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LER-1977-020, Forwards LER 77-20/04T-0 |
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| 2891977020R00 - NRC Website |
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DISTRIBUTION:
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UNITED STATES Rdg.
NUCLEAR REGULATORY COMMISSION RIngram WASHINGTON. D.C. 20555 August 29, 1977 Docket No.
50-289 Addressees: See next page
Subject:
'Ibe following documents coocerning our review of the subject facility are transmitted for your information:
Notice of Receipt of Application.
Draft / Final Environmental Statement, dated Safety Evaluation, or Supplement No.
. dated Notice of Hearing on Application for Construction Permit.
Notice of Consideration of Issuance of Facility Operating License.
App c.ation and Safety Analysis Report, Vol.
Amendment No.
to Application /SAR, dated Construction Permit No. CPPR-
. dated Facility Operating License No. DPR.
, dated Amendment No.
to CPPR-or DRR-
, dated X'
Other: Licensee Everit Roonet Rn 8;n '>Ao/77 2nfar O
Division of Ooeratino Reactors, ORBf4 Office of Nuclear Reactor Regulation
Enclosures:
As stated cc:
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METROPOLITAN EDISON COMPANY sussiman cr atianuusucur:urus acnonna..
TELEPHONE 215 - 923 2501 POST OFFICE COX 542 READING. PENNSY LVANI A 19C03 kagust 12, 1977 GQ.L 1013
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Mr. B. H. Grier, Director Office of Inspecticns and Inforcement, Regicn 1 J g ",
U. S. IIuclear Regula cry Cc =ission
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631 Park Avenue
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King of Prus ta, Pennsylvania 19hC6
Dear Sir:
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Docket !!c. 50-269 Operating license :!c. JFE-50 In acecrdance with the Technical Specifications of cur Three Mile Island I!uclear Statien Unit 1 (T.E-1), ve re reporting the fcileving reporticle occurrence.
This repcrt is being sut=itted late per the telephone conversatien with Mr. Streeter on kagust 10, 1977.
is late lue to a clerical errer.
To prevent a future cecurrence This report of this tree an additional positive check-off has been added to the tracking system.
(1) Repcr :Iu=ber: 77-20/kT Dpf0 ]@p p, p o&
'A. W M G s' d
udi 2 u J (2a) Required Reper: Date: 6/2/77 a
(2b) Este Of Cecurrence:
7/19/77
'n.ree /ile :sland :iuc' c atica - Unit 1 (3) Facility:
(i)
Identifica: ice of Occurrence:
C Statien Eiver h;er Discha ge Te=perature exceedei 3 F Title:
belev inlet te perature.
A reperti::le,ccrrence as defined by Irviren=ertal Tjpe:
Technical Specifics:icn; 2.1.1(1) in tha: the sta:icncf river va:er discharge :enpert: re exceeded to lini:
3c? belev the inle river vster tempera: re.
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~7 9 <- v'/ O C u/ 9 i
Mr.'3. H. Grier, Dire
' Auguet 12, 197J GQL 1013 (5) Conditiens Prior to Cccurrence:
Fever:
Cere: 251? MWt Elec: 804 sWe Gross 0
RC Flev:
lh5 x 10 lbs/hr RO Fressure:
2166 psig 0
RC Te=p:
579 F FRZR Level 223 inches 0
FRZR Te=p:
650 F (6) Description of Occurrence:
On 7/19/77, while operating at steady state cenditiens, a ster = frcnt passed through the area at apprcximately 1635 hours0.0189 days <br />0.454 hours <br />0.0027 weeks <br />6.221175e-4 months <br /> reculting in a rapid increase in vind velocity frc= 5 to 35 =ph and a rapid decrease in a bient air te=perature frca 9h0F to 52cF.
The effect of thin transient was to decrease the river vater discharge te=perature.
Frier to this transient, river water AT vas being =aintained between -1 and -2cy 37 go 333ure ec=pliance with ETS 2.1.a(3) since inlet river water temperature v C
above 67 F.
At approxi=ately 1637, the Centrol Rec Opera:cr shut-off the A and 3 MDCT fans to decrease the effect of the stcrs frcnt en the rivt.r water AT.
