text
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1 i
2 LICENSEE EVENT REPORT (LER)
Form Rev. 3 0 j
5 Faciljty Name(I)
Docket Number (2)
Page (3)
Quad Cities Unit One 0 l5 l0 l0 l0 l2 l5 l4 I l of l 0 l 4 Title (4)
I j
A visual exammation,(VT 2), was not performed due to procedural deficiencies following a High Pressure Coolant Injection (HFCI) System valve j
replacement, as required by the American Society of Mechanical Engineers (ASME)Section XI and Technical Specification (TS) Section 4.0.E.
Other Facihties involved (8) i Event Date f 5)
LER Number (6)
Re pt Date (7)
Docket Number (s)
)
l Monei Day Year Year sepameel Revmon Moenh Day Year Factiny 0
5 0
0 0
4 Number Number Names 3
u 0
4 2
9 9
7 9
7 0
0 3
0 0
0 5
2 9
9 7
0 5
0 0
0 OPERATING MODE 1105 REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10CFR i
j (9)
(Chad one or more of the following)(Il)
POWER 20 402(b) 20.405(c) 50.73(ay2Xiv) 73.71(b) l LEVEL 20.405(aXIXi) 50.36(cKI) 50.73(aX2Xv) 73.71(c)
X (10) 1 0
0 20 405(aX1Xii) 50.36(cX2) 50.73(aX2 Xvii)
Other (Specify in l
20 405(ayIXiii) 50.73(aX2Xi)
[
50.73(aX2XviiiXA) abstract below and 20.405(aXIXiv) 50.73(aX2Xii) 50.73(aXviiiXB) in text y
M 20.405(aX1Xv) 50.73(aX2yiii) 50.73(aX2Xx)
LICENSEE CONTACT FOR THIS LER (12)
Name TELEPHONE NUMBER h
AREA CODE Charles Peterson, Regulatory Affairs Manager, est. 3609 3 l0 l9 l6 I 5 l4 l-l2 l2 l4 l1 1
COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) i REPORT-REPORT.
CAUSE
SYSTEM cOMPONENr MANLTACRJRER ABLE
CAUSE
SYSTEM cot 4POhnNr MANUFACTURER ABLE TO NPRDS TO NPRDS 4
((
l.
SUPPLEMENTAL REPORT EXPECED (14)
Expected Masah Day Year Submission O YES (If yes, complete EXPECTED SUBMISSION DATE)
E No Date(15)
ABSTRACT (Limit to 1400 spaces, i.e. approximately fifteen single-space typewritten lines) (16)
ABSTRACT:
On 042997 at 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br /> the Station identified a visual exanunation (VT-2) was not performed following a replacement of the 1-2301-45 valve in the High Pressure Coolant injection (HPCI) System. This is contrary to the American Society of Mechanical Engineers (ASME)Section XI 1989 Edmon, Subsection IWA, Paragraph IWA-5214 and Technical Specification (TS) Secten 4.0.E. U-l HPCI was subsequently declared inoperable at 1930 on 050197 following an operability screening of the event.
The root cause of the event is inadequate procedures (QCAP 0307-20, QCAP 2200-04, and QCAP 2200-09), winich failed to provide clear instructions for ensuring ASME Section XI Repair / Replacement (R/R) Program requirements are included in the Work Request packages, and alto entered in the Post Maintenance Testing (PMT) matrix Corrective actions included an immediate VT-2 exammation of the 1-2301-45 valve, a resiew of other R/R programs for similar occurrences, and the planned revision of the administrative procedures responsible for the generation of ASME Section XI R/R Programs, Work Requests and assignment of PMT requirements.
The Safety Analysis concluded that despite the lack of a VT-2 exammation, the health and safety of on-site personnel and the public was not affected. Ahhough certified VT Examination personnel were not present during the initial HPCI Test and the ASME Code required VT-2 examination was not performed, the valve was verified to be leak tight by the HPCI system i
. engineer. The valve would have been able to perform its function in case of an accident and subsaluent HPCI initiation.
