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OPS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit GEC 0 2 1996 LR-N96391 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
LER 272/96-027-00 SALEM GENERATING STATION -
UNIT 1 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 This Licensee Event Report entitled "Diesel Watt Meter Inaccuracies Not Accounted for in Surveillance Testing" is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR50. 73 (a) (2) (i) (B).
Attachment SORC Mtg.96-169 BJT/
c Distribution LER File 3.7 9612100006 961202 PDR ADOCK 05000272 S
PDR The pom~r is in your h,mds.
Sincerely, Qg~~w General Manager -
Salem Operations
-~-
95-2168 REV. 6/94
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 (4-95)
EXPIRES 04/30/98 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS MANDATORY INFORMATION COLLECTION REQUEST: 50.0 HRS.
LICENSEE EVENT REPORT (LER)
REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE LICENSING PROCESS AND FED BACK TO INDUSTRY.
FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION (See reverse for required number of AND RECORDS MANAGEMENT BRANCH (T-6 F33), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, AND TO digits/characters for each block)
THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.
FACILITY NAllE (1)
DOCKET NUllBER (2)
PAGE (3)
SALEM GENERATING STATION UNIT 1 05000272 1 OF 4 TITLE (4)
Diesel Watt Meter Inaccuracies Not Accounted for in Surveillance Testing EVENT DATE (5)
LER NUMBER (6)
REPORT DATE (7)
OTHER FACILITIES INVOLVED (8)
YEAR I FACILITY NAME DOCKET NUMBER MONTH DAY YEAR SEQUENTIAL I REVISION MONTH DAY YEAR NUMBER NUMBER Salem, Unit 2 05000311 10 31 96 96 027 00 12 02 96 FACILITY NAME DOCKET NUMBER OPERATING N
THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more) (11)
MODE (9) 20.2201(b) 20.2203(a)(2)(v) x 50. 73(a)(2)(i)
- 50. 73(a)(2)(viii)
POWER 000 20.2203(a)(1) 20.2203(a)(3)(i)
- 50. 73(a)(2)(ii)
- 50. 73(a)(2)(x)
LEVEL (10) 20.2203(a)(2)(i) 20.2203(a)(3)(ii)
- 50. 73(a)(2)(iii) 73.71 20.2203(a)(2)(ii) 20.2203(a)(4)
- 50. 73(a)(2)(iv)
OTHER 20.2203(a)(2)(iii) 50.36(c)(1)
- 50. 73(a)(2)(v)
Spec~in Abstract below or in C Form 366A 20.2203(a)(2)(iv) 50.36(c)(2)
- 50. 73( a)(2)(vii)
LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NUMBER (Include Area Code)
Brian Thomas, Licensing Engineer 609-339-2022 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
CAUSE
SYSTEM COMPONENT MANUFACTURER REPORTABLE
CAUSE
SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPRDS TO NPRDS SUPPLEMENTAL REPORT EXPECTED (14)
EXPECTED MONTH DAY YEAR IVES XINO SUBMISSION (If yes, complete EXPECTED SUBMISSION DATE).
DATE (15)
ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)
During a review of Emergency Diesel Generator (EDG) instrument inaccuracies, on October 31, 1996, the review determined that the inaccuracies of the EDG watt meter used for recording surveillance test data did not ensure that the EDG remained within the Technical Specification (TS) surveillance band.
The apparent cause is attributed to the lack of consideration of all aspects of the watt meter inaccuracy when the load bands were developed for the TS changes.
A contributing cause was the lack of detailed instructions to load the EDG in the center of the TS surveillance load band.
Higher accuracy Maintenance and Test Equipment (M&TE) will be used to measure the EDG kw values.
EDG surveillance procedures will be revised prior to their next performance to include the use of the higher accuracy M&TE and provide an acceptance band in the surveillance procedure to ensure that the kw values remain with the TS loading bands.
This event is reportable in accordance with 10 CFR 50.73(a) (2) (i) (B), any condition prohibited by the plant's Technical Specifications.
