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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20045D9071993-06-24024 June 1993 Special Rept:From 930511-0611,7 Fire Detectors in Circuit FLP3-3 Out of Svc for 32 Days.Caused by Failed Fire Detector.Detector Replaced & Containment Air Temps Monitored Hourly ML20044G5371993-05-28028 May 1993 Rev to 910925,1231 & 930731 Special Repts,Correcting Administrative Error in Equipment Designation of Passive Triaxial Peak Accelerograph.All Other Info Remains Unchanged ML20024H3011991-05-22022 May 1991 Special Rept:On 910412,loose Parts Detection Sys Declared Inoperable Due to Repetitive Spurious Alarms & Inoperable pre-amplifier Unit.Loose Parts Monitoring Troubleshooting Currently Under Review ML20043F8251990-06-0808 June 1990 Special Rept:On 890425,gas Sample Drawn from PASS Indicated Reactor Gases Not Removed from Liquid Sample Rcs.Four RCS Liquid Samples Successfully Obtained & Two of 4 Samples Produced RCS Dissolved Gas Samples ML20042G8911990-05-0707 May 1990 Special Rept:On 900408,pressurizer Spray Valve Failed Open Causing Depressurization of Rcs.Caused by Equipment Malfunction.Feedback Arm Holding Screw on Pressurizer Spray Valves Replaced W/Longer Screws & Secured W/Locknuts ML20006C2141990-01-23023 January 1990 Special Rept:On 900102,radiation Monitor Removed from Svc & 7-day Time Allowed Exceeded During Calibr.Replacement Detector on Order Since Nov 1989 & Will Be Replaced & Recalibr ML20005G1281990-01-0202 January 1990 Supplemental Special Rept:On 890716,2 of 12 Loose Parts Monitor Channels Declared Inoperable When Monitors Alarmed Continuously.Caused by Malfunctions in Equipment Inside Containment Bldg.Replacement Scheduled for Next Outage ML19351C7341989-12-11011 December 1989 Special Rept:On 891110,turbine Electrical Trip Solenoid Valve Failed to Meet Surveillance Acceptance Criteria. Caused by Particulate Contamination in Secondary or Electronic Trip Valves.Valves Replaced W/Rebuilt Valves ML20024D0251983-07-15015 July 1983 Ro:On 830421,following Preliminary Manual Test Insertion (Mti)Test,Actuation Module Lights Came on Due to Module Energizing.Cause Unknown.Operators Stationed to Mitigate Problems or Actuation If Mti Required ML20052D7771982-04-29029 April 1982 Ro:On 820415,steam Generator 1 Increased Primary to Secondary Leakage Rate of 0.049 Gpm from Valve.Cause of Leak Rate Unknown.Increase Appears to Be Related to Plant Shutdowns/Trips Experience in Thermal Cycling ML20050A0081982-03-18018 March 1982 RO Re Steam Generator Tube Plugging as Specified in Tech Spec 4.4.5.1.4.Degradation Resulting in Tube Plugging Is Characterized by Localized Areas of Small Pits on Tube Outside Diameter.Investigation of Corrosion Cause Continues ML20040F6091982-01-29029 January 1982 RO:30-day Rept & 10-day Rept Per App B ETS Re Excessive Liquid Waste Discharge & Excessive Level of Radioactivity.Caused by Steam Generator Primary Side to Secondary Side Leakage.Doses within Bases for 2.5 Ci Limit ML20039E0401981-12-28028 December 1981 RO 50-336/81-41:discovered Abnormal Degradation of Reactor Coolant Sys Pressure Boundary,Specifically,Steam Generator Tubes.Frequency of Occurrence Primarily on Cold Leg Side. Two-wk Rept Will Be Submitted ML19350F1331981-06-17017 June 1981 RO 50-336/81-20:Dresser Industries Model 31739A Safety Valves Found to Have Less than Min Upstream Inside Diameter. Caused by Facility Design.Significant Impact Unlikely ML20004E3611981-06-0505 June 1981 RO 81-018/03L-0:insp of safety-related Pipe Hangers Inside Containment Containing Mechanical Snubbers Revealed Snubbers Installed on Small Diameter Piping.Caused by Listing Not Including Review of Diameter Piping ML20003B6491981-02-17017 February 1981 RO 50-336/81-8:as-built Hanger Review of Reactor Vessel Head Vent Piping Sys Determined Spring Can Type Hanger Was Installed Incorrectly,Resulting in Overstressing Socket Welded Joint.Spring Can Hanger Removed ML20002D6361981-01-13013 