:on 980114,loss of Security Computers Was Noted.Caused by Equipment Failure.Rebooting of Primary or Backup Servers Will Be Manually Monitored to Prevent Failure| ML20202F455 |
| Person / Time |
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| Site: |
San Onofre  |
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| Issue date: |
02/12/1998 |
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| From: |
Krieger R SOUTHERN CALIFORNIA EDISON CO. |
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| To: |
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| Shared Package |
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| ML20202F266 |
List: |
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| References |
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| LER-98-001, LER-98-1, NUDOCS 9802190203 |
| Download: ML20202F455 (3) |
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text
.
e LICENSEE EVENT REPORT (LER)
Fro 111ty Name (1)
Docket Number (2)
Page (3) san onofre Nuclear Generating station Unit 1 0l5l0l0l0l2l0l6 1ldl0l3 Title (4)
Ioss of n=r
- tv ocuiEmators uvner tsas (5) im NinaEst (6) l suscstr tare (7)
I oneR ysctLrrIEs INuttuno (e) acust Imr YEnk team aEG MerIAL IsVISIM M3RN thy YEML FACILITY NAMES DOCKET NUMBER (S)
Unit 2 0
5 0
0 0
3 6
1 0l1 1l 4 9l 8 9l8 010l1 0 l0 0l2 1l 2 9l 8 Unit 3-0 5
0 0
0 3
6 2
OPERATING THIS REPoPT IS SUBNITTED PURSUANT To THE REQUIREMENTS oF toCFR St WODE (9)
(CHECK oNE o0L HORE ol' TRE FoLLottly.0) (11)
_PoNER_IAVEL,J1od o l o l o
- 20. 402 (b)
_ 20.405 tc)
_ 50.73 (a) (2) (iv)
_ 73.71 (b)
_ 20. 405 (a) (1) (1)
_ 50. 36 (c) (1)
_ 50.73 (a) (2) (v)
_ 73.71(c)
- 20. 405 (a) (1) (11) _ 80.36(c) (2)
_ 50.73 (a) (2) (vii) 1 other (specify in
_ 20. 405 (a) (1) (iii) _ 50.73 (a) (2) (1)
_ 50.73(a) (2) (viii) (A) abstract below
_ 20.405 (a) (1) (iv) _ 50.73 (a) (2) (11)
_ 50.73(a) (2) (viii) (a) and in test)
_ 20.405 (a) (1) (v)
_ 50.73 (a) (2) (iii) _ 50.73 (a) (2) (a) 73.71 (d)
LICENSEE CONTACT FoR THIS LER (12)
NAME TELEPHONE NUMBER AnEA cooE A_.MuErieger, Vice._Presidentu Huclear_ Generation 7l1 l4 3l6le el2l5l5 CoHPLETE oNE LINE FoR RACH COMPONENT FAILURE DESCRIBED IN THIS REPo8tT (13) chuBE SYSTM 03MFCEEENT ENLWAc-REpcatrAmtA ChDER SYrrW otteCREENT E NUFAc-REPCstrASEA TtatER To N5ODS
'ItstER To NPIDS I
SUPPLEMENTAL REPORT EXPECTED (14)
EXPECTED WoNTH DAY YEAR SUBWIS81oM l Yee (If yes, coegdete EXPECTE) SLEEGSSICel DhTE) lXlNo DATE (15) l l
l ABST; Act (Limit to 140o spaces, i.e.,
approximately fifteen single space typewritten lines.)
(16) on January 14, 1998 (discovery date), Southern California Edison (SCE). prepared to install a chart recorder on the primary security comouter for system diagnostic testing. At about 9:25 a.m.,
1efore starting the installation, SCE had t'
conservatively posted compensatory guards for the appropriate plant areas, as specified in Station Procedures SO123-IV-6.8, " Protected Area and Vital Area Barrier Patrols," for a complete loss of security computers.- SCE switched to the backup security computer, removed the primary computer from service and installed the chart recorder. When returning the primary computer to service, a computer network server software error occurred, causing the prirary computer to initialize incorrectly. At about 10:26 a.m.,
the backup computer also failed as a result of this error.