9706060056 970529 PDR ADOCK 05000254 S
PDR 1
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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Form Rev. 2.0 FACILITY NAME (1)
DOCKET NUMBER (2)
LER NUMBER (6)
PAGE (3)
Year Sequential Revision Number Number Quad Cities Unit One 0
5 0
0 0
2 5
4 9
7 0
0 3
0 0
2 of 0
4 Text Energy Inoustry Identification system (EIIs) cooes are toentitseo in the text as txx)
]
PLANT AND SYSTEM IDENTIFICATION
General Electric - Boiling Water Reactor - 2511 MWt rated core thermal power.
EVENT IDENTIFICATION: A visual exammation, (VT-2), was not performed due to procedural deficiencies following a High Pressure Coolant Injection (HPCI) System valve replacement, as required by the American Society of Mechanical Engineers ( ASME)Section XI and Technical Specification (TS) Section 4.0.E.
A.
CONDITIONS PRIOR TO EVENT
Unit: 1 Event Date:
42997 Event Tinw I800 Reactor Mode: 1 Mode Name:
Run Power Level:
100 %
This report was initiated by Licensee Event Report 254\\97\\003.
Power Operation - Mode switch in the RUN position with average reactor coolant temperature at any temperature.
B.
DESCRIPTION OF EVENT
On 042697 the Unit i High Pressure Coolant injection System (HPCI)[BJ] Turbine Exhaust Check Valve (1-2301-45) was replaced. Following the valve's replee, a pressure test was required by the Americca -
Society Mechanical Engmeers (ASME)Section XI Code and the requirement was documented on the ASME Repair / Replacement (R/R) Program that was inserted into the work request package. However, the R/R
{
Program did not explicitly state a VT-2 was required although it was implied by the pressure testag requirement. Subsequently, a VT-2 was not added electronically to the Post-Maintenance Testing (PMT)
Matrix. On 042997, following the testmg of Unit 1 HPCI, a station Level Ill VT Exammer inquired if a VT-2 was performed on the HPCI Turbine Exhaust Check Valve (1-2301-45) and discovered that it had not been performed. A Problem Identification Form was then generated and an Operability Screemng was requested to determine the Operability Status of Unit i HPCI. On 050197, the Operability Screemng determmed that Unit 1 i
HPCI was inoperable due to the missed test.
Technical Specification (TS) 4.0.E.1 states: "Insenice Inspection of ASME Code Class 1,2 and 3 components and Insenice Testing (IST) of ASME Code Class 1,2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda LER254 97@03. DOC
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I LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Fonn Res. 2.0
[
4 FACILITY NAME (1)
DOCKET NUMSER (2)
LER NUMBER (6)
PAGE (3)
Year Sequential Revision Number Number i
Quad Cities Unit one 0
5 0
0 0
2 5
4 9
7 0
0 3
0 0
3 of 0
4 4
a Text Energy Inoustry Identitication system (EIIs) codes are toenttried in ene text as (xxj i
i j-C.
CAUSE OF EVENT
he root cause of the event is due to inadequate procedures QCAP 0307-20, "ASME Section XI Repair And l
Replacement Program Preparation", QCAP 2200-04, " Preparation And Control Of Work Packages", and j
QCAP 2200-09, Post Maintenance Testing Guide. These procedures failed to provide clear instruction for ensuring ASME Section XI R/R Program requirements that are included in Work Request packages, are also entered electronically into the Work Request's PMT matrix.
l QCAP 0307-20 Attachment A, "Section XI Repair /Replacenwnt Program" that was generated for the work package did not mark the VT-2 requirement in the Pre-Service exam section, however a Functional pressure 3
test was specified in the pressure testing requirements that implied that VT-2 exam was required. His contradictory information created confusion and contributed to the nussed test.
i i
QCAP 2200-04 and QCAP 2200-09 requires the Work Analyst to include any testmg requirements specified on l
the R/R Program into the PMT matrix in the electronic work package Discussions with the Work Analysts indicated that they may not necessarily see the R/R program especially when the R/R program is generated j
during the course of work. In this case, any testing requirements specified on the R/R program may not be
{
included into the PMT matrix.
j D.
