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AGILITY NAHE (I)
LICENSEE EVENT REPORT (LER)
Mashin ton Nuclear Plant - Unit 2 ITLE (4)
DOCKET NUHB R (
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I OF NONWATER TIGHT PENEIRATION SEALS IN ECCS PUMP ROOMS COULD RESULT IN COMMON MODE FAILUREFROM FLOODING EVENT DATE (5)
LER NUHBER 6)
REPORT DATE (7)
OTHER FACILITIES INVOLVED (8)
HONTH DAY 0
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3 YEAR 9
2 YEAR 9
2 SEQUENTIAL NUHBER gi 0
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6 DAY YEAR 2
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3 FACILITY NAHES CKE NUHB R (5) 5 0 0 0 5 0 0 0 PERATING ODE (9)
OWER LEVEL (iO) 0.402(b) 0.405(a)(1)(i) 0.405(a)(1)(ii) 0.405(a)(1)(iii) 0.405(a)(1)(iv) 0.405(a)(1)(v) 0.405(C) 50.36(c)(l) 50.36(c)(2) 50.73(a)(2)(i) 50.73(a)(2)(ii) 50.73(a)(2)(iii) 50.73(a)(2)(iv) 50.73(a)(2)(v) 50.73(a)(2)(vii) 50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B) 50.73(a)(2)(x) 77.71(b) 73.73(c)
THER (Specify in Abstract elow and in Text, NRC orm 366A)
HIS REPORT IS SUBHITTED PURSUANT TO THE REQUIREHENTS OF 10 CFR 5:
(Check one or more of the following) (11)
AHE LICENSEE CONTACT FOR THIS LER 12 R.
E. Fuller, Licensing Engineer art 21 TELEPHONE NUHBER REA CODE 5
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COHPLETE ONE LINE FOR EACH COHPONENT FAILURE DESCRIBED IN THIS REPORT (13)
CAUSE
SYSTEH COHPONENT HANUFACTURER EPORTABLE 0 NPRDS
CAUSE
SYSTEH COHPONENT HANUFACTURER EPORTABLE TO NPROS SUPPLEHENTAL REPORT EXPECTED (14)
YES (If yes, complete EXPECTED SUBHISSION DATE)
NO 11VCT nOI EXPECTED SUBHISSION HONTN DAY TEAR ATE (15)
On July 13, 1992, a Design Engineer determined that selected penetrations in all of the Emergency Core Cooling System (ECCS) pump rooms could fail to perform as a flooding barrier following a design basis flood. This could result in flooding of adjacent ECCS pump rooms.
Review and identification of this condition occurred as part of the review process of Plant penetration seals being done per a commitment in LER 89-026. It was later determined that stairwell flooding could result in concurrent flooding of associated ECCS pump rooms due to door seal leakage and may result in common mode failure of the Residual Heat Removal (RHR) capability.
This condition is also reportable per 10CFR Part 21 as a deficiency in the seal design of the ECCS pump room penetrations by the Plant Architect/Engineer (A/E),
Burns and Roe, Inc.
Immediate corrective actions included hourly fire/flood tours and temporary installation of cameras in stairwells and ECCS pump rooms to provide early warning capability of an unlikely flood condition.
The root causes of deficient penetration seals were less than adequate change management of the penetration seal requirements and inappropriate performance requirements of the sealant material.
The root cause of the potential loss of RHR from door seal leakage was management methods did not ensure sufficient information to determine the acceptability of concurrent flooding of the ECCS pump rooms.
9306300319 930624 PDR ADOCK 05000397 S
PDR
I I
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION AGILITY NANE (1)
Washington Nuclear Plant - Unit 2 DOCKET NUMBER (2) 0 5
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9 7
LER NUNBER (6) ear umber ev.
No.
2 34 2
AGE (3) 2 F
6 ITLE (4)
NONWATER TIGHT PENETRATION SEALS IN ECCS PUMP ROOMS COULD RESULT IN COMMON MODE FAILURE FROM FLOODING
~AA (C
Allof the identified inadequate penetration seals in the ECCS pump rooms except for the door seals have been reworked to be water tight.
The safety significance of this condition is negligible.
The probability of a flooding event occurring without recognition by the Reactor Operators to mitigate the event is highly unlikely. Also, no event occurred during the period this condition existed that required the penetration seals to perform the flooding barrier function. This condition posed no threat to the health and safety of Plant personnel or the public.
In ni n
Power Level - 0%
Plant Mode - 4 vnD ri in On July 13, 1992, a Design Engineer determined that selected penetrations in all of the Emergency Core Cooling System (ECCS) pump rooms could fail to perform as a flooding barrier following a design basis flood. This could result in flooding of adjacent ECCS pump rooms.
Review and identification of this condition occurred as part of the review process of Plant penetration seals being done per a commitment in LER 89-026.