The primary and backup computers were restarted at about 10:32 a.m. and 10:36 a.m.,
respectively.
The cause of this event was an equipment failure.
During the reboot of the primary computer, the network server function for the security computers did not start.
.However, the "be,ot" sequence continued, until the main sect.rity program started on l
the primary computer. Without the network server function, the two computers could not completely communicate and consequently, could not fully function.
The main security program was not capable of recognizing that the network server function had not started and tried to regain the primary role in the security monitoring system.
As a result, a conflict arose and the backup program became unstable and failed to function.
Since the primary had no network server function, it could not communicate properly, leaving both primary and backup down.
SCE is evaluating modifications to the program software to eliminate this problem.
In the interim, any required rebooting of the primary or backup servers will be manually monitored to prevent this type failure.
9802190203 980212 PDR ADOCK 05000206 S
PDR
e LICENSEE EVENT REPORT (LER) TEXT CONTINUATION SAN ONOFRE NUCLEAR GENERATION STATION DOCKET NUMBER LER NUMBER PAGE UNIT 1 05000206 1-98-001 2 of 3 Plant San Onofre Nuclear Generating Station (SONGS) Unit 2 and 3 Reactor Vendor:
Combustion Engineering
(
Event Date:
January 14, 1998
)
Event Times 10:26 Modes Unit 1 - Permanently shutdown
{
Unit 2 - Mode 1 - Power Optration j
Unit 3 - Mode 1 - Power Operation Power Units 2 and 0 - approximately 100 percent l
Background:
In LER 1-97-003, Southern California Edison (SCE) reported four instances in 1997 where the primary and backup security computers were out of service as follows:
May 20 (23 minutes), July 29 (21 ndnutes), October 30 (93 minutes), and December 19 (20 ndnutes). As stated in LER 1-97-003, SCE is completing an engineering review of the computer systems to determine required corrective actions to improve system l
reliability.
Description of Events i
j On January 14, 1998 (discovery date), SCE prepared to install a chart recorder on the primary security computer [IA] for system diagnostic testing. At about 9:25 a.m., before starting the installation, SCE had conservatively posted compensatory guards for the appropriate plant areas, as specified in Station Procedures SO123-IV-6.8, " Protected Area and Vital Area Barrier Patrols," for a complete loss of security computers.
SCE switched to the backup security computer, removed the rrimary computer from service and installed the chart recorder. When returning tbs primary computer to service, a computer network server software error occurred, causing the primary computer to initialize incorrect 3v.
At about 10:26 a.m.,
the backup computer also failed as a result of this error.
The primary and backup computers were restarted at about 10:32 a.m.
(six minutes later) and 10:36 a.m.
(ten minutes later), respectively.
During an NRC Security Inspection Exit interview on November 21, 1997, the NRC indicated that establishing compensatory measures within ten minutes would not be sufficient to preclude reporting a complete loss of security computers to the NRC within one hour.
Consequently, to address the NRC's concerns, SCE revised procedure SO123-IV-11.2, " Reporting Safeguards Events," to require a report to be made within one hour, even when compensatory measures are taken within ten minutes.
Therefore, a 1-hour report was conservatively made to the NRC on January 14, 1998, even though, as a precaution, prestaged compensatory measures were in place prior to the security computer system failure.
Subsequently, SCE is providing this 30 day follow-up report as required by 10 CFR 73.71(d).
Cause of the Event
The cause of this event was an equipment failure.
During the reboot of the primary computer, the network server function for the security computers did not start.
However, the " boot" sequence continued, until the main security program started on the primary computer. Without the network server function, the two computers could not completely communicate and consequently, could not fully function.
The main security program was not capable of recognizing that the network server function had not started and tried to regain the primary role in the security monitoring system.
As a result, a conflict arose and the backup program became unstable and failed to function.
Since the primary had no network server function, it could not communicate properly, leaving both primary and backup down.
.3 LICEHOEE EVENT REPORT -(LER). TEXT CONTINUATION
.. SAN ONOFRE NUCLEAR GENERATION STATION DOCKET NUMBER LER NUMBER.
