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MONTHYEARCPSES-200600627, Updated Response to Requested Information Part 2 of NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors.2006-03-31031 March 2006 Updated Response to Requested Information Part 2 of NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors. Project stage: Request CPSES-200601177, Supplement to License Amendment Request (LAR) 05-010 Revision to Technical Specification 3.3.2, ESFAS Instrumentation, 3.5.2, ECCS-Operating, and 3.6.7, Spray Additive System.2006-06-23023 June 2006 Supplement to License Amendment Request (LAR) 05-010 Revision to Technical Specification 3.3.2, ESFAS Instrumentation, 3.5.2, ECCS-Operating, and 3.6.7, Spray Additive System. Project stage: Supplement ML0624404202006-08-25025 August 2006 Supplement to License Amendment Request (LAR) 05-010 and Response to Request for Information Project stage: Supplement CPSES-200601743, Supplement to License Amendment Request (LAR) 05-010 and Response to Request for Information2006-09-0505 September 2006 Supplement to License Amendment Request (LAR) 05-010 and Response to Request for Information Project stage: Supplement CPSES-200601951, Supplement to License Amendment Request (LAR) 05-010 and Response to Request for Information2006-09-28028 September 2006 Supplement to License Amendment Request (LAR) 05-010 and Response to Request for Information Project stage: Supplement ML0625500762006-10-0505 October 2006 Issuance of Amendments Revisions to TS 3.3.2, ESFAS (Engineered Safety Features Actuation System) Instrumentation; and TS 3.5.2, ECCS (Emergency Core Cooling System) - Operating Project stage: Approval ML0628401022006-10-0505 October 2006 Technical Specification, Revisions to TS 3.3.2, ESFAS Instrumentation; and TS 3.5.2, ECCS - Operating Project stage: Other 2006-06-23
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Category:Letter type:CPSES
MONTHYEARCPSES-201001000, Operator Licensing Examination Data, Form 5362010-07-28028 July 2010 Operator Licensing Examination Data, Form 536 CPSES-200901377, Operator Licensing Examination Data2009-09-29029 September 2009 Operator Licensing Examination Data CPSES-200701127, Response to Request for Additional Information Related to License Amendment Request (LAR) 06-009, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times.2007-11-15015 November 2007 Response to Request for Additional Information Related to License Amendment Request (LAR) 06-009, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times. CPSES-200701495, Withdrawal of License Amendment Request (LAR) 06-007, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Offsite Circuits2007-10-22022 October 2007 Withdrawal of License Amendment Request (LAR) 06-007, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Offsite Circuits CPSES-200701530, Additional Information in Connection with the Indirect Transfer of Facility Operating Licenses and Conforming License Amendments2007-10-0909 October 2007 Additional Information in Connection with the Indirect Transfer of Facility Operating Licenses and Conforming License Amendments CPSES-200701496, Information Required by Order Approving the Indirect Transfer of Facility Operating Licenses and Conforming License Amendments2007-10-0202 October 2007 Information Required by Order Approving the Indirect Transfer of Facility Operating Licenses and Conforming License Amendments CPSES-200701351, Transmittal of First-Half 2007 Fitness-for-Duty Program Performance Data2007-08-29029 August 2007 Transmittal of First-Half 2007 Fitness-for-Duty Program Performance Data CPSES-200701076, Revision to the Operating License and Technical Specifications 1.0, Use and Application and 3.7.17, Spent Fuel Assembly Storage to Revise Rated Thermal Power from 3458 Mwt to 3612 Mwt2007-08-28028 August 2007 Revision to the Operating License and Technical Specifications 1.0, Use and Application and 3.7.17, Spent Fuel Assembly Storage to Revise Rated Thermal Power from 3458 Mwt to 3612 Mwt CPSES-200701302, Relief Request B-4 to the Unit 2 Inservice Inspection (ISI) Program Plan from the 1998 Edition of ASME Code, Section XI, Through 2000 Addenda (Interval Start Date - August 03, 2004, Second Interval)2007-08-22022 August 2007 Relief Request B-4 to the Unit 2 Inservice Inspection (ISI) Program Plan from the 1998 Edition of ASME Code, Section XI, Through 2000 Addenda (Interval Start Date - August 03, 2004, Second Interval) CPSES-200701324, Supplement to License Amendment Request (LAR) 07-003 Revision to Technical Specification 3.1, Reactivity Control Systems, 3.2, Power Distribution Limits, 3.3, Instrumentation, and 5.6.5 B, Core