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| | issue date = 04/02/1980 | | | issue date = 04/02/1980 |
| | title = LER 80-014/01T-0:on 800320,informed by Westinghouse That Incident of Stress Corrosion Cracking in Control Rod Support Pins & Flexures Noted in Foreign Plant.Vendor Testing & Assessment Program in Progress.Appropriate Action Planned | | | title = LER 80-014/01T-0:on 800320,informed by Westinghouse That Incident of Stress Corrosion Cracking in Control Rod Support Pins & Flexures Noted in Foreign Plant.Vendor Testing & Assessment Program in Progress.Appropriate Action Planned |
| | author name = WILSON J L | | | author name = Wilson J |
| | author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) | | | author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| | addressee name = | | | addressee name = |
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| =Text= | | =Text= |
| {{#Wiki_filter:. (7-77) e LICENSEE EVENT REPORT | | {{#Wiki_filter:. (7-77) ~ |
| * CONTROL BLOCK: ~_.___,.____._
| | CONTROL BLOCK: ~_.___,.____.__ |
| _ _._l_.._!~18 6 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) jv IA Is IP Isl rl0lo I ol -1 ol al al al a1-lolol01411!
| | e LICENSEE EVENT REPORT |
| 1! 1l 1l©I I 10 7 8 9 LICENSEE CODE 14 U, LICENSE NUMBER 2!> 26 LICENSE TYPE :30. 57 <:AT SB CON*T [oTiJ L!.1©1 01 s I o Io I ol 2 1 s I o 10)1 | | _._l_.._!~18 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 6 |
| * o I 3 I 2 Io I s Io l©L.-l -* .... 1__.__..._...___._~IG) 7 B 60 61 DOCKET N.UMBER . 68 69 EVENT DATE 74 75 REPORT DATE 80 .EVENT DESCRIPTION AND ?ROBABLE CONSEQUENCES@ . . . [IJIJ !Westinghouse has informed.us that an incident of stress corrosion cracking.in the control I [£JI] I rod support pins and flexures in a foreign plant has been noted, and although there is no f I safety issue in. domesti_c operating plants the event is reportable under Title 10 CFR part I [[]}] I 21. Should a broken pin develop from this condition, the control rod operation could be [TID I adversely affected.* | | ~ jv IA Is IP Isl rl0lo I ol -1 ol al al al a1-lolol01411! 1! 1l 1l©I I 10 7 8 9 LICENSEE CODE 14 U, LICENSE NUMBER 2!> 26 LICENSE TYPE :30. 57 <:AT SB CON*T |
| This event is reportable in accordance with T.S. 6.6.2.A.5. | | [oTiJ :~:~~~ L!.1©1 01 sIo Io I ol 2 1s I. o6810)169*o I 3EVENT I 2 Io I s Io 74l©L.-l75-*....1__.__..._...___._~IG) 7 B 60 61 DOCKET N.UMBER DATE REPORT DATE 80 |
| Since [BI) I these parts did not fail and both units were at cold shut down, the health and safety of * ! I the public were not affected.
| | .EVENT DESCRIPTION AND ?ROBABLE CONSEQUENCES@ . . . |
| 7 8 9 SYSTEM CODE I RI Bl@ 9 10 (';:;\ . LE R/RO CVENT YEAR REPORT I 8 lo j NUMBER 21 . 22 CAUSE CAUSE COMP. CODE SUBCODE COMPONENT CODE SUBCODE w@ 1.!J@) lclRIDIR!V'IE ,e w@ 11 p . 13 18 19 SEQUENTIAL OCCURRENCE REPORT REPORT NO. CODE TYPE l.:=J 1011141 1.......-1 lolil LI.J 23 24 26 27 28 29 30 VALVE . SUBCODE lci 20 L=1 31 PRIME C:OMP. 80 REVISION COMPONENT ACTION FUTURE TAKEN ACTION EFFECT .ON PLANT SHUTDOWN | | [IJIJ !Westinghouse has informed.us that an incident of stress corrosion cracking.in the control I |
| * r:;::;,. ATTACHMENT NPRD-4 .METHOD HOURS .~ SUBMITTED FORM SUB. L.Ll@L!J@) | | [£JI] I rod support pins and flexures in a foreign plant has been noted, and although there is no f |
| L~@ LU I 010 l*O IO I LU@ W@ SUPPLIER . MANUFACTURER | | ~ I safety issue in. domesti_c operating plants the event is reportable under Title 10 CFR part I |
| .. 33 34 J!, .36 37 ,', ~---. . 40 41 42 W@ !w I 11 2 Io I CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @ . 43 D:J::§J I The cracked pins identified were all from one heat treatment lot of material used in J:[[J I foreign reactors .. A Westinghouse testing an~ an assessment_program is in.progress.to J:ID .I examine this situation more fully and the:.liceusee is prepared take ?P'P,rol?irat~
| | ((]}] I 21. Should a broken pin develop from this condition, the control rod operation could be |
| action JIIJ I based ~pon tlrn results of this rev~ew. JTI] 8 9 FACILITY STATUS :iliJ*W@ % POWER OTHER STATUS @ I O I O j O l ..... I ____ N_A_* ---8 9 10 12 *13 . 44 ACTIVITY CONTENT . Q\. RELEASED OF RELEASE AMOUNT OF ACTIVITY ~/ IIT]_ w @ ul@)I NA 8 9 10 11 PERSONNEL EXPOSURES | | [TID I adversely affected.* This event is reportable in accordance with T.S. 6.6.2.A.5. Since |
| * Q\ METHOD OF DISCOVERY DISCOVERY DESCRIPTION 32 W@INotification from Westinghouse.
