:on 961009,HPCI Sys Declared Inoperable.Caused by Improper Filling & Venting After Aug 1996 Maint.Air Purged from Sys & line-up Procedure Revised to Ensure Filling & Venting of Piping| ML20134H813 |
| Person / Time |
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| Site: |
Quad Cities  |
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| Issue date: |
11/05/1996 |
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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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| ML20134H811 |
List: |
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| References |
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| LER-96-002-10, LER-96-2-10, NUDOCS 9611140328 |
| Download: ML20134H813 (6) |
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text
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Faer q t A Facdity Name (1)
Quad Cities Unit Two 0l5l0l0l0l2l6l5 1 l of l 0 l 6 Title (4)
High Pressure Coolant Injection Inoperable Due to Inadequate Venting.
i Event Date (5)
LER Number (6)
Report Date (7)
Other Facilities involved (8) j Month Day Year Year Sequential Revision Month Day Year Facility Docket Number (s)
Number Number Names j
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1l0 0l9 9l6 9l6 0l0l2 0l0 1
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OPERATING THIS REPORT IS SUBMI 1 & :.D PU GUMT lio T 1E REQU REN ENTS OF 10CFR l
MODE (9)
(Check one or more of the following) (11) i, 1
20.402(b) 20.405(c) 50.73(a)G)(iv) 73.71(b) a POwLR 20.405(a)(1)0) 50.36(c)(1)
T50.73(a>G)(v)
- - 73.7:(c)
LEVEL 20.405(a)(1)Gi) 50.36(c)G) 50.73(a)G)(vii)
Other (Specify (10) 1 l0l 0
~~~20.405(a)(1)0ii) 50.73(a)G)0) 50.73(a)C)(viii)(A) in Abstract j
20.405(a)(1)0v) 50.73(a)G)0i) 50.73(a)G)(viii)(B) below and in 20.405(a)(1)(v) 50.73(a)G)0ii) 50.73(a)G)(x)
Text)
LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NUMBER f
AREA CODE Chales Peterson Regulatory Affairs Manager, ext. 3602 3 0l9 6l5l4l-l2l2l4l1 g!
COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN 'IHIS REPORT (13)
CAUSE
SYSTEM COMPONENT MANUF ?TURER REFORTABd
CAUSE
SYSTEM COMPONEN'I' MANUFACTU RER REPORTABM g'
10 NPRDS TD NPRDS 1
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SUPPEMENTAL REPORT EXPECTED (14) 4-Month Day Yew sh-lYES (if yes, complete EXPECTED SUBMISSION DATE)
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AB5 TRACT (Lams: to 1400 apacca, a.c., appronunately fifteen smg6e-epace syyewnnen lmes) (16)
ABSTRACT On October 9,1996 at 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> the Unit Two High Pressure Coolant Injection (HPCI) System was declared inoperable when the pump discharge piping failed to vent during performance of QCOS 2300-09, "HPCI Monthly Vent Verification" procedure.
An Emergency Notification System call was made at 1248 hours0.0144 days <br />0.347 hours <br />0.00206 weeks <br />4.74864e-4 months <br /> on October 9,1996 and an investigation was initiated.
The root cause was an improper fill and vent of HPCI injection piping after maintenance was performed on the system during August 1996.
This improper fill and vent trapped air in the HPCI pump discharge piping downstream of the system isolation valve (M0-2301-8) preventing proper system venting.
Corrective actions included purging the air from the system and correcting the HPCI system-line-up procedure to ensure filling and venting of all system piping.
It was verified that the Unit 1 HPCI piping was properly filled and vented.
The consequences of this event on the health and safety of the public are considered minimal because the amount of air trapped in the system piping would not have prevented the HPCI system from performing its design function.
9611140328 961104 PDR ADOCK 05000265 S
PDR
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LICENSEE EVENT REPCOT (LER) TEXT CONTINUATION Form Rsv. 2.0 F ACILTTY,N e3tF (!),
WKET NUMBER (2) li.EP NUM51FR f 6)
PAGE (3)
T*3.lgT27 ~"'M. n en s.
s y,-
i Number Number l
0lol2 0l0 2 lOFl 0 l 6 f
Quad Cities Unit Two ol5 0l0l0l2l6l5 9l6 TEXT Energy industry identificauon System (EIIS) codes are idenuted in the text as (XXj
PLANT AND SYSTEM IDENTIFICATION
General Electric - Boiling Water Reactor - 2511 MWt rated core thermal power.