There are six ECCS pumps that are in compartments surrounding Primary Containment at the 422-foot elevation.
Flooding can occur from various events to an elevation of 466 feet.
These events include a long term passive failure of an ECCS pump seal or valve bonnet following a LOCA, or moderate energy pipe cracks in the Reactor Building resulting in flooding of the stairwells or the ECCS pump rooms.
The penetration seals protect against common mode failure of ECCS equipment from these flooding events.
During review of ECCS pump room pressurization due to flooding, some of the penetrations in the ECCS pump room walls were found to be fire barrier sealed with BISCO silicone foam SF-20.
The silicone foam is not qualified or rated as a water tight seal by the vendor for pressures greater than 0.25-inches w.g.
The FSAR states that the ECCS pump rooms are water tight compartments designed to withstand a static head of 44 feet w.g. Therefore, the potential exists for internal flooding among redundant ECCS pump rooms if the silicone foam is exposed to design basis flooding.
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION ACILlTY NAME (1)
Washington Nuclear Plant - Unit 2 OOCKET NUHBER (2) 0 5
0 0
0 3
9 7
LER NUHBER (8)
Year umber ev.
No.
2 34 2
AGE (3) 3 F
6 ITLE (4)
NONWATER TIGHT PENETRATION SEALS IN ECCS PUMP ROOMS COULD RESULT IN COMMON MODE FAILURE FROM FLOODING The initial review found approximately 377 penetrations through walls of the ECCS pump rooms where unqualified sealant materials were used.
Further review identified an additional 234 penetrations requiring evaluation.
The reasons for the additional penetrations included:
(1) the flooding analysis calculated a two foot higher flood level than that stated in the FSAR; (2) long term integrity of the boots used to seal the exterior side of the exterior wall penetrations is questionable; (3) the Biological Shield Wall portion of the rooms were not considered in the original scope of problem barriers, and (4) testing of water seal configurations revealed that threaded connections previously considered to be water tight were a leakage path.
The majority of the nonwater tight seals are internal conduit seals that contain cables.
The majority of the penetration sizes of concern are less than four inches in diameter.
Approximately 100 of the penetra-tions are sealed with a fire rated sealant, which is qualified and acceptable for use as a water pressure sealant.
Therefore, approximately 500 penetrations required rework to install a qualified watertight seal.
Imm it rr iv A i n Hourly flood tours were initiated in appropriate areas of the Plant to ensure mitigation measures could be implemented before the operability of redundant ECCS equipment is compromised due to flooding. In addition, temporary cameras were installed in selected stairwells and ECCS pump rooms to provide additional early warning capability to the Reactor Operators in the unlikely event of a flooding condition.
The camera monitors are continuously monitored by personnel for flooding conditions.
ECCS pump room flood level instrumentation and corresponding Control Room annunciation were verified operable.
In addition, non-Class 1 sump alarms in the ECCS pump rooms are also available to alert the Operators of a possible flooding condition. A Plant procedure was developed to give the Plant Operators direction on how to mitigate a variety of postulated accident conditions.
Equipment was prestaged, such as ladders, portable lights, hoists over access hatches, etc., to expedite mitigation of postulated accident conditions.
The lowest penetration height of approximately 8 feet above the floor of the ECCS pump rooms provides adequate time for the Operators to mitigate a flooding event and prevent flooding of an adjacent ECCS pump room.
Practice exercises performed with the new procedure verified the time needed for the operators to implement the mitigating actions.
These actions were completed prior to startup from the refueling outage.
F hrEvl in n
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F~h 1.
This event is considered reportable per 10CFR50.73(a)(2)(ii)(A) and (B) as a condition which was unanalyzed and was outside the design basis of the Plant.
The BISCO silicone foam in selected ECCS pump room common wall penetrations would not prevent a common mode failure of safety related equipment from a design basis flooding event.
This condition is also reportable per 10CFR50.73(a)(2)(v)(A), (B), and (D) as a condition alone that could have
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION AGILITY NANE (1)
Washington Nuclear Plant - Unit 2 DOCKET NUNBER (2) 0 5
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LER NUMBER (6) ear umber ev.
No.
2 34 2
AGE (3) 4 6
ITLE (4)
NONWATER TIGHT PENETRATION SEALS IN ECCS PUMP ROOMS COULD RESULT IN COMMON MODE FAILURE FROM FLOODING prevented the fulfillmentof the safety function of systems needed to shutdown the reactor and maintain it in a safe shutdown condition, remove residual heat, and mitigate the consequences of an accident.
The NRC was verbally notified on July 13, 1992, at 1614 hours0.0187 days <br />0.448 hours <br />0.00267 weeks <br />6.14127e-4 months <br /> PST per 10CFR50.72(b)(2)(i) as a degraded condition found while shutdown.
