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| | Title = Forwards LER 97-001-00 Re Automatic Actuation of Any Esf. Commitments Made by Ltr,Listed | | | Title = Forwards LER 97-001-00 Re Automatic Actuation of Any Esf. Commitments Made by Ltr,Listed |
| | Plant = | | | Plant = |
| | Reporting criterion = | | | Reporting criterion = 10 CFR 50.73(a)(2)(v), 10 CFR 50.73(a)(2)(iv) |
| | Power level = | | | Power level = |
| | Mode = | | | Mode = |
| | Docket = 05000265 | | | Docket = 05000265 |
| | LER year = 2097 | | | LER year = 1997 |
| | LER number = 1 | | | LER number = 1 |
| | LER revision = | | | LER revision = 0 |
| | Event date = | | | Event date = |
| | Report date = | | | Report date = |
| Line 33: |
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| =text= | | =text= |
| {{#Wiki_filter:.. | | {{#Wiki_filter:.. |
| Onnmoewcalth IMivm Company Quad 4.itics Generatmg St.ition 22710 2@th Asenue North | | Onnmoewcalth IMivm Company Quad 4.itics Generatmg St.ition 22710 2@th Asenue North Girdova, II. 612 42 C au Tei S m,u 22ii e |
| . Girdova, II. 612 42 C au Tei S m ,u 22ii e
| |
| LWP-97-029 March 27, 1997 United States Nuclear Regulatory Commission Washington, DC 20555 | | LWP-97-029 March 27, 1997 United States Nuclear Regulatory Commission Washington, DC 20555 |
| . Attention: Document Control Desk
| | . Attention: |
| | Document Control Desk |
|
| |
|
| ==Reference:== | | ==Reference:== |
| Quad Cities Nuclear Power Station Docket Number 50-265, DPR-30, Unit Two Enclosed is Licensee Event Report (LER) 97-001, Revision 00, for Quad Cities Nuclear Power Station. | | Quad Cities Nuclear Power Station Docket Number 50-265, DPR-30, Unit Two Enclosed is Licensee Event Report (LER) 97-001, Revision 00, for Quad Cities Nuclear Power Station. |
| This report is submitted in accordance with the requirements of the Code of Federal Regulations, Title 10, Part 50.73(a)(2)(v)(D). The ! | | This report is submitted in accordance with the requirements of the Code of Federal Regulations, Title 10, Part 50.73(a)(2)(v)(D). The licensee shall report any event or condition that alone could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident. |
| licensee shall report any event or condition that alone could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident. t Also submitted in accordance with Part 50.73(a)(2)(iv). The licensee l shall report any event or condition that resulted in manual or l automatic actuation of any Engineered Safety Feature. . | | t Also submitted in accordance with Part 50.73(a)(2)(iv). |
| | The licensee l |
| | shall report any event or condition that resulted in manual or automatic actuation of any Engineered Safety Feature. |
| The following commitments are being made by this letter: | | The following commitments are being made by this letter: |
| : 1. Communicate the specific management expectation for the person in charge of the work to review the appropriate prints to ensure that he/she is aware of the effects to plant and system operation from the activities performed. (May 1, 1997).
| | 1. |
| : 2. Communicate the specific management expectation that procedure !
| | Communicate the specific management expectation for the person in charge of the work to review the appropriate prints to ensure that he/she is aware of the effects to plant and system operation from the activities performed. |
| writers include 10CFR50.59 safety screening / evaluation !
| |
| requirements in the associated procedure prerequisites. '
| |
| (May 1, 1997). | | (May 1, 1997). |
| : 3. Revise QCAP 1100-04, " Procedure Revision, Review and Approval" to require the procedure prerequisites be bounded by the 10CFR50.59 safety screening / evaluation mode requirements. Train all departments on this procedure change. (April 27, 1997).
| | 2. |
| : 4. The Operations Manager and the Work Control Superintendent will meet with the Lead Unit Planners to provide expectations for i Lead Unit Planner, Work Week Manager and Scheduler responsibilities when reviewing and scheduling work.
