:on 961228,surveillance for Radiation Monitors Source Check Required by TS Was Missed.Caused by Lack of Attention to Detail.Reemphasized Mgt Expectations Concerning Surveillance Test Accountability| ML18102A800 |
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Salem  |
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| Issue date: |
01/29/1997 |
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| From: |
Hassler D Public Service Enterprise Group |
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| To: |
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| Shared Package |
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| ML18102A799 |
List: |
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| References |
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| LER-96-041, LER-96-41, NUDOCS 9702050352 |
| Download: ML18102A800 (3) |
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text
NRCFORM388 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 8150-0104 (4-16)
EXPIRES 04130188 EmllATED BURDEN PER Al!8PON81! TO COMPLY WITH THIS MANDATORY INFORMATION COUEC1lON REQUEST: IO.O HRS.
LICENSEE _EVENT REPORT (LER)
REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE LICENSING PROCESS AND FED BACK TO INDUSTRY.
FORWARD COllllENTS REGARDING BURDEN ESl'IMATE TO THE INFORMATION (See reverse for required number of AND RECORDS llANAOEMENT 9RAHCH (T.e ~
U.S. NUCLEAR REGULATORY COMlllSSION~ASHINGTON, DC All 0001~.f TO dlgltalcharactera for each block)
THE PAPERWORK REDU PROJECT M:11CMHM),
Of' llANAGEMENT AND BUDGET, WASHINCITON.
20150S.
FACILITY -- (1)
-~- 1 NUMBER (2) l"AU&lllJ SALEM GENERATING STATION UNIT 1 05000272 1 OF 3 TITLE (4)
MISSED SURVEILLANCE FOR RADIATION MONITORS SOURCE CHECK REQUIRED BY TECHNICAL SPECIFICATION EVENT DATE (5)
LER NUMBER (8)
REPORT DATE (7)
OTHER FACllmES INVOLVED (8)
YEAR I I FACILITY NAME DOCKET NU11BER llONTH DAY YEAR SEQUENTIAL
'REVISION llONTH DAY YEAR NUMBER NUMBER 05000 12 28 96 96 -
041 -
00 01 29 97 F"(;IUTY NAME
""'°KET NUMBER OPERATING N
THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR f: (Check one or more) (11)
MODE(9) 20.2201(b) 20.2203(a)(2)(v) x 50. 73(a)(2)(i)
- 50. 73(*)(2)(vili)
POWER 000 20.2203(*)(1) 20.2203(a)(3)(i)
- 50. 73(a)(2)(ii)
- 50. 73(*)(2)(x)
LEVEL(10) 20.2203(*)(2)(1) 20.2203(*)(3)(11)
- 50. 73(a)(2)(iii) 73.71
¥mmmwnwmmmmmmi 20.2203(*)(2)(ii) 20.2203(*)(4)
- 50. 73(a)(2)(iv)
OTHER 1111111111111111~1*111111111111111111 20.2203(a)(2)(iii) 50.36(c)(1)
- 50. 73(a)(2)(v)
~~In Abetract below or In C Form 388A 20.2203(a)(2)(iv) 50.36(c)(2)
- 50. 73(a)(2)(vii)
LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NUMBER (Include Araa Code)
Dennis v. Hassler, LER Coordinator 609-339-1989 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (18)
CAUSE
SYSTEM COMPONENT MANUFACTURER "!fu",:p;.,'"t" II
CAUSE
SYSTEM COMPONENT MANUFACTURER REPORTABLE TONPRDS
~
~~:
1111!!!!~~1.~
- ~~====~====~~===
~~~I~~~~~~~~~~
SUPPLEMENTAL REPORT EXPECTED (14)
EXPECTED MONTH DAV YEAR IYES XINO SUBMISSION (If yes, complete EXPECTED SUBMISSION DATE).
DATE(15)
ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)
On December 28, 1996, the source check surveillances for the Unit 1 Fuel Storage Area radiation monitor (1R5) and the Plant Vent Header Noble Gas Activity monitor ( 1Rl6) were not completed within the allowed surveillance interval.
The Surveillance Requirement for 1R5 is stated in Technical Specification 4.3.3.1, Table 4.3-3, Item 1.a and is applicable when fuel is in the storage pool or Fuel Handling Building.
The Surveillance Requirement for 1R16 is stated in Technical Specification 4.3.3.9, Table 4.3-13, Item 3.a and is applicable at all times.
The failure to perform these surveillances was identified on December 31, 1996 and the surveillances were satisfactorily performed on that date.
The causes of this occurrence involved lack of attention to detail.
Contributing factors included complexities in overdue reporting mechanisms and an inappropraite change to the shift turnover process.
Corrective actions
include personnel accountability; reemphasis of management expectations concerning surveillance test accountability and restoration of the overdue surveillance review to the shift turnover process.
This event is reportable in accordance with 10 CFR 50. 73 (a) (2) (i) (B), any condition prohibited by the.plant's Technical Specifications.
