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NRC FORM 366 U.s. NUCLEAR REGUL RY COMMISSION (6-19961
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LICENSEE EVENT REPORT (LER)
(See reverse for required number of digits/characters for each block)
APPROVE OMB No. 3150 0104 EXPIRES 06/30/2001 Estimated burden per response to compty with this mendatoly Infoimetion cogecUon requesl: 50 tus.
Reported lessons learned are Incorporated Into the gcenslng process and fed back to Industry. Foweid comments regarding burden estimate to the Records Management Branch (TR F33), U.S, Nudeer Regulatory Commission, Washington, DC 205554001.
end to the Papetwlk ReducUon Project (31500104), Oftice of Management end Budget, Washington, OC 20503, It an hfonnegon cotlecthn does not display a cuirentfy vetkf OMB control number, the NRC mey not conduct or sponsor. end e person Is rot required to respond lo, the hfonneUon coiecUon.
FACILITYNAMEl1)
Cook Nuclear Plant Unit 1 DOCKET NUMBER (21 05000-315 PAGE (3) 1 OF 3
TITLE I4)
Requirements of Technical Specification 4.0.5 Not Met for Boron Injection Tank Bolting EVENT DATE (5)
MONTH OAY YEAR SEQUENTIAL NUMBER REVISION NUMBER LER NUMBER (6)
REPORT DATE (7)
MONTH DAY YEAR FACILITYNAME OTHER FACILITIES INVOLVED(6)
OOCKET NVMBLA OPERATING MODE (9)
POWER LEVEL (10) 1999 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)
THIS REPORT IS SUBMITTED PURSUANT TO THE REQU FAclLITYNAME Cook Nuclear Plant Unit 2 IREMENTS OF 10 CFR E: (Check X
50.73(a)(2)(i) 50.73(a)(2)(ii) 50.73(a)(2)(iii)
DOCKET NUMBER 05000-316 one or moro) (11) 50.73(a) (2) (viii) 50.73(a) (2) (x) 73.71 20.2203(a)(2) (ii) 20.2203(a) I2)(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 pecify ln Abstract below or in NRC Form 366A NAME Mr. Dennis D. Snodgrass, Compliance Engineer TELEPHONE NUMBBA(Include Ares Code)
(616) 465-5901 X1627 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DES CRIBED IN THIS REPORT (13)
CAUSE
SYSTEM COMPONENT MANUFACTURER REPORTABLE To EPIX
CAUSE
SYSTEM COMPONENT MANUFACTURER REPORTABLE To EPIX SUPPLEMENTAL REPORT EXPECTED 14 YES (I( yes. complete EXPECTED SUBMISSION DATE).
X No EXPECTED MONTH DAY YEAR ABSTRACT (Limitto 1400 spaces, i.e., approximately 15 single.spaced typewritten lines) (16)
On May 21, 1999, the Engineering Programs group determined that the Boron Injection Tank (BIT) manway bolts were not included in the ISI Program, creating a missed examination for the previous ISI interval.
The bolts were being reviewed for surveillance requirements for replacement of two bolts that were identiTied with no markings by the System Engineer while performing an Expanded System Readiness Review walkdown.
Pressure retaining bolting greater than 2 inches in diameter are required to be volumetrically examined once each ISI interval per the 1989 ASME XI Code.
The bolting on the Boron Injection Tank manway is 2-1/2 inches in diameter and as such is required to be in the ISI Program.
This is reportable per 10CFR50.73(a)(2)(i)(B) as a condition prohibited by the plant's Technical Specifications (T/S), for the failure to comply with T/S 4.0.5 on the ISI program.
This condition was found to exist on both Units. The apparent cause for this event is programmatic weakness.
The BIT manway bolts were removed from the ISI Program without proper review, approval and documentation.
This occurred in the early 1980's when ISI Program correspondence and documentation was less formal.
No immediate corrective actions were required as the Units are currently in Mode 5 making the BIT and associated piping in the current Mode exempt from examination in accordance with the 1989 ASME Section XI Code.
The BIT manway bolting has been administratively placed in the ISI Program for the third ISI interval, and will be examined prior to Mode 4.
Review of the ISI database did not identify any other Code category C-D bolts that had not been examined during the previous ISI intervals.
Engineering has developed an action plan to review the ISI Program for compliance with applicable regulatory requirements prior to restart.
Based on the System Engineer walkdown identifying no degraded BIT manway bolts and a work history of no bolt failures, it has been determined that'the failure to perform BIT manway bolting examinations for the previous ISI intervals had minimal impact on the safe operation of either Unit.
