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Safety Evaluation Supporting Modified Design Basis Documented in Amend 61ML20214X180 |
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Comanche Peak ![Luminant icon.png](/w/images/d/d7/Luminant_icon.png) |
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Issue date: |
06/08/1987 |
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From: |
NRC |
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Shared Package |
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ML20214X144 |
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References |
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NUDOCS 8706160364 |
Download: ML20214X180 (4) |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212F7671999-09-24024 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) 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 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 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 ML20196J0621999-06-29029 June 1999 Safety Evaluation Supporting Proposed Changes to Emergency Plan Re Licenses NPF-87 & NPF-89 Respectively 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 ML20203A4881999-02-0303 February 1999 Safety Evaluation Granting Requests for Relief B-3 - B-6,C-2 & C-3 for Plant,Unit 2 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 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 ML20237C4061998-08-14014 August 1998 Safety Evaluation Supporting Request to Implement Risk Informed IST Program ML20135B7911996-11-29029 November 1996 Safety Evaluation Approving Corporate Restructuring of TU to Facilitate Acquisition of Enserch Corp ML20128C1721993-01-29029 January 1993 Safety Evaluation Accepting First 10-yr Interval Inservice Testing Program for Pumps & Valves ML20198D3331992-05-0606 May 1992 Safety Evaluation Supporting Licensee Response to Generic Ltr 82-33 Concerning Implementation of Reg Guide 1.97,rev 2 ML20235U5631989-02-24024 February 1989 Safety Evaluation Concluding That Stated 10CFR70 License Conditions Should Be Incorporated Into 10CFR50 License ML20153C8171988-08-25025 August 1988 Safety Evaluation Supporting Corrections to Amends 9 & 8 to CPPR-126 & CPPR-127,respectively ML20236A5741987-10-13013 October 1987 Safety Evaluation Re Util 850502 Request to Eliminate Arbitrary Intermediate Pipe Breaks.Request Acceptable Provided Applicant Maintains Environ Qualification of safety-related Mechanical & Electrical Equipment ML20214X1801987-06-0808 June 1987 Safety Evaluation Supporting Modified Design Basis Documented in Amend 61 ML20214T7661987-05-28028 May 1987 Handwritten Sser on Allegation Re Qa/Qc Repair,Rework & Maint ML20214J7221986-08-15015 August 1986 SER on Tdi Diesel Generator Owners Group Findings & Recommendations Re Operability/Reliability of Tdi Emergency Diesel Generators ML20141P2181986-03-13013 March 1986 Evaluation Approving Use of ASME Code Cases N-397 & N-411. Applicant Must Investigate Root Cause by Considering Physical Mods Made to Piping Sys & Indicate Extent to Which Issues Resolved as Result of Revised Analyses Using Cases ML20210S8041986-02-18018 February 1986 Marked-up SER Re Rev 3 to Comanche Peak Response Team Program Plan ML20133H9021985-08-0606 August 1985 Sser of Qualifications & Training of Operators & Adequacy of Extant Training Programs to Maintain Operator Readiness. Training Programs Acceptable,Barring Major Problems ML20133Q0231985-08-0606 August 1985 Mechanical Engineering Branch Sser Re Inservice Testing of Pumps & Valves.Program for Pumps & Valves Acceptable ML20133Q0281985-07-12012 July 1985 SER Supporting Pump & Valve Inservice Testing Program ML20128L8791985-07-0101 July 1985 SER Re Conformance of post-accident Monitoring Design,Per Reg Guide 1.97,Rev 2 Re Emergency Response Capabilities. Neutron Flux Instrumentation Must Be Provided Before Fuel Loading ML20199G4531985-03-19019 March 1985 Partially Withheld marked-up Rev 5 to Sser Re Allegation AQ-91 Concerning Inadequate Training of Personnel.Related Info Encl ML20215K6461985-03-15015 March 1985 Partially Deleted Draft Sser Providing Results of Staff Evaluation & Resolution of Approx 400 