January 1981 Ro:On 801209,inservice Insp Revealed That Required Valve Operability Tests Not Performed During Third Calendar Quarter 1980.Valves Successfully Tested.Action Taken to Assure Timely Review of Valve Test Data ML19330C0201980-08-0101 August 1980 RO 80-26:water Seal for Piping Penetration in Refueling Water Storage Tank Pipe Tunnel Does Not Meet Design Requirements.Plugged Yard Storm Drain Caused Water Backup. Repairs to Water Seal Will Be Evaluated ML19323C3571980-05-0909 May 1980 RO 50-336/80-18:during Ongoing Hanger Base Plate Analysis Required by IE Bulletin 79-02,discovered That Several Svc Water Support Hangers Did Not Provide Factor of Safety Greater than Two.Repair Work on 12 Hangers Is Underway ML19294B6771980-01-23023 January 1980 Ro:On 791229,loss of Main Control Board Annunciators Occurred.Fourteen Power Supplies That Are Paralleled to Provide Voltages for Annunciator Electronics,Lamps & Field Contacts Failed.Surveillance Implemented ML19275A2751979-09-25025 September 1979 RO 50-336/79-27:during Engineering Review,Section of 4-inch Cast Iron Floor Drain Piping Passing Each Station Battery Was Found Not Supported in Accordance W/Design.Drain Working & Ductwork Removed 1993-06-24
[Table view] Category:LER)
MONTHYEARML20045D9071993-06-24024 June 1993 Special Rept:From 930511-0611,7 Fire Detectors in Circuit FLP3-3 Out of Svc for 32 Days.Caused by Failed Fire Detector.Detector Replaced & Containment Air Temps Monitored Hourly ML20044G5371993-05-28028 May 1993 Rev to 910925,1231 & 930731 Special Repts,Correcting Administrative Error in Equipment Designation of Passive Triaxial Peak Accelerograph.All Other Info Remains Unchanged ML20024H3011991-05-22022 May 1991 Special Rept:On 910412,loose Parts Detection Sys Declared Inoperable Due to Repetitive Spurious Alarms & Inoperable pre-amplifier Unit.Loose Parts Monitoring Troubleshooting Currently Under Review ML20043F8251990-06-0808 June 1990 Special Rept:On 890425,gas Sample Drawn from PASS Indicated Reactor Gases Not Removed from Liquid Sample Rcs.Four RCS Liquid Samples Successfully Obtained & Two of 4 Samples Produced RCS Dissolved Gas Samples ML20042G8911990-05-0707 May 1990 Special Rept:On 900408,pressurizer Spray Valve Failed Open Causing Depressurization of Rcs.Caused by Equipment Malfunction.Feedback Arm Holding Screw on Pressurizer Spray Valves Replaced W/Longer Screws & Secured W/Locknuts ML20006C2141990-01-23023 January 1990 Special Rept:On 900102,radiation Monitor Removed from Svc & 7-day Time Allowed Exceeded During Calibr.Replacement Detector on Order Since Nov 1989 & Will Be Replaced & Recalibr ML20005G1281990-01-0202 January 1990 Supplemental Special Rept:On 890716,2 of 12 Loose Parts Monitor Channels Declared Inoperable When Monitors Alarmed Continuously.Caused by Malfunctions in Equipment Inside Containment Bldg.Replacement Scheduled for Next Outage ML19351C7341989-12-11011 December 1989 Special Rept:On 891110,turbine Electrical Trip Solenoid Valve Failed to Meet Surveillance Acceptance Criteria. Caused by Particulate Contamination in Secondary or Electronic Trip Valves.Valves Replaced W/Rebuilt Valves ML20024D0251983-07-15015 July 1983 Ro:On 830421,following Preliminary Manual Test Insertion (Mti)Test,Actuation Module Lights Came on Due to Module Energizing.Cause Unknown.Operators Stationed to Mitigate Problems or Actuation If Mti Required ML20052D7771982-04-29029 April 1982 Ro:On 820415,steam Generator 1 Increased Primary to Secondary Leakage Rate of 0.049 Gpm from Valve.Cause of Leak Rate Unknown.Increase Appears to Be Related to Plant Shutdowns/Trips Experience in Thermal Cycling ML20050A0081982-03-18018 March 1982 RO Re Steam Generator Tube Plugging as Specified in Tech Spec 4.4.5.1.4.Degradation Resulting in Tube Plugging Is Characterized by Localized Areas of Small Pits on Tube Outside Diameter.Investigation of Corrosion Cause Continues ML20040F6091982-01-29029 January 1982 RO:30-day Rept & 10-day Rept Per App B ETS