PAGE UN27 1 05000206 1-98-001 3 of 3 l
- - Corrective Actions:
1 SCE is evaluating modifications to the program software to eliminate this problem.
In the interim, any required rebooting of the primary or backup servers will be
. manually _ monitored to prevent this type failure.
4 i
safety significaneet-During the time the computers were off-line, there was no reduction in detection capabilities as compensatory measures (security posts) were already in place.- As such,'there was no safet,v significance to this event.
' Additional Infosaation:
SCE reported similar. instances in LER 1-97-003.
The event reported ~herein occurred during diagnostle testing to correct the events reported in LER l-97-003, and consequently, could not have been prevented.
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| 05000206/LER-1998-001, :on 980114,loss of Security Computers Was Noted.Caused by Equipment Failure.Rebooting of Primary or Backup Servers Will Be Manually Monitored to Prevent Failure |
- on 980114,loss of Security Computers Was Noted.Caused by Equipment Failure.Rebooting of Primary or Backup Servers Will Be Manually Monitored to Prevent Failure
| 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)(iii) 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(1) | | 05000361/LER-1998-001, :on 980113,loose Collar Was Noted on Turbine Driven AFW Speed Circuit.Caused by Collar Not Properly Being Tightened at Last Documented Reassembly in 1993.Collar & Plug Were Reassembled |
- on 980113,loose Collar Was Noted on Turbine Driven AFW Speed Circuit.Caused by Collar Not Properly Being Tightened at Last Documented Reassembly in 1993.Collar & Plug Were Reassembled
| 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) | | 05000206/LER-1998-002-01, :on 980219,diesel Fuel Filtration Unit Access Was Not Controlled as Vital Area.Caused by Inadequate Training.Security Personnel Will Be Trained on Concept of Vital Matls |
- on 980219,diesel Fuel Filtration Unit Access Was Not Controlled as Vital Area.Caused by Inadequate Training.Security Personnel Will Be Trained on Concept of Vital Matls
| | | 05000361/LER-1998-002, :on 980126,reactor Coolant Sys Boundary Leakage Occurred.Caused by Cracking of Inconel 600 Nozzle.Four Nozzles (2TW0139B,2TE0122-4,2PDT0978-1 & 2PDT0978-2) Were Repaired |
- on 980126,reactor Coolant Sys Boundary Leakage Occurred.Caused by Cracking of Inconel 600 Nozzle.Four Nozzles (2TW0139B,2TE0122-4,2PDT0978-1 & 2PDT0978-2) Were Repaired
| 10 CFR 50.73(a)(2)(1) | | 05000206/LER-1998-003-01, :on 980316,unauthorized Protected Entry Area Entry,Was Determined.Caused by Data Entry Error.Appropriate Collection Site Personnel Were Coached.Computer Data Base Modified |
- on 980316,unauthorized Protected Entry Area Entry,Was Determined.Caused by Data Entry Error.Appropriate Collection Site Personnel Were Coached.Computer Data Base Modified
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(1) | | 05000206/LER-1998-003, Forwards LER 98-003-00,involving Unauthorized Access to Protected Area | Forwards LER 98-003-00,involving Unauthorized Access to Protected Area | | | 05000361/LER-1998-003, LOCA Evaluation of Safety Significance of Failure of Emergency Sump Valve Linestarter (LER 1998-003) | LOCA Evaluation of Safety Significance of Failure of Emergency Sump Valve Linestarter (LER 1998-003) | | | 05000206/LER-1998-004-01, Forwards LER 98-004-01,re Safeguard Drawings That Were Incorrectly Decontrolled,Iaw NUREG-1022,rev 1.No New Commitments Made within LER | Forwards LER 98-004-01,re Safeguard Drawings That Were Incorrectly Decontrolled,Iaw NUREG-1022,rev 1.No New Commitments Made within LER | | | 05000206/LER-1998-004, :on 980323,safeguards Drawing Was Inappropriately Decontrolled.Caused by Personnel Error. Revised Procedure for Decontrolling SI & Has Established New Detailed Process for SCE to More Effectively Control SI |
