:on 990420,concluded That Auxiliary Bldg ESF Ventilation Sys Not Capable of Maintaining ESF Room Temps post-accident.Caused by Inadequate Control of Sys Design Inputs.Comprehensive Action Plan Being Developed| ML17325B600 |
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Cook  |
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| Issue date: |
05/20/1999 |
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| From: |
Orourke B INDIANA MICHIGAN POWER CO. |
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| ML17325B598 |
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| References |
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| LER-99-012, LER-99-12, NUDOCS 9905260279 |
| Download: ML17325B600 (4) |
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Similar Documents at Cook |
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text
NRC Form 366 U.S. NUCLEAR REGULATORYCOMMISSION (6-1998)
LICENSEE EVENT REPORT (LER)
(See reverse for required number of digits/characters for each block)
APPROVED BYOMB No. 3150.0104 EXPIRES 06/30/2001 ESTIMATED BURDEN PER
RESPONSE
TO COMPLY WITH THIS MANDATORY INFORMATIONCOLLECTION REOVESD 50.0 HRS. REPORTED LESSONS LEARNED ARE INCORPORATED BJTO THE UCEJISING PROCESS AND FED BACK TO INDUSTRY.
FORWARD COMMENTS REGARDUIG BURDEN ESTSJATE TO THE II&ORMATIONANO RECORDS MANAGEMENT BRANCH IT4 AS),
V.S.
NVCLEAR RFGUIATORY COMMISSION. WASHBJGTON. OC 205S54XI. ANO TO THE PAPERWORK REDUCTION PROJECT tst50410l), OFFICE OF MANAGEMENT AND BUCGEf, WASIeNGTceL DC 2050$
FACILITYNAMEI1)
Cook Nuclear Plant Unit 1 DOCKET NUMBERr2) 05000-315 PAGE I5) 1 of 3 TITLEI4)
Auxiliary Building ESF Ventilation System May Not be Capable of Maintaining ESF Room Temperatures Post-Accident MONTH 04 DAY YEAR 20 1999 EVENT DATE (5)
YEAR 1999 LER NUMBER (8)
SEQUENTIAL NUMBER 012 REVISION NUMBER 00 REPORT DATE (7)
MONTH DAY YEAR 05 20 1999 ILI D.C. Cook, Unit 2 A ILI NAM 05000-316 D
C NUMBER OTHER FACILITIESINVOLVED(8)
OPERATING MODE (9)
POWER LEVEL(10) 0%
20.2201 (b) 20.2203(a)(1) 20.2203(a)(2)(i) 20.2203(a)(2)(v) 20.2203(a)(3)(i) 20.2203(a)(3)(ii) 50.73(a)(2)(l) 50.73(a)(2)(ii) 50.73(a)(2)(iii) 50.73(a)(2)(viii) 50.73(a)(2)(x) 73.71 THIS REPORT IS SUBMITTEDPURSUANT TO THE REQUIREMENTS OF 10 CFR II: (Check one or more) (11) 20.2203(a)(2)(ii) 20.2203(a)(2)(iii) 20.2203(a)(2)(iv) 20.2203(a)(4) 50.36(c)(1) 50.36(c)(2)
LICENSEE CONTACT FOR THIS LER (12) 50.73(a)(2)(iv) 50.73(a)(2)(v) 50.73(a)(2)(vii)
OTHER Specii/y In Abstract bekrrr or nNRC Form 366A NAME Ms. Brenda W. O'ourke, Compliance Engineer TELEPHONE NUMBER (IIK5ude Area Code)
(616) 465-5901 x2604 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
.CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO EPIX
CAUSE
SYSTEM COMPONENT MANUFACTURER REPORTABLE TO EPIX SUPPLEMENTAL REPORT EXPECTED (14 X
YES (IfYes, complete EXPECTED SUBMISSION DATE)
NO EXPECTED SUBMISSION DATE 15 MONTH 10 DAY 31 1999 Abstract (Limitto 1400 spaces, I.e., approximately 15 singie-spaced typewritten lines) (16)
On April20, 1999, during performance of the Expanded System Readiness Review (ESRR) for the Auxiliary Building Ventilation Systems, it was concluded that there is insufficient assurance that the Engineered Safety Features Ventilation (AES) system is capable of performing its safety and accident mitigation function. This conclusion was based on a preliminary evaluation of numerous identified system deficiencies taken in the aggregate.
