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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20199J8551997-11-24024 November 1997 Special Rept 2-SR-97-001:on 971025,RCS Pressure Transient Resulted in Automatic Actuation of Pressurizer Porv.Caused by Operator Misconception Over Actual Arming Setpoint of LTOP Sys.Alarm Procedures Will Be Revised ML20083R7491995-05-22022 May 1995 Special Rept 1-SR-95-002:on 950505,lightning Strike Damaged Meteorological Instrumentation at Primary & Backup Towers ML20078A3221995-01-12012 January 1995 Special Rept:On 941222,unit 1 Train a EDG Tripped.Caused by Internal Oil Leak of Trip Device Bypassed in Emergency Operating Mode.Trip Device Replaced W/New,Calibr Pressure Switch ML20058C0011993-11-18018 November 1993 Ro:On 931117,unusual Event Declared Due to Loss of All Primary & Backup Meteorological Sys Instruments.Caused by Lightning Strike Damaging back-up Tower Instruments.Local Natl Weather Svc Contacted ML20101L2991992-06-29029 June 1992 Special Rept 1-SR-92-001-00:on 920528,engine Trip Occurred Due to Apparent High Vibration at Engine Rear Vibration Sensor.Caused by Low Lube Oil Pressure.Sensor & Related Components Replaced ML20101D2201992-06-0404 June 1992 Ro:On 920603,control Room Alarms Annunicated Loss of One of Two Compressors in Train a of Control Room HVAC Sys.Caused by Low Oil Pressure in Compressor.Both Trains of Control Room HVAC Sys Restored to Svc & Declared Operable ML20092F0281992-02-13013 February 1992 Special Rept 1-SR-90-002-01:on 900221,RCS Transient Resulted in Automatic Actuation of Porv.Caused by Insufficient Letdown Flow.Repetitive Step of Differing Plant Responses Expected Eliminated ML20062F8251990-11-20020 November 1990 Ro:On 901118,control Room Alarms Annunciated Failure of Inverter Associated W/One of Four 118-volt Ac Safeguards Instrument Buses.Caused by Failed Components within Scr/Diode Assembly ML20058C5131990-10-29029 October 1990 Special Rept SR-1-90-007-00:on 900726,charging Flow Diverted Through Safety Injection Line Due to Personnel Error. Operator Counseled.Procedures Reviewed for Accuracy ML20056A1691990-07-31031 July 1990 Ro:On 900730,ESFAS Occurred Which Resulted in Initiation of Safety Injection Followed by lo-lo Steam Generator Level Reactor Trip Signal.Caused by Potential Problem W/Emergency Lighting.Actions to Prevent Recurrence Will Be Determined ML20056A0821990-07-27027 July 1990 Ro:On 900726,ESF Actuation Signal Occurred Which Resulted in Initiation of Safety Injection.Cause Indeterminate.Plant Restored to Stable Condition ML20236T9321987-10-27027 October 1987 Special Rept:On 870831,Train a Safety Injection Occurred During Performance of Bimonthly Surveillance of solid-state Protection Sys.Caused by Cognitive Personnel Error.Emergency Procedure 2BEP-0 Entered & Exited When Plant Stabilized 1997-11-24
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217E8021999-10-0707 October 1999 CPSES Unit 1 Cycle 8 Colr ML20217G4151999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Cpses,Units 1 & 2 ML20212F7671999-09-24024 September 1999 SER Granting Relief Request C-4 Pursuant to 10CFR50.55a(g)(6)(i) for Unit 2,during First 10-year ISI Interval & Relief Requests B-15,B-16 & B-17 Pursuant to 10CFR50.55a(g)(6)(i) ML20216J5701999-09-16016 September 1999 Rev 2 to CPSES Unit 2 Cycle 5 Colr TXX-9920, Monthly Operating Repts for Aug 1999 for Cpses.