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| {{#Wiki_filter:}} | | {{#Wiki_filter:REGULATORY'ORMATION DISTRIBUTION 8 M (RIDS)'ACCESSION NBR: 8710060387 DOC.DATE: 87/09/30 NOTARIZED: |
| | NO FACIL: 50-400 Shearon Harris, Nuclear Power Plant>Unit 1>Carolina AUTH.NAME AUTHOR AFFILIATION HUDSON>O.N.Carolina Power 4 Light Co, WATSON>R.A.Carol ina Power 8c Li gh t Co.RECIP.NAME RECIPIENT AFFILIATION DOCKET 05000400 |
| | |
| | ==SUBJECT:== |
| | LER 87-051-00: |
| | on 870831>main feedwater pump A tripped due feedwater oscillation. |
| | Caused bg feedwater sos design problems.Valve stem repaired 0 feedwater sos changes to improve reliability under evaluation. |
| | W/870930.ltr.DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR+ENCL/'IZE: TITLE: 50 73 Licensee Event Report (LER)>Incident Rpt>etc..NOTES: Application for permit renewal filed.ta 05000400 RECIPIENT ID CODE/NAME PD2-1 LA BUCKLEY, B COPIES LTTR ENCL 1 1 1 REC IP IENT ID CODE/NAME PD2-1 PD COPIES LTTR ENCL 1 1 INTERNAL: ACRS MICHE!SQN AEOD/DQA AEQD/DSP/ROAB DEDRQ'RR/DEST/CEB NR R/DEST/I C SB NRR/DEST/MTB NRR/DEST/RSB NRR/DLPG/HFB NRR/DQEA/EAB NRR/DREP/RPB NRR/PMAS/ILRB RES DEPY GI RES/DE/EIB EXTERNAL: EGS.Q GRQH, M LPDR NSIC HARRIS>J 1 1 1 1 1 1 1 2 1 1 1 1 1 2 1 1 1 1 1 1 1 2 1 1 ACRS MOELLER AEOD/DSP/NAS AEOD/DSP/TPAB NRR/DEBT/ADS NRR/DEST/ELB NRR/DEST/MEB NRR/DEST/PSB NRR/DEST/SQB NRR/DLPG/GAB NRR/DREP/RAB |
| | /SIB REQ 02 RES TELFORD>J RQN2 FILE 01 H ST LOBBY WARD NRC PDR NSIC NAYS>G 2 2 1 1 1 1 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 TOTAL NUMBER OF COP IES REQUIRED: LTTR 44 ENCL 43 NRC Form 38$'0;83)LICENSEE EVENT REPORT{LER)U.S.NUCLEAR REOULATORY COMMISSION APPROVED OMB NO.31504)104 EXPIRES: 8/31/88 FACILITY NAME (Il SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 DOCKET NUMBER (2)PA E 3 0 5 0 p p4 00 1OFO'UXILIARY FEEDWATER SYSTEM ACTUATIONS ON MAIN FEEDWATER PUMP TRIPS DUE TO DESIGN AND E UIPMENT FAILURE MONTH DAY YEAR EVENT DATE ISI YEAR LER NUMBER (8)SFOUSNTIAI. |
| | 'rgb NUMBER REVISION NUMBER MONTH DAY YEAR REPORT DATE (7)DOCKET NUMBER(S)r 0 5 0 0 0 FACILITY NAMES OTHER FACILITIES INVOLVED (8)31 87 8 7 0 5 1 0 0 9 3 0 8 7 0 5 0 0 0 OPERATINO MODE (8)POWE R LEYEL 0 0 20A02(B)20A05(~l (1)(B 20.405(e)(1 l(ii)20.405(~Ill((i)i)20A05(~)(1)(Iv)20.405(e)(I l(v)20.40S(cl 50.38(cll1) 50.38(cl(2) 50.73(e)l2)(0 50.73(el(2l(ill 50.73(e l(2)(Iii)X 50.73(e)(2)(ivl 50,73(e)(2)(v) 50.73(e)(2)(vip 50,73(e l(2)(v)it)(Al 50.73(e)(2)(viii)(Bl 50.73(~)(2)(x)THIS REPORT IS SUBMITTED PURSUANT T 0 THE REOUIREMENTS OF 10 CF R ()l/Check one or more of the IOIlovfinP) |
| | (11 73.71(B)73.71(c)OTHER (Specify in At)street below enrf In Test, IVRC Form 366A/LICENSEE CONTACT FOR THIS LER (12)NAME 0.N.HUDSON, SENIOR ENGINEER-REGULATORY COMPLIANCE TELEPHONE NUMBER AREA CODE 919 362-2 63 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)CAUSE SYS'EM COMPONENT MANUFAC-TURER REPORTABLE TO NPRDS.B)S 1?R..~,V,'I CAUSE SYSTEM COMPONENT MANUFAC.TURER EPORTAB LE TO NPRDS X S J FC VM 120 Y))o:.(l?o&~?:ia Ni SUPPLEMENTAL REPORT EXPECTED (14)YES (If yes, complete EXPECTED SIIShtISSIDII DATE)NO ABSTRACT ILlmlt to f400 specer, Ie., epproeimetely fifteen slnpre spree typetnritten Ilnesl (18)EXPECTED SU 8 M I SS ION DATE (15)MONTH DAY YEAR Abstract On August 31, 1987, the Shearon Harris Nuclear Power Plant was performing a Technical Specification required shutdown due to excess unidentified leakage (see LER-87-050-00). |
| | At 0408 with the reactor at 8/power, the"A" Main Feedwater Pump (MFP)tripped due to a feedwater oscillation. |
| | The root cause is Feedwater System design problems.Both motor-driven auxiliary feedwater (AFW)pumps started as required on loss of feedwater, since the"A" pump was the only MFP in operation at the time.MFP"B" was started at 0716 on August 31 and AFW was secured.At approximately 1530 on August 31, while the unit was in Mode 3, the"B" MFP tripped and AFW actuated.A restart attempt was made on the"B" MFP at 1703, but the pump tripped immediately. |
| | AFW actuated again.The cause of the trip was a separated valve stem on the"B" MFP recirculation valve.The valve stem was repaired.Feedwater system changes to improve reliability are being evaluated. |
| | Both MFPs were returned to service on September 1, 1987.8710060387 870930 PDR ADQCK 05000400 S PDR NRC Form 388 ro.srvi |
| | |
| | NRC Form 300A (94)3)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REGULATORY COMMISSION APPROVED OMB NO.3150-0104 EXPIRES: 8/31/BB FACILITY NAME (1)SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NUMBER (2)YEAR LER NUMBER (5)SEQUENTIAL NUMBER REv/BICN NUMBER PAGE (3)TEXT/K/rrcro<<>>ce/my/rr/ror/ |
| | r>>o r/8/or>>/NRC Forrn38549/(IT) |
| | Descri tion of Events 0 5 0 0 0 4 0 8 7.0 5 1 0 0 0 2 OF 0 r On August 31, 1987, the Shearon Harris Nuclear Power Plant (SHNPP)was performing a plant shutdown required by Technical Specifications due to exceeding 1 gallon per minute (gpm)unidentified Reactor Coolant System (EIIS:AB)leakage (see LER 87-050-00). |
| | Only one train of main feedwater (EIIS:SJ)was in operation. |
| | At 0408 on August 31, with the reactor (EIIS:AC)at 8X power, the"A" MFP tripped.Both motor-driven (MD)auxiliary, feedwater (AFW)pumps (EIIS:BA)started on the loss of the only running MFW pump as required.The turbine generator (EIIS:TB)was removed from the grid and the reactor shutdown per plant procedures. |
| | The"B" AFW pump was secured at 0425;the"A" pump was left running.The following actions were taken to investigate why.the MFP tripped.1.A p).intout of feedwater parameters during the time of the pump trip was obtained from the plant computer.From this printout, it appears that a high discharge pressure condition existed on the"A" MFP and caused it to trip.This was induced by a feedwater oscillation. |
| | 2.A work ticket was issued for Instrumentation and Control (ISC)personnel to check the setpoints on the"A" MFP high discharge pressure switches.A calibration check on one of the four discharge pressure switches showed that no significant drift had occurred since the last calibration. |
| | As a result, no other pressure switches were checked.The"A" MFP was restarted at 0303 on September 1, 1987 and ran normally.Meanwhile, the"B" MFP was started at 0716 and the"A" AFW pump was secured at 0819 on August 31.At approximately 1530 on August 31, while the unit was in Mode 3 (Hot Standby), the"B" MFP tripped.As required, both MD AFW pumps started.The"B" AFW pump was secured at 1532, and the"A" pump remained running.At 1703,'restart attempt on the"B" MFP was made from the Control Room, but the pump tripped immediately. |
| | As required, the"B" MD AFW pump started (the"A" MD AFW pump was still running).The"B" MD AFW pump was secured at 1704.Investigation of the"B" MFP trips revealed a separated valve stem on the"B" MFP recirculation valve (Masoneilan International Inc.Model f37-40412-8A-6"). |
| | The valve was repaired and"B" MFP was returned to service at 1620 on September 1, 1987.NRC FORM 300A (943)*U.S.GPO;1988 0 824 538/455 NRC Form 366A (943)LICENSEE EVENT EPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REOULATORY COMMISSION APPROVED OMB NO.3(50-0(04 EXPIRES: 8/31/88 FACILITY NAME (I)DOCKET NUMBER (2)YEAR LER NUMBER (6)SEOUENTIAL NUMSER REVISION NUMEER PACE (3)SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 TEXT//Prr>>ro<<>>co lr rodUEa/I/w a////Oo>>///l(C |
| | %%<<3//8/(9/(17)0 5 0 0 0 4 0 0 8 7 0 1-0 0 0 3 OF 0 3 Cause The cause of the first AFW actuation was the"A" MFP trip which was due to a feedwater oscillation. |
| | The oscillation was caused by the feedwater isolation valve reopening following the licensed control operator's two attempts to close it, in accordance with plant procedures. |
