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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000289/LER-1984-007, Corrected LER 84-007-01:on 841116,once-through Steam Generator a Tubes Identified as Category C-3 Defective (More than 1% of Insp Tubes Defective).Further Manifestation of Problem Found During 1981 & 1982 Testing1985-05-31031 May 1985 Corrected LER 84-007-01:on 841116,once-through Steam Generator a Tubes Identified as Category C-3 Defective (More than 1% of Insp Tubes Defective).Further Manifestation of Problem Found During 1981 & 1982 Testing 05000289/LER-1983-046, Revised LER 83-046/01T-1:on 831214,nuclear safety-related Circuit for make-up Pump Lube Oil Pressure Trip Found Incorrectly Routed.Caused by Design Oversight.Circuits for make-up Pumps Rerouted in Raceways1984-01-31031 January 1984 Revised LER 83-046/01T-1:on 831214,nuclear safety-related Circuit for make-up Pump Lube Oil Pressure Trip Found Incorrectly Routed.Caused by Design Oversight.Circuits for make-up Pumps Rerouted in Raceways 05000289/LER-1982-001, Updated LER 82-001/01T-2:on 820225,during Control Room Habitability Review of NUREG-0737,Item III.D.3.4,potential Discovered for Contaminated Air to Enter Area Served by Control Bldg Ventilation Sys.Flange Installed1983-09-0707 September 1983 Updated LER 82-001/01T-2:on 820225,during Control Room Habitability Review of NUREG-0737,Item III.D.3.4,potential Discovered for Contaminated Air to Enter Area Served by Control Bldg Ventilation Sys.Flange Installed 05000289/LER-1983-003, Updated LER 83-003/01T-1:on 830211,PORV Special Insp Revealed Corrosion.Caused by Use of Acid Sulfur Compounds. PORV Internals Replaced & Leak Tested & Pressurizer Steam Space Inspected1983-06-0606 June 1983 Updated LER 83-003/01T-1:on 830211,PORV Special Insp Revealed Corrosion.Caused by Use of Acid Sulfur Compounds. PORV Internals Replaced & Leak Tested & Pressurizer Steam Space Inspected 05000320/LER-1979-015, Sanitized Version of LER 79-015/13L-1:on 790328,during Investigation of Radwaste & Makeup Sys,Three People Received Radiation Doses in Excess of Quarterly Limit.One Person Received Excess Dose to Skin.Investigation Suspended1982-06-10010 June 1982 Sanitized Version of LER 79-015/13L-1:on 790328,during Investigation of Radwaste & Makeup Sys,Three People Received Radiation Doses in Excess of Quarterly Limit.One Person Received Excess Dose to Skin.Investigation Suspended 05000289/LER-1982-0041982-04-14014 April 1982 LER 82-004:on 820413,EPRI Tests on Pressurizer Code Safety Valves Revealed Failure to Determine Ability of Valve to Perform Under Feed & Bleed Cooling If Pressurizer Power Operated Relief Valve Isolated.Investigation Underway 05000289/LER-1977-016, Supplemental LER 77-016/01T:on 770924,emergency Core Cooling Actuation Occurred.Caused by Full Open Pressurizer Power Relief Valve.Valve Closed1977-02-14014 February 1977 Supplemental LER 77-016/01T:on 770924,emergency Core Cooling Actuation Occurred.Caused by Full Open Pressurizer Power Relief Valve.Valve Closed 1985-05-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K4701999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for TMI-1.With ML20211H5111999-08-31031 August 1999 Non-proprietary Rev 1 to MPR-1820(NP), TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis ML20211Q3551999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Tmi,Unit 1.With ML20210R4791999-08-13013 August 1999 Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2 ML20210U4791999-07-31031 July 1999 Monthly Operating Rept for July 1999 for TMI-1.With ML20209G0011999-07-0909 July 1999 Staff Evaluation of Individual Plant Exam of External Events Submittal on Plant,Unit 1 ML20210K7651999-07-0909 July 1999 Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp Loca ML20209H8251999-07-0101 July 1999 Provides Commission with Evaluation of & Recommendations for Improvement in Processes Used in Staff Review & Approval of Applications for Transfer of Operating Licenses of TMI-1 & Pilgrim Station ML20209H1421999-06-30030 June 1999 Monthly Operating Rept for June 1999 for TMI-1.With ML20195H0751999-06-0808 June 1999 Drill 9904, 1999 Biennial Exercise for Three Mile Island ML20195H9261999-05-31031 May 1999 Monthly Operating Rept for May 1999 for TMI-1.With ML20209G0351999-05-31031 May 1999 TER on Review of TMI-1 IPEEE Submittal on High Winds,Floods & Other External Events (Hfo) ML20207B6621999-05-27027 May 1999 SER Finding That Licensee Established Acceptable Program to Periodically Verify design-basis Capability of safety-related MOVs at TMI-1 & That Util Adequately Addressed Actions Required in GL 96-05 ML20206R0571999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Tmi,Unit 1.With ML20206D4201999-04-20020 April 1999 Safety Evaluation Granting Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c for Fire Areas/Zones AB-FZ-4,CB-FA-1,FH-FZ-1,FH-FZ-6,FH-FZ-6, IPSH-FZ-1,IPSH-FZ-2,AB-FZ-3,AB-FZ-5,AB-FZ-7 & FH-FZ-2 ML20209G0071999-03-31031 March 1999 