9702050352 970129 PDR ADOCK 05000272 S
PDR
NRC FORll 388A U.S. NUCLEAR REGULATORY OOllMISSION (4-116~
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1)
DOCKET NUMBER (2)
LER NUMBER 8)
SALEM GENERATING STATION UNIT 1 05000272 YEAR I SEQUENTIAL NUMBER REVISION NUMB En 96 -
041 -
00 TEXT (If more space is required, use additional copies of NRC Form 388A) (17)
PLANT AND SYSTEM IDENTIFICATION
Westinghouse - Pressurized Water Reactor Radiation Monitoring System {IL/-}*
- Energy Industry Identification System (EIIS) codes and component function identifier codes appear as {SS/CC}
CONDITIONS PRIOR TO OCCURRENCE At the time of occurrence, Salem Unit 1 was shutdown and defueled.
DESCRIPTION OF OCCURRENCE PAGE(3) 2 OF 3
On December 28, 1996, the source check surveillances for the Unit 1 Fuel Storage Area radiation monitor (1R5) {IL/MON} and the Plant Vent Header Noble Gas Activity monitor (1R16){IL/MON} were not completed within the allowed surveillance interval.
The Surveillance Requirement for lRS is stated in Technical Specification 4.3.3.1, Table 4.3-3, Item 1.a and is applicable when fuel is in the storage pool or Fuel Handling Building.
The specified surveillance interval for this monitor is 31 days.
The Surveillance Requirement for 1R16 is stated in Technical Specification 4.3.3.9, Table 4.3-13, Item 3.a and is applicable at all times.
The specified surveillance interval for this monitor is also 31 days.
The failure to perform these surveillances was identified on December 31, 1996 and the surveillances were satisfactorily performed on that date.
The source check surveillance requirements for lRS and 1R16 are satisfied by the performance of procedure Sl.OP-ST.RM-OOOl(Q), "Radiation Monitoring -
Source Checks."
This procedure had last been performed on November 20, 1996 and was due to be performed by December 21, 1996.
Surveillances which are required to be performed at a specified surveillance interval of greater than seven days are assigned recurring tasks in the Station's computerized tracking system, the Managed Maintenance Information System (MMIS).
Work orders are generated from the recurring task data to perform specific surveillance procedures.
Computer printouts of surveillances approaching their respective due dates are used to review upcoming surveillance requirements and prevent such surveillances from exceeding their respective allowed surveillance intervals.
The missed surveillance was scheduled and should have been performed by Operations shift personnel.
The responsibility for being cognizant of surveillance requirements approaching their respective overdue dates resided with the Senior Nuclear Shift Supervisors (SNSSs) and the Nuclear Shift Supervisors (NSSs); however, for the period of December 21, 1996 through December 31, 1996, the on-shift SNSSs and NSSs failed to note that the source check surveillances were scheduled and overdue.
NRC FORM 388A U.S. NUCLEAR REGULATORY COMMISSION (4-95~
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILfTV NAME (1)
DOCKET NUMBER (2)
LER NUMBER (8)
SALEM GENERATING STATION UNIT 1 05000272 YEAR I SEQUENTIAL I REVISION NUllSER M.-iER 96 -
041 -
00 TEXT (If more space is required, use additional copies of NRC Form 368A) (17)
DESCRIPTION OF OCCURRENCE (CONT'D)
PAGE(3) 3 OF 3
During the period of December 21 to 31, 1996, the Salem Technical Specification Administrator and the Operations Department Technical Specification Surveillance Coordinator also failed to note that the surveillances were scheduled and overdue.
CAUSE OF OCCURRENCE Personnel were not devoting sufficient time and attention to the review of the Unit 1 overdue surveillance report.
Contributing factors related to this issue involved the complexity of the Unit 1 overdue surveillance report and an inappropriate change to the shift turnover checklist which deleted requirements for shift personnel to review the overdue surveillance report.
PRIOR SIMILAR OCCURRENCES In the past two years there was one similar LER.
LER 272/95-013-00 addressed a missed surveillance that was attributed to personnel error by the Maintenance Department Technical Specification Coordinator and the Technical Specification Administrator.
In this LER, the surveillance was not included on the daily outage schedule for performance.
The corrective actions included disciplinary action and actions within the Planning and Scheduling Department.
SAFETY CONSEQUENCES AND IMPLICATIONS
There were no safety consequences in failing to perform the Source Check surveillance procedure.
The surveillance procedure was successfully performed on December 31, 1996.
There was no impact on the public health and safety.
CORRECTIVE ACTIONS
- 1. The surveillances for 1R5 and 1R16 were satisfactorily performed on December 31, 1996.
- 2. A review of scheduled surveillances for Units 1 and 2 was performed on December 31, 1996 and no other overdue surveillances were identified.
- 3. This event and Management's expectations regarding preventing recurrence were conununicated to Operations Personnel in a Night Order entry on December 31, 1996.
- 4. Personnel involved with the occurrence were held accountable for their actions in accordance with PSE&G's disciplinary policy.
- 5. Review of the overdue surveillance report was reinstated as part of the shift turnover process on December 31, 1996.
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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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