Despite this ccrrective reasure, the river vater LT C
exet eded the 3 F LT li=it for about ten (10) minutes, reaching a taxinu=
O f.'. 907 c' "a.
(7) Apparent Cause of Occurrence:
It has been determined that the cause of this cecurrence was due to a stora frcnt passing thrcush the area.
(8) Analysis of Occurrence:
It has been deter =ined that this cecurrence did not constitute a threat to the health and safety of the public, ner did it cause any env'----=
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damage in that the negative temperature differential transient was nc:
large encush, ner did the cenditien exis; icng encush to significantly alter the anbien temperature cf the river.
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August 12, 1977
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3-Mr. B. H. Grier, Directt GQL 1013 (9) Corrective Action:
Innediate:
A and 3 Mechanical Draft Cooling Tever fans vere stopped, 0
reducing AT to lesa than -3 7.
Long Ters:
None (10) Failure Data:
Ucne EI Th-8, II 75-7, EI 75-8, R0 ~6-26
Similar Events
Sincerely, b &b$f
/J. G.,Herbein Vice President JGH:DGM: ki Enclosure: Licensee Event Report ec:
Ms. Margaret Reilly Chief Division of Reacter Review PaDER Tulten Builiing Harristurg, PA 17120 kk0
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| 05000289/LER-1977-001, Forwards LER 77-001/01T.Provides Supplemental Info | Forwards LER 77-001/01T.Provides Supplemental Info | | | 05000289/LER-1977-001-01, /01T:on 770203,w/diesel Generator B Out of Svc,A Generator Was Lost,Causing Operation at Limiting Condition Less Conservative than Tech Specs.Generator a Out of Svc Due to Binding of Oil Pressure Low Speed Switch | /01T:on 770203,w/diesel Generator B Out of Svc,A Generator Was Lost,Causing Operation at Limiting Condition Less Conservative than Tech Specs.Generator a Out of Svc Due to Binding of Oil Pressure Low Speed Switch | | | 05000289/LER-1977-002-04, /04T-0:on 770304,river Water Discharge Exceeded Inlet River Water Temp by 14 F,Violating 12 F Limit During Normal Operation.Caused by Atmospheric Conditions & Personnel Error.Standby Decay Heat Water Pump Reduced Temp | /04T-0:on 770304,river Water Discharge Exceeded Inlet River Water Temp by 14 F,Violating 12 F Limit During Normal Operation.Caused by Atmospheric Conditions & Personnel Error.Standby Decay Heat Water Pump Reduced Temp | | | 05000289/LER-1977-003-03, /03L:on 770309,reactor Bldg Spray Pump Suction Isolation Valve Motor Failed.Caused by Excessive Grease in Operators Spring Pack Which Stopped Normal Compression of Spring,Preventing Torque Switch Sensing Force to Be Applied | /03L:on 770309,reactor Bldg Spray Pump Suction Isolation Valve Motor Failed.Caused by Excessive Grease in Operators Spring Pack Which Stopped Normal Compression of Spring,Preventing Torque Switch Sensing Force to Be Applied | | | 05000289/LER-1977-003, Forwards LER 77-003/03L.Provides Supplemental Info | Forwards LER 77-003/03L.Provides Supplemental Info | | | 05000289/LER-1977-004-01, /01T:on 770415,error in Safety Analysis Discovered.Caused by Personnel Using Erroneous Combined Relief Valve Capacity Figures from Vendor Valve Drawing in Safety Analysis | /01T:on 770415,error in Safety Analysis Discovered.Caused by Personnel Using Erroneous Combined Relief Valve Capacity Figures from Vendor Valve Drawing in Safety Analysis | | | 05000289/LER-1977-004, Forwards LER 77-004/01T.Provides Supplemental Info | Forwards LER 77-004/01T.Provides Supplemental Info | | | 05000289/LER-1977-005, Forwards LER 77-005/04T.Provides