This condition is also reportable per 10CFR Part 21 as a deficiency in the seal design of the ECCS pump room penetrations by the Plant Architect/Engineer (A/E), Burns and Roe, Inc.
The deficiency resulted in the possible inability of the ECCS pumping systems to perform their safety function in the unlikely event of a design basis flooding condition.
2.
In 1978, the NRC issued IE Circular Number 78-06 which required divisional ECCS equipment installed in water tight rooms to preclude common mode flooding. Holders of reactor operating licenses were instructed to assure that pathways that could lead to common flooding of redundant equipment did not exist in their facilities. In 1978 the WNP-2 FSAR was issued stating, "The [reactor building] compartments, comprising interior walls and building exterior walls and doors and penetrations therein, are designed so that any one com-partment at a time can withstand flooding to elevation 466'-3", slightly above the operating level of the suppression chamber pool, which is 44 feet above the top of the foundation mat.'"
The current revision of the FSAR, Revision 44, contains this statement.
The A/E's 1980 design specification for penetration seals to be installed at elevations below 471 feet in the Reactor Building required them to be water tight to a pressure of 35 feet w.g.
This did not agree with the FSAR statement of 44 feet w.g. on flooding pressure.
The design specification for the seals was changed later in the same year to 46 feet w.g. to account for increased pressure due to seismic sloshing.
In December of 1982, the A/E inappropriately reduced the seal pressure requirement to 25 feet w.g. for seals installed between elevations of 461.5 feet and 436 feet.
This requirement is less than what the actual pressure would be of 30 feet w.g. at 436 feet elevation with the water level at 466 feet elevation.
At the same time the maximum pressure requirement for seals installed below 436 feet was also inappropriately reduced to 39 feet w.g., which is less than the 44 feet w.g.
indicated in the FSAR. In February of 1983, the A/E deleted the water tight pressure requirement for penetration seals entirely.
The basis for this change was not documented.
3.
During evaluations to consider additional flood monitoring instrumentation as required by Revision 0 of LER 92-034, a Design Engineer determined that the doors leading into selected ECCS pump rooms from the stairwells would not preclude leakage into the rooms.
The condition of possible concurrent flooding from stairwell flooding is limited to the RHR "C" and Low Pressure Core Spray (LPCS) pump rooms, or the RHR "A" and the Reactor Core
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION AC1L1TY KAKE (1)
Washington Nuclear Plant - Unit 2 DOCKET KUHBER (2) 0 5
0 0
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LER KUKBER (8) umber ev.
Ko.
2 3 4 2
AGE (3) 5 F
6 ITLE (4)
NONWATER TIGHT PENETRATION SEALS IN ECCS PUMP ROOMS COULD RESULT IN COMMON MODE FAILURE FROM FLOODING Isolation Cooling (RCIC) pump rooms.
This condition was previously recognized and was deemed acceptable because there would still remain redundant systems to bring the Plant to a safe cold shutdown.
Part of the study to consider additional flood monitoring instrumentation willbe to reevaluate this condition.
4.
The root causes of inadequate penetration sealant in the ECCS pump rooms were:
- 1) Less Than Adequate Change Management because System Interaction Was Not Considered, and 2)
Inappropriate Performance Requirements of Plant Equipment Design.
With respect to the first root cause, the water tight pressure requirement for the seals was deleted without consideration by the A/E of common mode failure of ECCS equipment due to flooding. The second root cause is the result of inconsistent performance requirements of the sealant material and design with regard to the design basis requirements of the ECCS pump rooms.
The root cause of the potential common mode failure of the RHR System due to concurrent room flooding from stairwell flooding was management methods were less than adequate to ensure there was sufficient information to support the acceptability of door leakage.
5.
There were no other structures, components, or systems inoperable prior to the event which contributed to the event.
B.
her rr iv A inT n
A contractor was retained to perform testing on a variety of sealant materials that willsatisfy the water pressure requirements and compatibility with existing fire barrier sealant.
Selection of the sealant materials was completed October 23, 1992.
2.
Work on the wall penetrations in the affected ECCS pump rooms was completed June 11, 1993, to be water tight.
C.
F hr rr iv A in 1.
An evaluation willbe completed and corrective action plan established by November 30, 1993, to determine the best course of action to resolve the issue of potential flooding of the above described ECCS pump rooms through the nonwater tight doors.
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION AGILITY NAME (I)
Washington Nuclear Plant - Unit 2 DOCKET NUMBER (2) 0 5
0 0
0 3
9 7
LER NUMBER (6) umber ev.
No.
AGE (3) 2 34 02 6
F 6
ITLE (4)
NONWATER TIGHT PENETRATION SEALS IN ECCS PUMP ROOMS COULD RESULT IN COMMON MODE FAILURE FROM FLOODING 2.