| | [BI) I these parts did not fail and both units were at cold shut down, the health and safety of * ! |
| 45 46 LOCATION OF RELEASE @ NA . 45 47 80 80 80 NUMBER TYPE DESCRIPTION 2EJ j O j O I O '~@L,._* | | ~ I the public were not affected. |
| ___ N_A_~----------------------J 8 9 11 12 13 PERSONNEL INJURIES (;':;\ NUMBER
| | 7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE . |
| * OESCRIPTION6 80 NA :QTI l O I O I O I@ | | ,e CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE I RI Bl@ w@ 1.!J@) |
| * 8 9 11 LOSS OF OR DAMAGE TO FACI.LITY | | 9 10 11 p . |
| '4J\ TYPE DESCRIPTION ~w@ * ... | | lclRIDIR!V'IE 13 18 w@ |
| * NA 80 8 9 10 PUBLICITY Q\ ISSUEDC,;\DESCRIPTION~
| | 19 lci 20 SEQUENTIAL OCCURRENCE REPORT REVISION |
| 8 {)()408v . . NRC USE ONLY e LN.Je,.__
| | (';:;\ . LE R/RO CVENT YEAR REPORT NO. CODE TYPE |
| _______ N_A _____________
| | ~ REPORT NUMBER I lo j 8 . l.:=J 1011141 1.......-1 lolil LI.J L=1 21 22 23 24 26 27 28 29 30 31 ACTION FUTURE TAKEN ACTION EFFECT SHUTDOWN |
| __, I I I I I I I I I I I I I : 8 9 10 68 . 69 80 ; 804.,-357-3184 NAME.OF PRFPAR*FR----.:._
| | * r:;::;,. ATTACHMENT NPRD-4 PRIME C:OMP. COMPONENT |
| __ .;r iL* Wilson .i:>w.n,,.11:::.
| | .ON PLANT .METHOD HOURS . ~ SUBMITTED FORM SUB. SUPPLIER . MANUFACTURER .. |
| 0 ,II, ,,*c *-* *
| | L.Ll@L!J@) |
| .------------------------------------------------- | | 33 34 L~@ |
| -------e ATTACHMENT, PAGE 1 of 1 SURRY POWER STATION, UNIT 1 DOCKET NO: 50-280; 50-281 REPORT NO: 80-014/0lT-0 EVENT DATE: 3-20-80
| | J!, |
| * TITLE OF EVENT: CONTROL ROD MECHANISM POSSIBLE DEFECT 1. DESCRIPTION OF EVENT: Westinghouse has provided information on the stress corrosion cracking of control rod support pins and flexures in an operating PWR plant in a foreign country. Although Westinghouse state_d_ tll~re __ is no safety issue in domestic operating plants, they reported the event to the NRC under Title 18 CFR part 21. In so much as the control rod operations could be adversely effected should a broken pin be experienced, the event is reported in accordance with T.S.6.6.2.A.5.
| | LU |
| : 2. PROBABLE CONSEQUENCES AND STATUS OF REDUNDANT SYSTEM: Westinghouse has stated that no known cracking of support pins or flexures has been discovered in domestic plants and that on going testing efforts will provide information giving further assurance that this situation will not be a concern for any Westinghouse plant, Under these circumstances the health and safety of the public were not affected.
| | .36 I 010 37 l*O IO I LU@ |
| : 3. CAUSE: The failure of Westinghouse supplied support pins noted to date has been limited to pins with solution heat treatment at 1625AF. It should be noted that the present process for solution heat treatment ( in the.range of 1950°F to 2000°F) gives little indication of potential stress corrosion cracking.
| | ,', ~--- . . 40 41 W@ |
| : 4. IMMEDIATE CORRECTIVE ACTION: Westinghouse has proposed a support pin inspection program and has recommended no licensee action be taken by Non URI plants until the results have been concluded.