| | Due to feedwater system design problems, the MFP discharge valves were in a throttled position to maintain a lower differential pressure across the feedwater regulating valves.The combination of these created a high discharge pressure condition on the MFP, causing it to trip.The root cause of the MFP trip is the system design problems.The second and third AFW actuations, on the"B" MFP trips, were caused by equipment failure.The valve stem on the"B" MFP recirculation valve had separated. |
| | The cause of the valve stem failure was vibration due to the large differential pressure across the valve.~Anal sis These actuations are reportable in accordance with 10CFR50.73(a)(2)(iv) as automatic actuations of an Engineered Safety Feature (Auxiliary Feedwater System).There were no safety consequences as a result of this event;although operation of a safety system was challenged (AFW).The AFW system started as required upon loss of Main Feedwater to maintain water levels in the steam generators. |
| | In all three actuations, the plant was in the process of shutting down, and the loss of Main Feedwater did not result in a plant trip.The AFW start is non-safety and anticipatory. |
| | Had this event occurred under worse conditions (i.e., at 100X power), the loss of the MFP would have resulted in an automatic turbine runback to 50X power with the potential for a reactor trip, due to low steam generator water levels during the transient. |
| | A loss of all Main Feedwater is an analyzed accident in the FSAR.Previous AFW System actuations not associated with reactor trips were reported in LERs 87-026-00, 87-046-00, and 87-047-00. |
| | Corrective Actions The separated stem on the"B" MFP recirculation valve was weld repaired.An orifice will be install.ed on the MFP recirculation lines to provide back pressure on the valve and reduce the differential pressure across the valve.Additional changes to the feedwater system to improve its reliability are being examined.NRC FORM 366A (983)*U.S.OPO:(988.OB2d 538/455 Carolina Power&Light Company HARRIS NUCLEAR PROJECT P.O.Box 165 New Hill, NC 27562 SEI'0 198/File Number'SHF/10-13510C Letter Number.'HO-870504 (0)U.S.Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO~50-400 LICENSE NO.NPF-63 LICENSEE EVENT REPORT 87-051-00 Gentlemen.'n accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted. |
| | This report fulfills the requirement for a written report within thirty (30)days of a reportable occurrence and is in accordance with the format set forth in NUREG-1022, September, 1983.Very truly yours, R.A.Watson Vice President Harris Nuclear Project RAW:skin Enclosure cc.'r.J.Nelson Grace (NRC-RII)Mr.B.Buckley (NRR)Mr.G.Maxwell (NRC-SHNPP)MEM/LER-87-051/1/OS1 E |
| | FUEL fPB BREACH RCS f PB BREACH CONTAINMENT FPB BREACH UPDATE Csf STATUS BOARD BELOW CSF-I SUBCRITICALITY CSF-2 CORE COOLING CSF-3 HEAT SINK CSF-4 INTEGRITY CSF-5 CONTAINMENT 0 0 0 0 0 O~1 0 0 0 0 0 0 0 0 8 0 0--0 0 0 CSF-I YES RED OR MAGENTA NQ CS.-2 RED NQ FUEL JEOPARDY FUEL FPB QK YES CSF 3 RED NQ YES CSF-4 ED QR MAGENTA RCS JEOPARDY NQ RCS FPB l3K csf-s YES RED NQ csf-s.YES MAGENTA NQ CONTAINMENT FPB QK CONTAINMENT JEOPARDY REVIEV ATTACHMENT 3 UPDATE FPB STATUS BOARD BELQV-FUEL FP3 INTACT INTACT RCS FPB CQNTAINTMENT FPB INTACT JEOPARDIZED JEOPARDIZED JEOPARDIZED BREACHED BREACHED BREACHED EAL f LQVPATH REVIEWED NQ 10 YES z 4TVS NQ YES YES GENERAL EMERGENCY NQ (F'RQM FLQVPATH OR ATWS)3 FPBs BREACHED/JEOPARDIZED YES NQ4 YES SITE-EMERGENCY NQ (FROM FLQVPATH QR ATVS)2 FPBs BRE4CHED/JEOPARDIZED YES ALERT (fROM FLQVP4TH OR ATVS)YES 1 FPB BREACHED/JEQP4RDIZED YES NQ EVALUATE 4GAINST UNUSUAL EVENT MATRIX 12 M4NUAL NQ REACTOR TRIP SUCCESSFUL YES ANY UNUSU4L NQ EVENT CONDITION YES FUEL f PB YES BREACHED 13 NQ 4TVS ALERT ATWS SITE EMERGENCY ATVS GENERAL EMERGENCY 4TVS ALERT CONDITION EXISTS GNLY FOR THE PERIOD VAEN RODS ARE UP 4TVS SITE EHERGENCY CONDITION EXISTS IR)LY FOR THE PERIOD VHEH RGGS ARE (P 47VS GDKRAL fJS)RGGHCY CONDITION EXISTS ONLY FOR THE PERIOD VHEN RODS ARE UP DECLARE GENERAL EMERGENCY DECLARE SITE EMERGENCY DECLARE ALERT DECL4RE UNUSUAL EVENT NQ EMERGENCY DECLARATION 14 TIME TIME TIHE TIME TIME UNUSUAL EVEN T MATRIX GASEOUS OR LIQUID EFFLUENT(S) |
| | EXCEEDING TECHNICAL SPECIf'ICATIQHS FUEL DAMAGE INDICATION 1)GROSS f'AILED f'UEL DETECTOR INDICATES AN INCREASE GREATER TH4H 2 X 10 CPH WITHIN 30 MINUTES.2>SPECIFIC ACTIVITY OF THE RE4CTOR COOLANT EXCEEDS THE SHHPP TECHNICAL SPECIF'IC4TIO 3.4.8.f4ILURE TO COHPLY VITH THE SHNPP TECHHICIAL SPECIF ICATIONS INSTAN-TANEOUS LIMITS IN 3.11 FOR G4SEOUS EFFLUEHTS OR F'R LIQUID Eff LUEHTS.LOSS Qf SECONDARY CQQL4NT OR COOLING HA AM VA BREAKS I)IHDIDE COHT4INHEHT, 2)OUTSIDE COHTAIHHEHT OR f'AILURE OF A STEAM GENERATOR SAFETY OR RELIEF VALVE TO RESEAT AFTER OPERATIO)4 OR STEAH GENERATOR BLOVDOVH LINE BREAK.(4PPLICABLE IN MODES L2,63)OR APID DEPRESSURIZATIOH OF SECONDARY SIDE.CONTAINMENT INTEGRITY LOSS OF CON HT INTEGRITY REQUIRING SHUTDOVN BY THE SHHPP TECHNICAL SPECIFICATIONS 3.6.LOSS OF REACTI1R COOLANT I)IN EXCESS OF THE SHHPP TECHNICAL SPECIFICATION 3.4.6, 2)FAILURE Of A PRES" SURIZER SAF'ETY OR RELIEF VALVE TO RESEAT ARTER OPER4TION. |
| | 3)PRIMARY TO SECOND4RY SYSTEM LEAK4GE IN EXCESS Of THE SHHPP TECHNICAL SPECIF'IC4TIOH 3.4.6.LOSS OF SHUTDOWN f UNCTIQNS (DECAY HEAT>LOSS F ESF'EQUIRING SHUTDOVN BY THE SHHPP TECHNICAL SPECIFICATIONS (E,G BECAUSE OF MALFUNCTION, PERSONNEL ERROR OR PROCEDURAL INADEQUACY.) |
| | LOSS Of PQVER I)LOSS OF OFFSITE POVER, OR 2)LOSS Of BOTH DIESEL GENERATORS. |
| | LOSS QF CONTROL BOARD 4L*RM, INDICATIONS 4SSESSHENT 4ND CQHHUNICATIQN CAPABILITY 1)LOSS OF INPUTS FROH IHSTRUHEHTATIOH INCLUDED IN THE SHHPP TECHNICAL SPECIF ICATION 3.3'IHSTRUHEHTATION'O AN EXTENT REQUIRING PLANT SHUTDOVH.2)LOSS OF'LL REPRESENTATIVE HETEOROLOGICAL DAT4.3>INABILITY OF'RFIS TO PERFORM ITS INTENDED FUNCTION FOR 4 CONTIN-UOUS PERIOD OF 60 HIHUTES VHILE IN MODES 1,2,3,OR 4 AS DEFINED BYi A.FAILURE OF BOTH CPU'S.B.FAILURE OF BOTH DATA COHCENTRATORS C.FAILURE OF'OTH D4TA DISCS.D.INABILITY TO DISPLAY SPDS IN THE CONTROL ROOM.E INABILITY TO UPDATE CURRENT DAT4 DISPLAYS IN THE CONTROL ROOM.(THIS IS HOT TO BE CONSTRUED AS A f AILURE OF A SINGLE V4RIABLE OR SMALL SUBSET Of DAT4.4)f'AILURE Of'OTH SITE TELEPHONE AHD EHERGEHCY TELEPHONE SWITCHES f IRE SECURITY THREAT FIRE LASTING MORE THAN A SECURITY ALERT HAS 10 HIHUTES WITHIN BEEN DECLARED 43 DEFINED PROTECTED AREAS.IN THE SECURITY PLAN NATURAL PHENOMENA 4ND OTHER PLANT H4ZARDS!)ALARM ON SEISHIC HOHITORS INDICATING EARTHQUAKE. |
| | 2)HURRICANE OR TORNADO CROSSING EAB.3)AIRCRAf T CRASH VITHIN EAB OR UNUSUAL 4IRCRAF ACTIVITY OVER f 4CILITY.4>TRAIN DERAILHEHT VITHI I EAB.5)UNPLANNED EXPLOSION VITHIH EAB.'6)UNPLANNED TOXIC OR fLAHM4BLE GAS RELEASE VITHIH CAIL 7)TURBINE ROTATING COMPONENT FAILURE CAUSING R4PID PLANT SHUTDOVH.8)V4TER LEVELS IN THE MAIN AHD 4UXILIARY RESERVOIRS |
| | >2402 f'T.4ND 257.7 f T RESPECTIVELY OR V4TER LEVEL LESS TH4N 205.7FT IN THE M4IH RESERVIOR. |
| | SITE EMERGENCY COORDINATOR JUDGEMENTS OTHER PL4HT CONDITIONS EXIST THAT VARRAHT INCREASED 4VAREHESS ON THE PART OF A PLANT OPERATING STAR'f;CHATHAH, H4RNETT, LEE, AND V4KE COUNTIES AHD THE ST4TE Of NORTH CAROLINA OR REQUIRE PL4HT SHUTDOVH UNDER SHHPP TECHNICAL SPECIFIC4TIOH OR INVOLVE OTHER THAN NORMAL CONTROLLED SHUTDOWN (EAi COOLDOVN RATE EXCEEDING TECHNICAL SPECIFICATION LIMITS, PIPE CR4CKIHG FOUND DURING OPERATION). |
| | ATTACHMENT 1 OTHER EVENTS OR PECIFIC LCQs EXCEEDE 1>UNPLANNED ECCS DISCHARGE TO VESSEL 2)IHITI*TKIN OF'NY PLANT SHUTDOVH REQUIRED BY TECHNICAL SPECIFICATION 3>LOSS OF FIRE PROTECTION SYSTEM f'UNCTION REQUIRING SHUTDOVH BY THE SHHPP TECHNICAL SPECIFICATIOH 3.7.10.4)COHT4HIHATED INJURED INDIVIDUAL REQUIRING OFF SITE HEDIC4L TRE4TMEHT. |
