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CONNECTICUT YANKEE ATOMIC POWER' COMPANY HADDAM NECK PLANT-Ei RRN1
- EAST HAMPTON,CT 06424-9341 f
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March 2, 1990 Re: 10CFR50.73 (a) (2) (v) (D) e t
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- - U.
S. Nuclear Regulatory Commission l Document Control Desk-Washington, D. C. 20555 4
Reference:
Facility Operating License No. DPR-61 Docket No. 50-213
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Reportable-Occurrence LER 50-213/90-001-00 Gentlemen:
This letter forwards the Licensee Event Report 90-001-00,-required
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.to be-submitted, pursuant to the requirements of Connecticut 1
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Yankee Technical Specifications.
l Very.truly yo s,
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fr Donald B.
Miller, Jr.
E Station Superintendent DBM:/dl 4
Attachment:
LER 50-213/90-001-00 l-cc:
- - Mr.
William T.
Russell
' Regional Administrator, Region I 475 Alienable Road King of Prussia, PA 19406 J. T.
Shedlosky l,
Sr. Resident' Inspector Haddam Neck t.
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.e i.aC Fe.m att U.S. NUCLE All 6.5EULATO AY C0testBION APPROVID Dept ho 3106410s UCENSEE EVENT REPORT (LER)
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PAWW (31 HaMam Neck 0 l 5 l 0 l 0 l 01211 13 1l0Fl013 18148 tes rocian Deficiency Identified In Service Water Filters IVENT DATI tEl LER NUMBER tel REPORT DATI (7i OTHth F ActLITil8 INVOLVED 05)
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MONTH DAY YEAR F ACILITv hAMas DOCKf Y NUMetRtsi 0l610l010l l l O!2 O! 2 9l0 9l0 O!0 l 1 0l0 0l3 0 l2 9l 0 0 Istol0gog l l THIS R$ PORT IS SUBMITTED PUR$VANT TO THE REQUIREMENTS OF 10 CPR 5 (Caece ea. ** me e e' fa. fe8/**ra#11118 OPE R ATING MODE m 00.73teH2Hwi 73.714tl
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NAME-TILIPHONE NUMSER AREA CODE n _ w. nrngn. rnaineer 21013 216 f7 l-12 1 51516 COMPLETE ONE LINE FOR E ACH COMPONENT F AILURE D60ChlSED IN THit REPORT 1136 j8dC-MAN Rt*0RTA E TU
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I I I I I I SUPPLEMENTAL REPORT E MPECTED 114l MONTH DAY YEAR SUSM14SiON 188 til res. comp.ru EM9ECTED SV8MisstON CA Til NO l
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r ABSTRACT On February 2, 1990 at approximately 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> with the plant shutdown in Mode 6 (refueling) an engineering evaluation revealed that it would be possible for a failure (i.e.,
clogging or breaking) of the Service Water filters to render the Containment Air Recirculation Fans inoperable following a Design Basis Loss-of-Coolant accident.
The root cause of this event is a design error which occurred during the original construction of the plant.
Corrective Action consists of installing bypass lines around both filters, which will have the capability of remote operation prior to plant startup.
This event is being reported under 10CFR50.73 (a) (2) (v) (D) since this condition alone could have prevented the fulfillment of a safety function of a system needed to mitigate the consequences of an accident.
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UCENSEE EVENT C.EPORT (LER) TEXT C NTINUATION t.rer.ovio ove no sioo-oioa EXPIRES: s'31/98 NM 88AIII hl DOCKET NUuttR (2p LtA NUMBER 161 PA06 (3)
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BACKGROUND INFORMATION
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'The two Service Water filters (EIIS Code: FLT) are part of the Containment Air Recirculation (CAR) Fan Cooling System (EIIS Code:
BK) which is required to reduce Reactor Containment pressure after a-design basis accident (DBA).
During normal operations one
~ filter is inservice and the other in standby, These filters remove particulate matter from the cooling water to the CAR fan cooling coils, motor coolers and spent fuel pit cooling system.