Specifically, significant errors in calculations for auxiliary building Engineered Safety Features cubicle temperatures expected during postulated accident scenarios, vulnerability of AES damper control air system modification to single failure; and lack of missile protection for the Component Cooling Water pump area supply fans.
Based on the combined effects of these deficiencies, the ability of the AES system to maintain auxiliary building temperatures to within safety-related equipment design temperatures under accident conditions cannot be assured.
The preliminary causes for identified conditions are: inadequate control of system design inputs; failure to adequately implement single failure design criteria during the modification process; and lack of a clear definition in design and licensing documents regarding design requirements for system protection against missile effects.
A comprehensive action plan is being developed to determine the auxiliary building design temperatures required to be maintained by the AES ventilation system.
In addition, a single failure analysis for the AES ventilation system willbe performed to identify failures that could prevent the system from performing its design and safety function. Based on the results of the completed evaluation, information regarding the safety significance, and corrective and preventive actions willbe provided in an update to this LER.
9905260279 990520 PDR ADOCK 050003'l5 S
PDRU.S. NUCLEAR REGULATORY COMMISSION (6-1998)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITYNAME(1)
Cook Nuclear Plant Unit 1 DOCKET NUMBER(2) 05000-315 YEAR LER NUMBER (6)
SEQUENTIAL NUMBER REVISION NUMBER PAGE (3) 2of3 TEXT (Ifmore space is required, use additional copies ofNRC Form (366A) (17)
Conditions Prior to Event
Unit 1 was in Mode 5, Cold Shutdown Unit 2 was in Mode 5, Cold Shutdown 1999 012 00 Descri tion of Event On April20, 1999, during performance of the Expanded System Readiness Review (ESRR) for the Auxiliary Building Ventilation Systems, it was concluded that there is insufficient assurance that the Engineered Safety Features Ventilation (AES) system is capable of performing its safety and accident mitigation function. This conclusion was based on a preliminary evaluation of numerous identified system deficiencies taken in the aggregate.
Specifically, significant errors in calculations for auxiliary building Engineered Safety Features (ESF) cubicle temperatures expected during postulated accident scenarios, combined with small design margins that existed between calculated room temperatures and design requirements; vulnerability of AES damper control air system modification to single failure; and lack of missile protection for the Component Cooling Water (CCW) pump area supply fans which could result in a single catastrophic failure-generated missile impacting both trains of AES. Based on the combined affects of these deficiencies, the ability of the Unit 1 and 2 AES systems to maintain auxiliary building temperatures to within safety-related equipment design temperatures under all accident conditions cannot be assured.
In accordance with the requirements of 10CFR50.72(b)(2)(iii)(D), a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> notification was made to the NRC on April20, 1999, at 1645 hours0.019 days <br />0.457 hours <br />0.00272 weeks <br />6.259225e-4 months <br />, for any event or condition that alone could have prevented the fulfillmentof the safety function of structures or systems that are needed to mitigate the consequences of an accident.
Cause of Event
The preliminary cause for the use of non-conservative and incorrect assumptions in auxiliary building heat load calculations is due to inadequate control of system design inputs. This issue was previously identified in AEP:NRC:1260GH, dated March 19, 1999, "Enforcement Actions98-150, 98-151,98-152 and 98-186, Reply to Notice ofViolation Dated October 13, 1998."
The preliminary cause for AES damper design single failure vulnerability is failure of the design change process to identify the potential adverse impact on the AES system created by the modification to the damper control air system in 1997.
The preliminary cause for CCW pump area supply fan susceptibility to missile effects is lack of a clear definition in design and licensing documents regarding AES design requirements for protection against missile effects.
Anal sis of Event This LER is submitted in accordance with 10CFR50.73(a)(2)(v)(D) for a condition that could prevent the fulfillmentof the safety functions of the AES system that are needed to mitigate the consequences of an accident:
The AES system safety and accident mitigation function is to provide sufficient cooling to the auxiliary building general areas and ESF equipment rooms required to operate during accident conditions. This includes the CCW, Containment Spray, Residual Heat Removal, Charging and Safety Injection equipment rooms. The AES system also maintains the auxiliary building at a negative pressure relative to the outside environment to ensure radioactive contamination released during an accident is contained within the auxiliary building, filtered and exhausted to the environment via a monitored, release path.