SAFETY ANALYSIS OF EVENT:
i j
ne Safety Analysis of the event was nummal and the health and safety of on-site personnel and the public was
}
not affected. Although certified VT Exammation personnel were not present during the initial HPCI Test and i
the ASME Code required VT-2 exammation was not performed, the valve was veri 6ed to be leak tight by the HPCI system engineer. He valve would have been able to perform its function in case of an accident and subsequent HPCIinitiation.
l i-E.
CORRECTIVE ACTIONS
i CORRECTIVE ACTIONS COMPLETED:
1.
He HPCI system was placed in operation and the valve was exammed by a certified VT-2 examiner on 050197. No leaks were noted by the examiner and the VT exam was acceptable.
j 2.
ASME R/R programs from other work packages were reviewed and no further instances of missed tests were found.
l tIR25497003. doc i
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L LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Fonn Rev. 2.0 FACILITY NAME (1)
DOCKET NUMBER (2)
LER NUMBER (6)
PAGE (3)
Year Sequential Revision Number Number Quad Cities Unit One 0
5 0
0 0
2 5
4 9
7 0
0 3
0 0
4 of 0
4 TEXT Energy Inoustry Ioentification system (EIIs) codes are toentified in tne text as txxl 2
3.
PMT requirements for VT-2 (Pressure Test) have been entered electronically into the PMT matrix by ISI personnel.
CORRECTIVE ACTIONS TO BE COMPLETED:
1.
Procedure QCAP 0307-20,"ASME Section XI Repair And Replacement Program Preparation",
Attachment A "Section XI Repair / Replacement Program," will be resised to proside clear instmetions of when a VT-2 is required. This procedure revision will be completed by 062797.
(NTS # 2541809700301; Engineering).
F.
PREVIOUS EVENTS:
1.
LER l-96-008, Testing performed on the CAM check valves does not meet Tech Spec requirements due to an inadequate procedure.
G.
COMPONENT FAILURE DATA
i No Component Failures occurred that resulted in this report.
LER23467003. DOC
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| 05000254/LER-1997-001, :on 970117 & 07,discovered TS Required,Once Per Shift Channel Check Readings Not Completed within Required Twelve H Time Interval Plus 25% Max Allowable Extension. Caused by Personnel Error.Readings Performed |
- on 970117 & 07,discovered TS Required,Once Per Shift Channel Check Readings Not Completed within Required Twelve H Time Interval Plus 25% Max Allowable Extension. Caused by Personnel Error.Readings Performed
| 10 CFR 50.73(a)(2)(1) | | 05000265/LER-1997-001-01, :on 970227,initiation of High Pressure Coolant Injection Occurred Due to Deficient Procedures.Will Revise Surveillance Procedures,Will Review Prerequisites of All Im Procedures & Will Communicate Mgt Expectations to Personne |
- on 970227,initiation of High Pressure Coolant Injection Occurred Due to Deficient Procedures.Will Revise Surveillance Procedures,Will Review Prerequisites of All Im Procedures & Will Communicate Mgt Expectations to Personnel
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) | | 05000265/LER-1997-001, Forwards LER 97-001-00 Re Automatic Actuation of Any Esf. Commitments Made by Ltr,Listed | Forwards LER 97-001-00 Re Automatic Actuation of Any Esf. Commitments Made by Ltr,Listed | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000265/LER-1997-001-07, :on 970227,instrument Maintenance Dept Was Performing Procedure to Test HPCI Initiation Logic.Caused by Deficient Procedure.Order Was Issued for All non-routine |
- on 970227,instrument Maintenance Dept Was Performing Procedure to Test HPCI Initiation Logic.Caused by Deficient Procedure.Order Was Issued for All non-routine