- on 980323,safeguards Drawing Was Inappropriately Decontrolled.Caused by Personnel Error. Revised Procedure for Decontrolling SI & Has Established New Detailed Process for SCE to More Effectively Control SI
| 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2)(1) | | 05000361/LER-1998-004-01, :on 980211,diesel Fuel Oil Particulates - ASTM Test Methods Yield Varying Results Were Received.Caused by Unexpected Variations Obtained from Different Test Methods. Fuel Oil Filtered & Confirmed by Reanalysis |
- on 980211,diesel Fuel Oil Particulates - ASTM Test Methods Yield Varying Results Were Received.Caused by Unexpected Variations Obtained from Different Test Methods. Fuel Oil Filtered & Confirmed by Reanalysis
| 10 CFR 50.73(a)(2)(1) | | 05000361/LER-1998-004, :on 980211,DG Fuel Oil Analysis Results Indicated Total Particulate Concentration Was Above TS Limit.Caused by Personnel Errors.Personnel Were Reprimanded & Fuel Oil Was Filtered to Return It to within TS Limits |
- on 980211,DG Fuel Oil Analysis Results Indicated Total Particulate Concentration Was Above TS Limit.Caused by Personnel Errors.Personnel Were Reprimanded & Fuel Oil Was Filtered to Return It to within TS Limits
| 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) | | 05000361/LER-1998-005, :on 980305,inadequate Voltage to 120 Vac Circuits Due to Calculation Error Occurred.Caused by Personnel Error.Sys Mods Made to Affected Sys to Correct Deficiencies |
- on 980305,inadequate Voltage to 120 Vac Circuits Due to Calculation Error Occurred.Caused by Personnel Error.Sys Mods Made to Affected Sys to Correct Deficiencies
| 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) | | 05000206/LER-1998-005, Forwards LER 98-005-00 Re Verbatim Compliance with TS Surveillances on Flow Indictors.Single Rept for Unit 1 Is Being Submitted IAW NUREG-1022,Rev 1,although Occurrence Is Applicable to All Three Units | Forwards LER 98-005-00 Re Verbatim Compliance with TS Surveillances on Flow Indictors.Single Rept for Unit 1 Is Being Submitted IAW NUREG-1022,Rev 1,although Occurrence Is Applicable to All Three Units | | | 05000206/LER-1998-005-01, :on 981124,noted That Radiological Effluent TS Flow Indicator Surveillance Had Not Been Performed.Caused by Misinterpretation of Wording.Licensee Will Review Issue & Revise ODCM Accordingly |
- on 981124,noted That Radiological Effluent TS Flow Indicator Surveillance Had Not Been Performed.Caused by Misinterpretation of Wording.Licensee Will Review Issue & Revise ODCM Accordingly
| 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) | | 05000361/LER-1998-006, :on 980421,missed TS Surveillance Due to Initial Procedural Error.Caused by Personnel Error.Revised Affected Procedures |
- on 980421,missed TS Surveillance Due to Initial Procedural Error.Caused by Personnel Error.Revised Affected Procedures
| 10 CFR 50.73(a)(2)(1) | | 05000206/LER-1998-006-01, :on 981207,unattended Security Weapon Was Noted Inside Pa.Cause of Event Is Under Investigation.Officer Was Relieved of All Duties,Removed PA Access & Was Placed on Investigatory Suspension |
- on 981207,unattended Security Weapon Was Noted Inside Pa.Cause of Event Is Under Investigation.Officer Was Relieved of All Duties,Removed PA Access & Was Placed on Investigatory Suspension