NRC FORM 366 (4-95)
U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1)
DOCKET NUMBER (2)
LER NUMBER (6)
PAGE (3)
SALEM GENERATING STATION UNIT 1 05000272 YEAR I SEQUENTIAL I REVISION NUMBER NUMBER 2
96 -
027 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
PLANT AND SYSTEM IDENTIFICATION
Westinghouse -
Pressurized Water Reactor Emergency Diesel Generators {EK/-}*
- Energy Industry Identification System (EIIS) codes and component function identifier codes appear as {SS/CCC}
CONDITIONS PRIOR TO OCCURRENCE OF 4
At the time of identification, Salem Units 1 and 2 were shutdown and defueled.
DESCRIPTION OF OCCURRENCE During a review of Emergency Diesel Generator (EDG) instrument inaccuracies, on October 31, 1996, the review determined that the inaccuracies of the EDG watt meter used for recording surveillance test data did not ensure that the EDG loading remained within the Technical Specification surveillance band.
The Salem Unit 1 and Unit 2 Technical Specifications (TS) for EDG loading are as follows:
TS 4.8.1.1.2.a.2 states that on a monthly or weekly frequency (depending upon the number of diesel failures in the past 20 valid tests):
".... verifying the generator is synchronized, gradually loaded to 2500-2600 kw, and operates at a load of 2500-2600 kw for greater than or equal to 60 minutes."
TS 4.8.1.1.2.c states that at least once per 6 months:
"... The generator shall be synchronized to its emergency bus, loaded to 2500-2600 kw in less than or equal to 60 seconds, and operate at a load of 2500-2600 kw for at least 60 minutes."
TS 4.8.1.1.2.d.7 states that at least once per 18 months during shutdown:
"Verifying the diesel generator operates for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
During the first 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of this test, the diesel generator shall be loaded to 2760-2860 kw.
During the remaining 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> of this test, the diesel generator shall be loaded to 2500 -
2600 kw.
The steady state voltage and frequency shall be maintained at ~ 3950 and ~ 4580 volts and 60 +/- 1.2 Hz during this test."
The load bands for the EDG surveillances were incorporated into the Unit 1 and Unit 2 TS by amendments 148 and 126, respectively.
These amendments were issued by the NRC on November 30, 1993.
The 100 kw band that was included in the TS was proposed by PSE&G in License Change Request (LCR) 87-07.
The 100 kw band was based on the EDG watt meter having an inaccuracy of 1% of full
U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1)
DOCKET NUMBER (2)
LER NUMBER (6)
SALEM GENERATING STATION UNIT 1 05000272 YEAR I SEQUENTIAL I REVISION NUMBER NUMBER 96 -
027 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
DESCRIPTION OF OCCURRENCE (cont'd)
PAGE (3) 3 OF scale (+/- 40 kw) with the operators instructed to place the EDG at the midpoint of the band.
However, the surveillance tests procedures did not provide any specific instructions to the operators to place the EDG in the midpoint of the band.
The surveillance test procedures require the operator to load the diesel to within the TS loading band.
Although the TS loading band took into account the inaccuracy of the watt meter itself, the loading band did not take into account the additional inaccuracy associated with the readability of the meter and the sensing instrumentation [Potential Transformers (PTs) and Current Transformers (CTs)].
This additional inaccuracy brought the total EDG watt meter inaccuracy to +/- 65 kw.
With the EDG set at the midpoint of the loading band, there is no assurance that the actual kw value would be within the TS loading band.
A review of past surveillance data revealed that the actual kw values could not be demonstrated to remain with the TS loading band.
This event is reportable in accordance with 10 CFR 50.73(a) (2) (i) (B), any condition prohibited by the plant's Technical Specifications.
APPARENT CAUSE OF OCCURRENCE The apparent cause is attributed to the lack of consideration of all aspects of the watt meter inaccuracy when the load bands were developed for the TS changes.
A contributing cause was the lack of detailed instructions to load the EDG in the center of the load band.