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) | | 05000254/LER-1997-002-02, :on 970127,several Isolable Piping Sections Could Experience Stresses Above Update FSAR Allowables Due to post-loss of Coolant Accident Thermal Pressurization. Initial Operability Evaluation Was Completed on 970124 |
- on 970127,several Isolable Piping Sections Could Experience Stresses Above Update FSAR Allowables Due to post-loss of Coolant Accident Thermal Pressurization. Initial Operability Evaluation Was Completed on 970124
| | | 05000254/LER-1997-002, Forwards LER 97-002-00 Documenting Condition That Was Discovered at Quad Cities Nuclear Power Station.Util Commitments Made within Ltr,Listed | Forwards LER 97-002-00 Documenting Condition That Was Discovered at Quad Cities Nuclear Power Station.Util Commitments Made within Ltr,Listed | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | | 05000265/LER-1997-002-05, :on 970228,unit 2 Was Shutdown,Because Four Main Steam Relief Valve Closure Time Did Not Meet IST Program Limits.Ist Acceptance Criteria for PORVs Will Be Revised Using Data Obtained from Qcos 0203-03 on 022897 |
- on 970228,unit 2 Was Shutdown,Because Four Main Steam Relief Valve Closure Time Did Not Meet IST Program Limits.Ist Acceptance Criteria for PORVs Will Be Revised Using Data Obtained from Qcos 0203-03 on 022897
| | | 05000265/LER-1997-002-01, :on 970301,Unit 2 Was Shutdown Per TS 3.5.A & 3.6.F.Caused by Personnel Cognitive Error.Containment Procedure Changes Were Implemented to Prevent Containment Pressure Suppression Bypass |
- on 970301,Unit 2 Was Shutdown Per TS 3.5.A & 3.6.F.Caused by Personnel Cognitive Error.Containment Procedure Changes Were Implemented to Prevent Containment Pressure Suppression Bypass
| | | 05000265/LER-1997-002, Forwards LER 97-002-00 Re Condition Prohibited by Plant Tss. Util Commitments Made by Ltr,Listed | Forwards LER 97-002-00 Re Condition Prohibited by Plant Tss. Util Commitments Made by Ltr,Listed | 10 CFR 50.73(a)(2)(1) | | 05000254/LER-1997-003, Forwards LER 97-003-00 IAW 10CFR50.73(a)(2)(v)(B)(D). Procedure Qcap 0307-02, ASME Section XI Repair & Replacement Program Preparation, Attachment a, Section XI Repair/Replacement Program Will Be Revised Re VT-2 | Forwards LER 97-003-00 IAW 10CFR50.73(a)(2)(v)(B)(D). Procedure Qcap 0307-02, ASME Section XI Repair & Replacement Program Preparation, Attachment a, Section XI Repair/Replacement Program Will Be Revised Re VT-2 | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat | | 05000265/LER-1997-003-04, :on 970321,2B Core Spray Room Cooler Fouled Due to Hydrolyzing Debris.Cs Room Cooler Was Cleaned Under Nwr 960039336-01 & Qctp 1110-12, ECCS Room Cooler Trending Program, Has Recently Been Rewritten |
- on 970321,2B Core Spray Room Cooler Fouled Due to Hydrolyzing Debris.Cs Room Cooler Was Cleaned Under Nwr 960039336-01 & Qctp 1110-12, ECCS Room Cooler Trending Program, Has Recently Been Rewritten
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000254/LER-1997-003-05, :on 970429,visual Exam (VT-2) Was Not Performed Due to Procedural Deficiencies Following HPCI Sys Valve Replacement Required by Asme,Section XI & TS Section 4.0.E. Examined VT-2 of 1-2301-45 Valve |
- on 970429,visual Exam (VT-2) Was Not Performed Due to Procedural Deficiencies Following HPCI Sys Valve Replacement Required by Asme,Section XI & TS Section 4.0.E. Examined VT-2 of 1-2301-45 Valve