Supplemental Info | Forwards LER 77-005/04T.Provides Supplemental Info | | | 05000289/LER-1977-005-04, /04t on 770319,change in River Water Discharge Temp More than 2 Degrees in Hour Period Violated Ets.Caused by Failure of Mechanical Cooling Tower C Fan.Fan to Be Repaired During Current Refueling Outage | /04t on 770319,change in River Water Discharge Temp More than 2 Degrees in Hour Period Violated Ets.Caused by Failure of Mechanical Cooling Tower C Fan.Fan to Be Repaired During Current Refueling Outage | | | 05000289/LER-1977-006-01, /01T:on 770324,during Reactor Refueling,Tech Specs for Leakage of Valves & Penetrations Were Exceeded. Caused by Inability of Carbon Steel Gate Valves in Cooling Water Sys to Keep Tight Seals Between Tests | /01T:on 770324,during Reactor Refueling,Tech Specs for Leakage of Valves & Penetrations Were Exceeded. Caused by Inability of Carbon Steel Gate Valves in Cooling Water Sys to Keep Tight Seals Between Tests | | | 05000289/LER-1977-006, Forwards LER 77-006/01T-0 | Forwards LER 77-006/01T-0 | | | 05000289/LER-1977-007, Forwards LER 77-007/01T.Provides Supplemental Info | Forwards LER 77-007/01T.Provides Supplemental Info | | | 05000289/LER-1977-007-01, /01T:on 770509,both Doors of Reactor Bldg Emergency Personnel Access Hatch Open at Same Time,Violating Tech Specs.Caused by Door Design Flaw Allowing Free Travel If Closed Against Obstruction,Causing Interlock Stress | /01T:on 770509,both Doors of Reactor Bldg Emergency Personnel Access Hatch Open at Same Time,Violating Tech Specs.Caused by Door Design Flaw Allowing Free Travel If Closed Against Obstruction,Causing Interlock Stress | | | 05000289/LER-1977-008-03, /03L:on 770504 Snubbers Failed to Perform within Acceptable Criteria,Resulting in Operation in Degraded Mode. Caused by Improperly Adjusted Locking Devices & O-ring Seal Leaks.Cause of Failure of Eight Snubbers Unknown | /03L:on 770504 Snubbers Failed to Perform within Acceptable Criteria,Resulting in Operation in Degraded Mode. Caused by Improperly Adjusted Locking Devices & O-ring Seal Leaks.Cause of Failure of Eight Snubbers Unknown | | | 05000289/LER-1977-008, Forwards LER 77-008/03L.Provides Supplemental Info | Forwards LER 77-008/03L.Provides Supplemental Info | | | 05000289/LER-1977-009-01, /01T:on 770512,loose Steam Generator LOCA Restraint Bolt Found.Caused Either by Improper Tightening During Installation or Loosening Due to Thermal Cycling & Bolt Relaxation in Svc | /01T:on 770512,loose Steam Generator LOCA Restraint Bolt Found.Caused Either by Improper Tightening During Installation or Loosening Due to Thermal Cycling & Bolt Relaxation in Svc | | | 05000289/LER-1977-009, Forwards LER 77-009/01T.Provides Supplemental Info | Forwards LER 77-009/01T.Provides Supplemental Info | | | 05000289/LER-1977-010, Forwards LER 77-010/01T.Provides Supplemental Info | Forwards LER 77-010/01T.Provides Supplemental Info | | | 05000289/LER-1977-011, Forwards LER 77-011/01T.Provides Supplemental Info | Forwards LER 77-011/01T.Provides Supplemental Info | | | 05000289/LER-1977-011-01, T:On 770519,engineered Safeguards Motor Control Center Tripped During Power Operation.Caused by Binding of a Phase Overload Device Tripping Stem.Preventive Maint Will Be Modified to Check for Tripping Stem Resetting | T:On 770519,engineered Safeguards Motor Control Center Tripped During Power Operation.Caused by Binding of a Phase Overload Device Tripping Stem.Preventive Maint Will Be Modified to Check for Tripping Stem Resetting | | | 05000289/LER-1977-012, RO 77-12/3L:on 770519,engineered