With the rework of the penetration seals completed, it is no longer necessary to maintain a continuous surveillance camera watch to ensure adequate time for detection and mitigation of a flood. However, hourly flood watch tours have been implemented until further evaluation indicates that flooding consequences in the stairwells are acceptable or additional doors are installed to prevent flooding of associated pump rooms.
The hourly flood tours in combination with the Class 1 leak detection provided in each room are considered adequate to ensure timely detection of any flood condition and to initiate the necessary mitigation actions.
fe i nifi n
The safety significance of this condition is negligible.
The source of flooding is from moderate energy line breaks rather than from high energy line breaks.
Therefore, recognition of the condition before significant flooding occurs is more likely. In addition, there are Class I level indications in each of the ECCS pump rooms and sump pump monitors to provide reliable flooding information to the Reactor Operators.
The probability of a flooding event occurring without recognition by the Reactor Operators to mitigate the event is highly unlikely. Also, no event occurred during the period this condition existed that required the penetration seals or the door seals to perform the flooding barrier function. This condition posed no threat to the health and safety of Plant personnel or the public.
i il rEvn LER 89-026 documents identification of selected Steam Tunnel penetration seals that could have failed to withstand the internal pressure from a design basis Main Steamline break.
A commitment made in LER 89-026 to review Plant penetration seals for pressure requirements identified the condition of the ECCS pump room penetration seals.
This review has been completed, and no other penetration seals were identified that would be needed to withstand pressure under accident conditions.
EII Inf rm i n Tx Rfrn BHHft
$gggm Q~m~nen High Pressure Core Spray System Low Pressure Core Spray System RHR/Containment Spray Reactor Core Isolation Cooling System BG BM BO BN PEN PEN PEN PEN
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| 05000397/LER-1992-001, :on 920102,high Pressure Core Spray Declared Inoperable Due to Battery Inoperability.Caused by Instructional Presentation Deficiencies in TS Requirements. Notes Were Added to Surveillance Procedure |
- on 920102,high Pressure Core Spray Declared Inoperable Due to Battery Inoperability.Caused by Instructional Presentation Deficiencies in TS Requirements. Notes Were Added to Surveillance Procedure
| 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)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-002, :on 920113,determined That MSIV Leakage Control Sys Fan Testing Incorrectly Performed.On 920127, Determined That Setpoint for Pressure Switch Did Not Ensure Proper Sys Operation.Ts Waiver Obtained |
- on 920113,determined That MSIV Leakage Control Sys Fan Testing Incorrectly Performed.On 920127, Determined That Setpoint for Pressure Switch Did Not Ensure Proper Sys Operation.Ts Waiver Obtained
| 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) 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)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-003, :on 920123,circulating Fan CAC FN-1B Failed to Start During Performance of Surveillance Test.Caused by Tripped Overloads.Thermal Overloads Reset & Surveillance Test Performed |
- on 920123,circulating Fan CAC FN-1B Failed to Start During Performance of Surveillance Test.Caused by Tripped Overloads.Thermal Overloads Reset & Surveillance Test 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)(iv), System Actuation 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)(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)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-004, :on 920227,noted Scram Discharge Vol Level Switches Not Tested Post Scram as Required.Caused by Testing Not Being Performed.Corrective Actions Were Not Required |
- on 920227,noted Scram Discharge Vol Level Switches Not Tested Post Scram as Required.Caused by Testing Not Being Performed.Corrective Actions Were Not Required
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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) 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)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-005, :on 920219,thermal Overloads Prevented Motors from Performing Safety Functions.Caused by Misapplication of Design Inputs.Motors Replaced |
- on 920219,thermal Overloads Prevented Motors from Performing Safety Functions.Caused by Misapplication of Design Inputs.Motors Replaced
| 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 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)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-006, :on 920220,reactor Bldg to Suppression Chamber Vacuum Breaker Setpoints Were Incorrectly Set.Caused by Analysis Deficiency.Setpoint Documentation Changed & Procedures Deviated & Setpoints Reset |
- on 920220,reactor Bldg to Suppression Chamber Vacuum Breaker Setpoints Were Incorrectly Set.Caused by Analysis Deficiency.Setpoint Documentation Changed & Procedures Deviated & Setpoints Reset
| 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) 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)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-007, :on 920225,both Divs of Primary Containment Atmosphere Control Hydrogen Recombiner Sys Inoperable & Plant Shutdown Initiated.Caused by Less than Adequate Design.Design Changes Implemented |