| | | 05000265/LER-1997-003-01, Forwards LER 97-003-01 Re Core Spray Room Cooler 2B That Fouled Due to Hydrolyzing Debris.Commitment Listed | Forwards LER 97-003-01 Re Core Spray Room Cooler 2B That Fouled Due to Hydrolyzing Debris.Commitment Listed | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | | 05000265/LER-1997-004, Forwards LER 97-004-00,IAW 10CFR50.73(a)(2)(ii)(B).Unit 1 DWEDS & DWFDS Will Be Examined to Verify Video Tape Determination During Next Refueling Shutdown to Ensure Covers on Unit Installed Per Applicable Design Drawings | Forwards LER 97-004-00,IAW 10CFR50.73(a)(2)(ii)(B).Unit 1 DWEDS & DWFDS Will Be Examined to Verify Video Tape Determination During Next Refueling Shutdown to Ensure Covers on Unit Installed Per Applicable Design Drawings | 10 CFR 50.73(a)(2) | | 05000265/LER-1997-004-06, :on 970509,drywell Equipment Drain Sump & Floor Drain Sump Covers Were Not Constructed IAW Design Drawings, Due to Original Construction Error.Design Change Package Has Been Completed |
- on 970509,drywell Equipment Drain Sump & Floor Drain Sump Covers Were Not Constructed IAW Design Drawings, Due to Original Construction Error.Design Change Package Has Been Completed
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000254/LER-1997-004-03, :on 961026,RHR Svc Water Pumps Declared Inoperable Due to Inadequate Evaluation of Replacement Pump Casing Bolts.Rhrsw Pump Bolting Inspected & Questionable Bolting Replaced |
- on 961026,RHR Svc Water Pumps Declared Inoperable Due to Inadequate Evaluation of Replacement Pump Casing Bolts.Rhrsw Pump Bolting Inspected & Questionable Bolting Replaced
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000254/LER-1997-005-03, :on 970319,HPCI Subsystem Was Made Inoperable to Protect Equipment Due to Uncertainties Re Abandoned Power Feed Cable,Which Had Been Inappropriately Abandoned. Plant Design Documents Have Been Updated |
- on 970319,HPCI Subsystem Was Made Inoperable to Protect Equipment Due to Uncertainties Re Abandoned Power Feed Cable,Which Had Been Inappropriately Abandoned. Plant Design Documents Have Been Updated
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(viii)(A) | | 05000254/LER-1997-005, Forwards LER 97-005-00 IAW Requirements of 10CFR50.73(a)(2)(v)(D) W/Listed Commitments | Forwards LER 97-005-00 IAW Requirements of 10CFR50.73(a)(2)(v)(D) W/Listed Commitments | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000265/LER-1997-005-01, Forwards LER 97-005-01 Re Unit 2 Reactor Placed in Mode 2 W/O Required Number of Emergency Diesel Generators Operable. Commitment Listed | Forwards LER 97-005-01 Re Unit 2 Reactor Placed in Mode 2 W/O Required Number of Emergency Diesel Generators Operable. Commitment Listed | 10 CFR 50.73(a)(2)(1) | | 05000265/LER-1997-005-02, :on 970608,Unit 2 Reactor Was Placed in Mode 2 W/O Required Number of EDGs Operable.Caused by Installation of Replacement Air Start Motors Which Did Not Have Same Characteristics as Original Motors.Revised Alternate Parts |
- on 970608,Unit 2 Reactor Was Placed in Mode 2 W/O Required Number of EDGs Operable.Caused by Installation of Replacement Air Start Motors Which Did Not Have Same Characteristics as Original Motors.Revised Alternate Parts
| 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) | | 05000265/LER-1997-006, Forwards LER 97-006-00 Re Cable in Unit 2 Being in Same Fire Area as Fire of Concern Due to Ineffective Implementation of Original Safe Shutdown Analysis.List of Commitments Provided | Forwards LER 97-006-00 Re Cable in Unit 2 Being in Same Fire Area as Fire of Concern Due to Ineffective Implementation of Original Safe Shutdown Analysis.List of Commitments Provided | 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor | | 05000265/LER-1997-006-01, :on 970729,cable 20865 Was Located in Same Turbine Bldg Fire Area as Fire of Concern & Could Have Been Damaged by Fire.Caused by Poor Work Practices.Revised Qarp 1000-01, Safe Shutdown Procedure C1 |