EVENT-IDENTIFICATION: High Pressure Coolant Injection Inoperable Due to Inadequate l
Venting.
A.
CONDITIONS PRIOR TO EVENT
Unit:
Two Event Date: October 9, 1996 Event Time:
1000 1
Reactor Mode: 1 Mode Name:
POWER OPERATION Power Level: 100%
This report was initiated by Licensee Event Report LER265\\96-002.
1 Power Operation (1) - Mode switch in the RUN position with average reactor coolant temperature at any temperature.
B.
EVENT DESCRIPTION
On October 9, 1996 at 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> the Unit Two (U-2) High Pressure Coolant Injection (HPCI)[BJ] System was declared inoperable when no water flow was observed from the f
pump discharge piping high point vent during performance of QCOS 2300-09, "HPCI Monthly Vent Verification" procedure. This indicated that the system piping up to the system isolation valve was not full of water as required by Technical Specification (Tech Spec)4.5.A.I.a.1. At the time of the event, a static head of water was being supplied to the HPCI system by the Contaminated Condensate Storage Tanks (CCST) [KM] which were filled to a level 1 foot 8 inches above the highest point of the HPCI discharge piping. Over the next nine hours, system venting was attempted several times in differing configurations and it could not be verified that the discharge piping was full. At approximately 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br /> on October 9, 1996, the HPCI Cooling Water Pump was run for one minute with its discharge lined up through i
the HPCI vent piping. After this fill and vent of the system piping, it was verified j
that all piping was full and the failure to vent event could not be recreated.
The HPCI pump suction was then switched to the suppression pool [NH], the Keep Fill system [BM] was valved in and the HPCI system was vented to verify the piping was i
full. The U-2 HPCI system was then declared operable at 2120 hours0.0245 days <br />0.589 hours <br />0.00351 weeks <br />8.0666e-4 months <br /> on October 9, 1996.
The system was declared operable even though the root cause of this event had not been determined because of the positive fill being provided by the keep fill system and the daily verification of this fill.
l 4
LER265\\9th0CC.WPF
LICENSEE EVENT REPOKr (LER) TEXT CONTINUATION Form Rw. 2.0 FACii,Y N AME (1)
D'CKF' ?".'HB 9P (2)
LER NUMBER (6)
PAGFth Year Sequensial.,.
,Jh.wm
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Number Number Quad Cities Unit Two 0l5 0l0l0l2l6l5 9l6 0l0l2 0l0 3 lOFl 0 l 6 i
TEXT Energy industry identification System (Elis) codes are idensd sd in the text as (XX)
During troubleshooting to determine the root cause of this event, a planned Limiting
- - l Condition for Operation (LCO) on the HPCI system was entered on October 12, 1996 at 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> when the pump suction was switched back to the CCST. The failure to vent could not be recreated during this troubleshooting and the system was again declared operable at 1820 hours0.0211 days <br />0.506 hours <br />0.00301 weeks <br />6.9251e-4 months <br /> on October 13, 1996. The HPC1 pump suction at this time was f
from the CCST and because the root cause had still not been determined, an increased frequency (daily) of venting the system was undertaken. This verified the system j
3 piping remained full up to the system isolation valve as required by the Tech Specs.
j An investigation team was formed on October 14, 1996 to determine the root cause.
This investigation team used a ". failure analysis method" to consider all possible root causes. These possible causes were then eliminated one by one through a combination of observations, testing and calculations until the one root cause was determined. The team completed their investigation on October 24, 1996. Daily venting of the HPCI discharge piping was discontinued at that time.
C.
APPARENT CAUSE OF THE EVENT The apparent cause of this event was a failure to properly vent the HPCI injection j
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piping downstream of the system isolation valve (2-2301-8) after maintenance in August 1996 on the system injection check valve (2-2301-7).
Refer to Figure 1 for a layout of the HPCI discharge piping high point.
Because QCOP 2300-1 "HPCI Preparation for Stand-by Operation" procedure did not provide steps for filling the section of discharge piping downstream of the system isolation valve, a Discreet Component Operation (DCO) war vritten to fill and vent this piping. The piping was filled and ventod by runnirj the HPCI cooling water pump with the discharge of the pump lined up to the "B" Feenw ater Header. The cooling water pump was run until water vented on the "B" Feed. der Header.