| | 17 EMERGENCY ACTION LEVEL NETWORK PEP-101 REV.2 PAGE 9 OF 12 9109&DDGR 7-c i}} |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML18017A9181999-10-0808 October 1999 LER 99-008-00:on 991008,CR Emergency Filtration Sys Tech Specs Occurred.Caused by Site Personnel Failed to Recognize That Blocking Open CR Emergency Filtration Sys.Procedures Revised.With 991008 Ltr ML18017A8671999-09-10010 September 1999 LER 99-007-00:on 990811,determined That Cvis ARMs High Alarm Setpoints Were Not within TS Limit.Caused by Not Having Procedure to Verify If Cvis ARM High Alarm Setpoints Were within TS Requirements.Revised Procedures.With 990910 Ltr ML18016B0481999-08-0404 August 1999 LER 99-006-01:on 981124,noted Failure to Comply with TS 4.0.4 & TS 3/4.6.3, Civs. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Was Revised ML18016A9801999-06-0404 June 1999 LER 99-006-00:on 981124,failed to Comply with TS 4.0.4 & TS 3/4.6.3, Civ. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Will Be Revised.With 990604 Ltr ML18016A9111999-04-12012 April 1999 LER 99-005-00:on 990313,plant Exceeded ESFAS TS 3.3.2,Action 21.Caused by Inadequate Procedure Rev Preparation.Licensee Revised Applicable Maint Surveillance Test Procedure (MST-10072) to Identify TS Required Actions.With 990412 Ltr ML18016A8971999-04-0808 April 1999 LER 99-004-00:on 990312,unit Trip Was Noted.Caused by Degraded Condition of SG Water Level Flow Control Valve. Replaced Positioners on All Three FW Regulating Valves.With 990408 Ltr ML18016A8261999-02-22022 February 1999 LER 99-003-00:on 990123,noted That Plant Was Outside Design Basis Due to Isolation of Fire Protection Containment Sprinkler Sys.Caused by Human Error.Restored Containment Sprinkler Sys to Operable Status.With 990222 Ltr ML18016A8111999-02-12012 February 1999 LER 99-002-00:on 990114,RT Due to Not Removing Temporary Device from Relay Following Calibration Was Noted.Caused by Human Error.Counseled Personnel Involved in Event.With 990212 Ltr ML18016A7971999-02-0505 February 1999 LER 99-001-00:on 990106,SF Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Fasteners Bending Under Specific Circumstances.Increased Water Level.With 990205 Ltr ML18016A7941999-01-29029 January 1999 LER 98-004-01:on 980313,identified Design Deficiency Re Potential Runout of Tdafwp.Caused by Inadequate Original AFW Sys Design.Operability Evaluation Was Completed on 980313 & Addl Engineering Analysis Was Performed by Vendor ML18016A7211998-11-17017 November 1998 LER 98-007-00:on 981023,turbine Control Anomaly Caused Manual Rt.Caused by Failure to Incorporate Verbal Vendor Guidance in Operating Procedures.Addl Vendor Guidance Will Be Verified & Added to Procedures.With 981117 Ltr ML18016A4841998-07-0707 July 1998 LER 97-002-01:on 970207,determined That Cold Weather Conditions Resulted in Mfiv Being Potentially Inoperable During Period 970117-20.Caused by Inadequate Design of HVAC Sys.Implemented Mods to Steam Tunnel HVAC Sys ML18016A4701998-06-30030 June 1998 LER 97-021-03:on 980210,discovered That SFP Water Level Had Not Been Verified Greater than 23 Feet Above BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements. Will Submit TS Change Request to Revise TS 3.9.1.11 ML18016A4491998-06-0808 June 1998 LER 98-006-00:on 980508,failure to Perform Insp & Preventive Maint on MCCB as Required by TS Was Noted.Caused by Inadequate Sps.Tested 9 Pressurizer Heater Bank Breakers by Cycling each.W/980608 Ltr ML18022B0551998-05-20020 May 1998 LER 98-005-00:on 980420,TS Verbatim non-compliance Was Determined.Caused by Misinterpretation of TS Requirements. Issued Memo to Reemphasize Need to Comply W/Literal Meaning of TS Requirements in Verbatim manner.W/980520 Ltr ML18016A4061998-04-30030 April 1998 LER 98-002-01:on 980121,determined Ssps (P-11 Permissive) Testing Deficiency.Caused by Inadequate Review of Initial Ts.Will Revise & Perform Surveillance Test Procedures to Verify Operability of P-11 Permissive ML18016A3841998-04-13013 April 1998 LER 98-004-00:on 980313,design Deficiency Related to Indequate Runout Protection for Turbine Driven AFW Pump Was Identified.Caused by Inadequate Original AFW Sys Design. Evaluation (ESR 98-00100) Will Be completed.W/980409 Ltr ML18016A3441998-03-12012 March 1998 LER 97-021-02:on 980210,identified Failure to Properly Test non-safety Related Pressurizer Porv.Caused by Inadequate Surveillance Test Procedures.Revised Operations Surveillance Test OST-1117 to Include Testing of Subject PORV ML18016A3291998-02-27027 February 1998 LER 98-003-00:on 980129,failure to Perform Shutdown Margin Calculation Required by TS Surveillance Requirements Occurred.Caused by Ambiguity in TS 3.1.3.1.c.Procedures revised.W/980227 Ltr ML18016A3211998-02-20020 February 1998 LER 98-002-00:on 980121,solid State Protection Sys Testing Deficiency Occurred.Caused by Inadequate Review of Initial Tech Specs.Ts Testing Frequency for P-11 Permissive Revised. W/980217 Ltr ML18016A3131998-02-0909 February 1998 LER 98-001-00:on 980109,potential Condition Outside Design Basis Related to Instrument Air Sys Leak Causing SG pre- Heater Bypass Isolation Valves to Be Inoperable Was Noted. Caused by Inadequate Design Control.Generated Jco 98-01 ML18016A2641997-12-18018 December 1997 LER 97-024-00:on 971118,SSPS Testing Deficiency Was Noted. Caused by Inadequate Testing Scheme Provided by Ssps Vendor. Revised procedure.W/971218 Ltr ML18016A2501997-11-24024 November 1997 LER 97-023-00:on 920721,RCS PIV Testing Deficiency Was Noted.Caused by Failure to Consider All Testing Variables During Initial Sp Development.Surveillance Tp OST-1506 Was Revised to Incorporate Correction factor.W/971124 Ltr ML18016A2201997-10-22022 October 1997 LER 97-021-01:on 970922,discovered That Spent Fuel Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements.Revised Daily Surveillance Procedures ML18016A2081997-10-14014 October 1997 LER 97-016-01:on 970608,reactor Trip Occurred,Due to Personnel Error While Attempting to Adjust Power Range Nuclear Instrumentation Channel Following Performance of Calorimetric.Procedures revised.W/971014 Ltr ML18016A2111997-10-14014 October 1997 LER 96-008-02:on 960425,turbine Trip/Reactor Trip Occurred. Caused by High Resistance Connection Resulting from a Phase Switch Jaw & Blade Contacts.Failed a Phase Disconnect Switch on Breaker 52-7 Replaced ML18016A1931997-09-29029 September 1997 LER 97-022-00:on 970829,TS Required Shutdown Due to Expiration of AFW Lco.Caused by Personnel Error.Completed Repairs TDAFW Pump & Returned Plant to Svc on 970831. W/970926 Ltr ML18016A1891997-09-12012 September 1997 LER 97-020-00:on 970814,inadequate Fire Protection Provided for safety-related EDG Fuel Oil Transfer Pump Cables Resulted in Operation Outside Design Basis.Caused by Engineering Oversight.Established Fire watches.W/970912 Ltr ML18016A1881997-09-12012 September 1997 LER 97-021-00:on 970814,spent Fuel Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Misinterpretation of Ts.Directions Provided to Operations.W/970912 Ltr ML18012A8641997-08-18018 August 1997 LER 97-019-00:on 970720,turbine Trip/Reactor Trip Occurred. Caused by Three Phase Fault That Collapsed Excitation Field in Main Generator,Resulting in Generator Lockout.Exciter Rotor Assembly Was replaced.W/970818 Ltr ML18012A8581997-08-0808 August 1997 LER 96-018-01:on 960903,manual Reactor Trip Occurred Due to Loss of Normal Sw.Caused by Mechanical Failure of B Water Pump & a Normal SW to Remain Running Once Manually Started.Restored a Normal SW Pump to Svc ML18012A8551997-08-0808 August 1997 LER 96-013-02:on 961028,condition Outside of Design Basis Where RWST Had Been Aligned w/non-seismically Qualified Sys Was Identified.Caused by Failure to Reconcile Operating Procedure Lineups.Established Administrative Controls ML18012A8471997-07-31031 July 1997 LER 97-018-00:on 970701,determined That Plant Procedures Had Not Received Proper Reviews & Approvals.Caused by Failure to Comply W/Plant Administrative Procedure AP-006.Counseled Involved individuals.W/970731 Ltr ML18012A8371997-07-24024 July 1997 LER 97-S01-00:on 970405,unescorted Access Inappropriately Granted to Contract Outage Workers Was Determined.Caused by Personnel Error.Access Files for Individuals Inappropriately Granted Unescorted Access Were Placed on Access Hold ML18012A8291997-07-11011 July 1997 LER 97-017-00:on 970612,failed to Recognize Inoperable Reactor Afd Monitor.Caused by Personnel Error.Operators Involved in Event Will Be Counseled