| | 42 W@ !w I 11 43 2 Io I 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @ . |
| : 5. SCHEDULED CORRECTIVE ACTION: Based upon the conclusion of the Westinghouse testing and assessment program, the licensee will take appropriate -measures to assure the reliability of this system. 6. ACTION TAKEN TO PREVENT RECURRENCE: | | D:J::§J I The cracked pins identified were all from one heat treatment lot of material used in J:((J I foreign reactors .. A Westinghouse testing an~ an assessment_program is in.progress.to J:ID .I examine this situation more fully and the:.liceusee is prepared take ?P'P,rol?irat~ action JIIJ I based ~pon tlrn results of this rev~ew. |
| None 7. GENERIC IMPLICATIONS:
| | JTI] |
| | 8 9 FACILITY STATUS % POWER OTHER STATUS @ METHOD OF DISCOVERY DISCOVERY DESCRIPTION 32 80 |
| | :iliJ*W@ I OI O j O lI. . .____N_A_*- - - |
| | 8 9 10 12 *13 . 44 W@INotification from Westinghouse. |
| | 45 46 80 ACTIVITY CONTENT . Q\. |
| | IIT]_ |
| | 8 w @ ul@)I RELEASED OF RELEASE 9 10 11 AMOUNT OF ACTIVITY ~ / |
| | NA 45 LOCATION OF RELEASE NA . |
| | 80 PERSONNEL EXPOSURES |
| | * Q\ |
| | NUMBER ~ TYPE DESCRIPTION 2EJ 8 j |
| | 9 Oj O I O11'~@L,._* |
| | 12 13 |
| | ___N _ A _ ~ - - - - - - - - - - - - - - - - - - - - - - J 80 PERSONNEL INJURIES (;':;\ |
| | NUMBER |
| | * OESCRIPTION6 |
| | :QTI8 l9 O I O I O11I@ |
| | * NA |
| | '-,2~~~~~~~~~~~-'--~~~~~~~~~~~~~~~....._~~~~~~~~~~~~~B_.O LOSS OF OR DAMAGE TO FACI.LITY TYPE DESCRIPTION |
| | '4J\ |
| | ~ |
| | ~w@ *. . . |
| | * NA 8 9 10 PUBLICITY Q\ ~ |
| | ~~ 80 ISSUEDC,;\DESCRIPTION~ 8 {)()408v . . NRC USE ONLY e |
| | ~ LN.Je,._________N_A_ _ _ _ _ _ _ _ _ _ _ _ ___, I I I I I I I I I I I I I: |
| | 8 9 10 68 . 69 80 ; |
| | NAME.OF PRFPAR*FR----.:.___ .;r iL* Wilson .i:>w.n,,.11:::. |
| | 804.,-357-3184 0 |
| | ,II, ,,*c *-* |
| | * e ATTACHMENT, PAGE 1 of 1 SURRY POWER STATION, UNIT 1 DOCKET NO: 50-280; 50-281 REPORT NO: 80-014/0lT-0 EVENT DATE: 3-20-80 TITLE OF EVENT: CONTROL ROD MECHANISM POSSIBLE DEFECT |
| | : 1. DESCRIPTION OF EVENT: |
| | Westinghouse has provided information on the stress corrosion cracking of control rod support pins and flexures in an operating PWR plant in a foreign country. Although Westinghouse state_d_ tll~re__ is no safety issue in domestic operating plants, they reported the event to the NRC under Title 18 CFR part 21. In so much as the control rod operations could be adversely effected should a broken pin be experienced, the event is reported in accordance with T.S.6.6.2.A.5. |
| | : 2. PROBABLE CONSEQUENCES AND STATUS OF REDUNDANT SYSTEM: |
| | Westinghouse has stated that no known cracking of support pins or flexures has been discovered in domestic plants and that on going testing efforts will provide information giving further assurance that this situation will not be a concern for any Westinghouse plant, Under these circumstances the health and safety of the public were not affected. |
| | : 3. CAUSE: |
| | The failure of Westinghouse supplied support pins noted to date has been limited to pins with solution heat treatment at 1625AF. It should be noted that the present process for solution heat treatment |
| | ( in the.range of 1950°F to 2000°F) gives little indication of potential stress corrosion cracking. |
| | : 4. IMMEDIATE CORRECTIVE ACTION: |
| | Westinghouse has proposed a support pin inspection program and has recommended no licensee action be taken by Non URI plants until the results have been concluded. |
| | : 5. SCHEDULED CORRECTIVE ACTION: |
| | Based upon the conclusion of the Westinghouse testing and assessment program, the licensee will take appropriate -measures to assure the reliability of this system. |
| | : 6. ACTION TAKEN TO PREVENT RECURRENCE: |
| | None |
| | : 7. GENERIC IMPLICATIONS: |
| At this time this event is.not considered generic. Past inspections by Westinghouse have revealed no material failures in the pins or flexures of domestic plants, however, they are pursuing a further inspection program to determine more fully the reliability of the parts used.}} | | At this time this event is.not considered generic. Past inspections by Westinghouse have revealed no material failures in the pins or flexures of domestic plants, however, they are pursuing a further inspection program to determine more fully the reliability of the parts used.}} |
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1999-08-27
[Table view]
Category:RO)
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LER 99-003-00:on 990331,potential Loss of Charging Pumps Was Noted.Caused by Main CR Fire.Station Deviation Was Issued on 990331.With 990428 Ltr
ML18153A2741999-03-29029 March 1999
LER 99-002-00:on 990301,prematurely Released Fire Watches Resulted in Violation of TS 3.21.B.7.Caused by Inadequate Procedure.Procedure for Opening & Sealing Fire Stops Was Revised on 990212
ML18153A2681999-03-19019 March 1999
LER 98-013-01:on 981122,turbine/reactor Tripped on High Due to Short Circuit in Summator for MSL C Loop Channel III Flow Transmitter.Replaced 1-MS-FT1494 Summator & Module Repair Procedure Revised.With 9903190 Ltr
ML18152B7261999-01-21021 January 1999