Since these vents are located below the high point of the HPCI discharge piping, the discharge piping was not completely filled. This improper venting left air in the piping downstream of the system isolation valve.
The system isolation valve, 2-2301-8, is opened on a quarterly frequency. The first time that it was opened after this improper venting was on October 8,1996 per QCOS 2300-6, " Quarterly HPCI System Power Operated Valve Test." When the system isolation valve was opened, the air trapped in the piping migrated to the upstream side of the 2-2301-8 system isolation valve since the upstream piping section was at a lower pressure than the downstream side.
Subsequently, on October 9, 1996 when QCOS 2300-09 was attempted, this trapped air prevented the system from venting properly even though there was a static head of water above the high point of the discharge piping.
LER265\\96W2.WPF
LICENSEE EVENT REPCIT (LER) TEXT CONTINUATION Form Rrv.2.0 1-ACl,Lif Y N AME (1)
WX3FY NWBER (2)
LER NUMBER g_
lPAGE Gi
,.,A Year %
t t a. at mm Number Number Quad Cities Urut Two 0l5l0l0l0l2l6l5 9l6 ol0l2 0l0 4 lOFl 0 l 6 TEXT Energy industry identification System (Ells) codes are idenufied in the text as (XXj The U-2 HPCI vent piping is hard piped to a six foot loop seal located about forty feet below the HPCI high point piping.
With this vent piping full of the air that was trapped in the HPCI discharge piping, six feet of static head could not be developed at the loop seal and water flow could not be established. When the HPCI discharge piping was completely evacuated of air during the cooling water pump run at about 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br /> on October 9,1996, continuous water flow was established through the vent piping.
This scenario was verified through conversations with hydraulic systems experts at General Electric Company.
D.
SAFETY ANALYSIS OF THE EVENT The consequences of this event are considered minimal. The amount of air trapped in the HPCI injection piping downstream of the system isolation valve was less than one cubic foot.
This estimate is based on the fact that it takes only 0.27 cubic feet to completely fill the HPCI vent piping and the system was successfully vented after a short, one minute, cooling water pump run on October 9, 1996. With only one cubic foot of air trapped in the system, based on engineering judgement, a significant water hammer event would not have occurred had the HPCI system injected.
Therefore, system piping integrity would have been maintained and the system was functional despite the trapped air and failure to vent.
Additionally, the Automatic Depressurization System (ADS)[RV] and the Low Pressure Coolant Injection (LPCI)[B0] systems were operable during this event and would also have provided protection for the fuel in the event of a Loss of Coolant Accident.
E.
CORRECTIVE ACTIONS
The corrective actions completed are:
1.
The U-2 HPCI discharge piping has been verified to be full of water to the system isolation valve (M02-2301-8).
2.
QCOS 2300-9, was completed following performance of QCOS 2300-6, thereby verifying no additional trapped air present in the HPCI piping downstream of the system isolation valve.
3.
It was verified that a similar problem did not exist on Unit 1 by ensuring that QCOS 2300-9, had been successfully completed following the performance of QCOS 2300-6.
4.
The root cause team report has been distributed to the Operating Department to ensure they understand the cause m this event.
5.
An engineering letter has been written to the Operating Department instructing them on the proper vent location for sy: tem venting. Additionally, this lettar included instructions on how to ensure that piping is completely filled if there is not a high point vent available.
LER265i96@2.WPF
LICENSEE EVFNT REPORT (LER) TEXT COtGINUATION Form Rev. 2.0 F AC41(V Mht u; DyNFT Ml'pDEP (?)
1 N NUMBER (6)
PAGE 0)
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Sequenuai Revisil l
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Number Number 0l0l2 0l0 5 lOFl 0 l 6 Quad Cities Unit Two 0l5l0l0l0l2l6l5 9l6
, TEXT Energy industry identi6 canon System (Elis) codes are idenn6ed in the text as (XXj Additional corrective actions to be completed are:
1.
Revise QCOP 2300-1, to ensure that the piping downstream of the system isolation valve is filled and vented after maintenance (that drains the piping). This will be completed by December 15, 1996. (NTS# 2651809600201, OP) 2.