Prior to Assuming Shift duties.W/970711 Ltr ML18012A8301997-07-0808 July 1997 LER 97-016-00:on 970608,reactor Trip Occurred Due to Personnel Error in Adjusting Power Range (Pr) Nuclear Instrumentation (Ni).Issued Night Order Prohibiting Pr Ni Adjustment When Redundant Channel inoperable.W/970708 Ltr ML18012A8241997-07-0202 July 1997 LER 97-015-00:on 970602,inadequate Auxiliary Feedwater Sys Flow Control Valve Surveillance Testing Deficiency Was Identified.Caused by Failure to Recognize Impact on TS 4.7.1.2.1.Readjusted AFW FCV Actuator spring.W/970702 Ltr ML18022B0181997-06-13013 June 1997 LER 97-014-00:on 970514,SI Occurred During Ssps Surveillance Testing.Caused by Inattention to Detail During Recent Rev to Surveillance Test Procedure Being Used.Revised Deficient Surveillance procedures.W/970613 Ltr ML18012A8081997-06-0909 June 1997 LER 97-013-00:on 970508,entry Into Mode-6 Without Operable Components,Resulting in TS 3.0.4 Violation Occurred.Caused by Personnel Error.Personnel Involved counseled.W/970609 Ltr ML18012A8021997-06-0606 June 1997 LER 97-023-02:on 961114,design Deficiency Was Identified in Emergency DG Protection Circuitry.Caused by Inadequate Plant Design.Revised Surveillance Test Procedures OST-1013 & OST-1073.W/970606 Ltr ML18012A8011997-06-0404 June 1997 LER 97-012-00:on 970505,determined That Previous Auxiliary Control Panel Had Not Verified Operability of Interposing Relays.Caused by Misinterpretation of Tss.Reviewed Other Remote Shutdown Panel Transfer circuitry.W/970604 Ltr ML18012A7951997-05-29029 May 1997 LER 96-023-01:on 961114,design Deficiency in EDG Protection Circuitry Was Identified.Caused by Inadequate Original Plant Design.Surveillance Test Procedures OST-1013 & OST-1073 revised.W/970529 Ltr ML18012A7891997-05-22022 May 1997 LER 97-011-00:on 970422,inappropriate TS Interpretation Resulted in Violations of ECCS Accumulator TS & Entry Into TS 3.0.3.Caused by Procedural Inadequacy.Tsi 88-001 Cancelled 970508 & Procedures revised.W/970522 Ltr ML18012A7871997-05-19019 May 1997 LER 97-010-00:on 970418,design Deficiency Determined Re Reactor Coolant Pump Motor Oil Collection Sys.Caused by RCP Ocs Design Detail.Rcp Ocs Enclosures for Each of Three Installed RCP Motors Have Been modified.W/970519 Ltr ML18012A7761997-05-0707 May 1997 LER 97-009-00:on 970407,fuse Was Removed from CR Ventilation Isolation Signal Power Supply Circuitry Due to Personnel Error.Individuals Involved Were counseled.W/970507 Ltr ML18012A7751997-05-0505 May 1997 LER 97-008-00:on 970404,safety-related AHU Not Declared Inoperable During Maintenance on Associated Temperature Switches Resulting in Violation of Ts.Caused by Incorrect Interpretation.Operations Night Order issued.W/970505 Ltr ML18012A6291997-04-24024 April 1997 LER 97-007-00:on 970325,inoperable CCW Sys TS 3.0.3 Entry Made.Caused by Combination of Procedural Inadequacies, Improper Use of Procedure Guidance & Poor Communication. Applicable Individuals counseled.W/970423 Ltr ML18022B0151997-04-17017 April 1997 LER 97-006-00:on 970318,breach Was Identified in Thermo-Lag Fire Barrier Wall Due to Inadequate Initial Design,Poor Construction Methods & Incomplete as-built Design.Visual Insp of Thermo-Lag Barrier Walls performed.W/970417 Ltr ML18012A6041997-04-0303 April 1997 LER 97-004-00:on 970304,in-plant Spent Fuel Cask Handling Activities Conducted Outside Design Basis.Caused by Lack of Understanding of Requirements.Operations Placed on Hold Pending NRC Review & Approval of procedures.W/970331 Ltr ML18012A6031997-03-31031 March 1997 LER 97-003-00:on 970227,steam Generator Low Level Protection Circuitry Outside Design Basis Occurred.Caused by Inadequate Failure Modes & Effects Analysis Performed as-built Piping Configuration for S/G Level.Review performed.W/970331 Ltr 1999-09-10
[Table view] Category:RO)
MONTHYEARML18017A9181999-10-0808 October 1999 LER 99-008-00:on 991008,CR Emergency Filtration Sys Tech Specs Occurred.Caused by Site Personnel Failed to Recognize That Blocking Open CR Emergency Filtration Sys.Procedures Revised.With 991008 Ltr ML18017A8671999-09-10010 September 1999 LER 99-007-00:on 990811,determined That Cvis ARMs High Alarm Setpoints Were Not within TS Limit.Caused by Not Having Procedure to Verify If Cvis ARM High Alarm Setpoints Were within TS Requirements.Revised Procedures.With 990910 Ltr ML18016B0481999-08-0404 August 1999 LER 99-006-01:on 981124,noted Failure to Comply with TS 4.0.4 & TS 3/4.6.3, Civs. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Was Revised ML18016A9801999-06-0404 June 1999 LER 99-006-00:on 981124,failed to Comply with TS 4.0.4 & TS 3/4.6.3, Civ. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Will Be Revised.With 990604 Ltr ML18016A9111999-04-12012 April 1999 LER 99-005-00:on 990313,plant Exceeded ESFAS TS 3.3.2,Action 21.Caused by Inadequate Procedure Rev Preparation.Licensee Revised Applicable Maint Surveillance Test Procedure (MST-10072) to Identify TS Required Actions.With 990412 Ltr ML18016A8971999-04-0808 April 1999 LER 99-004-00:on 990312,unit Trip Was Noted.Caused by Degraded Condition of SG Water Level Flow Control Valve. Replaced Positioners on All Three FW Regulating Valves.With 990408 Ltr ML18016A8261999-02-22022 February 1999 LER 99-003-00:on 990123,noted That Plant Was Outside Design Basis Due to Isolation of Fire Protection Containment Sprinkler Sys.Caused by Human Error.Restored Containment Sprinkler Sys to Operable Status.With 990222 Ltr ML18016A8111999-02-12012 February 1999 LER 99-002-00:on 990114,RT Due to Not Removing Temporary Device from Relay Following Calibration Was Noted.Caused by Human Error.Counseled Personnel Involved in Event.With 990212 Ltr ML18016A7971999-02-0505 February 1999 LER 99-001-00:on 990106,SF Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Fasteners Bending Under Specific Circumstances.Increased Water Level.With 990205 Ltr ML18016A7941999-01-29029 January 1999 LER 98-004-01:on 980313,identified Design Deficiency Re Potential Runout of Tdafwp.Caused by Inadequate Original AFW Sys Design.Operability Evaluation Was Completed on 980313 & Addl Engineering Analysis Was Performed by Vendor ML18016A7211998-11-17017 November 1998 LER 98-007-00:on 981023,turbine Control Anomaly Caused Manual Rt.Caused by Failure to Incorporate Verbal Vendor Guidance in Operating Procedures.Addl Vendor Guidance Will Be Verified & Added to Procedures.With 981117 Ltr ML18016A4841998-07-0707 July 1998 LER 97-002-01:on 970207,determined That Cold Weather Conditions Resulted in Mfiv Being Potentially Inoperable During Period 970117-20.Caused by Inadequate Design of HVAC Sys.Implemented Mods to Steam Tunnel HVAC Sys ML18016A4701998-06-30030 June 1998 LER 97-021-03:on 980210,discovered That SFP Water Level Had Not Been Verified Greater than 23 Feet Above BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements. Will Submit TS Change Request to Revise TS 3.9.1.11 ML18016A4491998-06-0808 June 1998 LER 98-006-00:on 980508,failure to Perform Insp & Preventive Maint on MCCB as Required by TS Was Noted.Caused by Inadequate Sps.Tested 9 Pressurizer Heater Bank Breakers by Cycling each.W/980608 Ltr ML18022B0551998-05-20020 May 1998 LER 98-005-00:on 980420,TS Verbatim non-compliance Was Determined.Caused by Misinterpretation of TS Requirements. Issued Memo to Reemphasize Need to Comply W/Literal Meaning of TS Requirements in Verbatim manner.W/980520 Ltr ML18016A4061998-04-30030 April 1998 LER 98-002-01:on 980121,determined Ssps (P-11 Permissive) Testing Deficiency.Caused by Inadequate Review of Initial Ts.Will Revise & Perform Surveillance Test Procedures to Verify Operability of P-11 Permissive ML18016A3841998-04-13013 April 1998 LER 98-004-00:on 980313,design Deficiency Related to Indequate Runout Protection for Turbine Driven AFW Pump Was Identified.Caused by Inadequate Original AFW Sys Design. Evaluation (ESR 98-00100) Will Be completed.W/980409 Ltr ML18016A3441998-03-12012 March 1998 LER 97-021-02:on 980210,identified Failure to Properly