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Cpses.With ML20211M2981999-08-0606 August 1999 Rev 1 to CPSES Fuel Storage Licensing Rept, CPSES Credit for Soluble Boron & Expansion of Spent Fuel Storage Capacity, Consisting of Revised Title Page and 4-1 ML20210U4081999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Cpses,Units 1 & 2 ML20210D8321999-07-23023 July 1999 Safety Evaluation Accepting Relief Requests Re Use of 1998 Edition of Subsections IWE & Iwl of ASME Code for Containment Insp ML20209H7661999-07-15015 July 1999 Safety Evaluation Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Comanche Peak Steam Electric Station,Units 1 & 2 ML20209H2721999-07-0909 July 1999 2RF04 Containment ISI Summary Rept First Interval,First Period,First Outage ML20209H2631999-07-0909 July 1999 2RF04 ISI Summary Rept First Interval,Second Period,Second Outage ML20209G7501999-07-0808 July 1999 SER Finding That Licensee Individual Plant Exam of External Events Complete with Regard to Info Requested by Suppl 4 to GL 88-20 & That IPEEE Results Reasonable Given Design, Operation & History of Comanche Peak Steam Electric Station ML20196L0191999-07-0808 July 1999 Safety Evaluation Granting Request Relief B-6 (Rev 2),B-7 (Rev2),B-12,B-13,B-14 & C-9,pursuant to 10CFR50.55a(g)(6)(i).Technical Ltr Rept Also Encl ML20210J9391999-06-30030 June 1999 CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-990630 ML20209G0801999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Cpses,Units 1 & 2 ML20196J0621999-06-29029 June 1999 Safety Evaluation Supporting Proposed Changes to Emergency Plan Re Licenses NPF-87 & NPF-89 Respectively ML20195G5141999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Comanche Peak Steam Electric Station,Units 1 & 2.With ML20216E0711999-05-21021 May 1999 1999 Graded Exercise - Comanche Peak Steam Electric Station ML20206Q0091999-05-14014 May 1999 Safety Evaluation Accepting GL 92-08, Thermo-Lag 330-1 Fire Barriers, Dtd 921217,for Comanche Peak Electric Station,Unit 1 ML20206H2061999-05-0606 May 1999 SER Accepting Exemption to App K Re Leading Edge Flowmeter for Plant,Units 1 & 2 ML20196L2241999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Cpses,Units 1 & 2 ML20205R5701999-04-14014 April 1999 Rev 6 to ER-ME-067, TU Electric Engineering Rept,Evaluation of Thermo-Lag Fire Barrier Sys 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 ML20205J7831999-04-0101 April 1999 Rev 0 to ERX-99-001, CPSES Unit 2 Cycle 5 Colr ML20205N3101999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Cpses,Units 1 & 2 ML20204H6371999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Comanche Peak Units 1 & 2 ML20205N1481999-02-28028 February 1999 Corrected Monthly Operating Rept for Feb 1999 for CPSES, Units 1 & 2 ML20203A4881999-02-0303 February 1999 Safety Evaluation Granting Requests for Relief B-3 - B-6,C-2 & C-3 for Plant,Unit 2 ML20210J9201999-02-0101 February 1999 CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802- 990201 ML20202D0101999-01-27027 January 1999 Safety Evaluation Supporting First 10-yr Interval ISI Program Plan Requests for Relief B-9,B-10 & B-11 for CPSES, Unit 1 ML20199E9961998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Cpses,Units 1 & 2 ML20207D6091998-12-31031 December 1998 1998 Annual Operating Rept for Cpses,Units 1 & 2. with ML20197K2371998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Cpses,Units 1 & 2 ML20195F3161998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Cpses,Units 1 & 2 ML20154M8841998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Cpses,Units 1 & 2 ML20154B5741998-09-30030 September 1998 Safety Evaluation Re Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Motor-Operated Valves. Licensee Has Established Acceptable Program ML20151W0361998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Cpses,Units 1 & 