LER 99-001-00:on 981222,auxiliary Feedwater Pipe Support Missed Surveillance.Caused by Personnel Error.Station Deviation Rept Was Submitted.Two Supports in Question Received Required Code Insp & Were Found Acceptable
ML18152B5811998-12-16016 December 1998
LER 98-013-00:on 981122,turbine/reactor Trip on High SG Level Occurred.Caused by Instrument Failure.Control Room Operators Placed Unit in Safe,Shutdown Condition
ML18152B5781998-12-16016 December 1998
LER 98-014-00:on 981126,manual Reactor Trip in Response to Main Feedwater Regulating Valve Failure Occurred.Caused by Dislocation of Retaining Clip in Positioner.Control Room Operators Placed Unit in Safe,Shutdown Condition
ML18152B7121998-12-0404 December 1998
LER 98-S01-00:on 981105,noted Failure to Deactivate Station Access Badge.Caused by Human Error.Licensee Will Now Deactivate Station Badges Before Clearance Is Revoked & Process for Badge Deactivations Have Been Strengthened
ML18152B7041998-12-0101 December 1998
LER 98-012-00:on 981102,noted That EDGs Were Concurrently Inoperable.Caused by Required Testing Per TS 3.16.B.1.a.2. Redundant EDG Was Returned to Svc within Two Hour Period, Following Satisfactory Testing.With 981201 Ltr
ML18152B6161998-11-0606 November 1998
LER 98-011-00:on 981008,diesel Driven Fire Pump Failed to Start During Performance of Monthly Operability Test.Caused by Faulty Overspeed Trip Device Failure.Diesel Driven Fire Pump Declared Inoperable
ML18152B6081998-10-23023 October 1998
LER 98-010-01:on 980715,intake Canal Level Probes Were Inoperable Due to Marine Growth.Caused by Design of Canal Level Instrumentation.Canal Level Probes Will Continue to Be Monitored More Closely
ML18152B7811998-07-31031 July 1998
LER 98-010-00:on 980715,low Intake Canal Level Instrument Channel I Was Declared Inoperable to Allow Testing of Intake Canal Level Probe 1-CW-LE-102.Subject Probe Was Cleaned by Diver,Tested & Channel I Was Returned to Operable Status
ML18153A2581998-06-0303 June 1998
LER 98-009-00:on 980509,nonisolable Leak of Reactor Coolant Pump Seal Injection Line Weld,Was Discovered.Caused by Lack of Fusion or Thermal Fatigue Coupled W/Vibration Stress Due to Loose Rod Hanger.Rcp Seal Injection Line Removed
ML18152B8241998-05-22022 May 1998
LER 98-008-00:on 980228,auxiliary Ventilation Fans Were Noted in Condition Outside of Design Basis.Caused by Failure to Recognize Potential Impact of Certain Design Basis Accident Scenarios.No Corrective Actions Needed
ML18152B7951998-04-29029 April 1998
LER 98-007-00:on 980330,radiation Monitors Were Declared Inoperable.Caused by Change in Operating Temperature Range. Preplanned Alternate Method of Monitoring Was Initiated IAW TS Table 3.7-6
ML18153A2521998-04-22022 April 1998
LER 98-005-01:on 980212,fire Watch Insp Exceeded One Hour. Caused by Lack of Attention to Detail by Individual Involved.Individual Involved Was Coached on Requirement to Perform Fire Watch Patrols within Required Time Frame
ML18153A2511998-04-22022 April 1998
LER 98-006-00:on 980324,unisolable Through Wall Leak of RCP Thermowell Was Noted.Cause of Leak Is Unknown.Rtd Will Be Replaced
ML18153A2391998-03-13013 March 1998
LER 98-005-00:on 980212,fire Watch Insp Frequency Exceeded One H Occurred.Category 2 Root Cause Evaluation Being Conducted to Determine Cause of Event.Station Deviation Issued
ML18153A2341998-03-0909 March 1998
LER 98-003-00:on 980226,no Procedural Guidance for Maintaining EDG Minimum Fuel Supply During Loop,Was Identified.Caused by Absence of Procedural Instructions. Deviation Rept Submitted to Document Deviating Condition
ML18153A2301998-03-0606 March 1998
LER 98-004-00:on 980206,fire Watch Was Released Prematurely Resulting in Violation of Ts.Caused by Inadequate Planning of Repair Activity.Work Orders Will Include Ref to Applicable Procedures Developed to Assist in Repairs
ML18153A2251998-03-0404 March 1998
LER 98-002-00:on 980202,automatic Turbine Trip Resulted in Automatic Reactor Trip.Caused Degraded Generator Voltage Regulator sub-component Failure.Placed Plant in Safe Hot SD & Replaced Intermittent Relay & Relay Socket
ML18153A2201998-02-0606 February 1998
LER 98-001-00:on 980108,deficient Test Due to Faulty Test Equipment Resulted in TS Violation.Caused by Faulty Vibration Analyzer Cable or Loose Connection.Station Deviation Rept Was submitted.W/980206 Ltr
ML18153A2071998-01-13013 January 1998
LER 97-012-01:on 971028,loss of Power to Latching Mechanism on Several Doors Occurred.Caused by Tripping of Two Breakers in Security Distribution Panel.Reset Affected Breakers Which Restored Power to Security Systems & Affected Doors
ML18153A2101998-01-13013 January 1998
LER 97-009-01:on 971014,declared Intake Canal Level Probes Inoperable Due to Marine Growth.Caused by Inadequate Maint of Intake Canal Level Probes.Subject Probes Were Cleaned, Tested Satisfactorily & Returned to Operable Status
ML18153A1911997-11-26026 November 1997
LER 97-011-00:on 971030,determined That Periodic Test Procedures for Testing Reactor Trip Bypass Breakers Did Not Test Manual Undervoltage Trip.Caused by mis-interpretation of Term in-service. Procedures Revised
ML18153A1971997-11-26026 November 1997
LER 97-012-00:on 971028,loss of Power to Latching Mechanism on Several Doors Occurred.Caused by Tripping of Breaker in Security Distribution Panel in Central Alarm Station (CAS) Panel.Breakers in Affected CAS Panel Reset