PRIOR SIMILAR OCCURRENCES A review of Salem Unit 1 and 2 LERs for the past two years did not reveal any LERs submitted due to failure to consider instrument inaccuracies when recording surveillance test data from installed plant equipment.
SAFETY CONSEQUENCES AND IMPLICATIONS
Public Service Electric and Gas (PSE&G) contacted the vendor of the EDGs (Coltec Industries).
The vendor agreed that use of the installed watt meter would ensure that the EDG was within its design ratings.
Although the EDG actual kw readings did not comply with the surveillance requirements of the TS, the EDGs are capable of performing their design function.
Based on the above, there was no impact to health and safety of the public. 4
U.S. NUCLEAR REGULATORY COMMISSION FACILITY NAME (1)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION DOCKET NUMBER (2)
LER NUMBER (6)
SALEM GENERATING STATION UNIT 1 0 5 0 0 0 2 7 2 YEAR I SEQUENTIAL I REVISION NUMBER NUMBER 96 -
027 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
CORRECTIVE ACTIONS
PAGE (3) 4 OF 4
- 1. Higher accuracy Maintenance and Test Equipment (M&TE) will be used to measure the EDG kw values.
EDG surveillance procedures will be revised prior to their next performance to include the use of the higher accuracy M&TE and provide an acceptance band in the surveillance procedure to ensure that the kw values remain with the TS loading bands.
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| 05000272/LER-1996-001, :on 960103,discovered Insufficent Thermal Overload Relay Heater Margin.Caused by Inadequate Design of TOLs in 1970s.Issued Calculation ES-18.007 for Sizing of Thermal Overload Heaters for SR Rotating Loads |
- on 960103,discovered Insufficent Thermal Overload Relay Heater Margin.Caused by Inadequate Design of TOLs in 1970s.Issued Calculation ES-18.007 for Sizing of Thermal Overload Heaters for SR Rotating Loads
| | | 05000311/LER-1996-001-01, :on 960109,TS Violation Occurred Re Failure to Perform Chemistry Sampling within Required Timeframe.Caused by Personnel Error.Personnel Counseled & Chemistry Dept Shift Turnover Process Improved |
- on 960109,TS Violation Occurred Re Failure to Perform Chemistry Sampling within Required Timeframe.Caused by Personnel Error.Personnel Counseled & Chemistry Dept Shift Turnover Process Improved
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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) | | 05000311/LER-1996-002-02, :on 960701,waste Gas Decay Tank Oxygen Concentration Exceeded TSs Limit.Caused by Poor Wording & Interpretation of Tss.Oxygen Concentration Levels Restored. Request to Resolve TS 3.11.2.5 Submitted to NRC on 960815 |
- on 960701,waste Gas Decay Tank Oxygen Concentration Exceeded TSs Limit.Caused by Poor Wording & Interpretation of Tss.Oxygen Concentration Levels Restored. Request to Resolve TS 3.11.2.5 Submitted to NRC on 960815
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000272/LER-1996-002, :on 960110,evaluation Determined That Motor Operated Gate Valves Susceptible to Pressure Locking & Thermal Binding.Caused by Inability to Meet GL 95-07 Criteria.Test Procedure Changed |
- on 960110,evaluation Determined That Motor Operated Gate Valves Susceptible to Pressure Locking & Thermal Binding.Caused by Inability to Meet GL 95-07 Criteria.Test Procedure Changed
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(e)(2)(v) | | 05000311/LER-1996-003-02, :on 960515,failed to Perform Surveillance for Fuel Handling Bldg (Fhb) Ventilation Sys Auto Start.Caused by Lack of Adequate Controls for Surveillance Procedures. Added auto-start Capability |
- on 960515,failed to Perform Surveillance for Fuel Handling Bldg (Fhb) Ventilation Sys Auto Start.Caused by Lack of Adequate Controls for Surveillance Procedures. Added auto-start Capability
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000272/LER-1996-003-01, :on 960220,TS Radiation Monitor Sampling in non-compliance.Caused by Failure of Plant Chemistry to Fully Understand TS Sample & Analysis Requirements.Established Process for Controlling Analyses |
