewed Results of Vendor Failure Analysis.Failures Identified as Random |
- on 880224,ESF Actuation Due to Inverter Failure.Caused by Dc to Dc Converter Assembly Failure.Plant Engineering Dept Reviewed Results of Vendor Failure Analysis.Failures Identified as Random
| 10 CFR 50.73(a)(2) | | 05000498/LER-1988-023, :on 880311,frequency of Required Surveillance Test on Essential Cooling Water Screen Wash Booster Pump Not Doubled as Required.Caused by Inadequate Procedure.Procedure Revised to Define Surveillance Frequency Info |
- on 880311,frequency of Required Surveillance Test on Essential Cooling Water Screen Wash Booster Pump Not Doubled as Required.Caused by Inadequate Procedure.Procedure Revised to Define Surveillance Frequency Info
| 10 CFR 50.73(a)(2)(1) | | 05000498/LER-1988-024, :on 880316,discovered That Resetting Safeguards Test Cabinet Master Reset Would Reset & Block Safety Injection Actuation on Train A,B or C.Caused by Design Error.Design Change Issued to Modify Circuitry |
- on 880316,discovered That Resetting Safeguards Test Cabinet Master Reset Would Reset & Block Safety Injection Actuation on Train A,B or C.Caused by Design Error.Design Change Issued to Modify Circuitry
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000498/LER-1988-025, :on 880323,ESF Actuation of Control Room Ventilation Sys to Recirculation Mode Occurred.Caused by Actuation of Control Room Ventilation Radiation Monitor. Continued Surveillance Testing Will Be Done |
- on 880323,ESF Actuation of Control Room Ventilation Sys to Recirculation Mode Occurred.Caused by Actuation of Control Room Ventilation Radiation Monitor. Continued Surveillance Testing Will Be Done
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000498/LER-1988-026, :on 880330,reactor Trip & Safety Injection Sequence Initiated Due to Partial Offsite Power Loss.Caused by Personnel Error & Design Inadequacy.Event Incorporated in Training Session & Protection Sys Evaluated |
- on 880330,reactor Trip & Safety Injection Sequence Initiated Due to Partial Offsite Power Loss.Caused by Personnel Error & Design Inadequacy.Event Incorporated in Training Session & Protection Sys Evaluated
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000498/LER-1988-028, :on 880401,leakage Observed at Number of Locations in aluminum-bronze Essential Cooling Water Sys. Caused by Crevice Corrosion in Small Bore Fittings & Valves. Leaking Components Replaced |
- on 880401,leakage Observed at Number of Locations in aluminum-bronze Essential Cooling Water Sys. Caused by Crevice Corrosion in Small Bore Fittings & Valves. Leaking Components Replaced
| | | 05000498/LER-1988-029, :on 880424,Tech Spec 3.0.3 Entered on Two Occasions for Total of 17 Minutes During Testing of Steam Generator Porvs.Caused by Shift Supervisor Determination Action Constituted Acceptable Entry |
- on 880424,Tech Spec 3.0.3 Entered on Two Occasions for Total of 17 Minutes During Testing of Steam Generator Porvs.Caused by Shift Supervisor Determination Action Constituted Acceptable Entry
| 10 CFR 50.73(a)(2)(1) | | 05000498/LER-1988-030, :on 880506,automatic Actuation of Control Room Ventilation to Recirculation Mode Occurred.Caused by High Hydrochloric Acid Trip on One of Two Toxic Gas Analyzers. Memo Issued to Plant Personnel |
- on 880506,automatic Actuation of Control Room Ventilation to Recirculation Mode Occurred.Caused by High Hydrochloric Acid Trip on One of Two Toxic Gas Analyzers. Memo Issued to Plant Personnel
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000498/LER-1988-031, :on 880509,extended Range Neutron Sys Cable Assemblies Mfg by Gamma-Metrics Found Incapable of Performing Required Safety Functions.Caused by Solder Joint Leakage.Cable Assemblies & Detectors Replaced |
- on 880509,extended Range Neutron Sys Cable Assemblies Mfg by Gamma-Metrics Found Incapable of Performing Required Safety Functions.Caused by Solder Joint Leakage.Cable Assemblies & Detectors Replaced
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2) | | 05000498/LER-1988-032, :on 880512,feedwater Pump Failed Performance Test.Caused by Stress Corrosion Cracking/Hydrogen Embrittlement of Sleeve Matl.Pump Sleeve Matl Will Be Replaced W/Softer Stainless Steel |
- on 880512,feedwater Pump Failed Performance Test.Caused by Stress Corrosion Cracking/Hydrogen Embrittlement of Sleeve Matl.Pump Sleeve Matl Will Be Replaced W/Softer Stainless Steel
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000498/LER-1988-033, :on 880418,loss of Suction Pressure to Pumps Occurred on Swap Over from Vol Control Tank to Refueling Water Storage Tank.Caused by Design Error in Piping Configuration.Procedures Modified |