ML18153A1921997-11-25025 November 1997
LER 97-010-00:on 971028,discovered Missed Fire Protection Surveillance Pt.Caused by Personnel Error.Satisfactorily Completed PT Procedure 0-OPT-FP-009 & Diesel Driven Fire Pump 1-FP-P-2 Declared operable.W/971125 Ltr
ML18153A1831997-11-12012 November 1997
LER 97-009-00:on 971014,declared Intake Canal Level Probes Inoperable Due to Marine Growth.Cause Indeterminate.Divers Inspected,Cleaned & Returned Probes to Operable Status & Initiated Interdepartmental Team to Investigate Cause
ML18153A1791997-11-0707 November 1997
LER 97-008-00:on 971011,invalid Actuation of ESF Occurred. Caused by Personnel Errors.Main CR Bottled Air Sys Isolated & Containment Hydrogen Analyzer Heat Tracing Actuation Signal Reset
ML18153A1721997-10-30030 October 1997
LER 97-007-00:on 970930,determined That Plant Was Outside App R Design Basis Due to Vital Bus Isolation Issue.Caused by Personnel Error.Installed Circuit Protective Device During Oct 1997 Refueling Outage
ML18153A1421997-06-10010 June 1997
LER 97-001-01:on 970123,shutdown Occurred Due to Drain Line Weld Leak.Inspected & Tested Turbine Trip Actuation circuitry.W/970610 Ltr
ML18153A1391997-05-28028 May 1997
LER 97-005-00:on 970502,Unit 1 Power Range Nuclear Instrumentation Was Inoperable Due to Personnel Error.Sro & STA That Were Involved in Event Were Counseled
ML18153A1291997-04-18018 April 1997
LER 97-006-00:on 970320,loss of Refueling Integrity Due to Inadequate Containment Closure Process & Verification.Fuel Movement Stopped IAW Action Statement Requirements of TS 3.10.B.W/970418 Ltr
ML18153A1281997-04-15015 April 1997
LER 97-004-00:on 970317,main Steam Safety Valve Was Outside as Found Setpoint Tolerance.Specific Cause Unknown,However, Minor Setpoint Drift Can Be Expected.No Immediate Corrective Actions performed.W/970415 Ltr
ML18153A1241997-04-0808 April 1997
LER 97-002-01:on 970116,one Train of Auxiliary Ventilation Sys Was Inoperable Outside of Ts.Caused by Personnel Error. Submitted Deviation Rept Re Reverse Rotation of Fan & Work Request to Adjust linkage.W/970408 Ltr
ML18153A1191997-03-19019 March 1997
LER 97-001-00:on 970218,manual Reactor Trip & ESF Actuation Occurred Due to Loss of EHC Control Power.Caused by Momentary Short.Relay Card Was replaced.W/970319 Ltr
ML18153A1201997-03-19019 March 1997
LER 97-003-00:on 970219,loss of Pressurizer Heaters Resulted in Manual U1 Trip & U2 ESF Actuation.Caused by Loss of Group C Pressurizer Proportional Heaters.Reactor Trip Breakers Were Verified open.W/970319 Ltr
ML18153A1131997-02-20020 February 1997
LER 97-001-00:on 970123,shutdown Occurred Due to Steam Drain Line Weld Leak.Management Was Notified & Shift Supervisor Invoked Requirements of TS 4.15.C.1.W/undtd Ltr
ML18153A1101997-02-13013 February 1997
LER 97-002-00:on 970116,one Train of Auxiliary Ventilation Sys Declared Inoperable.Caused by Personnel Error.Properly Adjusted Damper 1-VS-MOD-58B & Exited Seven Day LCO on 970116.W/970214 Ltr
ML18153A0951997-01-0202 January 1997
LER 97-002-00:on 961213,automatic Reactor Trip Occurred During Planned Shutdown.Caused by Steam Flow/Feedwater Flow Mismatch.Rps Functioned as Designed & Plant Placed in Hot Shutdown
ML18153A0931996-12-12012 December 1996
LER 96-008-00:on 961112,water Gas Decay Tank Oxygen Analyzer Pressure Sensors Inoperable Due to Vendor Supplied Equipment Not Meeting Procurement specifications.Post-implementation Procedures Revised & Transducers replaced.W/961212 Ltr
ML18153A0691996-09-19019 September 1996
LER 96-007-00:on 960821,failed to Complete Fire Detection Zone Inspections within Required Time Period.Caused by Personnel Error.Counseled Personnel Re Fire Detection Zone Inspections & Revised Fire Watch training.W/960920 Ltr
ML18153A0481996-08-26026 August 1996
LER 96-005-00:on 960803,manual Reactor Trip.Caused by Loss of Electro Hydraulic Control Pressure.Repaired Two Compression Fitting Union Connections on Leaking Fitting & Performed Evaluations on Other tubing.W/960826 Ltr
ML18153A0521996-08-20020 August 1996
LER 96-004-01:on 960510,discovered Hydrogen Analyzers Inoperable.Caused by Procedural Deficiencies.Implemented Permanent Changes to Hydrogen Analyzer Instrument Calibr Procedures.W/960820 Ltr
ML18153A0321996-07-30030 July 1996
LER 96-006-01:on 960618,anti-corrosion Coating Had Not Been Reapplied to Station Battery 2B.Caused by Procedural Error in That Verbatim TS Compliance Not Reflected in Procedures. Coating Was Applied to batteries.W/960730 Ltr
ML18153A0281996-07-17017 July 1996
LER 96-006-00:on 960618,failed to Apply anti-corrosion Coating to Station Battery 2B.Caused by Procedural Error. Applied anti-corrosion Coating to Batteries & Revised TS 4.6.C.1.f Re Battery Coating requirements.W/960717 Ltr
ML18153A0141996-07-0202 July 1996
LER 96-004-00:on 960606,turbine/reactor Trip Occurred.Caused by High Level in Steam Generator B.Placed Plant in Hot Shutdown Condition,Calculated Shutdown Margin & Monitored Critical Safety Function Status trees.W/960702 Ltr
1999-08-27
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML18152A2811999-10-12012 October 1999
Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619.