Test non-safety Related Pressurizer Porv.Caused by Inadequate Surveillance Test Procedures.Revised Operations Surveillance Test OST-1117 to Include Testing of Subject PORV ML18016A3291998-02-27027 February 1998 LER 98-003-00:on 980129,failure to Perform Shutdown Margin Calculation Required by TS Surveillance Requirements Occurred.Caused by Ambiguity in TS 3.1.3.1.c.Procedures revised.W/980227 Ltr ML18016A3211998-02-20020 February 1998 LER 98-002-00:on 980121,solid State Protection Sys Testing Deficiency Occurred.Caused by Inadequate Review of Initial Tech Specs.Ts Testing Frequency for P-11 Permissive Revised. W/980217 Ltr ML18016A3131998-02-0909 February 1998 LER 98-001-00:on 980109,potential Condition Outside Design Basis Related to Instrument Air Sys Leak Causing SG pre- Heater Bypass Isolation Valves to Be Inoperable Was Noted. Caused by Inadequate Design Control.Generated Jco 98-01 ML18016A2641997-12-18018 December 1997 LER 97-024-00:on 971118,SSPS Testing Deficiency Was Noted. Caused by Inadequate Testing Scheme Provided by Ssps Vendor. Revised procedure.W/971218 Ltr ML18016A2501997-11-24024 November 1997 LER 97-023-00:on 920721,RCS PIV Testing Deficiency Was Noted.Caused by Failure to Consider All Testing Variables During Initial Sp Development.Surveillance Tp OST-1506 Was Revised to Incorporate Correction factor.W/971124 Ltr ML18016A2201997-10-22022 October 1997 LER 97-021-01:on 970922,discovered That Spent Fuel Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements.Revised Daily Surveillance Procedures ML18016A2081997-10-14014 October 1997 LER 97-016-01:on 970608,reactor Trip Occurred,Due to Personnel Error While Attempting to Adjust Power Range Nuclear Instrumentation Channel Following Performance of Calorimetric.Procedures revised.W/971014 Ltr ML18016A2111997-10-14014 October 1997 LER 96-008-02:on 960425,turbine Trip/Reactor Trip Occurred. Caused by High Resistance Connection Resulting from a Phase Switch Jaw & Blade Contacts.Failed a Phase Disconnect Switch on Breaker 52-7 Replaced ML18016A1931997-09-29029 September 1997 LER 97-022-00:on 970829,TS Required Shutdown Due to Expiration of AFW Lco.Caused by Personnel Error.Completed Repairs TDAFW Pump & Returned Plant to Svc on 970831. W/970926 Ltr ML18016A1891997-09-12012 September 1997 LER 97-020-00:on 970814,inadequate Fire Protection Provided for safety-related EDG Fuel Oil Transfer Pump Cables Resulted in Operation Outside Design Basis.Caused by Engineering Oversight.Established Fire watches.W/970912 Ltr ML18016A1881997-09-12012 September 1997 LER 97-021-00:on 970814,spent Fuel Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Misinterpretation of Ts.Directions Provided to Operations.W/970912 Ltr ML18012A8641997-08-18018 August 1997 LER 97-019-00:on 970720,turbine Trip/Reactor Trip Occurred. Caused by Three Phase Fault That Collapsed Excitation Field in Main Generator,Resulting in Generator Lockout.Exciter Rotor Assembly Was replaced.W/970818 Ltr ML18012A8581997-08-0808 August 1997 LER 96-018-01:on 960903,manual Reactor Trip Occurred Due to Loss of Normal Sw.Caused by Mechanical Failure of B Water Pump & a Normal SW to Remain Running Once Manually Started.Restored a Normal SW Pump to Svc ML18012A8551997-08-0808 August 1997 LER 96-013-02:on 961028,condition Outside of Design Basis Where RWST Had Been Aligned w/non-seismically Qualified Sys Was Identified.Caused by Failure to Reconcile Operating Procedure Lineups.Established Administrative Controls ML18012A8471997-07-31031 July 1997 LER 97-018-00:on 970701,determined That Plant Procedures Had Not Received Proper Reviews & Approvals.Caused by Failure to Comply W/Plant Administrative Procedure AP-006.Counseled Involved individuals.W/970731 Ltr ML18012A8371997-07-24024 July 1997 LER 97-S01-00:on 970405,unescorted Access Inappropriately Granted to Contract Outage Workers Was Determined.Caused by Personnel Error.Access Files for Individuals Inappropriately Granted Unescorted Access Were Placed on Access Hold ML18012A8291997-07-11011 July 1997 LER 97-017-00:on 970612,failed to Recognize Inoperable Reactor Afd Monitor.Caused by Personnel Error.Operators Involved in Event Will Be Counseled Prior to Assuming Shift duties.W/970711 Ltr ML18012A8301997-07-0808 July 1997 LER 97-016-00:on 970608,reactor Trip Occurred Due to Personnel Error in Adjusting Power Range (Pr) Nuclear Instrumentation (Ni).Issued Night Order Prohibiting Pr Ni Adjustment When Redundant Channel inoperable.W/970708 Ltr ML18012A8241997-07-0202 July 1997 LER 97-015-00:on 970602,inadequate Auxiliary Feedwater Sys Flow Control Valve Surveillance Testing Deficiency Was Identified.Caused by Failure to Recognize Impact on TS 4.7.1.2.1.Readjusted AFW FCV Actuator spring.W/970702 Ltr ML18022B0181997-06-13013 June 1997 LER 97-014-00:on 970514,SI Occurred During Ssps Surveillance Testing.Caused by Inattention to Detail During Recent Rev to Surveillance Test Procedure Being Used.Revised Deficient Surveillance procedures.W/970613 Ltr ML18012A8081997-06-0909 June 1997 LER 97-013-00:on 970508,entry Into Mode-6 Without Operable Components,Resulting in TS 3.0.4 Violation Occurred.Caused by Personnel Error.Personnel Involved counseled.W/970609 Ltr ML18012A8021997-06-0606 June 1997 LER 97-023-02:on 961114,design Deficiency Was Identified in Emergency DG Protection Circuitry.Caused by Inadequate Plant Design.Revised Surveillance Test Procedures OST-1013 & OST-1073.W/970606 Ltr ML18012A8011997-06-0404 June 1997 LER 97-012-00:on 970505,determined That Previous Auxiliary Control Panel Had Not Verified Operability of Interposing Relays.Caused by Misinterpretation of Tss.Reviewed Other Remote Shutdown Panel Transfer circuitry.W/970604 Ltr ML18012A7951997-05-29029 May 1997 LER 96-023-01:on 961114,design Deficiency in EDG Protection Circuitry Was Identified.Caused by Inadequate Original Plant Design.Surveillance Test Procedures OST-1013 & OST-1073 revised.W/970529 Ltr ML18012A7891997-05-22022 May 1997 LER 97-011-00:on 970422,inappropriate TS Interpretation Resulted in Violations of ECCS Accumulator TS & Entry Into TS 3.0.3.Caused by Procedural Inadequacy.Tsi 88-001 Cancelled 970508 & Procedures revised.W/970522 Ltr ML18012A7871997-05-19019 May 1997 LER 97-010-00:on 970418,design Deficiency Determined Re Reactor Coolant Pump Motor Oil Collection Sys.Caused by RCP Ocs Design Detail.Rcp Ocs Enclosures for Each of Three Installed RCP Motors Have Been modified.W/970519 Ltr ML18012A7761997-05-0707 May 1997 LER 97-009-00:on 970407,fuse Was Removed from CR Ventilation Isolation Signal Power Supply Circuitry Due to Personnel Error.Individuals Involved Were counseled.W/970507 Ltr ML18012A7751997-05-0505 May 1997 LER 97-008-00:on 970404,safety-related AHU Not Declared Inoperable During Maintenance on Associated Temperature Switches Resulting in Violation of Ts.Caused by Incorrect Interpretation.Operations Night Order issued.W/970505 Ltr ML18012A6291997-04-24024 April 1997 LER 97-007-00:on 970325,inoperable CCW Sys TS 3.0.3 Entry Made.Caused by Combination of Procedural Inadequacies, Improper Use of Procedure Guidance & Poor Communication. Applicable Individuals counseled.W/970423 Ltr ML18022B0151997-04-17017 April 1997 LER 97-006-00:on 970318,breach Was Identified in Thermo-Lag Fire Barrier Wall Due to Inadequate Initial Design,Poor Construction Methods & Incomplete as-built Design.Visual Insp of Thermo-Lag Barrier Walls performed.W/970417 Ltr ML18012A6041997-04-0303 April 1997 LER 97-004-00:on 970304,in-plant Spent Fuel Cask Handling Activities Conducted Outside Design Basis.Caused by Lack of Understanding of Requirements.Operations Placed on Hold Pending NRC Review & Approval of procedures.W/970331 Ltr ML18012A6031997-03-31031 March 1997 LER 97-003-00:on 970227,steam Generator Low Level Protection Circuitry Outside Design Basis Occurred.Caused by Inadequate Failure Modes & Effects Analysis Performed as-built Piping Configuration for S/G Level.Review performed.W/970331 Ltr 1999-09-10
