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| ML18102A307 |
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Salem  |
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| Issue date: |
08/16/1996 |
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| From: |
Hassler D Public Service Enterprise Group |
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| Shared Package |
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| ML18102A306 |
List: |
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| References |
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| LER-96-014-01, LER-96-14-1, NUDOCS 9608200201 |
| Download: ML18102A307 (4) |
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Similar Documents at Salem |
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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 |
| Event date: |
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| Report date: |
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| Reporting criterion: |
10 CFR 50.73(a)(2)(viii) |
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| 2721996014R00 - NRC Website |
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text
NRC FORM 366 U.S.NU R REGULATORY COMMISSION OVED BY OMB NO. 3150--0104 (4-95)
EXPIRES 04/30198 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS MANDATORY INFORMATION COLLECTION REQUEST: 50.0 HRS.
Ll.CENSEE EVENT REPORT (LER)
REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE LICENSING PROCESS ANO FED BACK TO INDUSTRY.
FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION (See reverse for required number of AND RECORDS MANAGEMENT BRANCH (T-8 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 NAME (1)
DOCKET NUMBER (2)
PAGE (3)
SALEM GENERATING STATION, UNIT 1 05000272 1 OF 4 TITLE (4)
Potential Hydrogen Embrittlement on 4KV Breaker Parts EVENT DATE (5)
LER NUMBER (6)
REPORT DATE (7)
OTHER FACILITIES INVOLVED (8)
FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEQUENTIAL MONTH DAY YEAR I
NUMBER
'REVISION NUMBER Salem unit2 05000311 07 17 96 96 014 00 08 16 96 FACILITY NAME DOCKET NUMBER 05000 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)
-.. ER 0
20.2203(a)(1) 20.2203(a)(3)(i)
- 50. 73(a)(2)(ii)
- 50. 73(a)(2)(>e)
LCVCL (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) x OTHER 20.2203(a)(2)(iii) 50.36(c)(1)
- 50. 73(a)(2)(v)
Spec~in Abstract below or in C Form 366A
- 50. 73(a)(2)(vii) 20.2203(a)(2)(iv) 50.36(c)(2)
Part 21 LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NUMBER (Include Area Code)
Dennis v. Hassler, LER Coordinator 609-339-1989 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
CAUSE
SYSTEM COMPONENT MANUFACTURER REPORTABLE I
CAUSE
SYSTEM COMPONENT MANUFACTURER REPORTABLE TONPRDS TONPRDS SUPPLEMENTAL REPORT E~.?ECTED (14)
EXPECTED MONTH DAY YEAR
'YES 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 July 17, 1996 a failure of a roll pin securing a spring for a latch pawl on a 4KV breaker was reviewed and a detennination made that the failure of this pin could cause the breaker to fail.
- Further investigation revealed that the roll pin failed as a result of hydrogen errbrittlement.
The roll pin failure was an unexpected occurrence and consequently detennined that this condition could place the plant in an unanalyzed condition. Later, an issue involving pemanently applied lubricant which was inadvertently removed from the breakers was identified. This also could potentially affect breaker operation.
The cause of the cracked roll pin was the lack of, knowledge of plating induced hydrogen errbrittlement.
The Nuclear Logistics Inc.-~porated (NLI) persor..r::..~ involved in the NLI procedure developnent were not aware that zinc plating of hardened steel parts could produce hydrogen embrittlement and subsequent cracking.
The cause of the lubricant being inadvertently rerroved from breaker parts is also due to the lack of knowledge by NLI personnel.
NLI is a PSE&G approved vendor for safety related work.
Corrective actions
include issuance of a stop work order on NLI's breaker activities and replacement of the affected parts and reapplication of the lubricant.
This event is reportable in accordance with 10 CFR 50.73(a) that resulted in 21.2 (c).