| 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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) | | 05000206/LER-1998-006, Forwards LER 98-006-00 Re Occurrence Involving Unattended Security Weapon Inside Pa.Any Actions Listed Are Intended to Ensure Continued Compliance with Any Existing Comments. Single Rept for Unit 1 Is Submitted IAW NUREG-1022,r | Forwards LER 98-006-00 Re Occurrence Involving Unattended Security Weapon Inside Pa.Any Actions Listed Are Intended to Ensure Continued Compliance with Any Existing Comments. Single Rept for Unit 1 Is Submitted IAW NUREG-1022,rev 1 | | | 05000361/LER-1998-006-01, Forwards LER 98-006-01,re Event Involving Missed TS Surveillance.Sce Is Submitting Revised TS to Provide Addl Info Re Missed TS | Forwards LER 98-006-01,re Event Involving Missed TS Surveillance.Sce Is Submitting Revised TS to Provide Addl Info Re Missed TS | | | 05000361/LER-1998-007, :on 980317,discovered Matl in Containment That Could Become Debris in Emergency Sumps.Caused by Ineffective Program Mgt.Removed Identified Matl & Will Issue Memo to Personnel Emphasizing Containment Cleanliness Maint |
- on 980317,discovered Matl in Containment That Could Become Debris in Emergency Sumps.Caused by Ineffective Program Mgt.Removed Identified Matl & Will Issue Memo to Personnel Emphasizing Containment Cleanliness Maint
| | | 05000361/LER-1998-008, :on 980306,4160 Vac Supply Cable Exceeded Ampacity Rating.Caused by Error in Feeder Cable Sizing Calculation Completed by Plant Architect/Engineer. Administrative Restrictions Imposed |
- on 980306,4160 Vac Supply Cable Exceeded Ampacity Rating.Caused by Error in Feeder Cable Sizing Calculation Completed by Plant Architect/Engineer. Administrative Restrictions Imposed
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) | | 05000361/LER-1998-009, :on 980429,discovered That CST Was Outside Design Basis Due to Procedure Error.Caused by Individual Error.Replaced Steps That Had Been Inadvertently Deleted from Aoi |
- on 980429,discovered That CST Was Outside Design Basis Due to Procedure Error.Caused by Individual Error.Replaced Steps That Had Been Inadvertently Deleted from Aoi
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) | | 05000361/LER-1998-010, :on 980526,post Accident Cleanup Unit Declared Operable.Util Did Not Determine Cause of Initial Error in Surveillance Test.Surveillance Procedures Revised |
- on 980526,post Accident Cleanup Unit Declared Operable.Util Did Not Determine Cause of Initial Error in Surveillance Test.Surveillance Procedures Revised
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2)(1) | | 05000361/LER-1998-010-01, Forwards LER 98-010-01 for Fuel Handling Bldg post-accident Cleanup Unit Being Inoperable Because of Flow Calibr Error. Health & Safety of Neither Public Nor Plant Personnel Affected by Occurrence | Forwards LER 98-010-01 for Fuel Handling Bldg post-accident Cleanup Unit Being Inoperable Because of Flow Calibr Error. Health & Safety of Neither Public Nor Plant Personnel Affected by Occurrence | | | 05000361/LER-1998-011-01, Forwards LER 98-011-01,re Inadequate Surveillance Test of Logarithmic Power Trip Bypass Removal Function.No New Commitments Are Made by Util | Forwards LER 98-011-01,re Inadequate Surveillance Test of Logarithmic Power Trip Bypass Removal Function.No New Commitments Are Made by Util | | | 05000361/LER-1998-011, :on 980617,determined That Setpoints for High Log Power Bypass Automatic Removal Had Not Been Verified IAW Ts.Caused by Log Power Not Satisfying TS as Written.Utils Investigation If Ongoing & LER Will Be Revised by 980930 |
- on 980617,determined That Setpoints for High Log Power Bypass Automatic Removal Had Not Been Verified IAW Ts.Caused by Log Power Not Satisfying TS as Written.Utils Investigation If Ongoing & LER Will Be Revised by 980930
| | | 05000362/LER-1998-012-01, Forwards LER 98-012-01 Re Occurrence Involving CCS RPV Being Set Above Required Relief Setpoint.Any Actions Listed Are Intended to Ensure Continued Compliance with Existing Commitments as Discussed in Applicable Licensing Do | Forwards LER 98-012-01 Re Occurrence Involving CCS RPV Being Set Above Required Relief Setpoint.Any Actions Listed Are Intended to Ensure Continued Compliance with Existing Commitments as Discussed in Applicable Licensing Documents | | | 05000362/LER-1998-012, :on 870302,noted That CCW Relief Valve Was Inoperable.Caused by Wrong Set Spring Being Installed Due to Vendor Data Error.Spring Was Replaced & Tested & Subsequently Personnel Set Lift Pressure at 150 Psig |