- on 880418,loss of Suction Pressure to Pumps Occurred on Swap Over from Vol Control Tank to Refueling Water Storage Tank.Caused by Design Error in Piping Configuration.Procedures Modified
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000498/LER-1988-034, :on 880517,discovered That Preoperational Test Procedures Did Not Include Test for One ESF Sequencer Actuations of Containment Spray Pumps.Caused by Procedural Inadequacy Due to Uniqueness of Signals |
- on 880517,discovered That Preoperational Test Procedures Did Not Include Test for One ESF Sequencer Actuations of Containment Spray Pumps.Caused by Procedural Inadequacy Due to Uniqueness of Signals
| 10 CFR 50.73(a)(2)(1) | | 05000498/LER-1988-035, :on 880518,discovered Nonperformance of Required Surveillance Test for Component Cooling Water Valve.Caused by Inadequate Procedure.Surveillance Program Revised to Provide Improved Tracking Sys |
- on 880518,discovered Nonperformance of Required Surveillance Test for Component Cooling Water Valve.Caused by Inadequate Procedure.Surveillance Program Revised to Provide Improved Tracking Sys
| 10 CFR 50.73(a)(2)(1) | | 05000498/LER-1988-036, :on 880607,unmonitored Release of 1,504 Gallons of Liquid Effluent Occurred.Caused by Personnel Error. Responsible Individual Counseled & Incident Reviewed W/ Others Involved W/Radioactive Effluents |
- on 880607,unmonitored Release of 1,504 Gallons of Liquid Effluent Occurred.Caused by Personnel Error. Responsible Individual Counseled & Incident Reviewed W/ Others Involved W/Radioactive Effluents
| 10 CFR 50.73(a)(2)(1) | | 05000498/LER-1988-037, :on 880609,480-volt Breaker Failed to Automatically Close Due to Mfg Defect.Insp Performed on 23 480-volt Class 1E Load Ctr Breakers Which Automatically Close After ESF Load Sequencer.Part 21 Related |
- on 880609,480-volt Breaker Failed to Automatically Close Due to Mfg Defect.Insp Performed on 23 480-volt Class 1E Load Ctr Breakers Which Automatically Close After ESF Load Sequencer.Part 21 Related
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability | | 05000498/LER-1988-038, :on 880613,failure to Perform Surveillance Testing of Intermediate Range Nuclear Instrumentation Prior to Entering Mode 2 Discovered.Caused by Inadequate Surveillance Program.Mode Change Rept Reviewed |
- on 880613,failure to Perform Surveillance Testing of Intermediate Range Nuclear Instrumentation Prior to Entering Mode 2 Discovered.Caused by Inadequate Surveillance Program.Mode Change Rept Reviewed
| 10 CFR 50.73(a)(2)(1) | | 05000498/LER-1988-040, :on 880623,surveillances Identified W/Tech Specs Re Reactor Trip Breaker Test Intervals Scheduled W/Method Which Could Result in Improper Staggering of Test Intervals.Caused by Inadequate Program |
- on 880623,surveillances Identified W/Tech Specs Re Reactor Trip Breaker Test Intervals Scheduled W/Method Which Could Result in Improper Staggering of Test Intervals.Caused by Inadequate Program
| 10 CFR 50.73(a)(2)(1) | | 05000498/LER-1988-041, :on 880710,high Toxic Gas Alarm Occurred W/O Automatic Actuation of Control Room Ventilation to Recirculation Mode.Caused by Incorrect Configuration of Wiring.Wiring Corrected |
- on 880710,high Toxic Gas Alarm Occurred W/O Automatic Actuation of Control Room Ventilation to Recirculation Mode.Caused by Incorrect Configuration of Wiring.Wiring Corrected
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(1) | | 05000498/LER-1988-042, :on 880711,automatic Actuation of Control Room Ventilation to Recirculation Mode Occurred as Result of High Hydrochloric Acid Trip on One of Two Toxic Gas Analyzers. Caused by Malfunction of Analyzer |
- on 880711,automatic Actuation of Control Room Ventilation to Recirculation Mode Occurred as Result of High Hydrochloric Acid Trip on One of Two Toxic Gas Analyzers. Caused by Malfunction of Analyzer
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000498/LER-1988-043, :on 880712,surveillance Test for Contamination in Generator Fuel Oil Not Performed Due to Personnel Error. Surveillance Performance on Due Date & Review of Overdue Repts Requirements Added |
- on 880712,surveillance Test for Contamination in Generator Fuel Oil Not Performed Due to Personnel Error. Surveillance Performance on Due Date & Review of Overdue Repts Requirements Added
| 10 CFR 50.73(a)(2)(1) | | 05000498/LER-1988-044, :on 880714,automatic Actuation of Control Room Ventilation Sys to Recirculation Mode Occurred.Caused by Presence of Halon Gas in zero-sample Gas Used as Ref Value for Measurement of Subsequent Samples |
- on 880714,automatic Actuation of Control Room Ventilation Sys to Recirculation Mode Occurred.Caused by Presence of Halon Gas in zero-sample Gas Used as Ref Value for Measurement of Subsequent Samples