Technical Concerns & Allegations in Mechanical & Piping Area Re Constr Practices at Plant ML20199G6201985-03-13013 March 1985 Partially Withheld marked-up Rev 4 to Sser Re Allegation AQ-98 Concerning Extensive Delays in Repair of safety-related Matl ML20199G7751985-01-22022 January 1985 Partially Withheld marked-up Rev 1 to Sser Re Allegation AQ-41 Concerning Sandblasted Pipe Sections Which Removed Heat Markings Used for Traceability.Related Info Encl ML20206U9251984-12-19019 December 1984 Partially Withheld Rev 1 to Sser Re Allegation AE-17, Alleging Field Run Conduit,Drywall & Lighting Installed Above Ceiling Panels in Control Room Classified as Nonseismic ML20206U6351984-12-19019 December 1984 Partially Withheld Rev 1 to Sser Re Allegations AQC-13, AQC-14,AQC-15,AC-18 & AC-40,alleging Unauthorized & Undocumented Holes Drilled Through Reinforcing Steel ML20206U9351984-12-19019 December 1984 Partially Withheld Draft 7 to Sser Re Allegation AC-41 Concerning Poor Workmanship in Use of Elastic Joint Filler Matl Between Seismic Category I Structures.Related Documentation Encl ML20199G6301984-11-0101 November 1984 Partially Withheld marked-up Rev 3 to Sser Re Allegation AQ-131 Concerning Electrical Boxes That Were Shipped to Facility in Damaged Condition or Were Damaged & Repaired by Unauthorized Personnel.Related Info Encl ML20199G6141984-10-0505 October 1984 Partially Withheld marked-up Rev 2 to Sser Re Allegation AQ-88 Concerning safety-related Work Performed by Illegal Aliens ML20199G6241984-10-0202 October 1984 Partially Withheld marked-up Draft 4 to Sser Re Allegation A-130 Concerning Valve Disc Numbers on Repair Travelers That Differ from Code Data Rept ML20202B9301983-08-10010 August 1983 SER Supporting Generic Westinghouse Mod for Reactor Trip Sys Automatic Actuation Using Shunt Coil Trip Attachments W/ Listed exceptions.Plant-specific Design Info Required for Westinghouse Plants Incorporating Shunt Trip Mod Encl 1999-09-24
[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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i ENCLOSURE COMANCHE PEAK STEAM ELECTRIC STATION , UNITS 1 AND 2 DOCKET NOS. 50-445 AND 50-446 SAFETY EVALUATION FOR IMPLEMENTATION OF REVISED GDC-4 Backaround In a letter dated August 29,1984 (Ref.1) the staff granted the applicant, Texas Utilities Electric Company (formerly Texas Utilities Generating Company),
a partial exemption from General Desian Criterion 4 (GDC-4)of 10 CFR 50, Ap-pendix A for Unit 1 of the Comanche Peak Steam Electric Station (CPSES). The partial exemption eliminated the requirement to install jet impingement shields at eiaht locations in the pipina loop of the reactor coolant system (RCS) for Unit 1. Based on its evaluation of the analyses for CPSES, contained in the Westinghouse Report WCAP-10527 (Ref. 2), the staff determined that the applicant had presented an acceptable technical justification for not installina protective devices to mitigate the dynamic effects associated with a postulated pipe break in the RCS pipina of CPSES Unit 1. In orantino the exemption, the staff had determined that the advance fracture mechanics techniques used by the ap-plicant provided assurance that leakace from a flaw in the primary system piping would be detected before such a flaw reaches a size that could lead to unstable crack growth. For this reason, further protection provided by jet impingement shields aaainst the dynamic effect of jet impingement resultina from the dis-charae from a double-ended cuillotine break in the primary pipina was found to be unnecessary. Although the analysis contained in the Westinahouse Report (Ref. 2) encompassed relief from the need to install pipe break protective devices (i.e., pipe whip restraints, reactor cavity non-crushable insulation, and jet impinaement shields) in Units 1 and 2, the applicant's request for exemption pertained solely to the installation of jet impingement shields as-sociated with eight pipe break locations per loop in CPSES Unit 1. The partial exemption was incorporated into Amendment 8 of the Comanche Peak Steam Electric Station Unit 1 Construction Permit (CPPR-126), by letter dated October 26, 1984 (Ref. 3).