- on 920225,both Divs of Primary Containment Atmosphere Control Hydrogen Recombiner Sys Inoperable & Plant Shutdown Initiated.Caused by Less than Adequate Design.Design Changes Implemented
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-008, :on 920301,standby Gas Treatment Sys Fan Flow Limiter Setpoint Error Identified.Caused by Analysis Deficiency.Investigation Into Instrument Setpoint Accuracy Ongoing |
- on 920301,standby Gas Treatment Sys Fan Flow Limiter Setpoint Error Identified.Caused by Analysis Deficiency.Investigation Into Instrument Setpoint Accuracy Ongoing
| 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)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-008-01, :on 920301,SGTS Fan Flow Limiter Setpoint Error Discovered.Caused by Analysis Deficiencies.Sgts Fan Flow Limiter Setpoint Changed & Rev 2 of Jco Approved W/New Offsite Dose Calculations |
- on 920301,SGTS Fan Flow Limiter Setpoint Error Discovered.Caused by Analysis Deficiencies.Sgts Fan Flow Limiter Setpoint Changed & Rev 2 of Jco Approved W/New Offsite Dose Calculations
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(iii) | | 05000397/LER-1992-009, :on 920302,determined That Containment Instrument Air Pressure Switch Setting Changes Required. Caused by Analysis Deficiency.Pressure Switches Were Reset in Accordance W/New Setpoint Calculations |
- on 920302,determined That Containment Instrument Air Pressure Switch Setting Changes Required. Caused by Analysis Deficiency.Pressure Switches Were Reset in Accordance W/New Setpoint Calculations
| 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)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-010, :on 920303,standby Gas Treatment Differential Pressure Controller Setpoint Error Identified.Caused by Analysis Deficiency.Setpoint Methodology Program to Review Selected non-harsh Setpoints Extended |
- on 920303,standby Gas Treatment Differential Pressure Controller Setpoint Error Identified.Caused by Analysis Deficiency.Setpoint Methodology Program to Review Selected non-harsh Setpoints Extended
| 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)(B) | | 05000397/LER-1992-011, :on 920305,discovered That Method of CRD Hydraulic Isolation Did Not Meet TS Requirements.Caused by Less than Adequate Procedures Due to Omission of Relevant Info in Procedure.Exhaust Water Valve Closed |
- on 920305,discovered That Method of CRD Hydraulic Isolation Did Not Meet TS Requirements.Caused by Less than Adequate Procedures Due to Omission of Relevant Info in Procedure.Exhaust Water Valve Closed
| 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) 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)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-012, :on 920318,determined That Removal of Access Plugs Over RHR Pump Rooms a & B Exposed Both Rooms to Potential Flooding from Common Source.Caused by Faulty Mgt Methods.Interim Guidance Provided |
- on 920318,determined That Removal of Access Plugs Over RHR Pump Rooms a & B Exposed Both Rooms to Potential Flooding from Common Source.Caused by Faulty Mgt Methods.Interim Guidance Provided
| 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 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)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-013, :on 920318,annunciator for RHR B/C VLV Open Permissive Found Lit & RHR Pressure Switch Found Isolated During Startup.Cause Not Determined.Pressure Switch Returned to Svc & Annunicator & Permissive Cleared |
- on 920318,annunciator for RHR B/C VLV Open Permissive Found Lit & RHR Pressure Switch Found Isolated During Startup.Cause Not Determined.Pressure Switch Returned to Svc & Annunicator & Permissive Cleared
| 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)(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)(A) | | 05000397/LER-1992-014, :on 920326,920414 & 920512,engineers Identified TS Violations Associated W/Flow Measurements in Hpcs,Lpcs & RHR Sys,Respectively.Caused by Inadequate Design Analysis. Tests Performed to Verify Flows |
- on 920326,920414 & 920512,engineers Identified TS Violations Associated W/Flow Measurements in Hpcs,Lpcs & RHR Sys,Respectively.Caused by Inadequate Design Analysis. Tests Performed to Verify Flows
| 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) 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-015, :on 920413,unexplained Pressure Drop in ADS B Section of Containment Instrument Air Sys Header Occurred. Caused by Inadequate Written Procedures.Valve CIA-V-41B Inspected & PPM-8.9.130 Replaced |
- on 920413,unexplained Pressure Drop in ADS B Section of Containment Instrument Air Sys Header Occurred. Caused by Inadequate Written Procedures.Valve CIA-V-41B Inspected & PPM-8.9.130 Replaced
| 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)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-016, :on 920424,determined That RCIC Sys Not Adequately Transferred to Remote Shutdown Panel.Caused by Misapplication of Design Inputs.Power Supply for RCIC Control Sys (48-volt Dc) Will Be Modified |
- on 920424,determined That RCIC Sys Not Adequately Transferred to Remote Shutdown Panel.Caused by Misapplication of Design Inputs.Power Supply for RCIC Control Sys (48-volt Dc) Will Be Modified