Submittal-Only Screening Review of Three Mile Island,Unit 1 Individual Plant Exam for External Events (Seismic Portion) ML20205K6851999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Tmi,Unit 1.With ML20210C0161999-03-0101 March 1999 Forwards Corrected Pp 3 of SECY-98-252.Correction Makes Changes to Footnote 3 as Directed by SRM on SECY-98-246 ML20207M8461999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for TMI-1.With ML20196K3561999-01-22022 January 1999 Safety Evaluation Concluding That Although Original Licensee Thermal Model Was Unacceptable for Ampacity Derating Assessments Revised Model Identified in 970624 Submittal Acceptable for Installed Electrical Raceway Ampacity Limits ML20207A9291998-12-31031 December 1998 1998 Annual Rept for TMI-1 & TMI-2 ML20196G4661998-12-31031 December 1998 British Energy Annual Rept & Accounts 1997/98. Prospectus of British Energy Share Offer Encl ML20196F6861998-12-0202 December 1998 Safety Evaluation Accepting Licensee Second 10-yr Interval ISI Program Plan Request for Alternative to ASME B&PV Code Section XI Requirements Re Actions to Be Taken Upon Detecting Leakage at Bolted Connection ML20198B8641998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for TMI-1.With ML20195C6921998-11-12012 November 1998 Safety Evaluation Supporting Amend 52 to License DPR-73 ML20195J8591998-11-12012 November 1998 Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan ML20196B7191998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for TMI-1.With ML20203G1211998-10-30030 October 1998 Informs Commission About Staff Preliminary Views Concerning Whether Proposed Purchase of TMI-1,by Amergen,Inc,Would Cause Commission to Know or Have Reason to Believe That License for TMI-1 Would Be Controlled by Foreign Govt ML20155E7511998-10-15015 October 1998 Rev 1 to Form NIS-1 Owners Data Rept for Isi,Rept on 1997 Outage 12R EC Exams of TMI-1 OTSG Tubing ML20154L5541998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for TMI Unit 1.With ML20153A9941998-09-16016 September 1998 Safety Evaluation Denying Request to Remove Missile Shields from Plant Design ML20151U8821998-09-0808 September 1998 SER on Revised Emergency Action Levels for Gpu Nuclear,Inc, Three Mile Island Nuclear Plant Units 1 & 2 ML20151V2811998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Tmi,Unit 1.With ML20237A8331998-08-12012 August 1998 Safety Evaluation Accepting USI A-46 Program Implementation at Plant,Unit 1 ML20237C6411998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Tmi,Unit 1 ML20236R2201998-06-30030 June 1998 Monthly Operating Rept for June 1998 for TMI-1 ML20236W9961998-06-0909 June 1998 1998 Quadrennial Simulator Certification Rept ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20249A1061998-05-31031 May 1998 Monthly Operating Rept for May 1998 for TMI-1 ML20247G0761998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Three Mile Island Nuclear Station,Unit 1 ML20212A2191998-04-22022 April 1998 Rev 3 to Gpu Nuclear Post-Defueling Monitored Storage QAP for Three Mile Island Unit 2 ML20248H6991998-04-0808 April 1998 Requests,By Negative Consent,Commission Approval of Intent to Inform Doe,Idaho Operations Ofc of Finding That Adequate Safety Basis Support Granting Exemption to 10CFR72 Seismic Design Requirement for ISFSI to Store TMI-2 Fuel Debris ML20216K1061998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Three Mile Island Nuclear Station,Unit 1 ML20217E0811998-03-24024 March 1998 Rev 0 to TR-121, TMI-1 Control Room Habitability for Max Hypothetical Accident ML20212E2291998-03-0404 March 1998 Rev 11 to 1000-PLN-7200,01, Gpu Nuclear Operational QAP, Consisting of Revised Pages & Pages for Which Pagination Affected ML20216F0981998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Three Mile Island Nuclear Station,Unit 1 ML20202F8121998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for TMI Nuclear Station, Unit 1 ML20199G8371998-01-22022 January 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Three Mile Island Nuclear Station,Unit 1 ML20198N2901998-01-12012 January 1998 Form NIS-1 Owners' Data Rept for Isi ML20199J3251997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Three Mile Island Nuclear Station,Unit 1 1999-09-30
[Table view] |
LER-2083-046, Revised LER 83-046/01T-1:on 831214,nuclear safety-related Circuit for make-up Pump Lube Oil Pressure Trip Found Incorrectly Routed.Caused by Design Oversight.Circuits for make-up Pumps Rerouted in Raceways |
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2892083046R00 - NRC Website |
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- _________-___ - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
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( EVENT DESCAIPTION AND PROBABLE CONSEQUEN ES h f I: f : l l_ A Nuclear Safety. related circuit for the make-up put; lube cil cressure rrir was l
, ; ., i l found to be incorrectly routed (MU-PIC) . The green tarked Cable was reuted in the l
- i .