'The filters also have a backwash system which runs continuously to extend the time between filter plugging.
During normal operations-j when the in service filter becomes clogged, as evidenced by a low-flow alarm in the CAR fan coolers, an operator is dispatched to manually switchover to the standby unit thus isolating the clogged filter for cleaning,- The existing backwash system is not safety-related, and therefore it is not credited as being available post-i accident.
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EVENT DESCRIPTION
On February 2, 1990, at approximately 1416 with the plant shutdown
'in Mode 6 (refueling), an engineering evaluation of a suspected 4
design deficiency of the Service Water Adam-Filters revealed that i
it would be possible for a failure (i.e.,
clogging or breaking) of the inservice filter to render the CAR fans inoperable following a Design Basis Loss-of-Coolant accident -(LOCA).
The identified failure mode results from the use of:a non-safety grade backwash filter cleaning system, and the inability of an~ operator to access
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the filter area to perform a manual switchover to the clean filter i
due to excessive radiation levels following a LOCA.
Based on historical information the plugging of the inservice filter might-occur before the CAR fans are able to remove sufficient heat from the containment atmosphere.
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CAUSE OF THE EVENT
The root cause of this condition is a design error which occurred during the original construction of the Haddam Neck Plant.
The failure mode described within was not recognized when the plant was originally designed.
The discovery of this design deficiency was part of the continuing investigation of the service water system to ensure that single failure conditions do not exist
'elsewhere.
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W 9ese M U.S NUCLE A% G_lOULATORY COMMIN60N
LICENSEE EVENT REPORT (LER) TEXT CONTINUATitN svaoveo ous so. sino-oio.
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'fWT Fmee ese 4 segueuW, amp esifumar NRC Mm AS4 W (17)
SAFETY ASSESSMENT
This event is being reported under 10CFR50.73 (a) (2) (v) (D) since this condition alone could have prevented the fulfillment of a safety function of a system needed to mitigate the consequences of an accident.
Without an operable backwash system, the filters will continue to clog at an increasing rate.
Discussions with the manufacturer-have indicated that the filters can clog fully.
Clogging of the filters will result in a continuous decrease in the cooling. water flow to the CAR fans, with a corresponding decrease in the CAR fan heat removal rate.
Insufficient heat removal from containment, following a LOCA, could result in the i
temperature and pressure limits of the equipment qualification to t
be exceeded.
In addition,-with severe cloggage, the integrity of the containment structure could be challenged.
CORRECTIVE ACTION
The installation of safety grade bypass lines around each filter is planned' prior to startup.
The bypasses will utilize remote operated valves to allow for manual bypassing of the filters without having to accees the area.
ADD.'.TIONAL INFORMATION None
SIMILAR EVENTS
None i
M' e u s opo seeo.o.e24.sas,4se ~
gone mea
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| 05000213/LER-1990-001, :on 900202,engineering Evaluation Revealed That Failure of Svc Water Filters May Occur Rendering Containment Air Recirculation Fans Inoperable.Caused by Design Error. Bypass Lines Installed Around Both Filters |
- on 900202,engineering Evaluation Revealed That Failure of Svc Water Filters May Occur Rendering Containment Air Recirculation Fans Inoperable.Caused by Design Error. Bypass Lines Installed Around Both Filters
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000213/LER-1990-002, :on 900214,discovered That No Fire Watch Established for Temporarily Sealed Penetration Fire Barrier. Caused by Past Procedure Deficiencies W/Penetration Fire Seal Program.Fire Watch Established |