In addition, Technical Specification 3.7.6.1 requires that two independent AES ventilation system fan/filter exhaust trains be operable in Modes 1 through 4.
Calculations were developed to establish the auxiliary building heat loads, ESF cubicle room and general area temperatures during normal, shutdown and accident conditions.
During the ESRR review of these calculations, numerous discrepancies were identified. For example, calculation of auxiliary building area temperature during accident conditionsU.S. NUCLEARREGULATORY COMMISSION (6-1998)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITYNAME(1)
Cook Nuclear Plant Unit 1 DOCKET NUMBER(2) 05000-315 YEAR LER NUMBER (6)
SEQUENTIAL NUMBER REVISION NUMBER PAGE (3) 3of3 1999 012 00 TEXT (ifmore space is required, use additional copies ofNRC Form (366A) (17) did not include the heat load for the CCW system piping. This equipment is considered a significant heat load in the auxiliary building and excluding it from the calculation could result in non-conservative auxiliary building area temperature values.
In addition, these values serve as input assumptions to other auxiliary building ventilation calculations.
As a result, actual auxiliary building area and ESF cubicle room temperatures could impact the qualification of the ESF equipment located in the areas served by the AES and CCW pump area ventilation systems.
The AES ventilation system consists of two fan/filter exhaust trains (one in standby) which draws air from the auxiliary building through the equipment cubicles from a common vent duct, and discharges the exhaust to the outside atmosphere via the vent stack.
Each train consists of a roughing filter, high efficiency particulate air (HEPA) filters, and a normally closed pneumatically operated face damper.
In addition, each train contains a bypass duct with a normally open pneumatically operated bypass damper which directs air flow around the charcoal adsorbers.
During normal operation, one fan/filter unit operates continuously, directing the exhaust air through the roughing and HEPA filters, bypassing the charcoal filters, and discharging to the unit vent. This operation aids in air distribution within the auxiliary building, isolates the atmosphere in the cubicies by inducing a draft through the entering portals and removes any heat generated within the enclosures.
In 1997, a modification to the damper control air system included the installation of solenoid valves in the air lines to the face and bypass dampers.
During the performance of surveillance test 12 OHP 4030 STP.25A/8, on two separate occasions, the face damper solenoid valve failed, resulting in the face damper failing to open while the bypass dampers remained closed.
For non-Sl initiated events, a failure of the face damper solenoid to open the'face damper or the bypass damper solenoid to open the bypass damper in response to a control signal could result in both the face and bypass dampers being in the closed position, blocking all air flow through the affected train.
In the event of a Phase B Isolation signal, the standby train is energized and the bypass dampers automatically close and the face dampers open to exhaust air directly through the charcoal filters, roughing and HEPA filters. Although the single failure of either the bypass or face damper solenoid valve would render one train of AES inoperable, it would not impact the capability of the standby fan/filter train from performing its safety and accident mitigation function.
The AES system design includes three vaneaxial supply fans located in the CCW equipment room which are located side by side, and connected to a common intake plenum and discharge duct. Because vaneaxial fans are susceptible to fan blade failures, the fan blades are a potential missile source which could impact the function of adjacent safety related components.
As a result, failure of the CCW pump area supply fans could impact the ability of the AES system to maintain ESF cubicle temperatures to within equipment design temperatures, impacting the qualification of the ESF equipment.
Because of the numerous system deficiencies identified during the ESRR, a comprehensive action plan is being developed to evaluate the identified conditions.
Until the aggregate effect of these conditions on AES system performance is evaluated, the overall safety impact cannot be determined.
Corrective Actions
A comprehensive action plan is being developed to determine the auxiliary building design temperatures required to be maintained by the auxiliary building ventilation systems:
In addition, a single failure analysis for the AES ventilation system willbe performed to identify failures which could prevent the system from performing its design and safety function. Based on the results of the completed evaluation, additional information regarding safety significance, including corrective and preventive actions willbe provided in an update to this LER.