NRC FORM 366 (4-95) 9608200201 PDR ADOCK s
the plant 960813 05000272 PDR being in an unanalyzed condition (2) (ii); any event or condition and in accordance with 10 CFR (4-95)
.S. NUCLEAR REGULATORY COMMISSION FACILITY NAME (1)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION DOCKET NUMBER (2)
LER NUMBER (6) 05000272 YEAR I SEQUENTIAL I REVISION NUMBER NUMBER Salem Generating Station, Unit 1 96 -
014 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
PLANT AND SYSTEM IDENTIFICATION
Westinghouse - Pressurized Water Reactor 4KV Breakers {-/BKR}*
PAGE (3) 2 OF 4
- Energy Industry Identification System (EIIS) codes and corrponent function identifier codes appear as (SS/CCC)
CONDITIONS PRIOR TO OCCURRENCE At the time of identification, Salem Units 1 and 2 were shutdown and defueled.
DESCRIPTION OF OCCURRENCE On July 17, 1996 a failure of a roll pin securing a latch pawl on a 4KV breaker was reviewed and a determination made that the failure of this pin could cause the breaker to fail.
Further investigation revealed that the roll pin failed as a result of hydrogen ernbrittlernent.
The roll pin failure was an unexpected occurrence, and consequently determined that this condition could place the plant in an unanalyzed condition.
Public Service Electric & Gas (PSE&G) contracted with Nuclear Logistics Incorporated (NLI) to overhaul/refurbish 4 KV breakers for Salem Units 1 and 2.
NLI is a PSE&G approved vendor for safety related work.
NLI utilized clear zinc plating on a number of breaker parts that had been heat treated to a hardness of RC 60.
The plated areas should have been masked off so that the hardened surfaces were not subjected to the acid and zinc plate baths.
Acid cleaning and electroplating generates hydrogen, which can diffuse into the metal.
This can result in instant cracking or delayed cracking.
The cracking is not normally dependent on the operating load.
On May 1, 1996 a lockwasher holding the breaker lower arc chutes cracked and broke on site.
The remainder of the breaker washers were visually checked and no other similar washers were found.
The crack appeared to have been caused by hydrogen ernbrittlement induced when the lockwasher was zinc plated.
This condition was reported to the industry through INPO OE 7875 dated June 5, 1996.
During the first week of May, the circuit breakers which were at the Texas facility of NLI were inspected and no problems related to plating or lockwashers were found.
PSE&G then asked for u corrplete list of breaker parts that were zinc plated.
The list was develc~cd but it did not include the roll pins used on the breakers, including the ratchet drive pawl roll pins.
During the same time frame, the vendor reported that the ratchet drive pawl in some circuit breakers was chipping.
Efforts then were started to remove all hardened steel parts which were zinc plated by NLI with the intention of replacing them with new unplated parts. When the new parts became unavailable, NLI and PSE&G agreed on an alternate solution to the plating problem:
the parts would be heat treated to relieve hyd~ogen induced stress and reinstalled in the circuit breakers.
Both NLI and PSE&G agreed that no further zinc plating would be performed.
Circuit breakers were then delivered to Salem and some were installed in the plant.
"NRC FORM 366A (4-95)
NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1)
DOCKET NUMBER (2)
LER NUMBER (6) 05000272 YEAR I SEQUENTIAL I REVISION NUMBER NUMBER Salem Generating Station, Unit 1 96 -
014 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
DESCRIPTION OF OCCURRENCE (CONT'D)
PAGE (3) 3 OF 4
On July 16, 1995, a circuit breaker in the Salem breaker shop was being tested prior to installation in the plant. A circuit breaker was found to have its inner latch pawl spring hanging down.
The latch pawl itself was not engaging the ratchet wheel.
Further inspection revealed that the roll pin that fits inside the bottom of the pawl return spring had broken along its longitude axis.
The roll pin that broke normally serves to keep the bottom of the pawl return spring in the proper position.
The support plate in which the roll pin is mounted and the roll pin itself appear to have been plated.
Subsequent to the above, an issue involving inadvertently removed lubricant was identified. This was identified during a visual inspection of an NLI rebuilt circuit breaker.
The procedures for refurbishment of 4KV circuit breakers included acid cleaning and zinc plating of some mechanical parts.