Safeguard Pump MU-P-1A Was Removed from Svc Prior to Testing Operability of Redundant Pump.Caused by Personnel Error.Redundant Pump Tested Satisfactorily on 770519.Forwards LER 77-12/03L | RO 77-12/3L:on 770519,engineered Safeguard Pump MU-P-1A Was Removed from Svc Prior to Testing Operability of Redundant Pump.Caused by Personnel Error.Redundant Pump Tested Satisfactorily on 770519.Forwards LER 77-12/03L | | | 05000289/LER-1977-012-03, /03L:on 770519,engineered Safeguard Pump MU-P-1A Was Removed from Svc Prior to Testing Redundant Pump. Caused by Personnel Error.Redundant Pump Tested Satisfactorily.Personnel Instructed in Procedures | /03L:on 770519,engineered Safeguard Pump MU-P-1A Was Removed from Svc Prior to Testing Redundant Pump. Caused by Personnel Error.Redundant Pump Tested Satisfactorily.Personnel Instructed in Procedures | | | 05000289/LER-1977-013-04, /04T:on 770523,during Normal Operation,Waste Concentration in River Water Discharge Found in Excess of Designated Max.Caused by Slug of Suspended Solids Breaking Loose During Sampling.Discharge Terminated | /04T:on 770523,during Normal Operation,Waste Concentration in River Water Discharge Found in Excess of Designated Max.Caused by Slug of Suspended Solids Breaking Loose During Sampling.Discharge Terminated | | | 05000289/LER-1977-014-03, /03L:on 770524,during Reactor Bldg Cooling & Isolation Sys Logic Channel & Component Test,Reactor Bldg Cooling Return Isolation Valve RB-V7 Failed to Close Upon Receipt of Signal.Caused by Dirt on Valve Diaphragm | /03L:on 770524,during Reactor Bldg Cooling & Isolation Sys Logic Channel & Component Test,Reactor Bldg Cooling Return Isolation Valve RB-V7 Failed to Close Upon Receipt of Signal.Caused by Dirt on Valve Diaphragm | | | 05000289/LER-1977-015, Notes Error in LER 77-15/3L Submitted 770628.Both Drawings in Section 9 Should Be Numbered 207-011 | Notes Error in LER 77-15/3L Submitted 770628.Both Drawings in Section 9 Should Be Numbered 207-011 | | | 05000289/LER-1977-015-03, /03L:on 770529,during Normal operation,230 Kv Substation Bus 4 Was de-energized by Differential Relay 87BB-1.Caused by Wiring Error on Auxiliary Transformer Due to Drawing Error.Bus & Transformer Returned to Svc | /03L:on 770529,during Normal operation,230 Kv Substation Bus 4 Was de-energized by Differential Relay 87BB-1.Caused by Wiring Error on Auxiliary Transformer Due to Drawing Error.Bus & Transformer Returned to Svc | | | 05000320/LER-1977-016, /01T-0 on 770924:half Trip of Steam & Feedwater Rupture Control Sys Resulted in Opening of Pressurizer Power Relief Valve.Possibly Caused by Loose Connections at Terminal Boards | /01T-0 on 770924:half Trip of Steam & Feedwater Rupture Control Sys Resulted in Opening of Pressurizer Power Relief Valve.Possibly Caused by Loose Connections at Terminal Boards | | | 05000289/LER-1977-016-01, /01T-0:on 770924,RCS Temp & Pressure Rose.Caused by Half Trip Condition from Steam & Feedwater Rupture Control Sys.Possible Cause of Half Trip Attributed to Loose Connection at Terminal Boards | /01T-0:on 770924,RCS Temp & Pressure Rose.Caused by Half Trip Condition from Steam & Feedwater Rupture Control Sys.Possible Cause of Half Trip Attributed to Loose Connection at Terminal Boards | | | 05000289/LER-1977-016, Forwards Supplemental Info to LER 77-016/01T-0 Re Half Trip in Steam Feedwater Rupture Control Sys | Forwards Supplemental Info to LER 77-016/01T-0 Re Half Trip in Steam Feedwater Rupture Control Sys | | | 05000289/LER-1977-017-03, /03L:on 770624,during Normal Operating & semi- Annual Leak