Previous Similar Events
LER 315/97-023-00
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| 05000316/LER-1999-001-01, Regarding Supplemental LER for Degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations | Regarding Supplemental LER for Degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 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)(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)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000315/LER-1999-001, :on 990106,noted That GE Hfa Relays Installed in EDGs May Not Meet Seismic Qualification.Caused by Operating Experience Info Incorrectly Dispositioned in 1985. Updated LER Will Be Submitted by 990405 |
- on 990106,noted That GE Hfa Relays Installed in EDGs May Not Meet Seismic Qualification.Caused by Operating Experience Info Incorrectly Dispositioned in 1985. Updated LER Will Be Submitted by 990405
| 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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) | | 05000316/LER-1999-001, :on 960610,degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations,Identified on 990226.Caused by Inadequate Understanding of Design Basis.Additional Investigations Ongoing |
- on 960610,degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations,Identified on 990226.Caused by Inadequate Understanding of Design Basis.Additional Investigations Ongoing
| 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) 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 | | 05000315/LER-1999-002, :on 990112,determined That RCS Pressurizer PORVs Had Not Been Tested,Per Ts.Caused by Inadequate Scheduling Controls Allowing Personnel Error.Surveillance Procedure Was Completed & Updated LER Will Be Submitted |
- on 990112,determined That RCS Pressurizer PORVs Had Not Been Tested,Per Ts.Caused by Inadequate Scheduling Controls Allowing Personnel Error.Surveillance Procedure Was Completed & Updated LER Will Be Submitted
| 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) | | 05000316/LER-1999-002-01, :on 990415,discovered That TS 4.0.5 Requirements Were Not Met Due to Improperly Performed Test. Caused by Incorrect Interpretation of ASME Code.App J Testing Will Be Completed & Procedures Will Be Revised |
- on 990415,discovered That TS 4.0.5 Requirements Were Not Met Due to Improperly Performed Test. Caused by Incorrect Interpretation of ASME Code.App J Testing Will Be Completed & Procedures 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)(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) | | 05000316/LER-1999-002, Forwards LER 99-002-00 Re TS 4.0.5 Requirements Not Being Met Due to Improperly Performed Test.Commitments Identified in Ler,Listed | Forwards LER 99-002-00 Re TS 4.0.5 Requirements Not Being Met Due to Improperly Performed Test.Commitments Identified in Ler,Listed | | | 05000315/LER-1999-003, :on 990107,CR Pressurization Sys Surveillance Test Did Not Test Sys in Normal Operating Condition.Caused by Failure to Recognize Door 12DR-AUX415 as Part of CR Pressure Boundary.Performed Walkdown of Other Doors |
- on 990107,CR Pressurization Sys Surveillance Test Did Not Test Sys in Normal Operating Condition.Caused by Failure to Recognize Door 12DR-AUX415 as Part of CR Pressure Boundary.Performed Walkdown of Other Doors
| 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)(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) | | 05000315/LER-1999-004-01, Forwards LER 99-004-01 Re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitments Made by Util Are Listed | Forwards LER 99-004-01 Re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitments Made by Util Are Listed | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000315/LER-1999-004, :on 971030,failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed Was Noted.Caused by Ineffective Mgt of Tss.Chemistry Personnel Have Been Instructed on Requirement to Follow TS as Written |
- on 971030,failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed Was Noted.Caused by Ineffective Mgt of Tss.Chemistry Personnel Have Been Instructed on Requirement to Follow TS as Written
| 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) | | 05000315/LER-1999-005, :on 940512,determined That RT Breaker Manual Actuations During Rod Drop Testing Were Not Previously Reported.Caused by Lack of Training.Addl Corrective Actions,Including Preventative Actions May Be Developed |
- on 940512,determined That RT Breaker Manual Actuations During Rod Drop Testing Were Not Previously Reported.Caused by Lack of Training.Addl Corrective Actions,Including Preventative Actions May Be Developed
| 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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) | | 05000315/LER-1999-006, :on 990115,personnel Identified Discrepancy Between TS 3.9.7 Impact Energy Limit & Procedure 12 Ohp 4030.STP.046.Caused by Lack of Design Basis Control.Placed Procedure 12 Ohp 4030.STP.046 on Administrative Hold |