| 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)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-017, :on 920508,personnel Determined That Heat Removal Capability of Train a RHR Heat Exchanger Less than Design Allowable.Caused by Insufficient Monitoring of Plant Components.Corrective Actions Not Required |
- on 920508,personnel Determined That Heat Removal Capability of Train a RHR Heat Exchanger Less than Design Allowable.Caused by Insufficient Monitoring of Plant Components.Corrective Actions Not Required
| 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 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) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) | | 05000397/LER-1992-018, :on 920428,determined That Six Locations Not Provided W/Emergency Lighting Capacity & Operator Actions Required for Fire Outside Main CR Not in Procedures.Caused by Inadequate Design.Lighting Provided |
- on 920428,determined That Six Locations Not Provided W/Emergency Lighting Capacity & Operator Actions Required for Fire Outside Main CR Not in Procedures.Caused by Inadequate Design.Lighting Provided
| 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)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-019, :on 920430,determined That Automatic Depressurization Sys Potentially Inoperable Due to Inadequate Installation Instructions of Solenoid Pilot Valve Power Cables.Design Change Implemented |
- on 920430,determined That Automatic Depressurization Sys Potentially Inoperable Due to Inadequate Installation Instructions of Solenoid Pilot Valve Power Cables.Design Change Implemented
| 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)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-020, :on 920508,discovered Low Elements for Low Pressure Core Spray Min Flow Control Not Properly Installed. Procedures Modified to Include Check of Instrument Startups Prior to Running Pump |
- on 920508,discovered Low Elements for Low Pressure Core Spray Min Flow Control Not Properly Installed. Procedures Modified to Include Check of Instrument Startups Prior to Running Pump
| 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) 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)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-021, :on 920513,discovered That Certain QC-2 Instruments Were Not Appropriately Isolated from QC-1.Caused by Less than Adequate Design.No Corrective Action Was Taken |
- on 920513,discovered That Certain QC-2 Instruments Were Not Appropriately Isolated from QC-1.Caused by Less than Adequate Design.No Corrective Action Was Taken
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-022, :on 920514,plant Engineer Determined That Labyrinth Seals Installed in Replacement CAC Blowers Were Not Environmentally Qualified.Caused by Inadequate Work Practices & Procedures.Personnel Counseled |
- on 920514,plant Engineer Determined That Labyrinth Seals Installed in Replacement CAC Blowers Were Not Environmentally Qualified.Caused by Inadequate Work Practices & Procedures.Personnel Counseled
| 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)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-023, :on 930519,review of non-licensed Operator Tour Log Revealed Missed TS Surveillance & Fire Tour Data Due to Less than Adequate Work Practices.Investigation Into Event Expanded.No Violations Noted |
- on 930519,review of non-licensed Operator Tour Log Revealed Missed TS Surveillance & Fire Tour Data Due to Less than Adequate Work Practices.Investigation Into Event Expanded.No Violations Noted
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000397/LER-1992-024, :on 920519,discovered Inadvertent Emergency Ventilation Actuation.Caused by Work Practices Being Less than Adequate.Technicians Were Counseled |
- on 920519,discovered Inadvertent Emergency Ventilation Actuation.Caused by Work Practices Being Less than Adequate.Technicians Were Counseled
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000397/LER-1992-025-01, :on 920528,HPCS Pump Motor & Small Piece of Aluminum Upper Air Deflector Found Lodged in Motor Stator & Cracks Found in Deflector.Caused by Use of Improper Work Practices.Deflectors Replaced.Not Reportable Per Part 21 |
- on 920528,HPCS Pump Motor & Small Piece of Aluminum Upper Air Deflector Found Lodged in Motor Stator & Cracks Found in Deflector.Caused by Use of Improper Work Practices.Deflectors Replaced.Not Reportable Per Part 21
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) | | 05000397/LER-1992-025, :on 920522,during Insp of HPCS Pump Motor,Small Piece of Aluminum Upper Air Deflector Found Lodged Inside Motor Stator.Caused by Personnel Error.Evaluation of ECCS Will Be Performed to Prevent Future Damage |
- on 920522,during Insp of HPCS Pump Motor,Small Piece of Aluminum Upper Air Deflector Found Lodged Inside Motor Stator.Caused by Personnel Error.Evaluation of ECCS Will Be Performed to Prevent Future Damage
| 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)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-026, :on 920605,determined That Mo of RHR Train a May Have Prevented Full Closure of Drywell Spray Supply Valve.Caused by Inadequate Testing of Plant Equipment.Mo Repaired & Tested to Perform Design Function |
- on 920605,determined That Mo of RHR Train a May Have Prevented Full Closure of Drywell Spray Supply Valve.Caused by Inadequate Testing of Plant Equipment.Mo Repaired & Tested to Perform Design Function