2. with ML20151Q1211998-08-14014 August 1998 Rev 0 to Control of Hazard Barriers ML20237C4061998-08-14014 August 1998 Safety Evaluation Supporting Request to Implement Risk Informed IST Program ML20237C6721998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Cpses,Units 1 & 2 ML20236V3121998-07-29029 July 1998 Final Part 21 Rept Re Enterprise DSR-4 & DSRV-4 Edgs.Short Term Instability Was Found During post-installation Testing & Setup as Part of Design mod/post-work Testing Process. Different Methods Were Developed to Correct Problem ML20236R0711998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Cpses,Units 1 & 2 ML20249B2581998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Cpses,Units 1 & 2 ML20248A1671998-05-22022 May 1998 Interim Part 21 Re Enterprise DSR-4 & DSRV-4 Emergency diesel.Post-installation Testing Revealed,High Em/Rfi Levels Affected New Controllers,Whereas Original Controllers Were unaffected.Follow-up Will Be Provided No Later than 980731 ML20247G3241998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Cpses,Units 1 & 2 ML20216B8661998-04-0101 April 1998 Rev 0 to ERX-98-001, CPSES Unit 1 Cycle 7 Colr ML20216J3061998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Cpses,Units 1 & 2 ML20216J1861998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Comanche Peak Steam Electric Station ML20197A6951998-02-24024 February 1998 Inservice Insp Summary Rept,First Interval,Second Period, First Outage ML20199J5391998-02-0202 February 1998 CPSES Commitment Matl Change Evaluation Rept 0002 for 960202-970801 1999-09-30
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Log # TXX 97250
.. 9 File # 10200
. .; 905.4 Ref. # 10CFR50.36(c)(2) nlELECTRIC' November 24, 1997 ,
C. I. awe Terry cw o he,+,
Mr. E. W. Herschoff. Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive Suite 400 Arlington TX 76011
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NO. 50 446 AUTOMATIC OPERATION OF PRESSURIZER PORV IN RESPONSE TO A LOW TEMPER $TURE OVERPRESSURIZATION SIGNAL (LTOP)
SPECIAL REPORT NO. 2 SR 97 001 Gentlemen:
Enclosed is a 30 day special report submitted in accordance with CPSES Unit 2 Technical Specification 3.4.8.3. " Reactor Coolant System Overpressure Protection System."
-' This communication contains new commitments regarding CPSES Units 1 and 2 as identified in the Attachment.
Pleasc contact Mr. Randy Blankenship at 254 897 5890, should you have questions concerning the material contained in this report.
Sincer y, hi&
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C. L. Ter i
i RTB/rb Attachment Enclosure -[-@)3 ,
c- NRC Document Control Desk J. I. Tapia Region IV T. J. Polich. NRR Resident Inspectors. CPSES 9711200250 971124 PDR ADocK050004g llIllNIjll,R,555 P. O. Don 1002 Glen Rme Tcsas 7 tot 3
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Attachment to TXX 97250 Page 1 of 1 .-
- Attachment :
-. l This communication contains the following new commitments:
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-; CDF Number. ComaitBent .
27114 CPSES will assess if the misconception of the LTOP- i arming temperature is a general knowledge deficiency ar.d :
conduct appropriate training if deemed necessary. l Alarm procedures ALM 0064A and B will be revised to i 27115 include the LTOP arming setpoint.
27116 - Integrated plant operating procedures. IPO 005A and B i will be revised to add appropriate provisions to ;
establish temperature and-pressure conditions during <
cooldown which will not unnecessarily challenge LTOP - l actuation.
- The CDF number is used by TV Electric for the internal tracking of CPSES ;
commitments. !