9906220207 990658 PDR ADOCK 05000315 S
PDRU.S. NUCLEAR REGULATORY COMMISSION (6 1998I ~
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITYNAME (1)
Cook Nuclear Plant Unit 1 DOCKET (2) 05000-315 YEAR LER NUMBER (6)
PAGE (3)
SEOUENTIAL NUMBER REvlsloN 2
QF 3
NUMBER 1999 014 00 TEXT (Ifmore spaceis required, use additional copies of NRC Form 36GA/ (17)
Conditions Prior To Event
Unit 1 Mode 5 in Cold Shutdown Unit 2 Mode 5 in Cold Shutdown Descri tion Of The Event On May 21, 1999, the Engineering Programs group determined that the Boron Injection Tank (BIT) manway bolts were not included in the ISI Program, creating a missed examination for the previous ISI interval. The bolts were being reviewed for surveillance requirements for replacement of two bolts that were identified with no markings by the System Engineer while performing an Expanded System Readiness Review walkdown.
The bolting on the Boron Injection Tank manway is 2-1/2 inches in diameter.
Bolting greater than 2 inches in diameter is required to be volumetrically examined once each ISI interval per the 1989 ASME XI Code, Category C-D, Item no. C4.10, "Class 2 Pressure Vessel Bolting Greater than 2 Inches".
The investigation determined the first ISI interval identified the BIT manway bolts as requiring examination.
The Unit 2 bolts were examined during the first ISI interval, however Unit 1 examination can not be verified. When the ISI Programs were updated for the second interval, the BIT manway bolts were not included in the ISI database and examinations were not performed on either Unit.
Cause Of The Event
The apparent cause for this event is programmatic weakness.
The BIT manway bolting was removed from the ISI Program without proper review, approval and documentation.
This occurred in the early 1980's when ISI Program correspondence and documentation was less formal.
Anal sis Of The Event This LER is submitted in accordance with 10CFR50.73(a)(2)(i)(B),
a condition prohibited by the plant's Technical Specifications, for the failure to comply with T/S 4.0.5 on the ISI program.
Technical Specification 4.0.5 requires inservice inspection of ASME Code Class 1, 2, and 3 components per the 1989 ASME Section XI Code. The Boron Injection Tanks are Class 2 components and examination of the manway bolting is intended to identify degraded bolting conditions before they worsen.
Visual observation of BIT manway bolting during the Expanded System Readiness Review walkdown indicated that there were no degraded bolts.
Review of maintenance records did not identify any problems with, or a failure of these bolts.
Based on these factors, it has been concluded that the failure to perform BIT manway bolting examinations for the previous ISI intervals had minimal impact on the safe operation of either Unit.~
U.S. NUCLEAR REGULATORY COMMISSION (6
1 999)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITYNAME I1)
Cook Nuclear Plant Unit 1 DOCKET I2) 05000-315 YEAR LER NUMBER I6)
SEQUENTIAL REVISION NUMBER NUMBER PAGE I3) 3 OF 3-1999 014 00 TEXT (Ifmore speceis required, use edditionel copies ofNRC Form 386A/ I17)
CORRECTIVE ACTIONS
The Boron Injection Tanks (BIT) bolting has been administratively placed in the ISI database for the third ISI interval.
Examination of the bolts has been scheduled and willbe performed prior to Mode 4.
A review of the ISI database did not identify any other Code Category C-D bolts that had not been examined during the previous ISI intervals.
The drawings for Class 2 bolted components were reviewed to determine if there were any other Category C-D bolting not included in the ISI database.
None were found.
Engineering has developed an action plan to review the ISI Program for compliance with applicable regulatory requirements prior to restart.
The ISI Program and the associated ISI database have been modiTied to include the BIT bolting examination requirement.
A lesson learned will be placed in the program notebook to alert personnel of the previously missed examinations and will ensure ISI Program Coordinators are aware of past problems on this component.
To prevent recurrence, PMI-5070, Inservice Inspection, will be revised to add a note that when the ISI Program or portions of the Program are revised, a review shall be made of the changes in accordance with the requirements of 10 CFR 50.59.
Engineering Programs has performed self-assessments of the ASME Section XI Inservice Inspection Program to review for effective implementation, documentation, organization, and degree of Code compliance.
These self-assessments have resulted in an action plan to review the ISI Program for compliance with all regulatory requirements prior to restart.
SIMILAREVENTS 316/98-041-00 316/98-043-00 315/99-002-00 1
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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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