Re Excessive Liquid Waste Discharge & Excessive Level of Radioactivity.Caused by Steam Generator Primary Side to Secondary Side Leakage.Doses within Bases for 2.5 Ci Limit ML20039E0401981-12-28028 December 1981 RO 50-336/81-41:discovered Abnormal Degradation of Reactor Coolant Sys Pressure Boundary,Specifically,Steam Generator Tubes.Frequency of Occurrence Primarily on Cold Leg Side. Two-wk Rept Will Be Submitted ML19350F1331981-06-17017 June 1981 RO 50-336/81-20:Dresser Industries Model 31739A Safety Valves Found to Have Less than Min Upstream Inside Diameter. Caused by Facility Design.Significant Impact Unlikely ML20004E3611981-06-0505 June 1981 RO 81-018/03L-0:insp of safety-related Pipe Hangers Inside Containment Containing Mechanical Snubbers Revealed Snubbers Installed on Small Diameter Piping.Caused by Listing Not Including Review of Diameter Piping ML20003B6491981-02-17017 February 1981 RO 50-336/81-8:as-built Hanger Review of Reactor Vessel Head Vent Piping Sys Determined Spring Can Type Hanger Was Installed Incorrectly,Resulting in Overstressing Socket Welded Joint.Spring Can Hanger Removed ML20002D6361981-01-13013 January 1981 Ro:On 801209,inservice Insp Revealed That Required Valve Operability Tests Not Performed During Third Calendar Quarter 1980.Valves Successfully Tested.Action Taken to Assure Timely Review of Valve Test Data ML19330C0201980-08-0101 August 1980 RO 80-26:water Seal for Piping Penetration in Refueling Water Storage Tank Pipe Tunnel Does Not Meet Design Requirements.Plugged Yard Storm Drain Caused Water Backup. Repairs to Water Seal Will Be Evaluated ML19323C3571980-05-0909 May 1980 RO 50-336/80-18:during Ongoing Hanger Base Plate Analysis Required by IE Bulletin 79-02,discovered That Several Svc Water Support Hangers Did Not Provide Factor of Safety Greater than Two.Repair Work on 12 Hangers Is Underway ML19294B6771980-01-23023 January 1980 Ro:On 791229,loss of Main Control Board Annunciators Occurred.Fourteen Power Supplies That Are Paralleled to Provide Voltages for Annunciator Electronics,Lamps & Field Contacts Failed.Surveillance Implemented ML19275A2751979-09-25025 September 1979 RO 50-336/79-27:during Engineering Review,Section of 4-inch Cast Iron Floor Drain Piping Passing Each Station Battery Was Found Not Supported in Accordance W/Design.Drain Working & Ductwork Removed 1993-06-24
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217P5391999-10-25025 October 1999 Rev 0,Change 1 to Millstone Unit 1 Northeast Utils QA Program ML20217C8721999-10-0606 October 1999 Rev 21,change 3 to MP-02-OST-BAP01, Nuqap Topical Rept, App F & G Only B17896, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 1.With B17894, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 2.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 2.With B17898, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 3.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 3.With ML20216J4341999-09-24024 September 1999 Mnps Unit 3 ISI Summary Rept,Cycle 6 ML20211N8401999-09-0202 September 1999 Rev 21,change 1 to Northeast Utils QA TR, Including Changes Incorporated Into Rev 20,changes 9 & 10 B17878, Monthly Operating Rept for Aug 1999 for Mnps,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Mnps,Unit 1.With B17874, Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 3.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 3.With ML20216F5141999-08-31031 August 1999 Rept on Status of Public Petitions Under 10CFR2.206 B17879, Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 2.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 2.With ML20211G9631999-08-30030 August 1999 SER Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20211A6561999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 2 B17858, Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 3.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 3.With B17856, Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 1.