: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| ML20140D010 |
| Person / Time |
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| Site: |
Quad Cities  |
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| Issue date: |
04/15/1997 |
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| From: |
Peterson C COMMONWEALTH EDISON CO. |
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| To: |
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| Shared Package |
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| ML20140D006 |
List: |
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| References |
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| LER-97-005-03, LER-97-5-3, NUDOCS 9704220076 |
| Download: ML20140D010 (4) |
|
text
s e
LICENSEE EVENT REPORT (LER)
Form Rev,2.0 f acihty Name (1-)
Docket Number G)
Page (3)
Quad Citi:s Nnit One 0l5l0l0l0l2l5l4 1 l of l 0 l 4 Titta (4)
The High Pressure Coolant injection Subsystem was Made Inoperable to Protect Equipment Due to Uncertainties Related to an Abandoned Power Feed Cable, Which Had Been inappropriately Abandoned.
Ennt Date (5)
LER Number (6)
Report Date (7)
Other Facihties involved (3)
Month Day Year Year Sequential Revision Month Day Year Facility Docket Numberts)
Number Number Names 015l0l0l0l l
l 0l3 1l9 9l7 9l7 0l0j5 0l0 0l4 1l5 9l7 0l5l0l0l0]
l l
OPERATING THis REPORT IS SUBMITTED PUR$UANT 'r0 THE REQUIREMENTS OF 10CFR MODE (9)
(Check one or more of the following) (1l) 1 20.402(b) 20.405(c) 50.73(a)(2)(iv) 73.71(b)
LOWER 20.405(a)(1)(i) 50.36(c)(1) x 50.73(a)G)(v)
- - 73.71(c)
LEVEL
- - 20.405(a)(1)Oi) 50.36(c)(2) 50.73(a)G)(vii)
Other (Specify (10) l8l o
20 405(a)(1)(iii) 50.73(a)c)(i) 50.73(a)(2)(viii)(A) m Abstract 20.405(a)(1)(iv) 50.73(a)C)(ii) 50.73(a)G)(viii)(B) below and in
- - 20.405(a)(1)(v) 50.73(a)G)(iii) 50.73(a)G)(x)
Text)
LICENSEE CONIACT FOR THIS LER (12)
NAME TELEPHON1* NUMBER AREA CODE 1
Ch.rlo P terson, Regulatory Affairs Manager, ext. 3609 3l0l9 6l5l4l-l2l2l4l1
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1 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) l CAU3E 5Y5 TEM COMPONENT MANUFACIURER REPORTABLE
CAUSE
SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPRDS TO NPRDS j
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I I
I I
I I
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1 I
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I 5UP 'LEMENTAL REPORT EXPEt;& w (14)
Expected Month Day Year Submsssion lYES (If yes. complete EXPECTED SUBMISSION DATE)
"T"lNO Dnie (15) l l
l AB5TRACI (Lanit to 1400 spaces, i.e., appronunately fineen omgle-space typewnuen hnos) (16; 1
ABSTRACT:
The High Pressure Coolant Injection (HPCI) Subsystem was declared inoperable at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> on 031997 when the HPCI Gland Seal Condenser Exhauster (GSCE) control switch was placed in the pull-to-lock (PTL) control position by the Unit One Nuclear Station Operator. The GSCE was placed in PTL due to a concern with the power feed cable to the exhauster.
Cable damage had been noted to a cable believed to provide power to the GSCE. At 2315 hours0.0268 days <br />0.643 hours <br />0.00383 weeks <br />8.808575e-4 months <br /> on 031997 it was determined that the damaged cable had been abandoned and the GSCE was placed back into the automatic control mcde making the HPCI subsystem operable. An Emergency Notification System (ENS) call was made at 2346 hours0.0272 days <br />0.652 hours <br />0.00388 weeks <br />8.92653e-4 months <br /> due to the HPCI subsystem inoperability.
The following actions contributed to this event: (1) The damaged cable had been improperly abandoned and (2) a previous Problem Identification Form (PIF) did not properly correct this problem, Corrective actions for this event include:
(1) updating the plant design documents to properly reflect the status of this abandoned cable; (2) laoeling this abandoned cable at each accessible location along its route and (3) reviewing and revising as necessary the Abandoned Equipment Procedure.