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18017A9181999-10-0808 October 1999 LER 99-008-00:on 991008,CR Emergency Filtration Sys Tech Specs Occurred.Caused by Site Personnel Failed to Recognize That Blocking Open CR Emergency Filtration Sys.Procedures Revised.With 991008 Ltr ML18017A9151999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Shearon Harris Npp. with 991012 Ltr ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML18017A8671999-09-10010 September 1999 LER 99-007-00:on 990811,determined That Cvis ARMs High Alarm Setpoints Were Not within TS Limit.Caused by Not Having Procedure to Verify If Cvis ARM High Alarm Setpoints Were within TS Requirements.Revised Procedures.With 990910 Ltr ML18017A8621999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Harris Nuclear Plant.With 990908 Ltr ML18016B0481999-08-0404 August 1999 LER 99-006-01:on 981124,noted Failure to Comply with TS 4.0.4 & TS 3/4.6.3, Civs. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Was Revised ML18017A8361999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Shearon Harris Nuclear Power Plant.With 990811 Ltr ML18016B0151999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Shearon Harris Npp. with 990713 Ltr ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML18016A9801999-06-0404 June 1999 LER 99-006-00:on 981124,failed to Comply with TS 4.0.4 & TS 3/4.6.3, Civ. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Will Be Revised.With 990604 Ltr ML18016A9851999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Shearon Harris Nuclear Plant,Unit 1.With 990614 Ltr ML18017A8981999-05-12012 May 1999 Technical Rept Entitled, Harris Nuclear Plant-Bacteria Detection in Water from C&D Spent Fuel Pool Cooling Lines. ML18016A9581999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Shearon Harris Nuclear Plant,Unit 1.With 990513 Ltr ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML18016A9111999-04-12012 April 1999 LER 99-005-00:on 990313,plant Exceeded ESFAS TS 3.3.2,Action 21.Caused by Inadequate Procedure Rev Preparation.Licensee Revised Applicable Maint Surveillance Test Procedure (MST-10072) to Identify TS Required Actions.With 990412 Ltr ML18016A8971999-04-0808 April 1999 LER 99-004-00:on 990312,unit Trip Was Noted.Caused by Degraded Condition of SG Water Level Flow Control Valve. Replaced Positioners on All Three FW Regulating Valves.With 990408 Ltr ML18016A8941999-04-0505 April 1999 Revised Pages 20-25 to App 4A of non-proprietary Version of Rev 3 to HI-971760 ML18016A9101999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Shearon Harris Nuclear Power Plant.With 990413 Ltr ML18016A8661999-03-31031 March 1999 Shnpp Operator Training Simulator,Simulator Certification Quadrennial Rept. ML18017A8931999-02-28028 February 1999 Risks & Alternative Options Associated with Spent Fuel Storage at Shearon Harris Nuclear Power Plant. ML18016A8551999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Shearon Harris Npp. with 990312 Ltr ML18016A8261999-02-22022 February 1999 LER 99-003-00:on 990123,noted That Plant Was Outside Design Basis Due to Isolation of Fire Protection Containment Sprinkler Sys.Caused by Human Error.Restored Containment Sprinkler Sys to Operable Status.With 990222 Ltr ML18016A8531999-02-18018 February 1999 Non-proprietary Rev 3 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris SFP 'C' & 'D'. ML18016A8111999-02-12012 February 1999 LER 99-002-00:on 990114,RT Due to Not Removing Temporary Device from Relay Following Calibration Was Noted.Caused by Human Error.Counseled Personnel Involved in Event.With 990212 Ltr ML18016A7971999-02-0505 February 1999 LER 99-001-00:on 990106,SF Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Fasteners Bending Under Specific Circumstances.Increased Water Level.With 990205 Ltr ML18022B0631999-02-0404 February 1999 Rev 0 to Nuclear NDE Manual. with 28 Oversize Uncodable Drawings of Alternative Plan Scope & 4 Oversize Codable Drawings ML20202J1161999-02-0101 February 1999 SER Accepting Relief Requests Associated with Second 10-year Interval Inservice Testing Program ML18016A8041999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Shearon Harris Nuclear Power Plant.With 990211 Ltr ML18016A7941999-01-29029 January 1999 LER 98-004-01:on 980313,identified Design Deficiency Re Potential Runout of Tdafwp.Caused by Inadequate Original AFW Sys Design.Operability Evaluation Was Completed on 980313 & Addl Engineering Analysis Was Performed by Vendor ML18016A7801998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Shearon Harris Npp. with 990113 Ltr ML18016A7671998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Shnpp,Unit 1.With 981215 Ltr ML18016A9731998-11-28028 November 1998 Changes,Tests & Experiments, for Harris Nuclear Plant.Rept Provides Brief Description of Changes to Facility & Summary & of SE for Each Item That Was Implemented Under 10CFR50.59 Between 970608-981128.With 990527 Ltr ML18016A8351998-11-28028 November 1998 ISI Summary 8th Refueling Outage for Shearon Harris Power Plant,Unit 1. ML18016A7411998-11-25025 November 1998 Rev 1 to Shnpp Cycle 9 Colr. ML18016A7211998-11-17017 November 1998 LER 98-007-00:on 981023,turbine Control Anomaly Caused Manual Rt.Caused by Failure to Incorporate Verbal Vendor Guidance in Operating Procedures.Addl Vendor Guidance Will Be Verified & Added to Procedures.With 981117 Ltr ML18016A7071998-11-0303 November 1998 Rev 0 to Harris Unit 1 Cycle 9 Colr. ML18016A7201998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Shearon Harris Nuclear Power Plant.With 981113 Ltr ML20154F8701998-10-0606 October 1998 Safety Evaluation Authorizing Proposed Alternative to Requirements of OMa-1988,Part 10,Section 4.2.2.3 for 21 Category a Reactor Coolant Sys Pressure Isolation Valves ML18016A6201998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Harris Nuclear Power Plant.With 981012 Ltr ML18016A5971998-09-21021 September 1998 Rev 1 to Harris Unit 1 Cycle 8 Colr. ML18016A5881998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Shnpp,Unit 1.With 980914 Ltr ML18016A5071998-07-31031 July 1998 Monthly Operating Rept for Jul 1998 for Shearon Harris Nuclear Plant.W/980811 Ltr ML18016A9431998-07-0707 July 1998 Rev 1 to QAP Manual. ML18016A4841998-07-0707 July 1998 LER 97-002-01:on 970207,determined That Cold Weather Conditions Resulted in Mfiv Being Potentially Inoperable During Period 970117-20.Caused by Inadequate Design of HVAC Sys.Implemented Mods to Steam Tunnel HVAC Sys ML18016A9371998-06-30030 June 1998 Technical Rept on Matl Identification of Spent Fuel Piping Welds at Hnp. ML18016A4861998-06-30030 June 1998 Monthly Operating Rept for June 1998 for SHNPP.W/980715 Ltr ML18016A4701998-06-30030 June 1998 LER 97-021-03:on 980210,discovered That SFP Water Level Had Not Been Verified Greater than 23 Feet Above BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements. Will Submit TS Change Request to Revise TS 3.9.1.11 ML18016A4491998-06-0808 June 1998 LER 98-006-00:on 980508,failure to Perform Insp & Preventive Maint on MCCB as Required by TS Was Noted.Caused by Inadequate Sps.Tested 9 Pressurizer Heater Bank Breakers by Cycling each.W/980608 Ltr ML18016A4521998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Shearon Harris Nuclear Power Plant.W/980612 Ltr ML18016A7711998-05-26026 May 1998 Non-proprietary Rev 2 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris Spent Fuel Pools 'C' & 'D'. 1999-09-30
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REGULATORY'ORMATION DISTRIBUTION 8 M (RIDS)'ACCESSION NBR: 8710060387 DOC.DATE: 87/09/30 NOTARIZED:
NO FACIL: 50-400 Shearon Harris, Nuclear Power Plant>Unit 1>Carolina AUTH.NAME AUTHOR AFFILIATION HUDSON>O.N.Carolina Power 4 Light Co, WATSON>R.A.Carol ina Power 8c Li gh t Co.RECIP.NAME RECIPIENT AFFILIATION DOCKET 05000400
SUBJECT:
LER 87-051-00:
on 870831>main feedwater pump A tripped due feedwater oscillation.
Caused bg feedwater sos design problems.Valve stem repaired 0 feedwater sos changes to improve reliability under evaluation.