| 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) 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) 10 CFR 50.73(a)(2)(viii)(8) | | 05000397/LER-1992-027, :on 920613,lack of Breaker Coordination Due to Instantaneous Trip Circuitry.Amptector Discriminator Circuit for Each of Six Feeder Breakers Disabled |
- on 920613,lack of Breaker Coordination Due to Instantaneous Trip Circuitry.Amptector Discriminator Circuit for Each of Six Feeder Breakers Disabled
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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 | | 05000397/LER-1992-028, :on 920617,diesel Room Normal Air Handling Fans Precluded Performance of Required Design Function.Caused by Equipment Design Deficiency.Loop Test Procedure Will Be Revised |
- on 920617,diesel Room Normal Air Handling Fans Precluded Performance of Required Design Function.Caused by Equipment Design Deficiency.Loop Test Procedure Will Be Revised
| 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)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-029, :on 920624,RHR Shutdown Cooling Isolation Occurred & Shutdown Cooling Supply Line Inboard Isolation Valve Automatically Closed.Caused by Inadequate Personnel Work Practices.Shutdown Cooling Reestablished |
- on 920624,RHR Shutdown Cooling Isolation Occurred & Shutdown Cooling Supply Line Inboard Isolation Valve Automatically Closed.Caused by Inadequate Personnel Work Practices.Shutdown Cooling Reestablished
| 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)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-030, :on 920630,containment Isolation Occurred, Resulting in Shutdown of nonsafety-related HVAC Equipment & Actuation of Containment Isolation Valves.Caused by Poor Work Place Layout.Event Reviewed W/Personnel |
- on 920630,containment Isolation Occurred, Resulting in Shutdown of nonsafety-related HVAC Equipment & Actuation of Containment Isolation Valves.Caused by Poor Work Place Layout.Event Reviewed W/Personnel
| 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)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-031, :on 920701,potential for Exceeding Continuous Rating of Divs I & II DG 1 & 2 Identified Due to Inadequate Circuit Electrical Separation.Caused by Design Deficiency. Items Placed on Hourly Fire Tour |
- on 920701,potential for Exceeding Continuous Rating of Divs I & II DG 1 & 2 Identified Due to Inadequate Circuit Electrical Separation.Caused by Design Deficiency. Items Placed on Hourly Fire Tour
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 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)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-032, :on 920702,unplanned Actuation of ESF Component Occurred Due to Decrease in Reactor Water Level Resulting from Voided Feedwater Piping.Water Level Restored within Normal Operating Parameters |
- on 920702,unplanned Actuation of ESF Component Occurred Due to Decrease in Reactor Water Level Resulting from Voided Feedwater Piping.Water Level Restored within Normal Operating Parameters
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) | | 05000397/LER-1992-033, :on 920706 & 920711,determined That SRV Failed to Reseat at Required Pressure Per Ts.Caused by Two Adjusting Rings within SRV Found Set at Wrong Position. Training Will Be Provided to Shop Personnel |
- on 920706 & 920711,determined That SRV Failed to Reseat at Required Pressure Per Ts.Caused by Two Adjusting Rings within SRV Found Set at Wrong Position. Training Will Be Provided to Shop Personnel
| 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)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-034, :on 920713,determined That Nonwater Tight Penetration Seals in ECCS Pump Rooms Could Result in Common Mode Failure from Flooding.Inadequate Penetration Seals in ECCS Pump Rooms Except for Door Seals Reworked |
- on 920713,determined That Nonwater Tight Penetration Seals in ECCS Pump Rooms Could Result in Common Mode Failure from Flooding.Inadequate Penetration Seals in ECCS Pump Rooms Except for Door Seals Reworked
| 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 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)(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)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-034-01, Forwards LER 92-034-01,describing Identification of Addl Unqualified Penetration Seals in ECCS Pump Room & Providing Status of Penetration Seal Rework | Forwards LER 92-034-01,describing Identification of Addl Unqualified Penetration Seals in ECCS Pump Room & Providing Status of Penetration Seal Rework | | | 05000397/LER-1992-034-02, Forwards LER 92-034-02.Supplemental Rept Describes Completion of Penetration Seal Rework & Changes to Flood Watch Requirements | Forwards LER 92-034-02.Supplemental Rept Describes Completion of Penetration Seal Rework & Changes to Flood Watch Requirements | | | 05000397/LER-1992-035, Responds to NRC 920831 Request for Addl Info Re LER 92-035 on Inadequate Testing of Scram Discharge Vol Vent & Drain Valves.Improvements to Plant Evaluation Requests Underway & Incident Review Board Established in June 1992 | Responds to NRC 920831 Request for Addl Info Re LER 92-035 on Inadequate Testing of Scram Discharge Vol Vent & Drain Valves.Improvements to Plant Evaluation Requests Underway & Incident Review Board Established in June 1992 | | | 05000397/LER-1992-035-01, Forwards LER 92-035-01.Suppls Provides Details & Clarifications Requested in NRC .Futher Review Indicates That Changes to post-mod Testing Plan Were Contributing Cause for Event | Forwards LER 92-035-01.Suppls Provides Details & Clarifications Requested in NRC .Futher Review Indicates That Changes to post-mod Testing Plan Were Contributing Cause for Event | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000397/LER-1992-036, :on 920719,primary Containment Lighting Circuit Not Deenergized as Required by Tech Specs.Caused by Technical Inaccuracy in Procedure for Plant Startup.Plant Startup Procedures & Drywell Entry Revised |