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8706160364 870600 PDR ADOCK 05000445 PDR P
i Evaluation In letters dated. March 12, 1985 (Ref. 4), and July 15,1985 (Ref. 5), the ap-plicant requested a partial exemption to GCD-4 for CPSES Unit 2. The Westing-house Report (Ref. 2) provided the bases for obviating the requirement for protection of structures, systems, and components from all dynamic effects associated with the eight RCS pipe breaks per loop in Units 1 and 2. Further-more, the applicant stated that granting the exemption would not affect the ECCS design bases, the containment and compartment design bases, the equipment qualification bases, the ESF systems response, and the design of RCS heavy com-ponent supports.
The Commission approved the final rule on this matter which stated that ap-plicants for operating licenses seeking to modify aesign features to take advantage of the rule are required to reflect the revised design in an amend-ment of the FSAR. On April 11, 1986 the final rule was published in the Federal Register (Ref. 6). By letter dated June 20,1986(Ref.7)thestaff informed the applicant of the final rule regarding the relief sought by the applicant for Unit 2. By letter dated November 10, 1986 (Ref. 8), the '
applicant transmitted advance copies of FSAR revisions which incorporated design changes related to the implementation of GDC-4 as modified by the April 11, 1986 final rule. The FSAR revisions were subsequently incorporated into the CPSES FSAR by Amendment 61 (Ref. 9) in a letter dated December 19, 1986 (Ref. 10).
Amendment 61 to the CPSES FSAR reflects a modified design basis for CPSES Units 1 and 2. The dynamic effects associated with eight postulated primary loop breaks per loop have been removed from the design basis of CPSES Units 1 and 2. However, the dynamic effects associated with the postulated rupture of the primary coolant loop branch line nozzles are still considered in the design basis. Accordingly, the jet impingement shields will not be installed in either Unit 1 or Unit 2. The applicant is currently evaluating the optimum
time to remove the primary coolant whip restraints and reactor covity non-crushable insulation from Units 1 and 2. Their removal will be documenteo in a future FSAR dmendment. It should be noted that dithough the mein RCS loop breaks are not part of the modified design basis, they are still included in the load ond stress evaluation for the RCS heavy component supports. Any future changes to the CPSES Unit 1 or Unit 2 RCS heavy component supports based upon the modified design basis will require prior staff dpprovdl.
Conclusion The technical justification for the exemption previously granted by the staff (Ref. 1), provided the basis for eliminating from the design basis the dynamic effects ossociated with the postulated primary coolant loop pipe breaks. These dynamic effects include pipe whip and jet impingement. Since technical justifi-cation had been reviewed and approved previously by the staff in granting the August 28, 1984 exemption for Unit 1, the staff considers the justification dssociated with that exemption to be adequate in demonstrating compliance with the revised GDC-4 as well. Therefore, the modified design basis documented in Amendment 61 of the CPSES FSAR is acceptable for Units 1 and 2. Furthermore, the staff concludes that for CPSES, the jet impingement shields, reactor cavity non-crushable insulation, and pipe whip restraints associated with primary coolant loop pipe breaks are unnecessary for compliance with the revised GDC-4.
Principal Contributor: D. Terao, OSP
' References
- 1) Letter for B. J. Youngblood (NRC) to M. D. Spence (TUGCO), dated Auoust 28, 1984.
- 2) Westinghouse Report WCAP-10527, " Technical Bases for Eliminatino Large Loop Pipe Rupture as the Structural Design Basis for Comanche Peak, Units 1 and 2 " April 1984, Westinghouse Class 2 proprietary.
- 3) Letter from B. J. Youngblood, (NRC) to M. D. Spence (TUGCO), dated October 26, 1984.
- 4) Letter from M. D. Spence (TUGC0) to H. R. Denton (NRC), dated March 12, 1985 (TXX-4426).
- 5) Letter from W. G. Counsil (TUGCO) to V. S. Noonan (NRC), dated July 15, 1985 (TXX-4692).
- 6) 51 Federal Register 12502, April 11, 1986.
- 7) Letter from V. S. Noonan (NRC), to W. G. Counsil (TUGCO), dated June 20, 1986.
- 8) Letter from W. G. Counsil to V. S. Noonan (NRC), dated November 10, 1986 (TXX-6086).
- 9) Letter from W. G. Counsil (TUGC0), to H. R. Denton (NRC), dated December 19, 1986 (TXX-6161).
- 10) Letter from W. G. Counsil (TUGC0), to V. S. Noonan (NRC), dated December 19, 1986 (TXX-6162).
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