W/870930.ltr.DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR+ENCL/'IZE: TITLE: 50 73 Licensee Event Report (LER)>Incident Rpt>etc..NOTES: Application for permit renewal filed.ta 05000400 RECIPIENT ID CODE/NAME PD2-1 LA BUCKLEY, B COPIES LTTR ENCL 1 1 1 REC IP IENT ID CODE/NAME PD2-1 PD COPIES LTTR ENCL 1 1 INTERNAL: ACRS MICHE!SQN AEOD/DQA AEQD/DSP/ROAB DEDRQ'RR/DEST/CEB NR R/DEST/I C SB NRR/DEST/MTB NRR/DEST/RSB NRR/DLPG/HFB NRR/DQEA/EAB NRR/DREP/RPB NRR/PMAS/ILRB RES DEPY GI RES/DE/EIB EXTERNAL: EGS.Q GRQH, M LPDR NSIC HARRIS>J 1 1 1 1 1 1 1 2 1 1 1 1 1 2 1 1 1 1 1 1 1 2 1 1 ACRS MOELLER AEOD/DSP/NAS AEOD/DSP/TPAB NRR/DEBT/ADS NRR/DEST/ELB NRR/DEST/MEB NRR/DEST/PSB NRR/DEST/SQB NRR/DLPG/GAB NRR/DREP/RAB
/SIB REQ 02 RES TELFORD>J RQN2 FILE 01 H ST LOBBY WARD NRC PDR NSIC NAYS>G 2 2 1 1 1 1 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 TOTAL NUMBER OF COP IES REQUIRED: LTTR 44 ENCL 43 NRC Form 38$'0;83)LICENSEE EVENT REPORT{LER)U.S.NUCLEAR REOULATORY COMMISSION APPROVED OMB NO.31504)104 EXPIRES: 8/31/88 FACILITY NAME (Il SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 DOCKET NUMBER (2)PA E 3 0 5 0 p p4 00 1OFO'UXILIARY FEEDWATER SYSTEM ACTUATIONS ON MAIN FEEDWATER PUMP TRIPS DUE TO DESIGN AND E UIPMENT FAILURE MONTH DAY YEAR EVENT DATE ISI YEAR LER NUMBER (8)SFOUSNTIAI.
'rgb NUMBER REVISION NUMBER MONTH DAY YEAR REPORT DATE (7)DOCKET NUMBER(S)r 0 5 0 0 0 FACILITY NAMES OTHER FACILITIES INVOLVED (8)31 87 8 7 0 5 1 0 0 9 3 0 8 7 0 5 0 0 0 OPERATINO MODE (8)POWE R LEYEL 0 0 20A02(B)20A05(~l (1)(B 20.405(e)(1 l(ii)20.405(~Ill((i)i)20A05(~)(1)(Iv)20.405(e)(I l(v)20.40S(cl 50.38(cll1) 50.38(cl(2) 50.73(e)l2)(0 50.73(el(2l(ill 50.73(e l(2)(Iii)X 50.73(e)(2)(ivl 50,73(e)(2)(v) 50.73(e)(2)(vip 50,73(e l(2)(v)it)(Al 50.73(e)(2)(viii)(Bl 50.73(~)(2)(x)THIS REPORT IS SUBMITTED PURSUANT T 0 THE REOUIREMENTS OF 10 CF R ()l/Check one or more of the IOIlovfinP)
(11 73.71(B)73.71(c)OTHER (Specify in At)street below enrf In Test, IVRC Form 366A/LICENSEE CONTACT FOR THIS LER (12)NAME 0.N.HUDSON, SENIOR ENGINEER-REGULATORY COMPLIANCE TELEPHONE NUMBER AREA CODE 919 362-2 63 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)CAUSE SYS'EM COMPONENT MANUFAC-TURER REPORTABLE TO NPRDS.B)S 1?R..~,V,'I CAUSE SYSTEM COMPONENT MANUFAC.TURER EPORTAB LE TO NPRDS X S J FC VM 120 Y))o:.(l?o&~?:ia Ni SUPPLEMENTAL REPORT EXPECTED (14)YES (If yes, complete EXPECTED SIIShtISSIDII DATE)NO ABSTRACT ILlmlt to f400 specer, Ie., epproeimetely fifteen slnpre spree typetnritten Ilnesl (18)EXPECTED SU 8 M I SS ION DATE (15)MONTH DAY YEAR Abstract On August 31, 1987, the Shearon Harris Nuclear Power Plant was performing a Technical Specification required shutdown due to excess unidentified leakage (see LER-87-050-00).
At 0408 with the reactor at 8/power, the"A" Main Feedwater Pump (MFP)tripped due to a feedwater oscillation.
The root cause is Feedwater System design problems.Both motor-driven auxiliary feedwater (AFW)pumps started as required on loss of feedwater, since the"A" pump was the only MFP in operation at the time.MFP"B" was started at 0716 on August 31 and AFW was secured.At approximately 1530 on August 31, while the unit was in Mode 3, the"B" MFP tripped and AFW actuated.A restart attempt was made on the"B" MFP at 1703, but the pump tripped immediately.
AFW actuated again.The cause of the trip was a separated valve stem on the"B" MFP recirculation valve.The valve stem was repaired.Feedwater system changes to improve reliability are being evaluated.
Both MFPs were returned to service on September 1, 1987.8710060387 870930 PDR ADQCK 05000400 S PDR NRC Form 388 ro.srvi
NRC Form 300A (94)3)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REGULATORY COMMISSION APPROVED OMB NO.3150-0104 EXPIRES: 8/31/BB FACILITY NAME (1)SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NUMBER (2)YEAR LER NUMBER (5)SEQUENTIAL NUMBER REv/BICN NUMBER PAGE (3)TEXT/K/rrcro<<>>ce/my/rr/ror/
r>>o r/8/or>>/NRC Forrn38549/(IT)
Descri tion of Events 0 5 0 0 0 4 0 8 7.0 5 1 0 0 0 2 OF 0 r On August 31, 1987, the Shearon Harris Nuclear Power Plant (SHNPP)was performing a plant shutdown required by Technical Specifications due to exceeding 1 gallon per minute (gpm)unidentified Reactor Coolant System (EIIS:AB)leakage (see LER 87-050-00).
Only one train of main feedwater (EIIS:SJ)was in operation.
At 0408 on August 31, with the reactor (EIIS:AC)at 8X power, the"A" MFP tripped.Both motor-driven (MD)auxiliary, feedwater (AFW)pumps (EIIS:BA)started on the loss of the only running MFW pump as required.The turbine generator (EIIS:TB)was removed from the grid and the reactor shutdown per plant procedures.
The"B" AFW pump was secured at 0425;the"A" pump was left running.The following actions were taken to investigate why.the MFP tripped.1.A p).intout of feedwater parameters during the time of the pump trip was obtained from the plant computer.From this printout, it appears that a high discharge pressure condition existed on the"A" MFP and caused it to trip.This was induced by a feedwater oscillation.
2.A work ticket was issued for Instrumentation and Control (ISC)personnel to check the setpoints on the"A" MFP high discharge pressure switches.A calibration check on one of the four discharge pressure switches showed that no significant drift had occurred since the last calibration.
As a result, no other pressure switches were checked.The"A" MFP was restarted at 0303 on September 1, 1987 and ran normally.Meanwhile, the"B" MFP was started at 0716 and the"A" AFW pump was secured at 0819 on August 31.At approximately 1530 on August 31, while the unit was in Mode 3 (Hot Standby), the"B" MFP tripped.As required, both MD AFW pumps started.The"B" AFW pump was secured at 1532, and the"A" pump remained running.At 1703,'restart attempt on the"B" MFP was made from the Control Room, but the pump tripped immediately.
As required, the"B" MD AFW pump started (the"A" MD AFW pump was still running).The"B" MD AFW pump was secured at 1704.Investigation of the"B" MFP trips revealed a separated valve stem on the"B" MFP recirculation valve (Masoneilan International Inc.Model f37-40412-8A-6").
The valve was repaired and"B" MFP was returned to service at 1620 on September 1, 1987.NRC FORM 300A (943)*U.S.GPO;1988 0 824 538/455 NRC Form 366A (943)LICENSEE EVENT EPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REOULATORY COMMISSION APPROVED OMB NO.3(50-0(04 EXPIRES: 8/31/88 FACILITY NAME (I)DOCKET NUMBER (2)YEAR LER NUMBER (6)SEOUENTIAL NUMSER REVISION NUMEER PACE (3)SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 TEXT//Prr>>ro<<>>co lr rodUEa/I/w a////Oo>>///l(C
%%<<3//8/(9/(17)0 5 0 0 0 4 0 0 8 7 0 1-0 0 0 3 OF 0 3 Cause The cause of the first AFW actuation was the"A" MFP trip which was due to a feedwater oscillation.
The oscillation was caused by the feedwater isolation valve reopening following the licensed control operator's two attempts to close it, in accordance with plant procedures.
Due to feedwater system design problems, the MFP discharge valves were in a throttled position to maintain a lower differential pressure across the feedwater regulating valves.The combination of these created a high discharge pressure condition on the MFP, causing it to trip.The root cause of the MFP trip is the system design problems.The second and third AFW actuations, on the"B" MFP trips, were caused by equipment failure.The valve stem on the"B" MFP recirculation valve had separated.
The cause of the valve stem failure was vibration due to the large differential pressure across the valve.~Anal sis These actuations are reportable in accordance with 10CFR50.73(a)(2)(iv) as automatic actuations of an Engineered Safety Feature (Auxiliary Feedwater System).There were no safety consequences as a result of this event;although operation of a safety system was challenged (AFW).The AFW system started as required upon loss of Main Feedwater to maintain water levels in the steam generators.
In all three actuations, the plant was in the process of shutting down, and the loss of Main Feedwater did not result in a plant trip.The AFW start is non-safety and anticipatory.
Had this event occurred under worse conditions (i.e., at 100X power), the loss of the MFP would have resulted in an automatic turbine runback to 50X power with the potential for a reactor trip, due to low steam generator water levels during the transient.
A loss of all Main Feedwater is an analyzed accident in the FSAR.Previous AFW System actuations not associated with reactor trips were reported in LERs 87-026-00, 87-046-00, and 87-047-00.
Corrective Actions The separated stem on the"B" MFP recirculation valve was weld repaired.An orifice will be install.ed on the MFP recirculation lines to provide back pressure on the valve and reduce the differential pressure across the valve.Additional changes to the feedwater system to improve its reliability are being examined.NRC FORM 366A (983)*U.S.OPO:(988.OB2d 538/455 Carolina Power&Light Company HARRIS NUCLEAR PROJECT P.O.Box 165 New Hill, NC 27562 SEI'0 198/File Number'SHF/10-13510C Letter Number.'HO-870504 (0)U.S.Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO~50-400 LICENSE NO.NPF-63 LICENSEE EVENT REPORT 87-051-00 Gentlemen.'n accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted.