- on 960220,TS Radiation Monitor Sampling in non-compliance.Caused by Failure of Plant Chemistry to Fully Understand TS Sample & Analysis Requirements.Established Process for Controlling Analyses
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(viii) | | 05000311/LER-1996-004-02, :on 960515,failed to Perform Compensatory Radiological Survey.Caused by Personnel Error.Performed Survey,Revised Radiation Protection Schedule,Purchased Alarm Clocks & Counseled Personnel Re Event |
- on 960515,failed to Perform Compensatory Radiological Survey.Caused by Personnel Error.Performed Survey,Revised Radiation Protection Schedule,Purchased Alarm Clocks & Counseled Personnel Re Event
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(viii) | | 05000272/LER-1996-004-01, :on 960307,surveillance Was Missed for Salem Generating Station.Caused by Lack of Adequate Control for Development & Maintenance of TS Surveillance Procedures. License Change Will Be Submitted |
- on 960307,surveillance Was Missed for Salem Generating Station.Caused by Lack of Adequate Control for Development & Maintenance of TS Surveillance Procedures. License Change Will Be Submitted
| | | 05000272/LER-1996-004, :on 960307,containment Isolation Valve Missed TS Surveillance.Caused by Lack of Adequate Controls & Inadequate Design Review.Ts Surveillance Improvement Project Has Been Initiated for Plant,Units 1 & 2 |
- on 960307,containment Isolation Valve Missed TS Surveillance.Caused by Lack of Adequate Controls & Inadequate Design Review.Ts Surveillance Improvement Project Has Been Initiated for Plant,Units 1 & 2
| 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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) | | 05000272/LER-1996-005-05, Forwards LER 96-005-05 Re Surveillance for turbine-driven AF Pump.Commitments Encl as Attachment a | Forwards LER 96-005-05 Re Surveillance for turbine-driven AF Pump.Commitments Encl as Attachment a | | | 05000272/LER-1996-005-01, :on 960325,channel Checks for Average Temp Not Performed as Required by Ts.Caused by Inadequate Controls for Development & Maint of TS Surveillance Procedures.Tssip Initiated |
- on 960325,channel Checks for Average Temp Not Performed as Required by Ts.Caused by Inadequate Controls for Development & Maint of TS Surveillance Procedures.Tssip Initiated
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000272/LER-1996-005, :on 971224,inadequate TS Testing of Containment Airlock Door Gasket Leakage Was Noted.Caused by Lack of Adequate Controls & Understanding of Development. Appropriate Procedures Reviewed |
- on 971224,inadequate TS Testing of Containment Airlock Door Gasket Leakage Was Noted.Caused by Lack of Adequate Controls & Understanding of Development. Appropriate Procedures Reviewed
| 10 CFR 50.73(a)(2)(1) | | 05000311/LER-1996-005-02, :on 960627,surveillance of Fuel Handling Bldg Ventilation Sys Charcoal Adsorber Test Was Missed.Caused by Inattention to Detail.Individual Involved Received Appropriate Level of Positive Discipline |
- on 960627,surveillance of Fuel Handling Bldg Ventilation Sys Charcoal Adsorber Test Was Missed.Caused by Inattention to Detail.Individual Involved Received Appropriate Level of Positive Discipline
| | | 05000272/LER-1996-005-15, Forwards LER 96-005-15, Inadequate TS Testing - Feedwater Sys Isolation Functional Test/Component Cooling Water Heat Exchanger Service Water Flow Control Valves | Forwards LER 96-005-15, Inadequate TS Testing - Feedwater Sys Isolation Functional Test/Component Cooling Water Heat Exchanger Service Water Flow Control Valves | | | 05000272/LER-1996-005-03, :on 960325,TS Surveillance Requirement Implementation Deficiencies Identified.Caused by Lack of Adequate Controls & Understanding of Development Weakness. Procedures Revised |