Revise QCOS 2300-9, to include adequate acceptance criteria to detect the HPCI discharge piping is not completely full. This will be completed by December 15, 1996.
(NTS# 2651809600202, OP) 1 3.
Revise QCOS 2300-6, to require that the Vent Verification procedure be performed immediately after the valve surveillance.
During the investigation into this event, it was determined that there is a period of time during the valve j
surveillance that the CCST supply water is valved out to the HPCI pump suction.
Therefore, to ensure that the piping has remained full, it is necessary to perform the vent verification immediately after. This will be completed by December 15, 1996.
(NTS# 2651809600203, OP) 4.
Evaluate the Reactor Core Isolation Cooling System and Safe Shutdown Make-up Pump piping configuration and procedures to determine if similar conditions exist.
This will be completed by December 1, 1996.
(NTS# 2651809600204, SED) 5.
Revise procedures as necessary following NTS# 2651809600204. This will be completed by March 1,1997.
(NTS# 2651809600205, OP).
6.
Perfom a calculation to determine the minimum volume of trapped air in the HPCI system discharge piping which would cause an unacceptable water hammer. This will be completed by December 15, 1996.
(NTS# 2651809600206, SED) 7.
Submit a supplemental LER after the calculation in NTS# 2651809600205 is complete, if it is determined that the amount of trapped air present in the HPCI piping during this event weald have caused an unacceptable water hammer. This will be completed by January 15, 1997.
(NTS# 2651809600207, SED) 8.
This event will be covered during mods and lessons learned training for licensed and non-licensed operators. This will be completed by May 1,1997.
(NTS# 2651809600208, TRN).
LER265\\96\\002.w?F
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4 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Form Rev. 2.0 T AC'LITY N AME (1) jNY"'." NU\\4*ER (7)
LER NUMBER (6)
!PAGE(N I
Year Sequesi C '
'd' Ii2/l
~ ~ ' ' " * ~ ~ ~ '
Number Number Quad Cities Unit Two 0l5l0l0l0l2l6l5 9l6 0l0l2 0l0 6 lOFl 0 l 6 1
TEXT Energy industry identification System (Ell 5) codes are identified in the text as (XXj i
2 F.
PREVIOUS EVENTS Problem Identification Form #95-2301 identifies a similar event which occurred in August of 1995 on U-2 while the reactor was shutdown. The piping was filled prior to reactor start-up by running the HPCI tooling water pump. This is the only similar event identified during the root cause investigation. No other LERs, within the last two years, have been identified.
+
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G.
COMPONENT FAILURE DATA
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There was no equipment failure associated with this event.
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| | | Reporting criterion |
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| 05000254/LER-1996-001-07, :on 960303,B CR HVAC Sys Inoperable Due to Malfunctioning Relay Which Prevented Isolation of Air Handling Unit Fan.Ems Replaced Relay & Forwarded Damaged Relay to Engineering for Evaluation |
- on 960303,B CR HVAC Sys Inoperable Due to Malfunctioning Relay Which Prevented Isolation of Air Handling Unit Fan.Ems Replaced Relay & Forwarded Damaged Relay to Engineering for Evaluation
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000265/LER-1996-001, Forwards LER 96-001-00.Listed Commitments Made,Including Event Will Be Included as Part of Continuing Training for Both Licensed Operators & Engineering Dept | Forwards LER 96-001-00.Listed Commitments Made,Including Event Will Be Included as Part of Continuing Training for Both Licensed Operators & Engineering Dept | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000265/LER-1996-001-10, :on 960417,HPCIS Was Declared Inoperable Due to Procedural Deficiency Which Allowed Isolation of Turbine Exhaust Vacuum.Licensed Operators Have Been Trained on Procedure Changes |
- on 960417,HPCIS Was Declared Inoperable Due to Procedural Deficiency Which Allowed Isolation of Turbine Exhaust Vacuum.Licensed Operators Have Been Trained on Procedure Changes
