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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
[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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momemame MM Log # TXX-90205
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~ ~ File # 10250 903.llN C C 903.11B nlELECTRIC 909 4 Ref. # 10CFR50.36(c)(5)
Dld,T, r,, a,,,, June 8, 1990 Mr. R. D. Martin, Region IV U. S. Nuclear Regulatory Commission 611 Ryan Plaza, Suite 1000 Arlington, Texas 76011
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NO. 50 445 ELEVATED TEMPERATURES IN SAFEGUARDS BUILDING NORMAL ARCAS SPECIAL REPORT NO. SR 1-90 006 00 Gentlemen:
Enclosed is a 30 day special report submitted in accordance with CPSES Unit 1 Technical Specification 3.7.10 " Plant Systems - Area Temperature Monitoring."
Sincerely,
/ '
f William J. C4 ill, Jr.
JRW/daj Enclosure c - Document Control Desk U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Resident Inspectors, CPSES (3) 1 DATE. ,
L 9006140346 900608 enn w oCu osooo44s FDC [78l l 400 North Ohre Street LB $1 Dallas Tnas 73201
1 Enclosure to TXX-90205 ,
Special Report SR 90-006 Elevated Temperatures in Safeguards Ba8 Wag Normal Areas 1.0 REPORT REQUIREMENT l
'Ihis Special Report is being submitted in accordance with Comanche Peak i i
Steam Electric Station Unit 1 Technical Specification 3/4.7.10, AREA TEMPERATURE MONITORING. Specification 3.7.10 requires that with one or more areas exceeding the specifled temperature limits for normal cond!Uons for more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, a Special Report be submitted to the I Nuclear Regulatory Commission, pursuant to Specification 6.9.2, providing a record of the cumulative time and the amount by which the temperature in the affected areas exceeded the limits and an analysis to demonstrate the ,
continued operability of the affected equipment. ;
l 2.0 SVENT DESCRIPTION l
On May 9,1990, during performance of the Power Ascension Heating l it was Ventilating discovered that and the Air Technical Conditioning (HVAC) Temperature Specification temperature limit Survey, for the main steam penetration area was exceeded for greater than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. For purposes of compliance with Technical Specification 3/4.7.10, these rooms
, are considered normal areas as specified in Technical Specification Table ;
I 3.7 3. The temperature limit for normal conditions was observed to be in l
excess of 104*F for a total of 58 hours6.712963e-4 days <br />0.0161 hours <br />9.589947e-5 weeks <br />2.2069e-5 months <br />, and the temperature reached a l
maximum of 119'F at the hottest measured locations within the affected rooms. .
The purpose of the Power Ascension HVAC Temperature Survey is to obtain temperature data at various power levels through Power Ascension. The data is evaluated by engineering to determine if design changes are requised to maintain indoor area temperatures below the values listed in the applicable design calculations. The test procedure requires immediate notiflcation of Operations Supervisory personnel if observed temperatures exceed or may exceed those listed in Technical Specification Table 3.7 3.
During test performance on May 9,1990, no additional areas were '
identified with temperatures in excess of the temperature limps of Technical Specification Table 3.7-3.
At the time the overtemperature condition was observed, only one set of 50 percent capacity main steam and feedwater area supp and exhaust fans was in operation. Operations personnel were informed o the overtemperature condition and initiated additional ventilation by starting the second set of '
supply and exhaust fans. Operation with both sets of fans was only partially effective at reducing area temperatures: an unrelated reactor shutdown initiated on Ma affected areas. y 9 contributed to the reduction in temperature in the
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Enclosure to TXX 90205 Performance of the Operations Shiftly Routine Tests procedure ensures that the sun'e111ance requirements of Technical Specification 3/4.7.10 are satisfled. The sun'elllance points consist of those areas listed on Technical Specification Table 3.7-3, except the normal areas which are sun'ellied by monitoring building area exhaust temperatures displayed in the Control Room. Upon notification by Performance and Test personnel of the overtemperature condition existing in the main steam and feedwater penetration are- +he Operations Department added that area to the list of surveillance 1 :catio ' to be surveyed locally by an Ativhry Operator during performanet of the Alftly test.
An analysis w c9,)erformed to determine the effects of the elevated temperature on the operability of the safety-related equipment in the affected areas. The maximum temperature obsen'ed is less than the maximum temperature limits for abnormal conditions specified in Technical ,
Specificadon Table 3.7-3. It is concluded that the elevated temperatures had no impact on the operability of equipment requiring environmental qualification in the affected area.
Analysis also determined the effects of the elevated temperature on the qualified life of the equipment located in the affected area. Since there is no record of temperatures in the area prior to May 9,1990, it has been conservatively as tumed that the temperature in the area may have been 119 degrees F from 3,'20/90 (entry into Mode 3) till 5/11/90, a total of 53 days, ne room temper,tture for the main steam and feedwater penetration area is a function of outsIde ambient air temperature, and meteorological history l data supports the conservatism of the assumed temperature. ;
Analysis using thi s assumption results in an equivalent expended life of one year at 104 degrees F for the most limiting material in the affected area, and reduces the first replacement interval by one year. 'Ihe most limiting qualified life of a part or component in these rooms is 4 years from fuel load.
The change in the first replacement interval does not result in any replacement activity prior to the first refueling outage.
3.0 CAUSE OF THE EVENT Root Cause l
The Main Steam and Feedwater Area HVAC System design calculations used to determine required system capacity do not normally consider the effects of thermal contributions from uninsulated valve bodies and pipe supports, small steam leaks, or convective heat transfer from the feedwater penetration area to the main steam penetration area.
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. Enc'losure to TXX-90205 !
3 Contributing Facton ne system operating procedure for the Safeguards Bul! ding Ventilation System did not cleary specify when both sets of 50 pervent capacity supply and exhaust fans are required to operate. He procedure implied that only one set of supply and exhaust fans is necessary for normal operation and that additional fans may be required if area temperatures are high. He design configuration for normal operations requires that both sets of supply and exhaust fans be in operation.
4.0 CORRECTIVE ACTIONS Cause: Less than adequate design Corrective Action: Various pipe supports, valve bodies, etc. In the main steam and feedwater penetration areas have been insulated to reduce heat gains into the affectec. rooms and resultant loads on the HVAC system.
Continuing engineering evaluation is being conducted to determine additional actions to be taken to control temperatures in the affected areas.
The Power Ascension HVAC Temperature Survey will continue to be performed at additional power plateaus to provide data for engo.:ering analysis, for the evaluation of the effectiveness of design modifications, and '
4 for verification of the representativeness of surveillance points in this and other areas to verify design.
Contributing Factor: Procedure ambiguity Corrective Action: The system operating procedure for the Safeguards Building Ventilation System has been revised to more clearly identify when both sets of supply and exhaust fans should be in operation.
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