- ; Ired channel tray. Some of the cables for the rakeur :::: lube cil'eressure :rir l l: ,s[ l circuit for MU-PlA, B and C are routed in non-safety trays. Due to current plant l
[o se l l condition no threat to public health and safety existed. This is reportable per [
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l c i 71 l T.S. 6.9.2. A.9. l Io te1 l E-1 7 8 9 SYST E M CAUSE CAUSE Cove. vA *.v f CODE CODE SUS; ODE COMPONENT CODI SUICODE SUB003E loisi 7 8 i S t r ]@ W@ l x l@ l zl 21 z ! z i :: 1 zl@ l xi@ !zi@
9 10 11 12 13 la 19 20 SEQUE NTI AL oCCURR ENCE REPORT REVISION EVENT YEAR REPORT NO e CODE TYPE N C, LE R
@ ,ajg/Ro ; 18 13 i L- .-] 1014161 lt_1 10111 IT I 3r' l--J 31 li I:
32 21 22 23 24 26 27 28 29 ACTION FUTURE EFFECT SHUTDOWN ATT ACHV ENT NDRD4 PRIME coup. Cou'ONENT TAKEN ACTION ON PLANT METHOD hours EUBMITTED FORMsv8. SUPPU E R MANUFACTURER l 0l 6l 0l lz l9 l9 l9 lg
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]@ 44 47 33 34 35 36 CAUSE DESCRIPT10N AND CORRECTIVE ACTIONS li l o l ] The circuits were originally installed as non-safety circuits and were not upgraded l li ;i l l vhen the circuir was mod'ified. This circuit will be disconnected until orcoer serara- t
,. ,_,j tion is achieved.
Circuits for all makeup pures will be rerouted in safety trade !
,. ,3; i raceways,
7 8 9 A S % POWER CTHER STATUS ISco RY -
DISCOVERY DESORI' TION NRC Order QC Report j i: 151,l X l@ l 0 l 0 l 0 ]Q] 44 l lB]Ql 45 4E s:
7 E' 9 10 12 11 ACTIVITY CONTENT 6 RELE ASED OF RELEASE AMOUNT oF ACTIVITY - LC0ATION OF RELE ASE J N/A S/A .I n s e l l zl @ Iz lgl 44 I l 45 E:
7 8 9 to 11 PERboNNEL T.xPCSURES NUv$ER TYPE CESCRIPTioN --
j, l - l l 0 l 0 l 0 l@l z j@l N/A E , ,. 2 i3 8402140323 840131 e e E RsoNr.E ; mUn iES PDR ADOCK 050002E!9 UvEER :ES:Risin:N S PDR 1
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LC05 C8 CR Dav4GE To FActuTv rl 3 ,q gpES:-T . 3,1 p
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l RESPONSE TO LER E3- 4 I. CURRENT ACTIVITES AT THE TIME OF OCCURRENCE
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- Three Mile Island Unit I was in cold shutdown.
g II. CIRCUMSTANCES LEADING TO HE OCCURRENCE -
In about 1974 a codification was implemented to pr: vide a icw lube cil pressure
- i. trip to MU-P1A, 3 and C. ~ The trip signal was blocked upon receipt of an Engineered Safeguards (ES) signal.
P b The oil pressure switches were replaced in (1977) with switches that were L seismically rated and ES interlock was removed. A: this time, the cables g should have been upgraded to safety grade, but were not.
4L Material Non-Conformance Report 115-81 identified a green marked cable in i a red channel tray. The cable was found to be related to the oil pressure trip. The cable was found to be incorrect 1" routec. .ne circuit was also
[ found to be classified as not important to safety.
t i III. DESCRIPTION The circuits for MU-PIC low oil pressure trip do not meet separation criteria. .
. The circuits were originally instelled as non-safety circuits and were not upgraded when the circuit was modified. This circuit did not meet the routing L' criteria for an important to safety circuit in that it originated in a green
- ~ b_ channel panel and was routed in a red channel tray. Trip circuits for MU-P1A k* and B have installed inacceptable aration. These circuits for MU-P1A B and C. are some non-sase!ety trays; however, the trays are all in Seismic 1 Buildings k- and have the same design as seismically mounted trays.