ML18152B3531999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for Surry Power Station,Units 1 & 2.With 991012 Ltr
ML18152B6651999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for Surry Power Station Units 1 & 2.With 990915 Ltr
ML18152B4421999-08-27027 August 1999
LER 99-006-00:on 990802,determined That Plant Was Outside of App R Design Basis Due to Fire Barrier Deficiencies. Caused by Original Plant Design Deficiencies.Fire Watches Were Established & Mods Have Been Completed.With 990827 Ltr
ML18152B4411999-08-27027 August 1999
LER 99-005-00:on 990731,effluent Radiation Monitors Were Declared Inoperable.Caused by Degraded Heat Trace Circuits for Monitors Sample Suction Line.Degraded Heat Trace Circuit Was Replaced & Addl Heat Trace Is Being Installed
ML18151A3981999-08-13013 August 1999
SPS Unit 2 ISI Summary Rept for 1999 Refueling Outage.
ML18152B3771999-08-13013 August 1999
LER 99-004-00:on 990714,TS Violation Due to non-safety Related Fans Effect on CR Boundary Was Noted.Cause of Event Has Not Yet Been Determined.Cable Spreading Room Doors Were Operned to Reduce Pressure in Rooms
ML18152B3791999-07-31031 July 1999
Monthly Operating Repts for July 1999 for Surry Power Station,Units 1 & 2.With 990811 Ltr
ML18152B3911999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Surry Power Station,Units 1 & 2.With 990713 Ltr
ML18152B4341999-05-31031 May 1999
Monthly Operating Repts for May 1999 for Surry Power Station,Units 1 & 2.With 990614 Ltr
ML20195E2401999-05-31031 May 1999
Rev 2 to COLR for SPS Unit 2 Cycle 16 Pattern Ag
ML18152B4181999-05-18018 May 1999
LER 99-002-00:on 990425,MSSVs Tested Out of Tolerance for as Found Setpoint.Caused by Minor Setpoint Drift.No Immediate Action Required.Deviation Rept Submitted for Each Valve.With 990518 Ltr
ML18152B4161999-04-30030 April 1999
Monthly Operating Repts for Apr 1999 for Surry Power Station Units 1 & 2.With 990512 Ltr
ML18152B4111999-04-28028 April 1999
LER 99-003-00:on 990331,potential Loss of Charging Pumps Was Noted.Caused by Main CR Fire.Station Deviation Was Issued on 990331.With 990428 Ltr
ML18152B6511999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for Surry Power Station Units 1 & 2
ML18153A2741999-03-29029 March 1999
LER 99-002-00:on 990301,prematurely Released Fire Watches Resulted in Violation of TS 3.21.B.7.Caused by Inadequate Procedure.Procedure for Opening & Sealing Fire Stops Was Revised on 990212
ML18153A2681999-03-19019 March 1999
LER 98-013-01:on 981122,turbine/reactor Tripped on High Due to Short Circuit in Summator for MSL C Loop Channel III Flow Transmitter.Replaced 1-MS-FT1494 Summator & Module Repair Procedure Revised.With 9903190 Ltr
ML18152B7331999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for Surry Power Station,Units 1 & 2.With 990310 Ltr
ML18152B5421999-01-31031 January 1999
Monthly Operating Repts for Jan 1999 for Surry Power Station,Units 1 & 2.With 990210 Ltr
ML18151A3031999-01-29029 January 1999
ISI Summary Rept for 1998 Refueling Outage,Including Form NIS-1, Owners Rept for ISIs & Form NIS-2, Owners Rept for Repairs & Replacements.
ML18152B7261999-01-21021 January 1999
LER 99-001-00:on 981222,auxiliary Feedwater Pipe Support Missed Surveillance.Caused by Personnel Error.Station Deviation Rept Was Submitted.Two Supports in Question Received Required Code Insp & Were Found Acceptable
ML18152B6011998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for Surry Power Station,Units 1 & 2.With 990115 Ltr
ML18152B5781998-12-16016 December 1998
LER 98-014-00:on 981126,manual Reactor Trip in Response to Main Feedwater Regulating Valve Failure Occurred.Caused by Dislocation of Retaining Clip in Positioner.Control Room Operators Placed Unit in Safe,Shutdown Condition
ML18152B5811998-12-16016 December 1998
LER 98-013-00:on 981122,turbine/reactor Trip on High SG Level Occurred.Caused by Instrument Failure.Control Room Operators Placed Unit in Safe,Shutdown Condition
ML18152B7121998-12-0404 December 1998
LER 98-S01-00:on 981105,noted Failure to Deactivate Station Access Badge.Caused by Human Error.Licensee Will Now Deactivate Station Badges Before Clearance Is Revoked & Process for Badge Deactivations Have Been Strengthened
ML18152B7041998-12-0101 December 1998
LER 98-012-00:on 981102,noted That EDGs Were Concurrently Inoperable.Caused by Required Testing Per TS 3.16.B.1.a.2. Redundant EDG Was Returned to Svc within Two Hour Period, Following Satisfactory Testing.With 981201 Ltr
ML18152B7081998-11-30030 November 1998
Rev 0 to COLR for Surry 1 Cycle 16,Pattern Un.