- on 970729,cable 20865 Was Located in Same Turbine Bldg Fire Area as Fire of Concern & Could Have Been Damaged by Fire.Caused by Poor Work Practices.Revised Qarp 1000-01, Safe Shutdown Procedure C1
| | | 05000254/LER-1997-006-03, :on 970327,loss of Reactor Coolant Inventory in Excess of Design Basis Limits Occurred Due to Inadequate Procedural Guidance.Procedure Qcop 1200-07 Was Revised to Administratively Control Power Feed Breaker |
- on 970327,loss of Reactor Coolant Inventory in Excess of Design Basis Limits Occurred Due to Inadequate Procedural Guidance.Procedure Qcop 1200-07 Was Revised to Administratively Control Power Feed Breaker
| | | 05000254/LER-1997-006, Forwards LER 97-006,Rev 00 & Submits Commitments Related to LER | Forwards LER 97-006,Rev 00 & Submits Commitments Related to LER | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | | 05000265/LER-1997-006-06, :on 970729,cable for Unit 2 in Same Fire Area as Fire of Concern Due to Ineffective Implementation of Original Safe Shutdown Analysis.Rev to Ssd Analysis to Credit Alternate Power Feeds,Will Be Performed |
- on 970729,cable for Unit 2 in Same Fire Area as Fire of Concern Due to Ineffective Implementation of Original Safe Shutdown Analysis.Rev to Ssd Analysis to Credit Alternate Power Feeds,Will Be Performed
| | | 05000254/LER-1997-007-03, :on 970331,unit One Emergency DG Inadvertently Started Due to Error by RSO While Operating Control Switch. Nso Removed from All Licensed Duties Until Completion of Remediation Plan |
- on 970331,unit One Emergency DG Inadvertently Started Due to Error by RSO While Operating Control Switch. Nso Removed from All Licensed Duties Until Completion of Remediation Plan
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000254/LER-1997-008, Forwards LER 97-008,Rev 00 & Submits Commitments.Revised Qcop 2300-13 Is to Include Steps to Fully Disengage Turning Gear If Necessary for Testing Purposes | Forwards LER 97-008,Rev 00 & Submits Commitments.Revised Qcop 2300-13 Is to Include Steps to Fully Disengage Turning Gear If Necessary for Testing Purposes | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000254/LER-1997-008-01, :on 970402,high Pressure Coolant Injection Was Inoperable Due to Turning Gear Failure.Turbine Turning Gear Was Manually Engaged |
- on 970402,high Pressure Coolant Injection Was Inoperable Due to Turning Gear Failure.Turbine Turning Gear Was Manually Engaged
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000265/LER-1997-008, Forwards LER 97-008-00 IAW Requirements of 10CFR50.73(a)(2)(i)(B).Commitments Made by Ltr,Listed | Forwards LER 97-008-00 IAW Requirements of 10CFR50.73(a)(2)(i)(B).Commitments Made by Ltr,Listed | 10 CFR 50.73(a)(2)(1) | | 05000265/LER-1997-008-05, :on 970629,five Control Rod Drives Did Not Receive Required Scram Insertion Time Testing Prior to 40% Power.Caused by Ineffective Operations.Rods Associated with Nwr Were Scram Timed & Declared Operable |
- on 970629,five Control Rod Drives Did Not Receive Required Scram Insertion Time Testing Prior to 40% Power.Caused by Ineffective Operations.Rods Associated with Nwr Were Scram Timed & Declared Operable
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000254/LER-1997-009, Forwards LER 97-009-00 Per 10CFR50.73(a)(2)(v)(D).Commitment Included in Ltr | Forwards LER 97-009-00 Per 10CFR50.73(a)(2)(v)(D).Commitment Included in Ltr | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000254/LER-1997-009-03, :on 970504,both Trains of Standby Gas Treatment Sys Were Inoperable.Caused by Cognitive Peersonnel Error. Blown Fuse Replaced,A Train of SBGTS Was Tested & Declared Operable & SRO Test Director Counseled |
