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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20045G6671993-07-0202 July 1993
RO:930702,unusual Event Declared When RCS Calculated Unidentified Leak Rate Exceeded 1 Gpm.Caused by Leakage from Reactor Coolant Pump Seal Injection Filter Drain Valve. Valves Corrected to Eliminate Leak
ML20043F2961990-06-0808 June 1990
Special Rept SR-1-90-006-00:on 900509,discovered That Tech Spec Temp Limit for Main Steam Penetration Area Exceeded for Greater than 8 H.Caused by Inadequate Operating Procedure for Safeguards Bldg Ventilation Sys.Pipe Supports Insulated
ML20042E5341990-04-16016 April 1990
Special Rept 1-SR-90-005-00:on 900404,positive Moderator Temp Coefficient Noted During Low Physics Testing Due to High Boron Concentration in Moderator.Rod Withdrawal Limits Imposed Per Tech Spec 3.1.1.3a,Action a.1
ML20012D9531990-03-21021 March 1990
Special Rept 1-SR-90-002:on 900221,RCS Pressure Transient Resulted in Automatic Actuation of Pressurizer Porv.Caused by Failure of Procedure to Consider Variation in Plant Response for Stated Sys.Operating Procedure Will Be Revised
ML20012B8541990-03-13013 March 1990
Special Rept:On 900312,ESF Actuation Signal Occurred Which Resulted in Initiation of Train a Safety Injection & RCS Pressure Transient.Caused by Failed Blocking Diode Due to Short.Plant Restored to Stabilized Condition
ML19309B8571980-03-28028 March 1980
Supplemental Ro:Violation Found Re Piping Min Wall Thickness.Cause Unstated.Engineering Review in Progress. Progress Rept Will Be Submitted by 800418
1993-07-02
[Table view]
Category:LER)
MONTHYEARML20045G6671993-07-0202 July 1993
RO:930702,unusual Event Declared When RCS Calculated Unidentified Leak Rate Exceeded 1 Gpm.Caused by Leakage from Reactor Coolant Pump Seal Injection Filter Drain Valve. Valves Corrected to Eliminate Leak
ML20043F2961990-06-0808 June 1990
Special Rept SR-1-90-006-00:on 900509,discovered That Tech Spec Temp Limit for Main Steam Penetration Area Exceeded for Greater than 8 H.Caused by Inadequate Operating Procedure for Safeguards Bldg Ventilation Sys.Pipe Supports Insulated
ML20042E5341990-04-16016 April 1990
Special Rept 1-SR-90-005-00:on 900404,positive Moderator Temp Coefficient Noted During Low Physics Testing Due to High Boron Concentration in Moderator.Rod Withdrawal Limits Imposed Per Tech Spec 3.1.1.3a,Action a.1
ML20012D9531990-03-21021 March 1990
Special Rept 1-SR-90-002:on 900221,RCS Pressure Transient Resulted in Automatic Actuation of Pressurizer Porv.Caused by Failure of Procedure to Consider Variation in Plant Response for Stated Sys.Operating Procedure Will Be Revised
ML20012B8541990-03-13013 March 1990
Special Rept:On 900312,ESF Actuation Signal Occurred Which Resulted in Initiation of Train a Safety Injection & RCS Pressure Transient.Caused by Failed Blocking Diode Due to Short.Plant Restored to Stabilized Condition
ML19309B8571980-03-28028 March 1980
Supplemental Ro:Violation Found Re Piping Min Wall Thickness.Cause Unstated.Engineering Review in Progress. Progress Rept Will Be Submitted by 800418
1993-07-02
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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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f a
TEXAS UTILITIES GENERATING COMPANY 2003 SRYAN TOWER
- DAh9. TEXAS 76201 n.a.cany March 28, 1980
'
"!*lL".2' ."'.*2 TXX-3115 Mr. W. C. Seidle, Chief
. Reactor Construction & Engineering Support Branch U. S. Nuclear Regulatory Comission Office of Inspection & Enforcement ,
611 Ryan Plaza Dr., Suite 1000 Docket Nos. 50-445 Arlington, Texas 76012 50-446 COMANCHE PEAK STEAM ELECTRIC STATION 1981-83 2300 MW INSTALLATION PIPING MINIMUM WALL FILE N0: 10110
Dear Mr. Seidle:
.This letter supplements our letter TXX-3092, dated January 23, 1980, relative to a violation of piping minimum wall thickness. The engineering review is active and a progress report .is to be submitted by April 18, 1980.
If we can provide any additional information, please advise.
Very truly yours, R. J. Gary RJG:df cc: NRC Region IV (0 + 1 copy)
Director, Inspection & Enforcement (15 copies)
- c/o Distribution Services Branch, DDC, ADM.
~
U. S. Nuclear Regulatory Commission Washington, D. C. 20555
.
80040702 %
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