ML18152B5721998-11-30030 November 1998
Monthly Operating Repts for Nov 1998 for Surry Power Station,Units 1 & 2.With 981214 Ltr
ML18152B6161998-11-0606 November 1998
LER 98-011-00:on 981008,diesel Driven Fire Pump Failed to Start During Performance of Monthly Operability Test.Caused by Faulty Overspeed Trip Device Failure.Diesel Driven Fire Pump Declared Inoperable
ML18152B6241998-10-31031 October 1998
Monthly Operating Repts for Oct 1998 for Surry Power Station Units 1 & 2.With 981111 Ltr
ML18152B6081998-10-23023 October 1998
LER 98-010-01:on 980715,intake Canal Level Probes Were Inoperable Due to Marine Growth.Caused by Design of Canal Level Instrumentation.Canal Level Probes Will Continue to Be Monitored More Closely
ML18152B6881998-09-30030 September 1998
Monthly Operating Repts for Sept 1998 for Surry Power Station Units 1 & 2.With 981012 Ltr
ML18153A3271998-08-31031 August 1998
Monthly Operating Repts for Aug 1998 for Surry Power Station,Units 1 & 2
ML18152B7811998-07-31031 July 1998
LER 98-010-00:on 980715,low Intake Canal Level Instrument Channel I Was Declared Inoperable to Allow Testing of Intake Canal Level Probe 1-CW-LE-102.Subject Probe Was Cleaned by Diver,Tested & Channel I Was Returned to Operable Status
ML18153A3161998-07-31031 July 1998
Monthly Operating Repts for July 1998 for Surry Power Station Units 1 & 2.W/980807 Ltr
ML18152B7621998-06-30030 June 1998
Monthly Operating Repts for June 1998 for Surry Power Station,Units 1 & 2.W/980707 Ltr
ML18153A2581998-06-0303 June 1998
LER 98-009-00:on 980509,nonisolable Leak of Reactor Coolant Pump Seal Injection Line Weld,Was Discovered.Caused by Lack of Fusion or Thermal Fatigue Coupled W/Vibration Stress Due to Loose Rod Hanger.Rcp Seal Injection Line Removed
ML20248F7441998-05-31031 May 1998
Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity
ML18153A3141998-05-31031 May 1998
Monthly Operating Repts for May 1998 for Surry Power Station,Units 1 & 2.W/980610
ML18152B8241998-05-22022 May 1998
LER 98-008-00:on 980228,auxiliary Ventilation Fans Were Noted in Condition Outside of Design Basis.Caused by Failure to Recognize Potential Impact of Certain Design Basis Accident Scenarios.No Corrective Actions Needed
ML18152B8161998-04-30030 April 1998
Monthly Operating Repts for Apr 1998 for Surry Power Station Units 1 & 2.W/980508 Ltr
ML18152B7951998-04-29029 April 1998
LER 98-007-00:on 980330,radiation Monitors Were Declared Inoperable.Caused by Change in Operating Temperature Range. Preplanned Alternate Method of Monitoring Was Initiated IAW TS Table 3.7-6
ML18153A2511998-04-22022 April 1998
LER 98-006-00:on 980324,unisolable Through Wall Leak of RCP Thermowell Was Noted.Cause of Leak Is Unknown.Rtd Will Be Replaced
ML18153A2521998-04-22022 April 1998
LER 98-005-01:on 980212,fire Watch Insp Exceeded One Hour. Caused by Lack of Attention to Detail by Individual Involved.Individual Involved Was Coached on Requirement to Perform Fire Watch Patrols within Required Time Frame
ML20217P9941998-04-0707 April 1998
Safety Evaluation Granting Licensee Third 10-yr Inservice Insp Program Relief Requests SR-018 - Sr-024
ML18153A2951998-03-31031 March 1998
Monthly Operating Repts for Mar 1998 for Sps,Units 1 & 2.W/ 980408 Ltr
ML18153A2391998-03-13013 March 1998
LER 98-005-00:on 980212,fire Watch Insp Frequency Exceeded One H Occurred.Category 2 Root Cause Evaluation Being Conducted to Determine Cause of Event.Station Deviation Issued
ML18153A2341998-03-0909 March 1998
LER 98-003-00:on 980226,no Procedural Guidance for Maintaining EDG Minimum Fuel Supply During Loop,Was Identified.Caused by Absence of Procedural Instructions. Deviation Rept Submitted to Document Deviating Condition
ML18153A2301998-03-0606 March 1998
LER 98-004-00:on 980206,fire Watch Was Released Prematurely Resulting in Violation of Ts.Caused by Inadequate Planning of Repair Activity.Work Orders Will Include Ref to Applicable Procedures Developed to Assist in Repairs
ML18153A2251998-03-0404 March 1998
LER 98-002-00:on 980202,automatic Turbine Trip Resulted in Automatic Reactor Trip.Caused Degraded Generator Voltage Regulator sub-component Failure.Placed Plant in Safe Hot SD & Replaced Intermittent Relay & Relay Socket
1999-09-30
[Table view] |
Text
. (7-77) ~
CONTROL BLOCK: ~_.___,.____.__
e LICENSEE EVENT REPORT
_._l_.._!~18 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 6
~ jv IA Is IP Isl rl0lo I ol -1 ol al al al a1-lolol01411! 1! 1l 1l©I I 10 7 8 9 LICENSEE CODE 14 U, LICENSE NUMBER 2!> 26 LICENSE TYPE :30. 57 <:AT SB CON*T
[oTiJ :~:~~~ L!.1©1 01 sIo Io I ol 2 1s I. o6810)169*o I 3EVENT I 2 Io I s Io 74l©L.-l75-*....1__.__..._...___._~IG) 7 B 60 61 DOCKET N.UMBER DATE REPORT DATE 80
.EVENT DESCRIPTION AND ?ROBABLE CONSEQUENCES@ . . .