- on 900214,discovered That No Fire Watch Established for Temporarily Sealed Penetration Fire Barrier. Caused by Past Procedure Deficiencies W/Penetration Fire Seal Program.Fire Watch Established
| 10 CFR 50.73(a)(2)(1) | | 05000213/LER-1990-003, :on 900329,determined That Emergency Diesel Generator & Containment Air Recirculation Fan Cooling Water Flow Rates Did Not Meet Min Acceptance Criteria.Caused by Piping Corrosion Buildup.Piping Cleaned |
- on 900329,determined That Emergency Diesel Generator & Containment Air Recirculation Fan Cooling Water Flow Rates Did Not Meet Min Acceptance Criteria.Caused by Piping Corrosion Buildup.Piping Cleaned
| | | 05000213/LER-1990-004, :on 891207,feedwater Regulator Bypass Check Valves Failed Surveillance Testing Due to Valve Chatter. Caused by Leakage of Downstream Flow Control Bypass Valves. Design Review Conducted |
- on 891207,feedwater Regulator Bypass Check Valves Failed Surveillance Testing Due to Valve Chatter. Caused by Leakage of Downstream Flow Control Bypass Valves. Design Review Conducted
| | | 05000213/LER-1990-005, :on 900606,containment Isolation Actuation Sys Spuriously Actuated.Caused by Improper Design Document Control During Initial Const.Design Documents Will Be Corrected |
- on 900606,containment Isolation Actuation Sys Spuriously Actuated.Caused by Improper Design Document Control During Initial Const.Design Documents Will Be Corrected
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000213/LER-1990-006, :on 900611,alarm Condition Identified on Local Fire Detection Panel FDS-1.Caused by Fouling of Detector. Continuous Fire Watch Established & Detector Replaced |
- on 900611,alarm Condition Identified on Local Fire Detection Panel FDS-1.Caused by Fouling of Detector. Continuous Fire Watch Established & Detector Replaced
| 10 CFR 50.73(a)(2)(1) | | 05000213/LER-1990-007, :on 900626,determined That Postulated Heating Steam Sys Could Affect safety-related Equipment.Caused by Incorrect Conclusion Drawn from High Energy Line Break Study in 1973.Heating Steam Sys Piping Modified |
- on 900626,determined That Postulated Heating Steam Sys Could Affect safety-related Equipment.Caused by Incorrect Conclusion Drawn from High Energy Line Break Study in 1973.Heating Steam Sys Piping Modified
| 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000213/LER-1990-008, :on 900709,engineering Evaluation Determined That Design Deficiency Existed That Could Disable Both Centrifugal Charging Pumps During Hypothetical Loca.Check Valves Installed in Each Charging Pump |
- on 900709,engineering Evaluation Determined That Design Deficiency Existed That Could Disable Both Centrifugal Charging Pumps During Hypothetical Loca.Check Valves Installed in Each Charging Pump
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000213/LER-1990-010, :on 900727,actuation of Reactor Protection Sys Occurred Due to Test Procedure Used at Inappropriate Time. Caused by Failure to Identify Test Procedure Incompatibility W/New Tech Spec Requirements.Procedure Revised |
- on 900727,actuation of Reactor Protection Sys Occurred Due to Test Procedure Used at Inappropriate Time. Caused by Failure to Identify Test Procedure Incompatibility W/New Tech Spec Requirements.Procedure Revised
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(1) | | 05000213/LER-1990-011, :on 900802,determined Potential for Loss of Sump Recirculation Due to Bus Undervoltage.Caused by Deficiency in Technical & Safety Review Process for Eops. Bus Undervoltage Setpoints Will Be Lowered |
- on 900802,determined Potential for Loss of Sump Recirculation Due to Bus Undervoltage.Caused by Deficiency in Technical & Safety Review Process for Eops. Bus Undervoltage Setpoints Will Be Lowered
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000213/LER-1990-012, :on 900802,charging Pump a Declared Inoperable When Determined That Pump Potentially Gas Bound.Cause Unknown.Operating Procedures Reviewed to Determine Adequacy to Prevent Gas Binding of Pumps |
