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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20211M2981999-08-0606 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 ML20210J9391999-06-30030 June 1999 CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-990630 ML20205R5701999-04-14014 April 1999 Rev 6 to ER-ME-067, TU Electric Engineering Rept,Evaluation of Thermo-Lag Fire Barrier Sys ML20151Q1211998-08-14014 August 1998 Rev 0 to Control of Hazard Barriers ML20199J5391998-02-0202 February 1998 CPSES Commitment Matl Change Evaluation Rept 0002 for 960202-970801 ML20198Q7181997-10-24024 October 1997 Rev 5 to ER-ME-067, Evaluation of Thermo-Lag Fire Barrier Systems ML20137D3601997-03-20020 March 1997 Engineering Self-Assessment Rept ML20129F6991996-10-25025 October 1996 Justification for SPC 1986 LBLOCA Evaluation Model W/Interim Adjustment for Non-Physical Behavior ML20100F2761996-02-13013 February 1996 Rev 0 of Engineering Rept, Resolution of NRC GL 95-07 'Pressure Locking & Thermal Binding of Safety-Related Power- Operated Gate Valves.' ML20116M4021996-02-0101 February 1996 Commitment Matl Change Evaluation Rept 0001 for 941101- 960201 ML20095K5411995-12-18018 December 1995 Nonproprietary Small Break LOCA Analysis Methodology ML20094P7971995-11-22022 November 1995 Rev 0 to CPSES Risk-Based IST Program Risk Ranking Determination Study ML20094P7821995-11-22022 November 1995 CPSES Risk-Based IST Program Risk Ranking Determination Study Summary Rept ML20094P4231995-09-29029 September 1995 Pyrolysis Gas Chromatography Analysis of 10 Thermo-Lag Fire Barrier Samples ML20085N2911995-06-21021 June 1995 Individual Plant Exam of External Events for Severe Accident Vulnerabilities TXX-9432, Rev 0 to CPSES Fuel Storage Licensing Rept,Cpses Expansion of Spent Fuel Storage Capacity1994-12-0909 December 1994 Rev 0 to CPSES Fuel Storage Licensing Rept,Cpses Expansion of Spent Fuel Storage Capacity ML20097A3821994-08-19019 August 1994 Individual Plant Exam of External Events,Seismic,Cpses ML20069M8761994-06-10010 June 1994 Engineering Rept Evaluation of Unit 1 & Unit 2 Thermo-Lag Configurations ML20064M6081994-03-21021 March 1994 Engineering Rept Evaluation of Thermo-Lag Fire Barrier Sys ML20059F5431993-10-0505 October 1993 Engineering Rept, Evaluation of Fir Endurance Test Results Related to Cable Functionality in 1-1/2 & 2 Inch Conduits ML18010B0841993-05-0505 May 1993 NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216. ML20127K8121993-01-19019 January 1993 Rev 0,to Evaluation of Unit 2 Thermo-Lag Configurations ML20126G2121992-12-23023 December 1992 Rev 2 to ER-ME-067, Evaluation of Thermo-Lag Fire Barrier Systems ML20126C0421992-12-18018 December 1992 Suppl 6 to Human Factors Control Room Design Review of Comanche Peak Steam Electric Station ML20126A3621992-12-15015 December 1992 Rev 3 to Receipt,Dispensing,Quality & Insp Requirements for Thermo-Lag Fire Barrier Matls ML18010A9521992-11-30030 November 1992 NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216. ML20116C9511992-10-27027 October 1992 Individual Plant Exam Submittal:Comanche Peak Steam Electric Station Vol II:Back-End Analysis ML20115D2241992-09-29029 September 1992 Rev 1 to HI-92880, Criticality SE of Comanche Peak Fuel Storage Facilities W/Fuel of 5% Enrichment ML20127C8291992-09-0808 September 1992 Rev 1 to Interim Engineering Rept, Evaluation of Thermo-Lag Fire Barrier Sys ML20114B8051992-09-0101 September 1992 Suppl 5 to Human Factors Control Room Design Review of Comanche Peak Steam Electric Station ML20114C6101992-08-31031 August 1992 Individual Plant Exam Comanche Peak Steam Electric Station Vol 1:Front-End Analysis ML20105A7821992-08-14014 August 1992 Engineering Rept on Thermo-Lag 330-1 Fireproofing Coating Thicknesses Required for 1 & 2 Hour Fire Ratings for Various Structural Steel Members Used by Texas