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000265/LER-1996-002, Forwards LER 96-002-00.Licensee Revised Qcop 2300-1 to Ensure That Piping Downstream of Sys Isolation Valve Is Filled & Vented After Maint | Forwards LER 96-002-00.Licensee Revised Qcop 2300-1 to Ensure That Piping Downstream of Sys Isolation Valve Is Filled & Vented After Maint | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000265/LER-1996-002-10, :on 961009,HPCI Sys Declared Inoperable.Caused by Improper Filling & Venting After Aug 1996 Maint.Air Purged from Sys & line-up Procedure Revised to Ensure Filling & Venting of Piping |
- on 961009,HPCI Sys Declared Inoperable.Caused by Improper Filling & Venting After Aug 1996 Maint.Air Purged from Sys & line-up Procedure Revised to Ensure Filling & Venting of Piping
| | | 05000254/LER-1996-002-04, :on 960220,CR HVAC Sys Inoperable.Caused by Design Oversight Involving Toxic Gas Anlayzer.On 960223 Procedure Change to Qcop 5750-09, CR Ventilation Sys, Made to Allow for Operation of Booster Fans |
- on 960220,CR HVAC Sys Inoperable.Caused by Design Oversight Involving Toxic Gas Anlayzer.On 960223 Procedure Change to Qcop 5750-09, CR Ventilation Sys, Made to Allow for Operation of Booster Fans
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2) | | 05000265/LER-1996-003-01, :on 961112,Unit 2 LPCI Was Declared Inoperable. Caused by Failure of 2D RHR Pump Discharge Check Valve.Lpci Kf Pressure Was re-established within One Hour |
- on 961112,Unit 2 LPCI Was Declared Inoperable. Caused by Failure of 2D RHR Pump Discharge Check Valve.Lpci Kf Pressure Was re-established within One Hour
| | | 05000265/LER-1996-003-13, :on 961112,Unit 2 LPCI Was Declared Inoperable to 2D RHR Pump Discharge Check Valve Failure.Lpci Kf Was re-established within 1 Hour & Operability Determination Was Completed for PIF 96-3196 |
- on 961112,Unit 2 LPCI Was Declared Inoperable to 2D RHR Pump Discharge Check Valve Failure.Lpci Kf Was re-established within 1 Hour & Operability Determination Was Completed for PIF 96-3196
| | | 05000265/LER-1996-003, Forwards LER 96-003-00 Submitted IAW Requirements of 10CFR50.73(a)(2)(v)(D).Commitments Made by Ltr,Submitted | Forwards LER 96-003-00 Submitted IAW Requirements of 10CFR50.73(a)(2)(v)(D).Commitments Made by Ltr,Submitted | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000254/LER-1996-003-02, :on 960222,unanticipated Start Occurred on Unit 1 Edg.Caused by Inadequate Guidance within Procedure Qcmms 6600-03.Procedure Qcmms 6600-03 Will Be Revised to Clarify Switch Settings |
- on 960222,unanticipated Start Occurred on Unit 1 Edg.Caused by Inadequate Guidance within Procedure Qcmms 6600-03.Procedure Qcmms 6600-03 Will Be Revised to Clarify Switch Settings
| 10 CFR 50.73(a)(2) | | 05000254/LER-1996-003, Forwards LER 96-003-00 Re Unit 1 Start of Egd Due to Inadequate Procedure | Forwards LER 96-003-00 Re Unit 1 Start of Egd Due to Inadequate Procedure | 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000254/LER-1996-004-01, :on 960130,HPCI Sys Declared Inoperable Due to Gland Exhauster Breaker Trip.Hpci Gland Exhauster Breaker Replaced & Tested for Proper Operation & AOP Time Delay Bypass Switches in Starting Circuit Replaced |
- on 960130,HPCI Sys Declared Inoperable Due to Gland Exhauster Breaker Trip.Hpci Gland Exhauster Breaker Replaced & Tested for Proper Operation & AOP Time Delay Bypass Switches in Starting Circuit Replaced
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2) | | 05000254/LER-1996-005-07, :on 960203,B CR HVAC Sys Declared Inoperable Due to Outside Air Temp.Submitted TS Change Requesting That Heater Power Be Measured Instead of Differential Temp Across Heater to Determine Operability |
- on 960203,B CR HVAC Sys Declared Inoperable Due to Outside Air Temp.Submitted TS Change Requesting That Heater Power Be Measured Instead of Differential Temp Across Heater to Determine Operability
| | | 05000254/LER-1996-006, :on 960210,TS 3.0.A Incorrectly Invoked Due to Procedural & Operator Knowledge Deficiencies.Policy Statement Developed & Presented to Licensed Operator Re Expectations for Use & Entry Into TS 3.0.A |