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 1.With ML20210J0311999-07-21021 July 1999 Rev 20,Change 10 to QAP 1.0, Organization ML20210E5931999-07-19019 July 1999 Revised Page 16 of 21,to App F of Northeast Util QA Program Plan ML20210C5911999-07-15015 July 1999 Revised Rev 20,change 10 to Northeast Util QA Program TR, Replacing Summary of Changes ML20210A0411999-07-15015 July 1999 Rev 20,change 10 to Northeast Util QA Program Tr B17814, Special Rept:On 990612 B Train EDG Failed to Restart within 5 Minutes Following Completion of 18 Month 24 H Endurance Run Required by TS 4.8.1.1.2.g.7.Caused by Procedural inadequacy.Re-performed Hot Restart Via Manual Start1999-07-12012 July 1999 Special Rept:On 990612 B Train EDG Failed to Restart within 5 Minutes Following Completion of 18 Month 24 H Endurance Run Required by TS 4.8.1.1.2.g.7.Caused by Procedural inadequacy.Re-performed Hot Restart Via Manual Start ML20209D1881999-07-0101 July 1999 Rev 20,change 9 to Northeast Util QA Program Tr ML20196J2191999-06-30030 June 1999 SER Concluding That Licensee USI A-46 Implementation Program,In General,Met Purpose & Intent of Criteria in GIP-2 & Staff Sser 2 for Resolution of USI A-46 ML20211A6751999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 2,providing Revised Average Daily Unit Power Level & Operating Data Rept ML20196A8451999-06-30030 June 1999 Post Shutdown Decommissioning Activities Rept ML20209J0541999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Unit 2 B17830, Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 3.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 3.With ML20196K1791999-06-30030 June 1999 Addendum 6 to Millstone Unit 2 Annual Rept, ML20196J1821999-06-30030 June 1999 Rev 21,Change 0 to Northeast Utilities QAP (Nuqap) Tr B17833, Monthly Operating Rept for June 1999 for Millstone Power Station,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Power Station,Unit 1.With ML20195H1011999-06-11011 June 1999 Rev 20,change 8 to Northeast Utilities QAP (Nuqap) TR ML20207G6411999-06-0303 June 1999 Safety Evaluation Supporting Amends 105,235 & 171 to Licenses DPR-21,DPR-65 & NPF-49,respectively ML20211A6631999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 2,providing Revised Average Daily Unit Power Level,Operating Data Rept & Unit Shutdowns & Power Reductions B17808, Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 3.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 3.With ML20211B7351999-05-31031 May 1999 Cycle 7 Colr B17804, Monthly Operating Rept for May 1999 for Mnps,Unit 2.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Mnps,Unit 2.With B17807, Monthly Operating Rept for May 1999 for Mnps,Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Mnps,Unit 1.With ML20209J0661999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Millstone Unit 2 ML20206M4631999-05-11011 May 1999 Safety Evaluation Supporting Alternative Proposed by Licensee to Perform Ultrasonic Exam on Inner Surface of Nozzle to safe-end Weld ML20206J8351999-05-0707 May 1999 Rev 20,Change 7 to QAP-1.0, Northeast Utls QA Program (Nuqap) Tr ML20206G6221999-05-0404 May 1999 SER Accepting Util Request to Apply leak-before-break Status to Pressurizer Surge Line Piping for Millstone Nuclear Power Station,Unit 2 B17782, Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station,Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station,Unit 1.With ML20205R3531999-04-30030 April 1999 Addendum 4 to Annual Rept, B17775, Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station Unit 3.