- on 960325,TS Surveillance Requirement Implementation Deficiencies Identified.Caused by Lack of Adequate Controls & Understanding of Development Weakness. Procedures Revised
| 10 CFR 50.73(a)(2)(i) | | 05000311/LER-1996-006-02, :on 960717,sample Flow to non-radioactive Liquid Radwaste Monitor Was Not Adequate to Meet Plant Ts.Cause of Event Is Under Investigation.Design of 2R37 Sample Line Has Been Revised |
- on 960717,sample Flow to non-radioactive Liquid Radwaste Monitor Was Not Adequate to Meet Plant Ts.Cause of Event Is Under Investigation.Design of 2R37 Sample Line Has Been Revised
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000272/LER-1996-006-01, :on 960421,missed Independent Verification of Release Lineup on Waste Gas Decay Tanks (Wgdt) Due to Personnel.Wgdt Releases Suspended Pending Rev of Procedures. Procedures Revised |
- on 960421,missed Independent Verification of Release Lineup on Waste Gas Decay Tanks (Wgdt) Due to Personnel.Wgdt Releases Suspended Pending Rev of Procedures. Procedures Revised
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 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 | | 05000311/LER-1996-006-01, :on 960717,determined That non-radioactive Liquid Basin Radwaste Monitor Inoperable During Low Head Conditions.Caused by Inadequate Design Change Package.Design Change 1EC3663-01 Has Been Installed.With |
- on 960717,determined That non-radioactive Liquid Basin Radwaste Monitor Inoperable During Low Head Conditions.Caused by Inadequate Design Change Package.Design Change 1EC3663-01 Has Been Installed.With
| 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)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) | | 05000272/LER-1996-007-01, :on 960524,determined P-12 Setpoint Above Tech Spec Table 3.3-3 Value.Caused by Incorrect Conversion from Standard Tech Spec for Westinghouse Pressurized Water Reactors. Revised Procedures |
- on 960524,determined P-12 Setpoint Above Tech Spec Table 3.3-3 Value.Caused by Incorrect Conversion from Standard Tech Spec for Westinghouse Pressurized Water Reactors. Revised Procedures
| | | 05000311/LER-1996-007, :on 980130,missed Surveillance of Containment Penetration Overcurrent Protection Devices Occurred.Caused by Failure to Tag 35 Amp Breaker.Surveillance Testing for Breakers 1ELC-1 & 1ELC-3 Will Be Completed |
- on 980130,missed Surveillance of Containment Penetration Overcurrent Protection Devices Occurred.Caused by Failure to Tag 35 Amp Breaker.Surveillance Testing for Breakers 1ELC-1 & 1ELC-3 Will Be Completed
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2) | | 05000311/LER-1996-007-02, :on 960716,containment Penetration Conductor Overcurrent Circuit Breakers Had Not Been Demonstrated Operable Per Ts.Caused by Failure to Assure That Info Was Incorporated Into Sr.Procedures Reviewed |
- on 960716,containment Penetration Conductor Overcurrent Circuit Breakers Had Not Been Demonstrated Operable Per Ts.Caused by Failure to Assure That Info Was Incorporated Into Sr.Procedures Reviewed
| 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)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(e)(2)(viii) | | 05000272/LER-1996-008-01, :on 960613,failed to Meet Tech Spec Requirement While in Mode 5 for Natural Circulation.Caused by Insufficient Technical Input for Development of Controls. Revised Operating Logs for Mode 5 |
- on 960613,failed to Meet Tech Spec Requirement While in Mode 5 for Natural Circulation.Caused by Insufficient Technical Input for Development of Controls. Revised Operating Logs for Mode 5
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000272/LER-1996-008-02, :on 960613,failure to Meet TS Requirements While in Mode 5 for Natural Circulation Was Noted.Caused by Insufficient Technical Input for Development of Controls. Revised Plant Operating Logs for Mode 5 |
- on 960613,failure to Meet TS Requirements While in Mode 5 for Natural Circulation Was Noted.Caused by Insufficient Technical Input for Development of Controls. Revised Plant Operating Logs for Mode 5