- on 960210,TS 3.0.A Incorrectly Invoked Due to Procedural & Operator Knowledge Deficiencies.Policy Statement Developed & Presented to Licensed Operator Re Expectations for Use & Entry Into TS 3.0.A
| 10 CFR 50.73(a)(2)(i) | | 05000254/LER-1996-007-02, :on 960510,secondary Containment Damaged.Caused by Tornado.Initiated Shutdown,Ac Power Restored to Prompt Notification Sys & Station Blackout Bldg Cables Spliced Per Er 9603099 |
- on 960510,secondary Containment Damaged.Caused by Tornado.Initiated Shutdown,Ac Power Restored to Prompt Notification Sys & Station Blackout Bldg Cables Spliced Per Er 9603099
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) 10 CFR 50.73(e)(2)(vii) | | 05000254/LER-1996-008-02, :on 960607,TS Required Pressure Not Met During Local Leak Rate Testing.Caused by Procedural Deficiency. Procedure Changes Submitted & Check Valves Retested Using Appropriate Vent Paths |
- on 960607,TS Required Pressure Not Met During Local Leak Rate Testing.Caused by Procedural Deficiency. Procedure Changes Submitted & Check Valves Retested Using Appropriate Vent Paths
| 10 CFR 50.73(a)(2)(viii)(B) | | 05000254/LER-1996-008, Forwards LER 96-008,Rev 00 & Makes Following Commitment: Procedure Qcts 0600-34 Will Be Revised to Ensure Appropriate Vent Path Exists When Leak Rate Testing 2251(2)-81A/B Panels | Forwards LER 96-008,Rev 00 & Makes Following Commitment: Procedure Qcts 0600-34 Will Be Revised to Ensure Appropriate Vent Path Exists When Leak Rate Testing 2251(2)-81A/B Panels | 10 CFR 50.73(a)(2)(1) | | 05000254/LER-1996-009-01, :on 960523,noted Discrepancy in Cable Length Modeled in Existing Degraded Voltage Calculations.Caused by Design Analysis Deficiency.Performed Design Changes to Correct Voltage Problems |
- on 960523,noted Discrepancy in Cable Length Modeled in Existing Degraded Voltage Calculations.Caused by Design Analysis Deficiency.Performed Design Changes to Correct Voltage Problems
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) | | 05000254/LER-1996-010-02, :on 960611,discovered Installed Gallery Steel Configuration Lacked Required Cross Bracing.Caused by Deficiency in Original Design Configuration Control Process. Installed Gallery Cross Bracing |
- on 960611,discovered Installed Gallery Steel Configuration Lacked Required Cross Bracing.Caused by Deficiency in Original Design Configuration Control Process. Installed Gallery Cross Bracing
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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) 10 CFR 50.73(a)(2)(viii)(A) | | 05000254/LER-1996-011, Forwards LER 96-011-00.Circuit Mods & Procedure Changes Will Be Implemented Prior to Startup & Review of Sample of Assumptions from Safe Shutdown Repts & Calculations Investigated | Forwards LER 96-011-00.Circuit Mods & Procedure Changes Will Be Implemented Prior to Startup & Review of Sample of Assumptions from Safe Shutdown Repts & Calculations Investigated | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | | 05000254/LER-1996-011-02, :on 960708,determined Postulated Fire Could Have Caused Disabling Damage to Selected Motor Operated Valves.Caused by Inadequate Design Analysis Review.Movs Analyzed for Susceptibility to Single Failure |
- on 960708,determined Postulated Fire Could Have Caused Disabling Damage to Selected Motor Operated Valves.Caused by Inadequate Design Analysis Review.Movs Analyzed for Susceptibility to Single Failure
| | | 05000254/LER-1996-012-02, :on 960620,diesel Fuel Oil Transfer Piping Noted in Unanalysed Condition Due to an Incomplete Safety Classification Upgrade.Minor Mod Has Been Completed Which Removes Autofill Capability for Fire Pump Day Tanks |
- on 960620,diesel Fuel Oil Transfer Piping Noted in Unanalysed Condition Due to an Incomplete Safety Classification Upgrade.Minor Mod Has Been Completed Which Removes Autofill Capability for Fire Pump Day Tanks