- on 920719,primary Containment Lighting Circuit Not Deenergized as Required by Tech Specs.Caused by Technical Inaccuracy in Procedure for Plant Startup.Plant Startup Procedures & Drywell Entry Revised
| 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) 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)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-037, :on 920815,reactor Manually Acrammed Due to Indications of Core Instability.Caused by Unanticipated Interaction of Operating Conditions & Components.Revised Operating Strategies & Related Procedures |
- on 920815,reactor Manually Acrammed Due to Indications of Core Instability.Caused by Unanticipated Interaction of Operating Conditions & Components.Revised Operating Strategies & Related Procedures
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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) 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)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-037-02, Forwards LER 92-037-02.Rev Provides Updated Info Re C/As for Manual Reactor Scram Due to Core Instability.Commitment to Obtain Amend to TS to Eliminate Requirements for Calculating T Deleted.Confusion Eliminated Through Trai | Forwards LER 92-037-02.Rev Provides Updated Info Re C/As for Manual Reactor Scram Due to Core Instability.Commitment to Obtain Amend to TS to Eliminate Requirements for Calculating T Deleted.Confusion Eliminated Through Training | | | 05000397/LER-1992-038, :on 921014,technicians Failed to Perform Main Condenser Offgas Sample Analysis Per TS 3.3.7.12,due to Personnel Error & Inadequate Work Mgt Methods.C/A Included Counseling,Equipment Repair & Further Training |
- on 921014,technicians Failed to Perform Main Condenser Offgas Sample Analysis Per TS 3.3.7.12,due to Personnel Error & Inadequate Work Mgt Methods.C/A Included Counseling,Equipment Repair & Further Training
| 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) 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)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-039, :on 920921,RWCS Isolated on High Differential Flow While ROs Were Attempting to Place filter-demineralizer RWCU-DM-1B Back Into Service.Caused by Inadequate Mgt Methods.Degraded Equipment Repaired & Procedures Updated |
- on 920921,RWCS Isolated on High Differential Flow While ROs Were Attempting to Place filter-demineralizer RWCU-DM-1B Back Into Service.Caused by Inadequate Mgt Methods.Degraded Equipment Repaired & Procedures Updated
| 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)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-040, :on 920930,determined That Start & Load Time for Standby & HPCS DG Not Measured During Monthly Surveillance Testing.Caused by Deficiencies in Mgt Methods. Expedited Effort Initiated to Amend Procedure |
- on 920930,determined That Start & Load Time for Standby & HPCS DG Not Measured During Monthly Surveillance Testing.Caused by Deficiencies in Mgt Methods. Expedited Effort Initiated to Amend Procedure
| 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)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-041, :on 921027,offsite Power Source Determined Inoperable During Brief Periods of Prior Operaton Due to Low Voltage Condition on 230 Kv Grid.Caused by Design Deficiency & Inadequate Mgt Methods.Ts Procedure Changed |
- on 921027,offsite Power Source Determined Inoperable During Brief Periods of Prior Operaton Due to Low Voltage Condition on 230 Kv Grid.Caused by Design Deficiency & Inadequate Mgt Methods.Ts Procedure Changed
| 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)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000397/LER-1992-042, Forwards Public Version of LER 92-042,Rev 0.Root Cause Is Inadequate Policy Re Free Release of Potentially Contaminated Liquids.Conclusions of Ongoing MORT Analysis Will Be in Suppl to LER | Forwards Public Version of LER 92-042,Rev 0.Root Cause Is Inadequate Policy Re Free Release of Potentially Contaminated Liquids.Conclusions of Ongoing MORT Analysis Will Be in Suppl to LER | | | 05000397/LER-1992-043, :on 921202,determined That Discrepancy Existed Between Plant Procedures & Monitoring Range of RPV Instrumentation in MCR & at Remote Shutdown Panel.Caused by Insufficient Communication.Procedures Revised |
- on 921202,determined That Discrepancy Existed Between Plant Procedures & Monitoring Range of RPV Instrumentation in MCR & at Remote Shutdown Panel.Caused by Insufficient Communication.Procedures Revised
| 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)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-044, :on 921208,HPCS Sys Pump Suction Valve Switchover Occurred,Due to Spurious Actuation of Either One or Both CST Pipe Break Detectors.Engineering Will Evaluate Replacement of Detectors & Alternate Design |
- on 921208,HPCS Sys Pump Suction Valve Switchover Occurred,Due to Spurious Actuation of Either One or Both CST Pipe Break Detectors.Engineering Will Evaluate Replacement of Detectors & Alternate Design
| 10 CFR 50.73(a)(2)(iv), System Actuation |
|