Test,Leakage Observed Around Inner Door Seal of Personnel Accces Hatch of Reactor Bldg.Caused by Procedural Inadequacies Causing Improper Installation of Door | /03L:on 770624,during Normal Operating & semi- Annual Leak Test,Leakage Observed Around Inner Door Seal of Personnel Accces Hatch of Reactor Bldg.Caused by Procedural Inadequacies Causing Improper Installation of Door | | | 05000289/LER-1977-018-03, /03L:on 770629,during Normal Operation,Nuclear Svcs River Water Pump NR-P1C Shaft Failed During Pump Operation.Caused by Mechanical & Procedural Problems.Pump Lined Up & Repaired within 4-h | /03L:on 770629,during Normal Operation,Nuclear Svcs River Water Pump NR-P1C Shaft Failed During Pump Operation.Caused by Mechanical & Procedural Problems.Pump Lined Up & Repaired within 4-h | | | 05000289/LER-1977-019-03, /03L:on 770713,during Normal Operation,Leak in Miscellaneous Waste Evaporator Feed Tank Immersion Heater Shorted Out Heater & Feed Pump.Caused by Leak in Temp Probe on Heater.Heater Replaced & Operating Procedure Modified | /03L:on 770713,during Normal Operation,Leak in Miscellaneous Waste Evaporator Feed Tank Immersion Heater Shorted Out Heater & Feed Pump.Caused by Leak in Temp Probe on Heater.Heater Replaced & Operating Procedure Modified | | | 05000289/LER-1977-020, Forwards LER 77-20/04T-0 | Forwards LER 77-20/04T-0 | | | 05000289/LER-1977-020-04, /4T:on 770719,during Passage of Storm Front,Station River Water Discharge Temp Fell to in Excess of 3 F Below Inlet Temp.Caused by Storm Front.A & B Mechanical Draft Cooling Fans Stopped | /4T:on 770719,during Passage of Storm Front,Station River Water Discharge Temp Fell to in Excess of 3 F Below Inlet Temp.Caused by Storm Front.A & B Mechanical Draft Cooling Fans Stopped | | | 05000289/LER-1977-021-01, /01T:on 770726,during Normal Operation,Radiation Monitor RM-A2 Failed & Atmosphere Sampling of Reactor Bldg Not Performed.Caused by Improper Reassembly Following 770725 Surveillance Test.Monitor Repaired.Procedure to Be Revi | /01T:on 770726,during Normal Operation,Radiation Monitor RM-A2 Failed & Atmosphere Sampling of Reactor Bldg Not Performed.Caused by Improper Reassembly Following 770725 Surveillance Test.Monitor Repaired.Procedure to Be Revised | | | 05000289/LER-1977-022-01, /01T:on 770825,during Normal Operation Restrictions Placed on Decay Heat Removal Pumps Found Contrary to Pump Operating Capability Per Fsar.Restrictions Placed on Pump by B&W Due to Pump Failure at Other Util | /01T:on 770825,during Normal Operation Restrictions Placed on Decay Heat Removal Pumps Found Contrary to Pump Operating Capability Per Fsar.Restrictions Placed on Pump by B&W Due to Pump Failure at Other Util | | | 05000289/LER-1977-023-01, /01T:on 770926,during Heatup Operation Both Doors of Reactor Bldg Emergency Personnel Access Hatch Open Simultaneously.Caused by Failure of Interlock,Poor Hatch Design & Operator Error.Addl Interlock to Be Added | /01T:on 770926,during Heatup Operation Both Doors of Reactor Bldg Emergency Personnel Access Hatch Open Simultaneously.Caused by Failure of Interlock,Poor Hatch Design & Operator Error.Addl Interlock to Be Added | | | 05000289/LER-1977-023, RO 77-23/1T:on 770920,both Doors of Reactor Bldg Emergency Personnel Access Hatch Open Simultaneously.Caused by Personnel Error.Doors Closed.Forwards LER 77-23/1T | RO 77-23/1T:on 770920,both Doors of Reactor Bldg Emergency Personnel Access Hatch Open Simultaneously.Caused by Personnel Error.Doors Closed.Forwards LER 77-23/1T | |
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