Utils Svcs,Inc ML20105A8471992-08-0606 August 1992 Rev 0 to Comanche Peak Steam Electric Station Unit 2 Engineering Bwip Check Valve 2AF-0083 Failure Investigation ML20116C9621992-07-16016 July 1992 Review of IPE Level 2 Draft Repts for Cpses ML20078H1581992-06-19019 June 1992 CPSES Thermo-Lag Barrier Applications Thermo-Lag Fire Test Conduit & J-Box Test Assemblies. Preliminary Test Results ML20095H2411992-04-13013 April 1992 Validation Efforts for Comanche Peak Steam Electric Station Unit 2 ML20094P3371992-03-26026 March 1992 Control Room Simulator 10CFR55 Certification Initial Rept TXX-9200, RHR Line Summary Rept1992-03-23023 March 1992 RHR Line Summary Rept ML20086E3861991-10-31031 October 1991 Pressurizer Surge Line Transient Justification ML20079D0481991-06-21021 June 1991 Engineering Rept, Testing & Analysis of Commercial-Grade Swing Arms in Borg-Warner Check Valves, June 1991 ML20077E0271991-05-31031 May 1991 Methodology for Reactor Core Response to Steamline Break Events ML20217C4601991-05-31031 May 1991 Reactivity Anomaly Events Methodology ML20073Q8291991-05-17017 May 1991 Small Break LOCA Analysis Methodology ML20084V1401991-03-31031 March 1991 Safety Evaluation for Operation of Comanche Peak Unit 1 W/ Positive Moderator Temp Coefficient ML20079D0571991-03-31031 March 1991 Final Rept on Analysis of Check Valve Swing Arms, Mar 1991 ML20066F4331991-01-31031 January 1991 Draft Analysis of Flow Stratification in Surge Line of Comanche Peak Reactor ML20066L0691990-12-31031 December 1990 Large Break LOCA Analysis Methodology ML20066B2391990-12-31031 December 1990 Control Rod Worth Analysis ML20067B1291990-12-24024 December 1990 Suppl 1 to TUE-1 DNB Correlation ML20062D9041990-11-12012 November 1990 Unit One Loose Parts Monitoring Sys Special Rept 1999-08-06
[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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i l Attachment to TXX-92401 4
Sl!PPLEMENT NO. 5 HUMAN FACTORS CONTROL ROOM DESIGN REVIEW 0F COMANCllE PEAK STEAM ELECTRIC STATION SEPIEMDER 1, 1992 l
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9208310257 920828 5 DR ADOCK 0500
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, - A'ttachment to TXV. 92401 Page 2-of 4 i
1.0 1813201tLI103 l A comprehensive review has beer accomplished utilizing detailed color photographs of Unit 1 Main Control Boatds as the basis for comparison. [
These photographs show the configuration of Unit ' after the first refueling
- outage and were compared compo,ent by component tu the current Unit I detail Computer Aided Design (CAD) control board layout drawings. Thase drawings :
show all surface enhencements such as labels, mimic, demarcation, legends, and component layout. The Unit I drawings were then compared to Unit 2 drawings with emphasis on the Human Engineering attributes outlined in the original Unit 1 DCRDR. These NUREG 0700 attributes have been captured as CPSES specific by Technical Procedure EEE 5.13 ' Human Factors Engineering Guidelines". Consistency between units was further maintained by having engineering personnel who had worked on the original Unit ) DCRD9 conduct the Unit 2 DCROR. !
The Unit 2 drawings were reviewed and compared component by component to 9.e Unit 2 cc7 trol boards to identify all unit differences, discrepancies, and ;
work remaining. This comprehensive information has then recorded in a PC ;
database for tracking and reporting.
- Some definitive information must be established to clarify what is ,
classified as a unit difference. The f ollowing are not considered design unit differences:
e All common controls and indicators are installed solely in the Unit 1 control boards: e.g., boric acid storage tank level indicators are not installed in bnit 2. The annunciators for these common tanks are repeated in Unit 2 as -are all alarms for common equipme.:t.