| | | 05000254/LER-1996-012, Forwards LER 96-012-00,for Quad Cities Nuclear Power Station.Review Plan Will Be Prepared to Identify Open Items within Component Classification Program & Ensure Resolution of Items.Plan Will Be Completed by 970301 | Forwards LER 96-012-00,for Quad Cities Nuclear Power Station.Review Plan Will Be Prepared to Identify Open Items within Component Classification Program & Ensure Resolution of Items.Plan Will Be Completed by 970301 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000254/LER-1996-013-01, :on 960808,zebra Mussels Were Discovered on Fire Pump Suction Strainers.Caused by Inadequate Insp Frequency of Fire Pump Suction Strainers.Divers Removed & Cleaned Zebra Mussels from Fire Pump Suction Strainers |
- on 960808,zebra Mussels Were Discovered on Fire Pump Suction Strainers.Caused by Inadequate Insp Frequency of Fire Pump Suction Strainers.Divers Removed & Cleaned Zebra Mussels from Fire Pump Suction Strainers
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(B) | | 05000254/LER-1996-013, Forwards LER 96-013,Rev 0 IAW Requirements of 10CFR50.73(a)(2)(i)(B).Commitments Made by Ltr,Listed | Forwards LER 96-013,Rev 0 IAW Requirements of 10CFR50.73(a)(2)(i)(B).Commitments Made by Ltr,Listed | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000254/LER-1996-014, Forwards LER 96-014-00.All Personnel Will Be Briefed in Event by 961215,reinforcing Expectations to Initiate Procedure Changes When Needed | Forwards LER 96-014-00.All Personnel Will Be Briefed in Event by 961215,reinforcing Expectations to Initiate Procedure Changes When Needed | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000254/LER-1996-014-03, :on 960927,electrical Distribution Weekly Surveillance Did Not Document Voltage Verification Due to an Inadequate Procedure.Qcos 0005-06 Has Been Revised to Ensure Verification of Proper Voltages |
- on 960927,electrical Distribution Weekly Surveillance Did Not Document Voltage Verification Due to an Inadequate Procedure.Qcos 0005-06 Has Been Revised to Ensure Verification of Proper Voltages
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000254/LER-1996-015-01, :on 960816,HPCI Sys Jet Impingement Support Baseplate/Concrete Expansion Anchors Were Improperly Installed,Due to Ineffective Work Practices & QA Program. Review Will Be Completed |
- on 960816,HPCI Sys Jet Impingement Support Baseplate/Concrete Expansion Anchors Were Improperly Installed,Due to Ineffective Work Practices & QA Program. Review Will Be Completed
| 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) | | 05000254/LER-1996-015, Forwards LER 96-015-00.Commits to Completion Review of All Pipe Whip & Vibration Restraint Configuations by 961231 | Forwards LER 96-015-00.Commits to Completion Review of All Pipe Whip & Vibration Restraint Configuations by 961231 | 10 CFR 50.73(a)(2)(1) | | 05000254/LER-1996-016-01, :on 960823,secondary Containment Would Not Have Satisfied All UFSAR Requirements,Due to Siding Explosion Bolts Which Were Damaged by Either High Winds or Ineffective Work Pratices.Damaged Bolts Replaced |
- on 960823,secondary Containment Would Not Have Satisfied All UFSAR Requirements,Due to Siding Explosion Bolts Which Were Damaged by Either High Winds or Ineffective Work Pratices.Damaged Bolts Replaced
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000254/LER-1996-017, Forwards LER 96-017-00,for Quad Cities Nuclear Power Station.Review Plan Will Be Prepared to Identify Open Items | Forwards LER 96-017-00,for Quad Cities Nuclear Power Station.Review Plan Will Be Prepared to Identify Open Items | 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000254/LER-1996-017-01, :on 960825,manual Scram Taken During Reactor Startup When Reactor Water Level Increased Following Unplanned Opening of All Main Turbine Bypass Valves Occurred,Due to Inadequate Procedures.Procedures Revised |
- on 960825,manual Scram Taken During Reactor Startup When Reactor Water Level Increased Following Unplanned Opening of All Main Turbine Bypass Valves Occurred,Due to Inadequate Procedures.Procedures Revised
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2) | | 05000254/LER-1996-018, Forwards Supplemental Info Re LER 96-018-00,correcting Editorial Error | Forwards Supplemental Info Re LER 96-018-00,correcting Editorial Error | | | 05000254/LER-1996-018-01, :on 960903,TS Surveillance Requirements Were Misinterpreted Due to Conservative Misunderstanding of Requirement.Memo Was Written to Explain Which Min TS Surveillances Must Be Performed Re Mode Switch |