- on 990115,personnel Identified Discrepancy Between TS 3.9.7 Impact Energy Limit & Procedure 12 Ohp 4030.STP.046.Caused by Lack of Design Basis Control.Placed Procedure 12 Ohp 4030.STP.046 on Administrative Hold
| 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 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) | | 05000315/LER-1999-007, :on 981020,calculations Showed That Divider Barrier Between Upper & Lower Containment Vols Were Overstressed.Engineers Are Currently Working on Analyses of Loads & Stress on Enclosures |
- on 981020,calculations Showed That Divider Barrier Between Upper & Lower Containment Vols Were Overstressed.Engineers Are Currently Working on Analyses of Loads & Stress on Enclosures
| 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) | | 05000315/LER-1999-008, :on 990115,plant Operators Reported Excessive Piping Vibration in RHR Rooms.Cause Unknown.Update to LER Will Be Submitted |
- on 990115,plant Operators Reported Excessive Piping Vibration in RHR Rooms.Cause Unknown.Update to LER Will Be Submitted
| 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) | | 05000315/LER-1999-009, :on 990304,as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit Occurred.Cause Investigation for Condition Has Not Been Completed.Update to LER Will Be Submitted,Upon Completion of Investigation |
- on 990304,as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit Occurred.Cause Investigation for Condition Has Not Been Completed.Update to LER Will Be Submitted,Upon Completion of Investigation
| 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) | | 05000315/LER-1999-010, :on 990401,RCS Leak Detection Sys Sensitivity Not in Accordance with Design Requirements Occurred.Caused by Inadequate Original Design of Containment Sump Level. Evaluation Will Be Performed to Clearly Define Design |
- on 990401,RCS Leak Detection Sys Sensitivity Not in Accordance with Design Requirements Occurred.Caused by Inadequate Original Design of Containment Sump Level. Evaluation Will Be Performed to Clearly Define Design
| 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 | | 05000315/LER-1999-011, :on 990407,air Sys for EDG Will Not Support Long Operability.Caused by Original Design Error.Temporary Mod to Supply Makeup Air Capability in Modes 5 & 6 Was Prepared |
- on 990407,air Sys for EDG Will Not Support Long Operability.Caused by Original Design Error.Temporary Mod to Supply Makeup Air Capability in Modes 5 & 6 Was Prepared
| 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) | | 05000315/LER-1999-012, :on 990420,concluded That Auxiliary Bldg ESF Ventilation Sys Not Capable of Maintaining ESF Room Temps post-accident.Caused by Inadequate Control of Sys Design Inputs.Comprehensive Action Plan Being Developed |
- on 990420,concluded That Auxiliary Bldg ESF Ventilation Sys Not Capable of Maintaining ESF Room Temps post-accident.Caused by Inadequate Control of Sys Design Inputs.Comprehensive Action Plan Being Developed
| 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 50.73(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) | | 05000315/LER-1999-012-01, Re Auxiliary Building ESF Ventilation System May Not Be Capable of Maintaining ESF Room Temperature Post-Accident | Re Auxiliary Building ESF Ventilation System May Not Be Capable of Maintaining ESF Room Temperature Post-Accident | | | 05000315/LER-1999-013, :on 990327,safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Have Led to ECCS Pump Failure.Caused by Inadequate Original Design Application of Si.Throttle Valves Will Be Developed |
- on 990327,safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Have Led to ECCS Pump Failure.Caused by Inadequate Original Design Application of Si.Throttle Valves Will Be Developed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(6) | | 05000315/LER-1999-014, :on 990521,determined That Boron Injection Tank Manway Bolts Were Not Included in ISI Program,Creating Missed Exam for Previous ISI Interval.Caused by Programmatic Weakness.Isi Program & Associated ISI Database Modified |
- on 990521,determined That Boron Injection Tank Manway Bolts Were Not Included in ISI Program,Creating Missed Exam for Previous ISI Interval.Caused by Programmatic Weakness.Isi Program & Associated ISI Database 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)(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) | | 05000315/LER-1999-015, :on 990408,RM Sys Was Not Tested IAW TS Srs. Caused by Inadequate Implementation of TS SRs in Plant Surveillance Procedures.Channel Functional Testing of RM Sys Unit Vent Effluent RMs Was Successfully Completed |
- on 990408,RM Sys Was Not Tested IAW TS Srs. Caused by Inadequate Implementation of TS SRs in Plant Surveillance Procedures.Channel Functional Testing of RM Sys Unit Vent Effluent RMs Was Successfully Completed