IV. RESULTANT EVENTS
! No significant event took place as a result of this event.
- 7. PREVIOUS EVENTS OF A SIMILAR NATUPZ LER 83-044 VI. ROOT CAUSE .
The apparent root cause for the occurrence was design oversight in that the trip circuits were not upgraded to meet separation criteria vhen the Field .4 Change package was issued to remove the ES interlock. ..
TII. IMMEDIATE CORRECTIVE ACTION So i==ediate corrective action is required because Of current plant conditien.
However, it should be noted that p ccedures implemen:ed sincy 9S1 previde assurance.that this type of event is unlikely te recur.
+ A mer- $=t I
Vill. LONG TERM CORRECTIVE ACTION
[
- 1. Circuit routing for MU-PlA and B were reviewed and found to have acceptable separation. The seismic adequacy of the circuits circuits for MU-PIA and B has been confirmed and lube oil pressure trip will be disconnected for MU-Plc until acceptable separation is established. The lube oil pressure trip circuit for MU-Plc may be reconnected for Tech Spec testing but will be disconnected when the
- l. test is complete. Disconnecting the low pressure trip is acceptable because it is for equipment protection only and the HPI function will be fully operable with cable disconnected. A modification package is being prepared to re-route the circuits in question for MU-PlA, B, and C. This modification is scheduled to be completed by July, 1984.
- 2. A review of all cable routing for modifications initiated after issuance of THI-1 Operating License, which upgraded a system or ecmponent to safety grade will be performed to assure that cables are properly routed and classified. This will be completed by July, 1984.
i i
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. o GPU Nuclear r.orporation Nuclear ;;;, cme:r8o s
Midd!etown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:
January 31, 1984 l 5211-84-2017 Dr. T. E. Murley Region I, Regional Administrator U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
Dear Sir:
Three Mile Island Nuclear Station; Unit l'(TMI-1)
Operating License No. DPR-50 Docket No. 50-289 LER 83-046/01T-1 Attached is revision (1) to Licensee Event Report 83-046/01T concerning improper safety-related circuit routing. Margin bars indicate where changes have been made.
Sincerely,
- 1. ). I kill Director, TMI-1 IIDil: RAS:j rg Enclosure cc: R. J. Conte Document Management Branch GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation d' i ' '
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05000289/LER-1983-002, Forwards LER 83-002/03L-0 | Forwards LER 83-002/03L-0 | | 05000289/LER-1983-003, Updated LER 83-003/01T-1:on 830211,PORV Special Insp Revealed Corrosion.Caused by Use of Acid Sulfur Compounds. PORV Internals Replaced & Leak Tested & Pressurizer Steam Space Inspected | Updated LER 83-003/01T-1:on 830211,PORV Special Insp Revealed Corrosion.Caused by Use of Acid Sulfur Compounds. PORV Internals Replaced & Leak Tested & Pressurizer Steam Space Inspected | | 05000289/LER-1983-005, Forwards LER 83-005/01T-0 | Forwards LER 83-005/01T-0 | | 05000289/LER-1983-006, Forwards LER 83-006/03L-0 | Forwards LER 83-006/03L-0 | | 05000289/LER-1983-007, Forwards LER 83-007/03L-0 | Forwards LER 83-007/03L-0 | | 05000289/LER-1983-008, Forwards LER 83-008/01T-0 | Forwards LER 83-008/01T-0 | | 05000289/LER-1983-009, Forwards LER 83-009/03L-0 | Forwards LER 83-009/03L-0 | | 05000289/LER-1983-010, Forwards LER 83-010/03L-0 | Forwards LER 83-010/03L-0 | | 05000289/LER-1983-011, Forwards LER 83-011/01T-0 | Forwards LER 83-011/01T-0 | | 05000289/LER-1983-044, Forwards LER 83-044/01T-1.Info Potentially Relevant to Plant Design & Procedures Phase of Proceeding.Svc List Encl | Forwards LER 83-044/01T-1.Info Potentially Relevant to Plant Design & Procedures Phase of Proceeding.Svc List Encl | | 05000289/LER-1983-046, Revised LER 83-046/01T-1:on 831214,nuclear safety-related Circuit for make-up Pump Lube Oil Pressure Trip Found Incorrectly Routed.Caused by Design Oversight.Circuits for make-up Pumps Rerouted in Raceways | Revised LER 83-046/01T-1:on 831214,nuclear safety-related Circuit for make-up Pump Lube Oil Pressure Trip Found Incorrectly Routed.Caused by Design Oversight.Circuits for make-up Pumps Rerouted in Raceways | |
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