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station Unit 3.With ML20205K6141999-04-30030 April 1999 Non-proprietary Version of Rev 2 to Holtec Rept HI-971843, Licensing Rept for Reclassification of Discharge in Millstone Unit 3 Spent Fuel Pool ML20206E2971999-04-30030 April 1999 Rev 1 to Millstone Nuclear Power Station,Unit 2 COLR - Cycle 13 B17777, Monthly Operating Rept for Apr 1999 for Millstone Unit 2. with1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Unit 2. with ML20205Q5891999-04-0909 April 1999 Rev 20,change 6 to QAP-1.0,Northeast Utils QA Program TR ML20205R8751999-04-0909 April 1999 Provides Commission with Staff Assessment of Issues Related to Restart of Millstone Unit 2 & Staff Recommendations Re Restart Authorization for Millstone Unit 2 ML20206T3991999-03-31031 March 1999 First Quarter 1999 Performance Rept, Dtd May 1999 B17747, Monthly Operating Rept for Mar 1999 for Millstone Nuclear Power Station,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Millstone Nuclear Power Station,Unit 1.With 1999-09-30
[Table view] |
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p ,U.S. Nuclear Regulatory Commission Attn: Document Control. Desk Washington, D.C. 20555, Gentlemen:
Millstone Nuclear Power Station, Unit No. 3 y- Failure of Pressurizer Spray Valve
- This. event is being submitted-as a Special Report since the event is '
7 . considered-to be of sufficient interest to warrant a report. However, none
, .of'the reporting criteria of 10CFR50.72 or 10CFR50.73 apply.
-On April 8, 1990,:at 1632. hours,;with the plant in. Mode 3, Hot' Standby, 555 _
[
degrees Fahrenheit and 2250 psia, the Number 1 Pressurizer Spray Valve (3RCS*PCV455B) failed open, causing a depressurization of the Reactor .
Coolant System ' (RCS) . . Attempts by the control room opcrators to close the valve failed. The Number 1 Reactor Coolant Pump was stopped, significantly
- reducing the: spray. flow through the failed open valve, and thereby reducing ' *
.the rate'of depressurization.. As the RCS depressurized, temperature 1in the
-RCS was reduced to maintain adequate subcooling. . Operations and Instrument 1
& Contro1 (I&C). personnel entered Containment at approximately 2030 hours0.0235 days <br />0.564 hours <br />0.00336 weeks <br />7.72415e-4 months <br /> ,
and. caused the valve to fail closed by isolating the air supply to the ;
valve.. The plant was then stabilized at 385 degrees Fahrenheit and 450 psia, a
The root cause of this event was equipment malfunction. . Investigation by ,
4 -I&C personnel revealed that the holding screw for the feedback arm of the L -valve positioner had loosened and fallen out of the valve bracket. This i V- Scaused the valve t.o fail open. The Pressurizer spray valves use a model
, AP4 Bailey positioner to control valve position. .A survey of other
. Westinghouse plants revealed two other instancras of Bailey positioner
@ failures causing. valves to fail open. +
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Operator response to this event was guided by plant Operating Procedure !{
OP 3208,. Plant Cooldown. In addition, Emergency Operating Procedure *
(EOPs) contain-guidance on- responding to a failed open Pressurizer Spray Valve. .Even though the entry conditions were not met for entering any of l 4 -
the EOPs, the guidance; contained in them were used.- .An uncontrolled depressurization-of the RCS from a failed open Pressurizer Spray valve is bounded in the accident analysis.for Millstone 3 by an uncontrolled l depressurization from an inadvertent opening-of.a Pressurizer Safety-Valve. 1 LTherefore, this event did not place the plant in an unanalyzed condition, nor was_the plant outside its design basis, and there' was no.significant L impact to public safety. y To prevent the failure that led to this event from recurring, the feedback f
" arm holding screw on both the Number 1 and Number 2 Pressurizer Spray; O ; Valves were replaced with longer screws, and secured with locknuts. This-E action-is consistent with corrective action taken at' other plants where'a y similar_ problem has occurred. Since this is the first instance were an uncontrolled depressurization of the RCS has occurred due to a failure of a
- Pressurizer Spray Valve, and since the corrective action should prevent'his
' type of failure from-recurring, no further action'is warranted or deemed
~
y, e necessary.