| | | 05000311/LER-1996-008-02, :on 960729,battery Chargers Were Declared Inoperable Due to Mfg Discrepancies.Unit 2 Battery Chargers Will Be Reworked to Design Specifications by 960915 |
- on 960729,battery Chargers Were Declared Inoperable Due to Mfg Discrepancies.Unit 2 Battery Chargers Will Be Reworked to Design Specifications by 960915
| 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)(x) 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) | | 05000272/LER-1996-009-01, :on 960530,concluded Potential Common Mode Failure for 4 Kv Magne-Blast Breakers.Caused by Misalignment of Breaker Mechanism & Internals.Assessed Breaker Mechanism Misalignment for Each Breaker |
- on 960530,concluded Potential Common Mode Failure for 4 Kv Magne-Blast Breakers.Caused by Misalignment of Breaker Mechanism & Internals.Assessed Breaker Mechanism Misalignment for Each Breaker
| | | 05000311/LER-1996-009-02, :on 960808,determined Current Shift Schedules Deviates from License Condition 2.C(24)(a).Caused by Inadequate Review of License Requirements.Will Continue to Operate on 12-hour Schedule |
- on 960808,determined Current Shift Schedules Deviates from License Condition 2.C(24)(a).Caused by Inadequate Review of License Requirements.Will Continue to Operate on 12-hour Schedule
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000272/LER-1996-010-01, :on 960619,identified Pressurizer Relief Tank Hydrodynamic Loads Had Not Previously Been Considered in Support Design.Caused by Failure to Consider Hydrodynamic Loads Caused by Water Discharge.Supports Revised |
- on 960619,identified Pressurizer Relief Tank Hydrodynamic Loads Had Not Previously Been Considered in Support Design.Caused by Failure to Consider Hydrodynamic Loads Caused by Water Discharge.Supports Revised
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000272/LER-1996-010, Forwards LER 96-010-00 Re Inadequate Pressurizer Relief Tank Supports.Attachment a Represents Commitment Made to NRC | Forwards LER 96-010-00 Re Inadequate Pressurizer Relief Tank Supports.Attachment a Represents Commitment Made to NRC | | | 05000311/LER-1996-010-02, :on 960819,TS 4.0.5 Surveillance for Two Pressurizer Welds Was Missed Due to Insufficient Verification & Validation of Entry of Data Into Database. Exam of Pressurizer Spray Nozzle Was Completed |
- on 960819,TS 4.0.5 Surveillance for Two Pressurizer Welds Was Missed Due to Insufficient Verification & Validation of Entry of Data Into Database. Exam of Pressurizer Spray Nozzle Was Completed
| | | 05000311/LER-1996-011, Forwards LER 96-011-00 Regarding Missed Surveillance for Sampling Boron Concentration of Refueling Canal as Required by Ts.Commitments Encl as Attachment a | Forwards LER 96-011-00 Regarding Missed Surveillance for Sampling Boron Concentration of Refueling Canal as Required by Ts.Commitments Encl as Attachment a | | | 05000311/LER-1996-011-01, :on 951206,missed Surveillance for Sampling Baron Concentration of Refueling Canal as Required by TS Occurred.Caused by Inadequate Implementation of Tech Specs Requirements.Procedure Revised |
- on 951206,missed Surveillance for Sampling Baron Concentration of Refueling Canal as Required by TS Occurred.Caused by Inadequate Implementation of Tech Specs Requirements.Procedure Revised
| 10 CFR 50.73(a)(2)(i) | | 05000272/LER-1996-011-02, :on 960620,pressurizer Safety Relief Valves Were Found Outside of TS Tolerance.Caused by Minor Testing Instrument Error.Valves Were Refurbished & Successfully Retested to within TS Tolerance |
- on 960620,pressurizer Safety Relief Valves Were Found Outside of TS Tolerance.Caused by Minor Testing Instrument Error.Valves Were Refurbished & Successfully Retested to within TS Tolerance
| 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) | | 05000311/LER-1996-012-02, :on 961005,two Potential Transformer Fuses Opened While Performing an Electrical Test of 21 Svc Water Pump.Cause Unknown.Work Practices for Specialized Electrical Testing Will Be Reviewed for Adequacy |