- on 870302,noted That CCW Relief Valve Was Inoperable.Caused by Wrong Set Spring Being Installed Due to Vendor Data Error.Spring Was Replaced & Tested & Subsequently Personnel Set Lift Pressure at 150 Psig
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) | | 05000361/LER-1998-012, :on 870302,potential for over-pressurization of Train & CCW Sys Due to Wrong Spring Installed on Relief Valve May Have Placed Plant Outside Design Basis. Investigation Is Ongoing.Ccw Sys Valves Were Tested |
- on 870302,potential for over-pressurization of Train & CCW Sys Due to Wrong Spring Installed on Relief Valve May Have Placed Plant Outside Design Basis. Investigation Is Ongoing.Ccw Sys Valves Were Tested
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) | | 05000361/LER-1998-013, :on 980708,control Room post-LOCA Dose Was Noted Outside Design Basis.Caused by Inadequate Original Calculations & Leakage Terms.Ler Will Be Revised When Calculations Complete |
- on 980708,control Room post-LOCA Dose Was Noted Outside Design Basis.Caused by Inadequate Original Calculations & Leakage Terms.Ler Will Be Revised When Calculations Complete
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) | | 05000361/LER-1998-013-01, Forwards LER 98-013-01,re Post LOCA CR Dose Being Outside Design Basis.Single Rept Is Being Submitted Because Condition Involves Similar Sys,Causes,C/As Applicable to Both Units 2 & 3 IAW NUREG-1022 | Forwards LER 98-013-01,re Post LOCA CR Dose Being Outside Design Basis.Single Rept Is Being Submitted Because Condition Involves Similar Sys,Causes,C/As Applicable to Both Units 2 & 3 IAW NUREG-1022 | | | 05000361/LER-1998-014, :on 980818,EFAS Outside Design Basis Occurred. Util Did Not Determine Cause,Due to Passage of Time.Other Vital Bus Failures Being Reviewed for Similar & Other Scenarios |
- on 980818,EFAS Outside Design Basis Occurred. Util Did Not Determine Cause,Due to Passage of Time.Other Vital Bus Failures Being Reviewed for Similar & Other Scenarios
| 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) 10 CFR 50.73(a)(2)(1) | | 05000361/LER-1998-015-01, Forwards LER 98-015-01 Re Event Involving Requirement to Obtain Isokinetic Samples of Airborne Radioactive Effluent Streams.Single Rept for Unit 2 Is Being Submitted,Per NUREG- 1022,Rev 1,although Occurrence Is Applicable to | Forwards LER 98-015-01 Re Event Involving Requirement to Obtain Isokinetic Samples of Airborne Radioactive Effluent Streams.Single Rept for Unit 2 Is Being Submitted,Per NUREG- 1022,Rev 1,although Occurrence Is Applicable to Both Units | | | 05000361/LER-1998-015, :on 980717,non-isokinetic Sampling of Airborne Effluent Streams Occurred.Caused by Personnel Error. Procedures Revised |
- on 980717,non-isokinetic Sampling of Airborne Effluent Streams Occurred.Caused by Personnel Error. Procedures Revised
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | | 05000361/LER-1998-016, :on 980710,EDG Fuel Storage Tank Volume Was Noted Outside of Design Basis.Cause Has Not Been Determined Because of Passage of Time.Revised Alarm Response Procedure |
- on 980710,EDG Fuel Storage Tank Volume Was Noted Outside of Design Basis.Cause Has Not Been Determined Because of Passage of Time.Revised Alarm Response Procedure
| 10 CFR 50.73(e)(2) | | 05000361/LER-1998-017, :on 980828,manual Tgis Actuation Occurred. Caused by Leaking Line from Sulfuric Acid Storage Tank 2T194.Immediate Area Was Evacuated & Barricaded with Flagging & Postings & Affected Area of Tank 2T194 Repaired |