| 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) | | 05000315/LER-1999-016, :on 990615,TS Requirements for Source Range Neutron Flux Monitors Not Met.Caused by Failure to Understand Design Basis of Plant.Procedures Revised.With |
- on 990615,TS Requirements for Source Range Neutron Flux Monitors Not Met.Caused by Failure to Understand Design Basis of Plant.Procedures Revised.With
| 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)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000315/LER-1999-017, :on 990625,noted That Improperly Installed Fuel Oil Return Relief Valve Rendered EDG Inoperable.Caused by Personnel Error.Fuel Oil Return Valve Was Replaced with Valve in Correct Orientation.With |
- on 990625,noted That Improperly Installed Fuel Oil Return Relief Valve Rendered EDG Inoperable.Caused by Personnel Error.Fuel Oil Return Valve Was Replaced with Valve in Correct Orientation.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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000315/LER-1999-018, :on 990629,determined That Valve Yokes May Yield Under Combined Stress of Seismic Event & Static,Valve Closed,Stem Thrust.Caused by Inadequate Design of Associated Movs.Operability Determinations Were Performed for Valves |
- on 990629,determined That Valve Yokes May Yield Under Combined Stress of Seismic Event & Static,Valve Closed,Stem Thrust.Caused by Inadequate Design of Associated Movs.Operability Determinations Were Performed for Valves
| 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) | | 05000315/LER-1999-019, :on 990716,noted Victoreen Containment Hrrms Not Environmentally Qualified to Withstand post-LOCA Conditions.Caused by Inadequate Design Control.Reviewing Options to Support Hrrms Operability in Modes 1-4 |
- on 990716,noted Victoreen Containment Hrrms Not Environmentally Qualified to Withstand post-LOCA Conditions.Caused by Inadequate Design Control.Reviewing Options to Support Hrrms Operability in Modes 1-4
| 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)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) | | 05000315/LER-1999-020, :on 990727,EDGs Were Declared Inoperable.Caused by Inadequate Protection of Air Intake,Exhaust & Room Ventilation Structures from Tornado Missile Hazards. Implemented Compensatory Measures in Form of ACs |
- on 990727,EDGs Were Declared Inoperable.Caused by Inadequate Protection of Air Intake,Exhaust & Room Ventilation Structures from Tornado Missile Hazards. Implemented Compensatory Measures in Form of ACs
| 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)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000315/LER-1999-021, :on 990728,determined That GL 96-01 Test Requirements Were Not Met in Surveillance Tests.Caused by Failure to Understand Full Extent of GL Requirements. Surveillance Procedures Will Be Revised or Developed |
- on 990728,determined That GL 96-01 Test Requirements Were Not Met in Surveillance Tests.Caused by Failure to Understand Full Extent of GL Requirements. Surveillance Procedures Will Be Revised or Developed
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000315/LER-1999-022, :on 990609,electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads,Was Discovered. Caused by Lack of Understanding of Design of Plant.No Immediate Corrective Actions Necessary |
- on 990609,electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads,Was Discovered. Caused by Lack of Understanding of Design of Plant.No Immediate Corrective Actions Necessary
| 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) | | 05000315/LER-1999-023, :on 990907,inadequate TS Surveillance Testing of ESW Pump ESF Response Time Noted.Caused by Inadequate Understanding of Plant Design Basis.Surveillance Tests Will Be Revised & Implemented |
- on 990907,inadequate TS Surveillance Testing of ESW Pump ESF Response Time Noted.Caused by Inadequate Understanding of Plant Design Basis.Surveillance Tests Will Be Revised & 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)(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) | | 05000315/LER-1999-024, :on 990708,literal TS Requirements Were Not Met by Accumlator Valve Surveillance.Caused by Misjudgement Made in Conversion from Initial DC Cook TS to W Std Ts.Submitted License Amend Request.With |
- on 990708,literal TS Requirements Were Not Met by Accumlator Valve Surveillance.Caused by Misjudgement Made in Conversion from Initial DC Cook TS to W Std Ts.Submitted License Amend Request.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) 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) | | 05000315/LER-1999-027, LER 315/99-027-00, Underrated Fuses Used in 250 Vdc System Could Result in Lack of Protective Coordination | LER 315/99-027-00, Underrated Fuses Used in 250 Vdc System Could Result in Lack of Protective Coordination | 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) |
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