There was no effect on the public or the control room personnel due to this eWnt and the safety consequences were minimal.
LER254\\9N)05.WPF 9704220076 970415 PDR ADOCK 05000254 S
PDR
s f
LICENSEE EVEN'T REPORT (LER) TEXT CONTINUATION Form Rsv. 2.0 FACILTTY NAME (1)
DCCKET NUMBER (2)
LER NUMBER (6)
PAGE (3)
Year Sequential Revision Number Number Quad Citirs Unit One 0l5l0l0l0l2l5l4 9l7 0l0l5 0l0 2 lOFj 0 l 4 TEXT Energy industry identification System (Ell 5) codes are identined in the text as [XX)
PLANT AND SYSTEM IDENTIFICATION
4 General Electric - Boiling Water Reactor - 2511 MWt rated core thermal power.
. EVENT IDENTIFICATION: The High Pressure Coolant Injection Subsystem was Made Inoperable to Protect Equipment Due to Uncertainties Related to an Abandoned Powe-. eed Cable, Which Had B en Inappropriately Abandoned.
A.
CONDITIONS PRIOR TO EVENT
Unit: One Event Date: 031997 Event Time:
2200 Reactor Mode: 1 Mode Name:
POWER OPERATION Power Level: 80%
POWER OPERATION Mode (1): Mode switch in the RUN position with average reactor coolant temperature at any temperature.
B.
EVENT DESCRIPTION
On 031997 while performing a walkdown in the Unit 1 High Pressure Coolant Injection (HPCI)[BJ) Subsystem Room, Station Support Engineering (SSE) personnel identified a damaged cable in the riser section of a cable tray.
SSE initiated Problem
)
Identification Form (PIF) #97-0965 and submitted it to the Shift Engineer (SE).
After a review of PIF #97-0965, the SE sent Electrical Maintenance (EM) personnel out to identify the damaged cable.
The EM's hand traced the damaged cable from the riser section of the cable tray to a wall penetration where the cable was identified as cable number #13975.
Cable #13975 was identified on cable tabulation drawing 4E-1904H as the feed cable for the HPCI Gland Seal Condenser Exhauster (GSCE)[DGS].
The EM's proceeded to 250 Volt Direct Current (VDC) Motor Control Center (MCC) 1A, Compartment C02 and verified that cable 1
- 13975 was in fact terminated as indicated on the cable tabulation drawings.
Due to the possibility of further cable damage, the SE had the HPCI GSCE control switch placed in the Pull-to Lock (PTL) position at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> to prevent inadvertent actuation. When the control switch was placed in PTL, the HPCI system was declared inoperable, an Emergency Notification System phone call was placed at 2346 hours0.0272 days <br />0.652 hours <br />0.00388 weeks <br />8.92653e-4 months <br /> and the unit entered a 14 day Limiting Condition of Operation (LCO) per Technical Specification 3.5.A.3.
The EM's continued tracing cable #13975 to the first junction box back from the HPCI GSCE, where they found the damaged cable cut, taped and labeled as abandoned.
It was determined that there were duplicate cables for cable #13975. One cable was in good condition and terminated as indicated on the cable tabulation drawing. The other cable, which was the damaged cable, had been cut, taped and labeled as abandoned, however it did not have it's installation status reflected on the cable tabulation drawings. At 2315 hours0.0268 days <br />0.643 hours <br />0.00383 weeks <br />8.808575e-4 months <br />, after determining the damaged cable status as abandoned, the HPCI GSCE switch was placed in automatic control position and the HPCI subsystem was declared operable.
LER254\\9"h005,WPF
__-_m._
e LICENSEE EVENT REPORT n.ER) TEXT CONTINUATION Form Rw,2.0 F ACILITY N AME (1)
DOCKET NUMBER (2)
LER NUMBER (6)
FAGE (3)
Year Sequennal Revision Number Number Quad Citils Unit ome 0l5l0lol0l2l5l4 9l7 0l0l5 olo 3 lOFl o l 4 TEXT Energy industry identification dystem (Ells) codes are identified in the text as IXXj i
C.