The licensee contact for this Special Report is Jeffry Langan, who may be-reached at (203) 447-1791, Ext. 5544.
Very truly yours,-
l NORTHEAST NUCLEAR ENERGY COMPANY j s
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Step e# E. Scace Director, Millstone Station SES/JAL:bjo t cc: T. T. Martin, Region I Administrator-W. J. Raymond, Senior Resident Inspector, Millstone Unit Nos. 1, 2 and 3 D. H. Jaffe, NRC Project Manager, Millstone Unit No. 3 4
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HARTFORD. CONNECTICUT 06141-0270 L L J "JZ',%fl',,CO'!!"ll. 1203) 665 5000 May 7, 1990 f MP-90-454- !
Docket No. 50-423 i
U.S. Nuclear Regulatcry Co:w.ission i
' Attn: Document Control. Desk Washington, D.C. 20555 Gentlemen:
Millstone Nuclear Power Station, Unit No. 3 Failure of Pressurizer Spray Valve This event is being' submitted as a Special Report since the event.is considered to be of sufficient interest to warrant a report. However,- none u of the reporting criteria of 10CFR50.72 or 10CFR50.73 apply. .!
On April 8, 1990, at 1632 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20976e-4 months <br />, with the plant in Mode 3, Hot Standby, 555 '
. degrees Fahrenheit and 2250Lpsia, the Number 1 Pressurizer Spray Valve
- (3RCS*PCV455B) failed open, causing a- depressurization of the Reactor il Coolant System (RCS) . Attempts by the contrcl room operators to close the valve ~ failed. The Number 1 Reactor Coolant Pump was stopped, significantly-reducing the spray flow through the , failed' open valve, and. thereby reducing
-the rate of depressurization. As'the RCS depressurized, temperature in the RCS was reduced to maintain adequate subcooling. Operations and Instrument i
& Control- (I&C) personnel entered Containment 'at approximately 2030 hours0.0235 days <br />0.564 hours <br />0.00336 weeks <br />7.72415e-4 months <br /> .
and caused the valve to fail closed by isolating the air supply to.the !
valve. The plant was then stabilized at 385. degrees Fahrenheit and 450 '
psia.
The root cause of this event was equipment malfunction. Investigation by I&C personnel revealed that the. holding screw for the feedback arm of the "
' valve positioner had loosened and fallen out of the valve bracket. This
. caused the valve to fail open. .The Pressurizer spray valves use a model :
AP4 Bailey positioner to control valve position. A survey of other Westinghouse plants revealed two other instances of Bailey positioner I failures causing valves to fail open.
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6-
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3
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- 2-r j Operator response to this event was guided by plant Operating Procedure OP 3208, Plant Cooldown. In addition, Emergency Operating Procedure (EOPs) contain guidance on responding to a failed open Pressurizer Spray Valve. Even though the entry conditions were not met for entering any of ,
the EOPs, the guidance contained in them were used. An uncontrolled depressurization of the RCS from a failed open Pressurizer Spray valve is bounded in the accident analysis for Millstone 3 by an uncontrolled depressurization from an inadvertent opening of a Pressurizer Safety Valve.
Therefore, this event did not place the plant in an unanalyzed condition,_
nor was the plant outside its design basis, and there was no significant impact to public safety.
To prevent the failure that led to this event from recurring, the feedback arm holding screw on both the Number 1 and Number 2 Pressurizer Spray Valves were replaced with longer screws, and secured witn locknuts. This action is consistent with corrective action taken at other plants where a similar problem has occurred. Since this.is the first: instance were an.
uncontrolled depressurization of the RCS has occurred due to a failure of a .
Pressurizer Spray Valve, and since the corrective action should prevent his I type of failure from recurring, no further action is warranted or deemed necessary.
The licensee contact for this Special Report is Jeffry Langan, who may be reached at (203) 447-1791, Ext. 5544.
1 Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY t&
Step e E. Scace Director, Millstone Station SES/JAL:bjo cc: T. T. Martin, Region I AdT.iniht:retor W. J. Raymond, Senior hesibent !cupector, Millstone Unit Nos.1, 2 and 3 D. H. Jaffe, NRC Projbet Manager, Millstone Unit No. 3 I
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