- j. o Design Modifications - This category of differences is very-Jynamic and I changes day to-day during the Unit 2 construction "hase. Unit 2 has been the lead unit for many design changes and Unit I for others; e.g.,
all Hagan recotders (28 units) have been replaced in Unit 2, and the balance of 23 units is scheduled to be installed in Unit 1. Another
- ma.ior change of this nature is the new Plant Process Computer System which is being installed in Unit 2. This system integrates the Westinghouse P2500 computer-and Emergency Response Facilities (ERF) functions and other minor computer systets. 'The features of the ERF i system reteio-the Safety Parameter Displav system (SPDSL displays and format. . The 19 inch monitor in the contrs , board has been replaced with -
L a 25-inch monitor and is controlled by a new board. mounted touchpad.
All these changes have been reviewed and comply with NUREG 0700 guidelines, o Electrical Switchyard'- The +.ag numbers for the electrical switchrard equipment'have no unit designatcrs. On the electrical panel in both units, the layout is the same but the tag numbers for similar svitchyard breakers and buses are different.
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$ Attachment to TXX 92401
' Page 3 of 4 A programmatic revitw is conducted by both system and design engineers on
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each design change for either unit, and all ut+it differences are identified and evaluated in accordance with procedure, STA-820, ' Reporting and Evaluation Unit Difference,' and tracted by a FC database. All unit differences must have Statica Operations Review Committee (50RC) approval.
for the Annunciators and Monitor Light Box engravings, the Unit 1
- photographs and drawings have been compared with the Unit 2 design drawings.
No significant unit differences have been noted. Minor syrnbols, forniat and '
abbreviations are being corrected during the final testing and turaover process for Unit 2 systens. A recent review of all annunciators was ,
conducted to resolve ' nuisance
- alarms which detract from the ' dark board' concept for Unit 1. All associated design changer were reviewed for j applicability to Unit 2'during their initial development for Unit 1.,
2.0 OlFFERENCES IN DEslGN e
2.1 Color Coded Oberatina Bandi
, Main Control Board indicator color coded operating bands have been reviewed and unit differences evaluated. The following systems .
have different operating bands:
o The Steam Generator level bands dif fer due to the dif ference in the Steam Generator models. A Westinghouse Model 04 is used in Unit 1, and a Modei 05 is used in Unit 4.
o The Steam Generator feedwater flow split between nozzles have
.different restriction orifices and corresponding aifferent bypass flow.
o- The Overtemperature N-16 trip setpoints are higher in Unit 2.
lhis 1s due to updated parameter values being used in the analysis for determining the Unit 2 setpt nts, it should be noted that these operating bands are based on engineering d6ta and operating experience and are subject to change as operating experience is gained. The bands are
- - controlled by 0Wi-109, " Operations Maman Factor Controls.'
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- 2.2 Mirror imaae Unit Difference Th13 difference developed from different techniqucs in system- I configuration
- " mirror image" philosophy of-the steam system,-
" slide along' pr'inciple for the terbine equipment and *180' rotation
- of some auxiliary skids. A major effort to resolve the interfacing of these. systems has been accomplished to minimize the '
main control board configuration and tagging differences without making actual equipment moves in the Plant.
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Attachment to TxX-92401 Page 4 of 4 o The final Unit 2 design which affects the control boards is the ' mirror image' configur ation of the two Moisture Separat ors and the f our Main Steam Lines. These differentes affect twelve valve position indicator descriptive labels. No controls, tag numbers, or component layout differences erist.
A control board graphic operator aid has been developed to depict the actual configuration of each unit to assist in recognition of the differences.
2.3 liandtwitch Mdide Deletion _
During the design validation of Unit 2. it was determined that the control of four isolation dampers was not needed. The corresponding two handswitch modules were deleted f rom the design of Unit 2. Thtse modules were on a back panel which is not constantly manned by an operator. Removal of the Unit I switches has been determined to be a low risk potential for operator error.
3.0 CONCLUSION
CPSES remains committed to the DCRDR program and continues to evaluate Human Engineering Discrepancies. In addition, the Unit 2 DCRDR environmental surveys will be conducted when all control room and remote shutdown systems are operational. The results of the ,urveys, together with eny proposed corrective action plan, will be transmitted to the NRC prior to issuance of the Unit 2 operating license. The Human Engineering Discrepancies identified as o result of this comparison have been resolved and the related documentation is available on site. _
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