| | Communicate the specific management expectation that procedure writers include 10CFR50.59 safety screening / evaluation requirements in the associated procedure prerequisites. |
| | (May 1, 1997). |
| | 3. |
| | Revise QCAP 1100-04, " Procedure Revision, Review and Approval" to require the procedure prerequisites be bounded by the 10CFR50.59 safety screening / evaluation mode requirements. |
| | Train all departments on this procedure change. (April 27, 1997). |
| | 4. |
| | The Operations Manager and the Work Control Superintendent will meet with the Lead Unit Planners to provide expectations for i |
| | Lead Unit Planner, Work Week Manager and Scheduler responsibilities when reviewing and scheduling work. |
| (April 30, 1997). | | (April 30, 1997). |
| : 5. Review and revise as necessary the work control procedures and p licies t
| | 5. |
| ,0 m inc rp rate the expectations provided by the #
| | Review and revise as necessary the work control procedures and |
| Operations Manager and Work Control Superintendent. | | ,0 m p licies t inc rp rate the expectations provided by the Operations Manager and Work Control Superintendent. |
| (June 1, 1997). | | (June 1, 1997). |
| /[ l 9704030001 970327 DR ADOCK0500g5 j gj}ggj{Q.
| | /[ |
| n i mcom o,mpans | | l 9704030001 970327 ADOCK0500g5 j |
| * I LWP-97-029 2 March 27, 1997
| | gj}ggj{Q. |
| : 6. Revise QCIPM 0100-10, " Refuel Outage ECCS Instrumentation Check Prior to ECCS Logic Test" to include prerequisites to identify j the plant conditions required prior to using each section of :
| | DR n i mcom o,mpans |
| this procedure and to clarify each of the individual impact ' | | |
| statements. (April 15, 1997). | | I LWP-97-029 2 |
| : 7. Instrument Maintenance shall review and establish a priority for-revising all of their power block procedures to determine if the impact statement or the prerequisite adequately identify the plant conditions that shall exist prior to. the use of the procedure. (April 30, 1997).
| | March 27, 1997 6. |
| | Revise QCIPM 0100-10, " Refuel Outage ECCS Instrumentation Check Prior to ECCS Logic Test" to include prerequisites to identify the plant conditions required prior to using each section of j |
| | this procedure and to clarify each of the individual impact statements. |
| | (April 15, 1997). |
| | 7. |
| | Instrument Maintenance shall review and establish a priority for-revising all of their power block procedures to determine if the impact statement or the prerequisite adequately identify the plant conditions that shall exist prior to. the use of the procedure. |
| | (April 30, 1997). |
| If there are any questions or comments concerning this letter, please refer them to Charles Peterson, Regulatory Affairs Manager at 309-654-2241, ext. 3609. | | If there are any questions or comments concerning this letter, please refer them to Charles Peterson, Regulatory Affairs Manager at 309-654-2241, ext. 3609. |
| Respectfully, , | | Respectfully, COMMONWEALTH EDIS0N COMPANY QUAD CITIES NUCLEAR POWER STATION |
| COMMONWEALTH EDIS0N COMPANY QUAD CITIES NUCLEAR POWER STATION | | $.0, b [ |
| $.0, b [ .
| |
| L. W. Pearce Station Manager LWP/CP/plm | | L. W. Pearce Station Manager LWP/CP/plm |
| . Enclosure cc: A. B. Beach, Regional Administrator, Region III R. M.. Pulsifer, Project Manager, NRR C. G. Miller, Senior Resident Inspector, Quad Cities ;
| | . Enclosure cc: |
| W. D. Leech, MidAmerican' Energy Company D. C. Tubbs, MidAmerican Energy Company j P. L. Piet, Licensing, Comed F. A. Spangenberg, Regulatory Affairs Manager, Dresden- ! | | A. B. Beach, Regional Administrator, Region III R. |
| INP0 Records Center ' | | M.. Pulsifer, Project Manager, NRR C. G. Miller, Senior Resident Inspector, Quad Cities W. D. Leech, MidAmerican' Energy Company D. C. Tubbs, MidAmerican Energy Company j |
| I I
| | P. L. Piet, Licensing, Comed F. A. Spangenberg, Regulatory Affairs Manager, Dresden-INP0 Records Center I |
| | I |
| }} | | }} |
|
| |
|
| {{LER-Nav}} | | {{LER-Nav}} |
text
..