- on 970504,both Trains of Standby Gas Treatment Sys Were Inoperable.Caused by Cognitive Peersonnel Error. Blown Fuse Replaced,A Train of SBGTS Was Tested & Declared Operable & SRO Test Director Counseled
| | | 05000265/LER-1997-009-05, :on 970713,control Room Personnel Misread Indication Delaying Discovery of Abnormal Offgas Radiation Readings Was Discovered.Caused by Personnel Error.Chemistry Sampled off-gas |
- on 970713,control Room Personnel Misread Indication Delaying Discovery of Abnormal Offgas Radiation Readings Was Discovered.Caused by Personnel Error.Chemistry Sampled off-gas
| 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(s)(2)(v) | | 05000254/LER-1997-010-02, :on 970407,train B of Control Room HVAC Sys Was Inoperable Due to Loss of Refrigerant.Caused by Failed Fitting.Replaced Fitting & Sys Tested Satisfactorily |
- on 970407,train B of Control Room HVAC Sys Was Inoperable Due to Loss of Refrigerant.Caused by Failed Fitting.Replaced Fitting & Sys Tested Satisfactorily
| | | 05000265/LER-1997-010-05, :on 970819,2B Offgas Hydrogen Analyzer Declared Inoperable.Caused by Communication Error.Offgas Hydrogen Sample Immediately Taken & Analyzed & Technicians Involved Counseled |
- on 970819,2B Offgas Hydrogen Analyzer Declared Inoperable.Caused by Communication Error.Offgas Hydrogen Sample Immediately Taken & Analyzed & Technicians Involved Counseled
| | | 05000265/LER-1997-010, Forwards LER 97-010-00 IAW Requirements of 10CFR50.73(a)(2)(i)(B).No Commitments Made | Forwards LER 97-010-00 IAW Requirements of 10CFR50.73(a)(2)(i)(B).No Commitments Made | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000254/LER-1997-010, Forwards LER 97-010-00 Which Repts Event That Occurred at Quad Cities Nuclear Station,Per 10CFR50.73(a)(2)(v)(D). Commitment Made by Ltr,Submitted | Forwards LER 97-010-00 Which Repts Event That Occurred at Quad Cities Nuclear Station,Per 10CFR50.73(a)(2)(v)(D). Commitment Made by Ltr,Submitted | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000254/LER-1997-011-01, :on 970409,RHRSW Sys Was Made Inoperable Due to Uncertainties Related to 4 Kv Air magne-blast Horizontal Gas Circuit Breakers.Caused by Improper Manufacturers Switch Mounting Design.Pif 97-1276 Written to Investigate Cause |
- on 970409,RHRSW Sys Was Made Inoperable Due to Uncertainties Related to 4 Kv Air magne-blast Horizontal Gas Circuit Breakers.Caused by Improper Manufacturers Switch Mounting Design.Pif 97-1276 Written to Investigate Cause
| | | 05000254/LER-1997-011, Forwards LER 97-011-00 Re an Event or Condition That Alone Could Have Prevented Fulfillment of Safety Function of Structures or Sys That Are Needed to Remove Residual Heat. Commitments Made by Ltr,Submitted | Forwards LER 97-011-00 Re an Event or Condition That Alone Could Have Prevented Fulfillment of Safety Function of Structures or Sys That Are Needed to Remove Residual Heat. Commitments Made by Ltr,Submitted | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(1) | | 05000265/LER-1997-011-05, :on 970904,determined That Offgas H Sampling Frequency Was Less than That Required by Ts.Caused by Inadequate Tracking of LCO Actions Re Recombiner Temp.Began Sampling at Four H Intervals |
- on 970904,determined That Offgas H Sampling Frequency Was Less than That Required by Ts.Caused by Inadequate Tracking of LCO Actions Re Recombiner Temp.Began Sampling at Four H Intervals
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000265/LER-1997-012-06, :on 971121,loss of Shutdown Cooling Due to Loss of Power to Reactor Protection Bus 2B.Caused by Undervoltage Condition at RPS 2B Bus When Bus Was Loaded.Voltage Regulating Transformer Cleaned & Adjusted |