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000498/LER-1988-045, :on 880719,reactor Trip on Over Temp/Delta Temp Occurred.Caused by Personnel Error.Detailed Instructions on Qualified Display Processing Sys Reset to Applicable Procedures & Technicians Trained |
- on 880719,reactor Trip on Over Temp/Delta Temp Occurred.Caused by Personnel Error.Detailed Instructions on Qualified Display Processing Sys Reset to Applicable Procedures & Technicians Trained
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000498/LER-1988-047, :on 880802,automatic Actuation of Control Room Ventilation to Recirculation Mode Occurred.Caused by Momentary High Level Reading on HC1 Channel of Single Toxic Gas Analyzer.Subcommittee Studying Problem |
- on 880802,automatic Actuation of Control Room Ventilation to Recirculation Mode Occurred.Caused by Momentary High Level Reading on HC1 Channel of Single Toxic Gas Analyzer.Subcommittee Studying Problem
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000498/LER-1988-048, :on 880816,reactor Tripped as Result of Main Turbine Trip.Caused by Failure of Stator Cooling Water Pump Discharge Check Valve to Close.Stator Cooling Water Pump Discharge Check Valve Packing Replaced |
- on 880816,reactor Tripped as Result of Main Turbine Trip.Caused by Failure of Stator Cooling Water Pump Discharge Check Valve to Close.Stator Cooling Water Pump Discharge Check Valve Packing Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000498/LER-1988-049, :on 880826,reactor Trip Occuured Due to Turbine Trip Subsequently on Low Stream Pressure at 1728 H.Caused by Defective Fuse Block in Stator Cooling Water Trip Circuit. Fuse Block Replaced & Operator Trained |
- on 880826,reactor Trip Occuured Due to Turbine Trip Subsequently on Low Stream Pressure at 1728 H.Caused by Defective Fuse Block in Stator Cooling Water Trip Circuit. Fuse Block Replaced & Operator Trained
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000498/LER-1988-050, On 880827,ESF Actuation of All Three Trains of HVAC for Control Room Envelope,Fuel Handling Bldg & Containment Bldg Occurred Simultaneously.Caused by Failure of Radiation Monitors.Investigation Underway | On 880827,ESF Actuation of All Three Trains of HVAC for Control Room Envelope,Fuel Handling Bldg & Containment Bldg Occurred Simultaneously.Caused by Failure of Radiation Monitors.Investigation Underway | | | 05000498/LER-1988-051, :on 880902,door Required to Separate Area Classified as Mild Environ from Area Classified as Harsh Environ Deleted During Const.Caused by Personnel Error. Design Change Issued to Install Door |
- on 880902,door Required to Separate Area Classified as Mild Environ from Area Classified as Harsh Environ Deleted During Const.Caused by Personnel Error. Design Change Issued to Install Door
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability | | 05000498/LER-1988-053, :on 880920,NRC Notified That Gaseous Effluent Radiation Monitor Alarm Setpoints Not Calculated in Accordance W/Offsite Dose Calculation Manual.Caused by Inadequate Review of Manual Rev |
- on 880920,NRC Notified That Gaseous Effluent Radiation Monitor Alarm Setpoints Not Calculated in Accordance W/Offsite Dose Calculation Manual.Caused by Inadequate Review of Manual Rev
| 10 CFR 50.73(a)(2)(1) | | 05000498/LER-1988-054, :on 880921,automatic Actuation of Control Room Ventilation to Recirculation Mode Occurred.Caused by High Level Reading on Ammonia Channel.Request to Increase Tech Spec Limit for High Level Ammonia Submitted |
- on 880921,automatic Actuation of Control Room Ventilation to Recirculation Mode Occurred.Caused by High Level Reading on Ammonia Channel.Request to Increase Tech Spec Limit for High Level Ammonia Submitted
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000498/LER-1988-055, :on 880930,automatic Actuation of Control Room Ventilation to Recirculation Mode Occurred.Caused by High Level Trip of Hydrochloric Acid Channel on One of Two Toxic Gas Analyzers.Analyzer Will Be Replaced |
- on 880930,automatic Actuation of Control Room Ventilation to Recirculation Mode Occurred.Caused by High Level Trip of Hydrochloric Acid Channel on One of Two Toxic Gas Analyzers.Analyzer Will Be Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000498/LER-1988-056, :on 880930,determined That Two Primary Penetration Protection Circuit Breakers Not Included in Surveillance Test Program as Required by Tech Spec.Caused by Use of Licensing Basis Document |
- on 880930,determined That Two Primary Penetration Protection Circuit Breakers Not Included in Surveillance Test Program as Required by Tech Spec.Caused by Use of Licensing Basis Document
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