Onnmoewcalth IMivm Company Quad 4.itics Generatmg St.ition 22710 2@th Asenue North Girdova, II. 612 42 C au Tei S m,u 22ii e
LWP-97-029 March 27, 1997 United States Nuclear Regulatory Commission Washington, DC 20555
. Attention:
Document Control Desk
Reference:
Quad Cities Nuclear Power Station Docket Number 50-265, DPR-30, Unit Two Enclosed is Licensee Event Report (LER)97-001, Revision 00, for Quad Cities Nuclear Power Station.
This report is submitted in accordance with the requirements of the Code of Federal Regulations, Title 10, Part 50.73(a)(2)(v)(D). The licensee shall report any event or condition that alone could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident.
t Also submitted in accordance with Part 50.73(a)(2)(iv).
The licensee l
shall report any event or condition that resulted in manual or automatic actuation of any Engineered Safety Feature.
The following commitments are being made by this letter:
1.
Communicate the specific management expectation for the person in charge of the work to review the appropriate prints to ensure that he/she is aware of the effects to plant and system operation from the activities performed.
(May 1, 1997).
2.
Communicate the specific management expectation that procedure writers include 10CFR50.59 safety screening / evaluation requirements in the associated procedure prerequisites.
(May 1, 1997).
3.
Revise QCAP 1100-04, " Procedure Revision, Review and Approval" to require the procedure prerequisites be bounded by the 10CFR50.59 safety screening / evaluation mode requirements.
Train all departments on this procedure change. (April 27, 1997).
4.
The Operations Manager and the Work Control Superintendent will meet with the Lead Unit Planners to provide expectations for i
Lead Unit Planner, Work Week Manager and Scheduler responsibilities when reviewing and scheduling work.
(April 30, 1997).
5.
Review and revise as necessary the work control procedures and
,0 m p licies t inc rp rate the expectations provided by the Operations Manager and Work Control Superintendent.
(June 1, 1997).
/[
l 9704030001 970327 ADOCK0500g5 j
gj}ggj{Q.
DR n i mcom o,mpans
I LWP-97-029 2
March 27, 1997 6.
Revise QCIPM 0100-10, " Refuel Outage ECCS Instrumentation Check Prior to ECCS Logic Test" to include prerequisites to identify the plant conditions required prior to using each section of j
this procedure and to clarify each of the individual impact statements.
(April 15, 1997).
7.
Instrument Maintenance shall review and establish a priority for-revising all of their power block procedures to determine if the impact statement or the prerequisite adequately identify the plant conditions that shall exist prior to. the use of the procedure.
(April 30, 1997).
If there are any questions or comments concerning this letter, please refer them to Charles Peterson, Regulatory Affairs Manager at 309-654-2241, ext. 3609.
Respectfully, COMMONWEALTH EDIS0N COMPANY QUAD CITIES NUCLEAR POWER STATION
$.0, b [
L. W. Pearce Station Manager LWP/CP/plm
. Enclosure cc:
A. B. Beach, Regional Administrator, Region III R.
M.. Pulsifer, Project Manager, NRR C. G. Miller, Senior Resident Inspector, Quad Cities W. D. Leech, MidAmerican' Energy Company D. C. Tubbs, MidAmerican Energy Company j
P. L. Piet, Licensing, Comed F. A. Spangenberg, Regulatory Affairs Manager, Dresden-INP0 Records Center I
I
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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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