- on 971121,loss of Shutdown Cooling Due to Loss of Power to Reactor Protection Bus 2B.Caused by Undervoltage Condition at RPS 2B Bus When Bus Was Loaded.Voltage Regulating Transformer Cleaned & Adjusted
| | | 05000254/LER-1997-013, Forwards LER 97-013-00 Re Any Single Cause of Inoperable Independent Train or Channel in Single Sys Designed to Remove Residual Heat.Commitments Made by Ltr,Listed | Forwards LER 97-013-00 Re Any Single Cause of Inoperable Independent Train or Channel in Single Sys Designed to Remove Residual Heat.Commitments Made by Ltr,Listed | 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability | | 05000254/LER-1997-013-01, :on 970416,RCIC Area High Temperature Switch Would Not Actuate Due to Excess Sealing Varnish Applied by Technician.Caused by Personnel Error.Removed Excess Varnish from Switch,Calibrated & Functionally Tested Switch |
- on 970416,RCIC Area High Temperature Switch Would Not Actuate Due to Excess Sealing Varnish Applied by Technician.Caused by Personnel Error.Removed Excess Varnish from Switch,Calibrated & Functionally Tested Switch
| | | 05000254/LER-1997-014, Forwards LER 97-014-00 Per 10CFR50.73(a)(2)(i)(B).Listed Commitment Made by Ltr | Forwards LER 97-014-00 Per 10CFR50.73(a)(2)(i)(B).Listed Commitment Made by Ltr | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000254/LER-1997-014-01, :on 970416,target Rock Safety Relief Valve Removed from Unit 2 During Q2R13 & Unit 1 During Q1R14 Were Not Tested within 12 Months.Caused by Defective Procedure. Revised Maintenance Procedure |
- on 970416,target Rock Safety Relief Valve Removed from Unit 2 During Q2R13 & Unit 1 During Q1R14 Were Not Tested within 12 Months.Caused by Defective Procedure. Revised Maintenance Procedure
| | | 05000265/LER-1997-015-05, :on 970622,TS Required Surveillance Was Not Properly Performed Due to Apparent Unfamiliarity w/10CFR50 Appendix G Which Resulted in Insufficient Tp.Cause Is Under Investigation.No Action Taken at Present Time |
- on 970622,TS Required Surveillance Was Not Properly Performed Due to Apparent Unfamiliarity w/10CFR50 Appendix G Which Resulted in Insufficient Tp.Cause Is Under Investigation.No Action Taken at Present Time
| | | 05000254/LER-1997-015, Informs NRC of Change of Committed Due Date Contained in LER 97-015,dtd 970812.Station Changing Due Date of Commitment to 990528 | Informs NRC of Change of Committed Due Date Contained in LER 97-015,dtd 970812.Station Changing Due Date of Commitment to 990528 | | | 05000254/LER-1997-015-02, :on 970622,discovered That 10CFRE50,App G Pressure Testing Requirements Were Not Met.Caused by Failure of Station Personnel to Recognize All Organizational Challenges Which Could Occur in Controlling.Performed Test |
- on 970622,discovered That 10CFRE50,App G Pressure Testing Requirements Were Not Met.Caused by Failure of Station Personnel to Recognize All Organizational Challenges Which Could Occur in Controlling.Performed Test
| | | 05000254/LER-1997-016-01, :on 970509,DG CW IST Requirements Were Not Completed When Inaccurate Predefined Work Request Used for Scheduling Was Implemented.Caused by Inappropriately Titled Work Request.Qcos 6600-08 Was Completed for Unit 1 |
- on 970509,DG CW IST Requirements Were Not Completed When Inaccurate Predefined Work Request Used for Scheduling Was Implemented.Caused by Inappropriately Titled Work Request.Qcos 6600-08 Was Completed for Unit 1
| | | 05000254/LER-1997-016, Forwards LER 97-016-00 Re DG CW IST Requirements Not Being Completed When Inaccurate Predefined Work Request Was Implemented | Forwards LER 97-016-00 Re DG CW IST Requirements Not Being Completed When Inaccurate Predefined Work Request Was Implemented | 10 CFR 50.73(a)(2)(1) |
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