- on 961005,two Potential Transformer Fuses Opened While Performing an Electrical Test of 21 Svc Water Pump.Cause Unknown.Work Practices for Specialized Electrical Testing Will Be Reviewed for Adequacy
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000272/LER-1996-012-01, :on 960723,potential Loss of Residual Capability Identified.Caused by Inadequate Valve Design.Rhr Flow Control Valves Replaced |
- on 960723,potential Loss of Residual Capability Identified.Caused by Inadequate Valve Design.Rhr Flow Control Valves Replaced
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | | 05000272/LER-1996-013-01, :on 960711,scaling Error of Over Temperature Delta Temp Resulted in Inoperable Protection Channels.Cause Under Investigation.Scaling Calculations Revised |
- on 960711,scaling Error of Over Temperature Delta Temp Resulted in Inoperable Protection Channels.Cause Under Investigation.Scaling Calculations Revised
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000272/LER-1996-013, :on 960711,concluded That Current Gain & Bias Settings Had Rendered Overtemperature Delta Temp Protection Channels Inoperable.Caused by Scaling Error.Licensee Will Revise Scaling Calculations.With |
- on 960711,concluded That Current Gain & Bias Settings Had Rendered Overtemperature Delta Temp Protection Channels Inoperable.Caused by Scaling Error.Licensee Will Revise Scaling Calculations.With
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000311/LER-1996-013-02, :on 961010,surveillance for Performing Tritium Grab Samples When Refueling Canal Is Flooded Was Missed. Caused by Inadequate Implementation of TS Requirements. Corrective Actions Include Procedure Revs |
- on 961010,surveillance for Performing Tritium Grab Samples When Refueling Canal Is Flooded Was Missed. Caused by Inadequate Implementation of TS Requirements. Corrective Actions Include Procedure Revs
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000272/LER-1996-014-02, :on 960717,potential Hydrogen Embrittlement on 4kV Breaker Parts Identified.Caused by Cracked Roll Pin,Due to Lack of Knowledge of Plating Induced Hydrogen Embrittlement.Cause Evaluation Being Conducted |
- on 960717,potential Hydrogen Embrittlement on 4kV Breaker Parts Identified.Caused by Cracked Roll Pin,Due to Lack of Knowledge of Plating Induced Hydrogen Embrittlement.Cause Evaluation Being Conducted
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000311/LER-1996-014-03, :on 961201,EDG Automatic Start Resulted in ESF Actuation.Caused by Defective anti-pump Relay in 23 Csd Vital Infeed Breaker.Defective anti-pump Relay Identified |
- on 961201,EDG Automatic Start Resulted in ESF Actuation.Caused by Defective anti-pump Relay in 23 Csd Vital Infeed Breaker.Defective anti-pump Relay Identified
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000272/LER-1996-014, Corrected LER 96-014-00:on 960717,potential Hydrogen Embrittlement on 4kV Breaker Parts Identified.Root Cause Investigation Being Conducted.All NLI Refurbished Breakers Removed Except 2B4D from Vital Loads | Corrected LER 96-014-00:on 960717,potential Hydrogen Embrittlement on 4kV Breaker Parts Identified.Root Cause Investigation Being Conducted.All NLI Refurbished Breakers Removed Except 2B4D from Vital Loads | 10 CFR 50.73(a)(2)(viii) | | 05000272/LER-1996-015-01, :on 960722,inadequate Cfcu Heat Removal Capability Identified.Caused by Failure to Effectively Chlorinate Service Water.Cfcu Monitoring Program Developed & Procedures & Training Revised |
- on 960722,inadequate Cfcu Heat Removal Capability Identified.Caused by Failure to Effectively Chlorinate Service Water.Cfcu Monitoring Program Developed & Procedures & Training Revised
| 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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) | | 05000311/LER-1996-015-02, :on 961219,breach of Containment Closure During Core Reload Occurred.Caused by Inadequate Inplementation of Outage Scheduling & Risk Management Requirements.Containment Closure Was Reestablished Using Alternate Isolation Poi |