This report fulfills the requirement for a written report within thirty (30)days of a reportable occurrence and is in accordance with the format set forth in NUREG-1022, September, 1983.Very truly yours, R.A.Watson Vice President Harris Nuclear Project RAW:skin Enclosure cc.'r.J.Nelson Grace (NRC-RII)Mr.B.Buckley (NRR)Mr.G.Maxwell (NRC-SHNPP)MEM/LER-87-051/1/OS1 E
FUEL fPB BREACH RCS f PB BREACH CONTAINMENT FPB BREACH UPDATE Csf STATUS BOARD BELOW CSF-I SUBCRITICALITY CSF-2 CORE COOLING CSF-3 HEAT SINK CSF-4 INTEGRITY CSF-5 CONTAINMENT 0 0 0 0 0 O~1 0 0 0 0 0 0 0 0 8 0 0--0 0 0 CSF-I YES RED OR MAGENTA NQ CS.-2 RED NQ FUEL JEOPARDY FUEL FPB QK YES CSF 3 RED NQ YES CSF-4 ED QR MAGENTA RCS JEOPARDY NQ RCS FPB l3K csf-s YES RED NQ csf-s.YES MAGENTA NQ CONTAINMENT FPB QK CONTAINMENT JEOPARDY REVIEV ATTACHMENT 3 UPDATE FPB STATUS BOARD BELQV-FUEL FP3 INTACT INTACT RCS FPB CQNTAINTMENT FPB INTACT JEOPARDIZED JEOPARDIZED JEOPARDIZED BREACHED BREACHED BREACHED EAL f LQVPATH REVIEWED NQ 10 YES z 4TVS NQ YES YES GENERAL EMERGENCY NQ (F'RQM FLQVPATH OR ATWS)3 FPBs BREACHED/JEOPARDIZED YES NQ4 YES SITE-EMERGENCY NQ (FROM FLQVPATH QR ATVS)2 FPBs BRE4CHED/JEOPARDIZED YES ALERT (fROM FLQVP4TH OR ATVS)YES 1 FPB BREACHED/JEQP4RDIZED YES NQ EVALUATE 4GAINST UNUSUAL EVENT MATRIX 12 M4NUAL NQ REACTOR TRIP SUCCESSFUL YES ANY UNUSU4L NQ EVENT CONDITION YES FUEL f PB YES BREACHED 13 NQ 4TVS ALERT ATWS SITE EMERGENCY ATVS GENERAL EMERGENCY 4TVS ALERT CONDITION EXISTS GNLY FOR THE PERIOD VAEN RODS ARE UP 4TVS SITE EHERGENCY CONDITION EXISTS IR)LY FOR THE PERIOD VHEH RGGS ARE (P 47VS GDKRAL fJS)RGGHCY CONDITION EXISTS ONLY FOR THE PERIOD VHEN RODS ARE UP DECLARE GENERAL EMERGENCY DECLARE SITE EMERGENCY DECLARE ALERT DECL4RE UNUSUAL EVENT NQ EMERGENCY DECLARATION 14 TIME TIME TIHE TIME TIME UNUSUAL EVEN T MATRIX GASEOUS OR LIQUID EFFLUENT(S)
EXCEEDING TECHNICAL SPECIf'ICATIQHS FUEL DAMAGE INDICATION 1)GROSS f'AILED f'UEL DETECTOR INDICATES AN INCREASE GREATER TH4H 2 X 10 CPH WITHIN 30 MINUTES.2>SPECIFIC ACTIVITY OF THE RE4CTOR COOLANT EXCEEDS THE SHHPP TECHNICAL SPECIF'IC4TIO 3.4.8.f4ILURE TO COHPLY VITH THE SHNPP TECHHICIAL SPECIF ICATIONS INSTAN-TANEOUS LIMITS IN 3.11 FOR G4SEOUS EFFLUEHTS OR F'R LIQUID Eff LUEHTS.LOSS Qf SECONDARY CQQL4NT OR COOLING HA AM VA BREAKS I)IHDIDE COHT4INHEHT, 2)OUTSIDE COHTAIHHEHT OR f'AILURE OF A STEAM GENERATOR SAFETY OR RELIEF VALVE TO RESEAT AFTER OPERATIO)4 OR STEAH GENERATOR BLOVDOVH LINE BREAK.(4PPLICABLE IN MODES L2,63)OR APID DEPRESSURIZATIOH OF SECONDARY SIDE.CONTAINMENT INTEGRITY LOSS OF CON HT INTEGRITY REQUIRING SHUTDOVN BY THE SHHPP TECHNICAL SPECIFICATIONS 3.6.LOSS OF REACTI1R COOLANT I)IN EXCESS OF THE SHHPP TECHNICAL SPECIFICATION 3.4.6, 2)FAILURE Of A PRES" SURIZER SAF'ETY OR RELIEF VALVE TO RESEAT ARTER OPER4TION.
3)PRIMARY TO SECOND4RY SYSTEM LEAK4GE IN EXCESS Of THE SHHPP TECHNICAL SPECIF'IC4TIOH 3.4.6.LOSS OF SHUTDOWN f UNCTIQNS (DECAY HEAT>LOSS F ESF'EQUIRING SHUTDOVN BY THE SHHPP TECHNICAL SPECIFICATIONS (E,G BECAUSE OF MALFUNCTION, PERSONNEL ERROR OR PROCEDURAL INADEQUACY.)
LOSS Of PQVER I)LOSS OF OFFSITE POVER, OR 2)LOSS Of BOTH DIESEL GENERATORS.
LOSS QF CONTROL BOARD 4L*RM, INDICATIONS 4SSESSHENT 4ND CQHHUNICATIQN CAPABILITY 1)LOSS OF INPUTS FROH IHSTRUHEHTATIOH INCLUDED IN THE SHHPP TECHNICAL SPECIF ICATION 3.3'IHSTRUHEHTATION'O AN EXTENT REQUIRING PLANT SHUTDOVH.2)LOSS OF'LL REPRESENTATIVE HETEOROLOGICAL DAT4.3>INABILITY OF'RFIS TO PERFORM ITS INTENDED FUNCTION FOR 4 CONTIN-UOUS PERIOD OF 60 HIHUTES VHILE IN MODES 1,2,3,OR 4 AS DEFINED BYi A.FAILURE OF BOTH CPU'S.B.FAILURE OF BOTH DATA COHCENTRATORS C.FAILURE OF'OTH D4TA DISCS.D.INABILITY TO DISPLAY SPDS IN THE CONTROL ROOM.E INABILITY TO UPDATE CURRENT DAT4 DISPLAYS IN THE CONTROL ROOM.(THIS IS HOT TO BE CONSTRUED AS A f AILURE OF A SINGLE V4RIABLE OR SMALL SUBSET Of DAT4.4)f'AILURE Of'OTH SITE TELEPHONE AHD EHERGEHCY TELEPHONE SWITCHES f IRE SECURITY THREAT FIRE LASTING MORE THAN A SECURITY ALERT HAS 10 HIHUTES WITHIN BEEN DECLARED 43 DEFINED PROTECTED AREAS.IN THE SECURITY PLAN NATURAL PHENOMENA 4ND OTHER PLANT H4ZARDS!)ALARM ON SEISHIC HOHITORS INDICATING EARTHQUAKE.
2)HURRICANE OR TORNADO CROSSING EAB.3)AIRCRAf T CRASH VITHIN EAB OR UNUSUAL 4IRCRAF ACTIVITY OVER f 4CILITY.4>TRAIN DERAILHEHT VITHI I EAB.5)UNPLANNED EXPLOSION VITHIH EAB.'6)UNPLANNED TOXIC OR fLAHM4BLE GAS RELEASE VITHIH CAIL 7)TURBINE ROTATING COMPONENT FAILURE CAUSING R4PID PLANT SHUTDOVH.8)V4TER LEVELS IN THE MAIN AHD 4UXILIARY RESERVOIRS
>2402 f'T.4ND 257.7 f T RESPECTIVELY OR V4TER LEVEL LESS TH4N 205.7FT IN THE M4IH RESERVIOR.
SITE EMERGENCY COORDINATOR JUDGEMENTS OTHER PL4HT CONDITIONS EXIST THAT VARRAHT INCREASED 4VAREHESS ON THE PART OF A PLANT OPERATING STAR'f;CHATHAH, H4RNETT, LEE, AND V4KE COUNTIES AHD THE ST4TE Of NORTH CAROLINA OR REQUIRE PL4HT SHUTDOVH UNDER SHHPP TECHNICAL SPECIFIC4TIOH OR INVOLVE OTHER THAN NORMAL CONTROLLED SHUTDOWN (EAi COOLDOVN RATE EXCEEDING TECHNICAL SPECIFICATION LIMITS, PIPE CR4CKIHG FOUND DURING OPERATION).
ATTACHMENT 1 OTHER EVENTS OR PECIFIC LCQs EXCEEDE 1>UNPLANNED ECCS DISCHARGE TO VESSEL 2)IHITI*TKIN OF'NY PLANT SHUTDOVH REQUIRED BY TECHNICAL SPECIFICATION 3>LOSS OF FIRE PROTECTION SYSTEM f'UNCTION REQUIRING SHUTDOVH BY THE SHHPP TECHNICAL SPECIFICATIOH 3.7.10.4)COHT4HIHATED INJURED INDIVIDUAL REQUIRING OFF SITE HEDIC4L TRE4TMEHT.
17 EMERGENCY ACTION LEVEL NETWORK PEP-101 REV.2 PAGE 9 OF 12 9109&DDGR 7-c i