The original equipment manufacturer design included a lubricant which was baked-on some moving parts. The baked-on lubricant (rnol:Ybdenum disulfide) was meant to last the life of the circuit breaker.
The molybdenum disulfide is a dry baked-on lubricant that is applied to various rotating and rubbing surfaces on the breaker. This lubricant is applied to minimize component wear.
The acid cleaning and zinc plating performed by NLI removed the original baked on lubricant.
After the zinc plating of parts was discontinued, the cleaning/polishing process used by NLI still resulted in the removal of the original baked on lubricant.
The effect of the above described problems is that all NLI circuit breakers which had parts zinc plated must be removed from the plant for parts replacement.
There were 15 breakers that were involved in the plating issue, and an additional four breakers involving the inadvertent removal of the lubricant.
Eleven of the 19 breakers were installed in the plant in vital load cubicles.
The buses where these breakers were installed were not operable but were considered available.
One of the 11 installed breakers, 2B4D, is currently installed in a vital application and is supplying loads (e.g.
spent fuel pool cooling pump).
At the time the broken roll pins.were found, it was not considered prudent, based on existing plant conditions, to remove this breaker. Also, an evaluation determined that failure of the plated roll pins in the breaker would not preclude this breaker from opening/tripping.
A contingency plan has been approved for replacement of this breaker and it is expected to be removed in the near future.
CAUSE OF OCCURRENCE The cause of the cracked roll pin was the lack of knowledge of plating induced hydrogen ernbrittlement.
The NLI procedure development and subsequent reviews failed to associate zinc plating of hardened steel parts *.:ith hydrogen embrittlement.
The NLI personnel involved in the NLI procedure were not aware that zinc plating of hardened steel parts could produce hydrogen ernbrittlement and the subsequent cracking.
The cause of the lubricant being inadvertently removed from breaker parts is also due to the lack of knowledge by NLI personnel. (4-95)
- NUCLEAR REGULATORY COMMISSION FACILITY NAME (1)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION DOCKET NUMBER (2)
LER NUMBER (6) 05000272 YEAR I SEQUENTIAL I REVISION NUMBER
- NUMBER Salem Generating Station, Unit 1 96 -
014 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
PRIOR SIMILAR OCCURRENCES PAGE (3) 4 OF 4
In the past two years, there has been one Salem LER that addressed breaker failures.
LER 272/96-009-00 addressed a potential common mode failure mechanism for 4KV breakers due to misalignment of the breaker mechanism.
The plating and lubrication issues discussed in this LER (272/96-014-00) were discovered as a result of the same overhaul work that identified the plating problem discussed above.
SAFETY CONSEQUENCES AND IMPLICATIONS
There were no safety consequences for this occurrence since the breaker failures were found while the plant was in a defueled condition and the buses are not operable.
However, the implications are that this is a potential common mode failure which could jeopardize the operability of safety related circuit breakers.
The operability of the AC Power Sources insures power will be available to supply safety related equipment.
In the event safety related equipment "ls required to start, but is prevented from starting due to a single circuit breaker failing, redundant safety equipment would be available.
- However, it is possible that during an event, more than one channel of safety related equipment could be affected.
The breaker installed in 2B4D was in the closed position and the roll pin was not cracked or missing.
The capability to open or trip the circuit breaker was reviewed and was determined not to be corrpromised.
The health and safety of the public were not affected by this occurrence.
CORRECTIVE ACTIONS
- 1. Removed all NLI refurbished breakers, except 2B4D, from vital loads.
Breaker 2B4D will be removed when its loads are available to be transferred to another bus.
"2. A QA stop work order was issued to NLI on July 26, 1996.
- 3. The circuit breakers will be sent for replacement and refurbishment.
This will be corrpleted for each breaker prior to that breaker being required to be operable.
- 4. Further corrective actions will be taken as a result of the root cause evaluation currently being conducted.
Significant corrective actions that affect the discussion in this LER, if any, will be reported in a supplement to this LER.
10CFR21 REPORTING 10CFR21 reporting requirements are met by this LER.
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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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