- on 900802,charging Pump a Declared Inoperable When Determined That Pump Potentially Gas Bound.Cause Unknown.Operating Procedures Reviewed to Determine Adequacy to Prevent Gas Binding of Pumps
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000213/LER-1990-013, :on 900806,engineering Evaluation Determined That Installation of Incorrect O-ring Matl in Four safety- Related motor-operated Valves Could Render Valves Inoperable.Caused by Procedural Inadequacies |
- on 900806,engineering Evaluation Determined That Installation of Incorrect O-ring Matl in Four safety- Related motor-operated Valves Could Render Valves Inoperable.Caused by Procedural Inadequacies
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000213/LER-1990-014, :on 900806,incorrect Torque Switch Settings Discovered on RCS Loop Isolation Valves.Caused by Inadequate Setpoint Control.Torque Switches Set to Mfg Recommended Setting |
- on 900806,incorrect Torque Switch Settings Discovered on RCS Loop Isolation Valves.Caused by Inadequate Setpoint Control.Torque Switches Set to Mfg Recommended Setting
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000213/LER-1990-017, :on 900902,auxiliary Feedwater Sys Actuated While Troubleshooting Feed Flow Recorder.Caused by Personnel Error.Individuals Involved Counseled |
- on 900902,auxiliary Feedwater Sys Actuated While Troubleshooting Feed Flow Recorder.Caused by Personnel Error.Individuals Involved Counseled
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000213/LER-1990-018, :on 900903,manual Plant Trip Occurred Due to Feedwater Control Valve Failing Open.Caused by Improper Part Fabrication at Factory.Stemplug Assemblies on Feedwater Regulating Valves Modified W/Welded Joint |
- on 900903,manual Plant Trip Occurred Due to Feedwater Control Valve Failing Open.Caused by Improper Part Fabrication at Factory.Stemplug Assemblies on Feedwater Regulating Valves Modified W/Welded Joint
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000213/LER-1990-020, :on 901019,manual Trip Occurred Due to Condensate Pump Degradation & Procedural Noncompliance |
- on 901019,manual Trip Occurred Due to Condensate Pump Degradation & Procedural Noncompliance
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000213/LER-1990-021, :on 901002,surveillance Frequency Exceeded for Turbine Bldg Heat Detector Test |
- on 901002,surveillance Frequency Exceeded for Turbine Bldg Heat Detector Test
| 10 CFR 50.73(a)(2)(1) | | 05000213/LER-1990-022, :on 901012,error Identified in Calibr of Auxiliary Feedwater Flow Transmitters |
- on 901012,error Identified in Calibr of Auxiliary Feedwater Flow Transmitters
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000213/LER-1990-030, :on 901125,card Reader for Central Alarm Station Door Discovered Inoperable.On 901126,discovered That Door Lacked Required Fire Watch.Caused by Personnel Error. Fire Watch Posted |
- on 901125,card Reader for Central Alarm Station Door Discovered Inoperable.On 901126,discovered That Door Lacked Required Fire Watch.Caused by Personnel Error. Fire Watch Posted
| 10 CFR 50.73(a)(2)(1) | | 05000213/LER-1990-031, :on 901130,discovered That 18-month Surveillance Frequency for Insp of Fire Penetration Seals Due on 890507 Not Completed Until 900404.Caused by Personnel Error.Personnel Counseled |
- on 901130,discovered That 18-month Surveillance Frequency for Insp of Fire Penetration Seals Due on 890507 Not Completed Until 900404.Caused by Personnel Error.Personnel Counseled
| 10 CFR 50.73(a)(2)(1) | | 05000213/LER-1990-032, :on 901227,all Four Containment Air Recirculation Fans Declared Inoperable Due to Fouling of Both Svc Water Filters.Caused by Excessive Silt Suspension in Connecticut River.Guidance Provided |
- on 901227,all Four Containment Air Recirculation Fans Declared Inoperable Due to Fouling of Both Svc Water Filters.Caused by Excessive Silt Suspension in Connecticut River.Guidance Provided
| 10 CFR 50.73(a)(2)(1) |
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