APPARENT CAUSE OF THE EVENT:
The apparent cause of this event is a failure to properly abandon cable #13975 prior to 1988. According to maintenance history, this cable was abandoned some time before November 1988. When the cable was abandoned, a new cable was pulled for the purpose of feeding the HPCI GSCE. This new cable was given the same cable number as the damaged cable which was being abandoned in place. The electrical prints were not updated to reflect this change and both the old damaged cable (which was being abandoned) and the new GSCE power feed cable were given the same number. This led to the confusion on March 19, 1997.
l A contributing cause to this event was that a previously written PIF (PIF #94-2828) had been dispositioned improperly. This PIF was written on 111194 due to identified damage to the same cable. An issue screening was performed which determined that this cable was abandoned and there was no operability concern. The PIF was then closed out without taking corrective actions to update the plant design documents.
D.
SAFETY ANALYSIS OF THE EVENT:
)
The consequences of this event are considered minimal. There was no effect on the public or the control room personnel due to this event.
The Unit 1 HPCI subsystem was available to start automatically during the 75 minutes i
l that the GSCE control switch was in Pll. Had a design basis accident occurred while this switch was in PTL, HPCI would have started and refilled the reactor vessel as designed.
i The GSCE normally removes non-condensables from the Gland Condenser and maintains a j
slight negative pressure on the HPCI turbine seals. Without the GSCC running, steam would have begun leaking out of the HPCI turbine seals and the stop and control valve stems. This leakage would have added to the heat load in the HPCI room eventually causing the subsystem to isolate on High Area Temperature at 155 degrees Fahrenheit (F). A previous calculation performed by Nuclear Fuel Services Department shows that the HPCI subsystem would remain operable for at least 13 minutes after initiation with a GSC failure.
Loss of Coolant Accident (LOCA) analysis for small liquid break accidents show that the reactor would depressurize to allow for effective low pressure Emergency Core Cooling Subsystem (ECCS) operation within about 10 minutes.
Therefore it is reasonable to assume for a small break accident the HPCI subsystem would have fulfilled it's design function even with the GSCE in PTL.
If the HPCI subsystem had been needed to slowly cooldown the reactor or for reactor coolant 4
inventory control during a steamline break accident, the HPCI Subsystem would potentially not have been available.
LER254\\97\\005.WPF
e LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Form Rzv. 2.0 FACILITY NAME (1)
DOCKET NUMBER (2)
LER NUMhER (6)
PAGE (3) i Year Sequential Revision Number Nurnber Quad Citi:s Unit one 0l5l0l0lol2l5l4 9l7 olol5 ol0 4 lOFl 0 l 4 I LXT Energy industry identi6 cation 6ystem (Ell 5) codes are identified in the text as (XXl Even if the HPCI Subsystem had not been able to operate for the required amount of time, the Automatic Depressurization (ADS)[RV) and the Low Pressure Coolant Injection (LPCI)[B0] subsystems were operable during this event and would also have provided protection for the fuel in the event of a LOCA.
E.
CORRECfIVE ACTIONS:
Corrective Actions Completed:
1.
The damaged cable was identified as abandoned and the HPCI GSCE was restored to an operable status.
2.
The cable was also labeled as abandoned at the cable tray in the HPCI room.
Corrective Actions to be Completed 1.
Update the plant design documents to reflect the status of this abandoned cable (Design Eng., NTS #2541809700501). This will be completed by 080197.
2.
Label this cable as abandoned at all accessible locations along its route (0ps.,
NTS #2541809700502). This will be completed by 081597.
1 3.
QCAP 0460-06, Abandoned Equipment Procedure, will be reviewed to ensure that the proper requirements are in place ta ensure drawing updates, cable numbering updates and labeling of abandoned cables (Design Eng., NTS #2541809700503).
This will be completed by 080197.
F.
PREVIOUS EVENTS:
1.
PIF #94-2828 identifies the same concern with the subject cable as this Licensee Event Report (LER). An issue screening was performed which determined that the i
cable was abandoned and no further corrective actions were taken under this PIF.
The HPCI subsystem was never made inoperable while addressing this PIF.
A review of the LER database was performed and there have been no LERs in the last two years caused by a failure of the abandoned equipment program or a misunderstanding caused by an inadequate design document.
G.
COMPONENT FAILURE DATA
There is no component failure associated with this event LER254\\97\\005.WPF
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| | | Reporting criterion |
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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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