- on 961219,breach of Containment Closure During Core Reload Occurred.Caused by Inadequate Inplementation of Outage Scheduling & Risk Management Requirements.Containment Closure Was Reestablished Using Alternate Isolation Points
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000311/LER-1996-015, Forwards LER 96-015-00,documenting Event That Occurred at Salem Generating Station,Unit 2 on 961219.Commitments Made within Ltr,Listed | Forwards LER 96-015-00,documenting Event That Occurred at Salem Generating Station,Unit 2 on 961219.Commitments Made within Ltr,Listed | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000311/LER-1996-016-02, :on 961220,missed Surveillance for Determining Response Time of High Containment Gaseous Radioactivity ESF Actuation Occurred.Caused by Inadequate Implementation of TS Requirements.Procedures Will Be Revised |
- on 961220,missed Surveillance for Determining Response Time of High Containment Gaseous Radioactivity ESF Actuation Occurred.Caused by Inadequate Implementation of TS Requirements.Procedures Will Be Revised
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000272/LER-1996-016-01, :on 960719,missed Surveillance for RHR Pump Dynamic Head Prior to Entering Mode 4.Caused by Inadequate Procedural Control for Verification of Change Requirements |
- on 960719,missed Surveillance for RHR Pump Dynamic Head Prior to Entering Mode 4.Caused by Inadequate Procedural Control for Verification of Change Requirements
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 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) 10 CFR 50.73(a)(2) | | 05000272/LER-1996-017-01, :on 960725,surveillance Was Missed for Plant Vent.Caused by Personnel Error.Lco Compensatory Action Was Immediately Completed Upon Discovery of Missed TS Requirement |
- on 960725,surveillance Was Missed for Plant Vent.Caused by Personnel Error.Lco Compensatory Action Was Immediately Completed Upon Discovery of Missed TS Requirement
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2) | | 05000272/LER-1996-018-01, :on 960719,potential Performance Impact on ECCS Identified Involving non-safety Related Refueling Water Storage Tank Piping.Caused by Design Discrepancy.Design Reviewed & Revised |
- on 960719,potential Performance Impact on ECCS Identified Involving non-safety Related Refueling Water Storage Tank Piping.Caused by Design Discrepancy.Design Reviewed & Revised
| | | 05000272/LER-1996-019-01, :on 960729,misclassification of Blow Down Sample Valves Noted.Caused by Flawed Engineering Evaluation. Review of Other Salem Piping Penetrations Performed |
- on 960729,misclassification of Blow Down Sample Valves Noted.Caused by Flawed Engineering Evaluation. Review of Other Salem Piping Penetrations Performed
| 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)(ii)(A), Seriously Degraded 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) | | 05000311/LER-1996-020, Provides Notification of Change in Commitment Implementation Schedule Re Potential for Thermal Overpressurization of Containment Fan Coil Unit Piping Per LER 96-020 | Provides Notification of Change in Commitment Implementation Schedule Re Potential for Thermal Overpressurization of Containment Fan Coil Unit Piping Per LER 96-020 | | | 05000272/LER-1996-020-01, :on 960820,containment Fan Coil Units Were Outside Plant Design Basis.Caused by Failure of Plant Design Change to Update Plant Design Basis.Mod to Provide Overpressure Protection Will Be Implemented |
- on 960820,containment Fan Coil Units Were Outside Plant Design Basis.Caused by Failure of Plant Design Change to Update Plant Design Basis.Mod to Provide Overpressure Protection Will Be Implemented
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability |
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