- on 960903,TS Surveillance Requirements Were Misinterpreted Due to Conservative Misunderstanding of Requirement.Memo Was Written to Explain Which Min TS Surveillances Must Be Performed Re Mode Switch
| 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) | | 05000254/LER-1996-019, Forwards LER 96-019 IAW Requirements of 10CFR50.73(a)(2)(ii)(B) & Discusses Listed Commitments | Forwards LER 96-019 IAW Requirements of 10CFR50.73(a)(2)(ii)(B) & Discusses Listed Commitments | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | | 05000254/LER-1996-019-01, :on 960904,main Steam Line Radiation Monitor Functional Test Was Not Performed within Frequency Established for TS When in Refueling Mode Due to Incomplete Documentation of TS Interpretation.Qcap 2300-11 Was Changed |
- on 960904,main Steam Line Radiation Monitor Functional Test Was Not Performed within Frequency Established for TS When in Refueling Mode Due to Incomplete Documentation of TS Interpretation.Qcap 2300-11 Was Changed
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000254/LER-1996-020, Forwards LER 96-020-00.Commitments Included in LER & Submitted | Forwards LER 96-020-00.Commitments Included in LER & Submitted | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000254/LER-1996-020-01, :on 960907,CR Emergency Filtration Sys Declared Inoperable.Caused by Operator Knowledge Weakness.Operators Declared CR Emergency Filtration Sys Inoperable & Entered 14-day LCO |
- on 960907,CR Emergency Filtration Sys Declared Inoperable.Caused by Operator Knowledge Weakness.Operators Declared CR Emergency Filtration Sys Inoperable & Entered 14-day LCO
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000254/LER-1996-021-01, :on 961011,B CR HVAC Sys Was Declared Inoperable Due to Crankcase Heater Power Supply Design Deficiency.Design Change Notice 9600380 Issued,Which Replaced Crankcase Heater W/Safety Related Heater |
- on 961011,B CR HVAC Sys Was Declared Inoperable Due to Crankcase Heater Power Supply Design Deficiency.Design Change Notice 9600380 Issued,Which Replaced Crankcase Heater W/Safety Related Heater
| | | 05000254/LER-1996-021, Forwards LER 96-021-00,for Quad Cities Nuclear Power Station.No Commitments Being Made | Forwards LER 96-021-00,for Quad Cities Nuclear Power Station.No Commitments Being Made | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000254/LER-1996-022-01, Extends Commitment Date for Completing Rev to Plant CR Dose Analysis of Record,Per LER 96-022-01 | Extends Commitment Date for Completing Rev to Plant CR Dose Analysis of Record,Per LER 96-022-01 | | | 05000254/LER-1996-023-01, :on 961124,CR Emergency Filtration Sys Failed to Maintain Required Airflow Due to Cognitive Personnel Error.Instrument Loop for Gauge Fi 1/2-5795-307 Calibr |
- on 961124,CR Emergency Filtration Sys Failed to Maintain Required Airflow Due to Cognitive Personnel Error.Instrument Loop for Gauge Fi 1/2-5795-307 Calibr
| | | 05000254/LER-1996-023, Provides Commitments Re LER 96-023.Predefined Model Work Request Which Initiates Perodic Maint Procedure Initiated | Provides Commitments Re LER 96-023.Predefined Model Work Request Which Initiates Perodic Maint Procedure Initiated | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000254/LER-1996-025, Forwards LER 96-025-00 Re Operability Calculations Performed on ECCS Suction Strainers W/Incorrect Head Loss Values | Forwards LER 96-025-00 Re Operability Calculations Performed on ECCS Suction Strainers W/Incorrect Head Loss Values | | | 05000254/LER-1996-025-01, :on 961220,discovered Original Value for Strainers Head Loss Incorrect.Cause Could Not Be Determined. Training Provided for Operators to Recognize Pump Cavitation During Design Basis Accidents |
- on 961220,discovered Original Value for Strainers Head Loss Incorrect.Cause Could Not Be Determined. Training Provided for Operators to Recognize Pump Cavitation During Design Basis Accidents
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) |
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