[IJIJ !Westinghouse has informed.us that an incident of stress corrosion cracking.in the control I
[£JI] I rod support pins and flexures in a foreign plant has been noted, and although there is no f
~ I safety issue in. domesti_c operating plants the event is reportable under Title 10 CFR part I
((]}] I 21. Should a broken pin develop from this condition, the control rod operation could be
[TID I adversely affected.* This event is reportable in accordance with T.S. 6.6.2.A.5. Since
[BI) I these parts did not fail and both units were at cold shut down, the health and safety of * !
~ I the public were not affected.
7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE .
,e CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE I RI Bl@ w@ 1.!J@)
9 10 11 p .
lclRIDIR!V'IE 13 18 w@
19 lci 20 SEQUENTIAL OCCURRENCE REPORT REVISION
(';:;\ . LE R/RO CVENT YEAR REPORT NO. CODE TYPE
~ REPORT NUMBER I lo j 8 . l.:=J 1011141 1.......-1 lolil LI.J L=1 21 22 23 24 26 27 28 29 30 31 ACTION FUTURE TAKEN ACTION EFFECT SHUTDOWN
- r:;::;,. ATTACHMENT NPRD-4 PRIME C:OMP. COMPONENT
.ON PLANT .METHOD HOURS . ~ SUBMITTED FORM SUB. SUPPLIER . MANUFACTURER ..
L.Ll@L!J@)
33 34 L~@
J!,
LU
.36 I 010 37 l*O IO I LU@
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42 W@ !w I 11 43 2 Io I 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @ .
D:J::§J I The cracked pins identified were all from one heat treatment lot of material used in J:((J I foreign reactors .. A Westinghouse testing an~ an assessment_program is in.progress.to J:ID .I examine this situation more fully and the:.liceusee is prepared take ?P'P,rol?irat~ action JIIJ I based ~pon tlrn results of this rev~ew.
JTI]
8 9 FACILITY STATUS % POWER OTHER STATUS @ METHOD OF DISCOVERY DISCOVERY DESCRIPTION 32 80
- iliJ*W@ I OI O j O lI. . .____N_A_*- - -
8 9 10 12 *13 . 44 W@INotification from Westinghouse.
45 46 80 ACTIVITY CONTENT . Q\.
IIT]_
8 w @ ul@)I RELEASED OF RELEASE 9 10 11 AMOUNT OF ACTIVITY ~ /
NA 45 LOCATION OF RELEASE NA .
80 PERSONNEL EXPOSURES
NUMBER ~ TYPE DESCRIPTION 2EJ 8 j
9 Oj O I O11'~@L,._*
12 13
___N _ A _ ~ - - - - - - - - - - - - - - - - - - - - - - J 80 PERSONNEL INJURIES (;':;\
NUMBER
- QTI8 l9 O I O I O11I@
'-,2~~~~~~~~~~~-'--~~~~~~~~~~~~~~~....._~~~~~~~~~~~~~B_.O LOSS OF OR DAMAGE TO FACI.LITY TYPE DESCRIPTION
'4J\
~
~w@ *. . .
~~ 80 ISSUEDC,;\DESCRIPTION~ 8 {)()408v . . NRC USE ONLY e
~ LN.Je,._________N_A_ _ _ _ _ _ _ _ _ _ _ _ ___, I I I I I I I I I I I I I:
8 9 10 68 . 69 80 ;
NAME.OF PRFPAR*FR----.:.___ .;r iL* Wilson .i:>w.n,,.11:::.
804.,-357-3184 0
,II, ,,*c *-*
- e ATTACHMENT, PAGE 1 of 1 SURRY POWER STATION, UNIT 1 DOCKET NO: 50-280; 50-281 REPORT NO: 80-014/0lT-0 EVENT DATE: 3-20-80 TITLE OF EVENT: CONTROL ROD MECHANISM POSSIBLE DEFECT
- 1. DESCRIPTION OF EVENT:
Westinghouse has provided information on the stress corrosion cracking of control rod support pins and flexures in an operating PWR plant in a foreign country. Although Westinghouse state_d_ tll~re__ is no safety issue in domestic operating plants, they reported the event to the NRC under Title 18 CFR part 21. In so much as the control rod operations could be adversely effected should a broken pin be experienced, the event is reported in accordance with T.S.6.6.2.A.5.
- 2. PROBABLE CONSEQUENCES AND STATUS OF REDUNDANT SYSTEM:
Westinghouse has stated that no known cracking of support pins or flexures has been discovered in domestic plants and that on going testing efforts will provide information giving further assurance that this situation will not be a concern for any Westinghouse plant, Under these circumstances the health and safety of the public were not affected.
- 3. CAUSE:
The failure of Westinghouse supplied support pins noted to date has been limited to pins with solution heat treatment at 1625AF. It should be noted that the present process for solution heat treatment
( in the.range of 1950°F to 2000°F) gives little indication of potential stress corrosion cracking.
- 4. IMMEDIATE CORRECTIVE ACTION:
Westinghouse has proposed a support pin inspection program and has recommended no licensee action be taken by Non URI plants until the results have been concluded.
- 5. SCHEDULED CORRECTIVE ACTION:
Based upon the conclusion of the Westinghouse testing and assessment program, the licensee will take appropriate -measures to assure the reliability of this system.
- 6. ACTION TAKEN TO PREVENT RECURRENCE:
None
- 7. GENERIC IMPLICATIONS:
At this time this event is.not considered generic. Past inspections by Westinghouse have revealed no material failures in the pins or flexures of domestic plants, however, they are pursuing a further inspection program to determine more fully the reliability of the parts used.