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t Enclosure to TXX 97250 ;
Page 1 of 2 ;
TU Electric Cceanche Peak Steam Electric Station. Unit 2 Docket No. 50 446 Automatic Opera. tion of Pressurizer Power Operated Relief Valve in Response 2 to a low Temperature Overpresture Protection (LTOP) Signal Special Report No. 2 SR 97 001 1.0 REPORT REQUIREMENT ;
Cn October 25. 1997, a Reactor Coolant System (RCS) pressure transient resulted in the automatic actuation of a Pressurizer Power Operated Relief Valve (PORV). This Special Report is being submitted in accordance with Comanche Peak Steam Electric Station (CPSES) Unit 2 Technical Specification 3.4.8.3. REACTOR COOLANT SYSTEM OVERPRESSURF PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION. Technical Specification 3.4.8.3 requires that a Special Report be submitted to the Nuclear Regulatory Commission pursuant to Technical Specification 6.9.2 describing any event in which a Pressurizer PORV. or the Residual Heat Removal suction relief valves, or the RCS vents are used to mitigate an RCS pressure transient.
The FORVs automatically opened for RCS pressure relief when the LTOP system actuated during a RCS cooldown and dcpressurization.
Actuation occurred when the RCS temperature decreased to the 6rming J' setpoint for the LTOP system. RCS pressure was not increasing at t'ae time of actuation.
1 2.0 EVENT DESCRIPTION Initiatina Circumstancn On October 25. 1997 CPSES Unit 2 was ccnducting a normal cooldown from H0DE 3. HOT STANDBY to MODE 5. COLD SHUTDOWN at the 1 commencement of the third refueling outage for the unit (2RF03).
Prior to pressurizer pressure decreasing below 800 psig isolation of the safety injection accumulators was to occur per normal plant cperating procedures. Delays were experienced during the accumulator isolation )rocess which maintained reactor coolant system ,'RCS) pressure ligher than was anticipated for the corresponding RCS temperature as cooldown continued. The control ,
room operators were awat e of the approaching arming of the LTOP actuation setpoint and that the RCS pressure was above the setpoint for the corresponding temperature. The operators believed that the pressure / temperature relationship would be acceptable for the LTOP logic prior to reaching the LTOP- arming temperature. This operational philosophy was acce) table with the exception that the operators were mistaken as to t1e arming temperature of L10P.
Alarms were also received indicating that the RCS .
pressure / temperature relationship would exceed the LTOP setpoint if
4
Enclosure to TXX 97250 l Page 2 of 2 t LTOP were armed. The operators responded to these alarms with the belief that the RCS pressure would be below the setpoint prior to 1 reaching the LTOP arming temperature which they believed to be 320'F , As such, when the RCS temperature decreased to approximately 350'F, LTOP actuated as the RCS pressure was still above the system -
setpoint.
PORV Mitiaation Effects At approximately 2105 CST, PORV 2 PCV 456 lifted when the RCS t temperature decreased to 352'F, The PORV remained open with the ;
operator monitoring the situation. Although decreasing, RCS 1 aressure remained above the setpoint for automatic actuation of the 20RV with the lower setpoint, 2 PCV 455A. Therefore at . i approximately 2108 CST, 2 PCV 455A armed and automatically opened further depressurizing the RCS. Once RCS pressure was below the -
corresponding pressure setpoint for the LT09 PORVs, the operator took manbal control and closed the valves terminating the RCS depressurization. The operator closed the valves to limit the discharge of RCS inventory to the pressurizer relief tank and over '
concern for personnel within the containment building. RCS parameters were stabilized at 340'F and 500 psig. The PORVs performed all required actions.
3.0 CORRECTIVE ACTIONS The root cause analysis performed by CPSES, concluded that the i primary cause was that of the operators' misconception over the actual arming setpoint of the LTOP system. The alarm procedures for system alarms did not serve as an effective barrier for this event as they did not contain the arming temperature for LTOP.
CPSES will assess if the misconception of the LTOP arming temperature is a general knowledge deficiency and conduct appropriate training if deemed necessary.
Alarm procedures ALM 0064A and D will be revised to include the LTOP arming setpoint.
Integrated plant operating procedures, IPO 005A and B will be ,
revised to add appropriate provisions to establish temperature and pressure conditions during cooldown which will not unnecessarily challenge LTOP actuation. ,
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