- on 980828,manual Tgis Actuation Occurred. Caused by Leaking Line from Sulfuric Acid Storage Tank 2T194.Immediate Area Was Evacuated & Barricaded with Flagging & Postings & Affected Area of Tank 2T194 Repaired
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) 10 CFR 50.73(n)(2) | | 05000361/LER-1998-018, :on 980909,ECCS Was Inoperable Due to Inadequate Surveillance Test.Cause Was Not Determined Due to Length of Time.Ts SR 3.0.3,required Surveillance Tests Were Successfully Completed |
- on 980909,ECCS Was Inoperable Due to Inadequate Surveillance Test.Cause Was Not Determined Due to Length of Time.Ts SR 3.0.3,required Surveillance Tests Were Successfully Completed
| 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) 10 CFR 50.73(a)(2)(1) | | 05000361/LER-1998-019, :on 980911,oxygen Monitor Setpoint Exceeded TS Limits.Cause Unknown Due to Passage of Time.Wghs Oxygen Concentration Instrument Setpoints Were Lowered to Incorporate Calculated Tlu |
- on 980911,oxygen Monitor Setpoint Exceeded TS Limits.Cause Unknown Due to Passage of Time.Wghs Oxygen Concentration Instrument Setpoints Were Lowered to Incorporate Calculated Tlu
| 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) | | 05000361/LER-1998-020, :on 980806,determined That Ecw Sys Was Inoperable.Caused by Faulty Temp Control Unit.Temp Control Unit Was Replaced & Chiller Performed Satisfactorily |
- on 980806,determined That Ecw Sys Was Inoperable.Caused by Faulty Temp Control Unit.Temp Control Unit Was Replaced & Chiller Performed Satisfactorily
| 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) 10 CFR 50.73(a)(2)(1) | | 05000361/LER-1998-021, :on 980903,train B Ecw Chiller Failed to Start Using CR Start Push Button.Caused by Incorrect Wiring of Switch by Personnel.Wiring Was Corrected & Chiller Was Declared Operable on 980926 |
- on 980903,train B Ecw Chiller Failed to Start Using CR Start Push Button.Caused by Incorrect Wiring of Switch by Personnel.Wiring Was Corrected & Chiller Was Declared Operable on 980926
| 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) | | 05000361/LER-1998-022, :on 981014,shutdown Cooling Sys Was Inoperable Due to Inadequate Surveillance Test.Caused by Failure to Consider Impact of Total Loop Uncertainty.No Corrective Actions Required |
- on 981014,shutdown Cooling Sys Was Inoperable Due to Inadequate Surveillance Test.Caused by Failure to Consider Impact of Total Loop Uncertainty.No Corrective Actions Required
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) | | 05000361/LER-1998-023, :on 981020,missed Surveillance of Fire Detector Circuit Supervision Inside Containment Occurred.Caused by Integration of Repetitive Maint Orders.Licensee Controlled Specifications Revised |
- on 981020,missed Surveillance of Fire Detector Circuit Supervision Inside Containment Occurred.Caused by Integration of Repetitive Maint Orders.Licensee Controlled Specifications Revised
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) | | 05000361/LER-1998-024, :on 981109,inadequate Creacs Boundary Control Was Noted During HVAC Component Maint.Caused Because P&Ids & HVAC Section Drawings Were Not Updated.Initiated Interim Administrative Controls |
- on 981109,inadequate Creacs Boundary Control Was Noted During HVAC Component Maint.Caused Because P&Ids & HVAC Section Drawings Were Not Updated.Initiated Interim Administrative Controls
| 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) | | 05000361/LER-1998-025, Forwards LER 98-025-00,re Occurrence Involving MSSV Setpoints.Actions Listed Are Intended to Ensure Continued Compliance with Existing Commitments.No New Commitments Made | Forwards LER 98-025-00,re Occurrence Involving MSSV Setpoints.Actions Listed Are Intended to Ensure Continued Compliance with Existing Commitments.No New Commitments Made | |
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