Operating Limits2007-08-16016 August 2007 Supplement to License Amendment Request (LAR) 07-003 Revision to Technical Specification 3.1, Reactivity Control Systems, 3.2, Power Distribution Limits, 3.3, Instrumentation, and 5.6.5 B, Core Operating Limits CPSES-200701323, License Amendment Request 07-006, Revision to Technical Specification 3.1.4, Rod Group Alignment Limits, Table 3.3.1-1, Reactor Trip System Instrumentation, Table 3.3.2-1, Engineered Safety Feature Actuation System..2007-08-16016 August 2007 License Amendment Request 07-006, Revision to Technical Specification 3.1.4, Rod Group Alignment Limits, Table 3.3.1-1, Reactor Trip System Instrumentation, Table 3.3.2-1, Engineered Safety Feature Actuation System.. CPSES-200701279, Mitigation of Alloy 82/182 Pressurizer Butt Welds in 20082007-08-0303 August 2007 Mitigation of Alloy 82/182 Pressurizer Butt Welds in 2008 CPSES-200701284, (Cpses), Operator Licensing Examination Data2007-08-0202 August 2007 (Cpses), Operator Licensing Examination Data CPSES-200701238, Submittal of the CPSES Units 1 and 2 Large and Small Break LOCA Analyses2007-07-31031 July 2007 Submittal of the CPSES Units 1 and 2 Large and Small Break LOCA Analyses CPSES-200701178, Supplement to Application for Order Approving Indirect Transfer of Control of Licenses and License Amendments to Reflect Proposed Licensee Name Change (TAC Nos. MD5289 and MD5280), Enclosures 1, 4, 5, 6 & 72007-07-20020 July 2007 Supplement to Application for Order Approving Indirect Transfer of Control of Licenses and License Amendments to Reflect Proposed Licensee Name Change (TAC Nos. MD5289 and MD5280), Enclosures 1, 4, 5, 6 & 7 CPSES-200701126, Response to Request for Additional Information to License Amendment Request (LAR) 06-007 Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Offsite Circuits2007-07-18018 July 2007 Response to Request for Additional Information to License Amendment Request (LAR) 06-007 Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Offsite Circuits CPSES-200701174, Submittal of Twelfth Refueling Outage (1RF12) Inservice Inspection Summary Report (1998 Edition of ASME Code Section XI Through 2000 Addenda, Interval Start Date - 08/03/2000, Second Interval)2007-07-17017 July 2007 Submittal of Twelfth Refueling Outage (1RF12) Inservice Inspection Summary Report (1998 Edition of ASME Code Section XI Through 2000 Addenda, Interval Start Date - 08/03/2000, Second Interval) CPSES-200701065, Response to NRC Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients.2007-06-21021 June 2007 Response to NRC Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients. CPSES-200700951, (Cpses), Unit 1, Pressurizer Weld Overlay 60 Day Report and Update for Unit 1 Reactor Pressure Vessel Head Replacement Regarding Revised Order EA-03-0092007-06-19019 June 2007 (Cpses), Unit 1, Pressurizer Weld Overlay 60 Day Report and Update for Unit 1 Reactor Pressure Vessel Head Replacement Regarding Revised Order EA-03-009 CPSES-200701059, Submittal of Startup Report, Cycle 132007-06-13013 June 2007 Submittal of Startup Report, Cycle 13 CPSES-200700738, License Amendment Request (LAR) 07-001 Revision to Technical Requirements Surveillance 13.3.33.2 Frequency for the Turbine Stop and Control Valves2007-05-22022 May 2007 License Amendment Request (LAR) 07-001 Revision to Technical Requirements Surveillance 13.3.33.2 Frequency for the Turbine Stop and Control Valves CPSES-200700915, Supplemental Response to Request for Information on Generic Letter 2003-01, Control Room Habitability2007-05-0707 May 2007 Supplemental Response to Request for Information on Generic Letter 2003-01, Control Room Habitability CPSES-200700871, Transmittal of Year 2006 Radioactive Effluent Release Report2007-04-30030 April 2007 Transmittal of Year 2006 Radioactive Effluent Release Report CPSES-200700859, Submittal of the Annual Non-Radiological Environmental Operating Report for 20062007-04-27027 April 2007 Submittal of the Annual Non-Radiological Environmental Operating Report for 2006 CPSES-200700517, Application for Order Approving Indirect Transfer of Control of Licenses and License Amendments to Reflect Proposed Licensee Name Change2007-04-18018 April 2007 Application for Order Approving Indirect Transfer of Control of Licenses and License Amendments to Reflect Proposed Licensee Name Change CPSES-200700719, Nuclear Liability Insurance2007-04-10010 April 2007 Nuclear Liability Insurance CPSES-200700605, License Amendment Request (LAR) 07-003, Revision to Technical Specifications 3.1, Reactivity Control Systems, 3.2, Power Distribution Limits, 3.3, Instrumentation, & 5.6.5b, Core Operating Limits Report2007-04-10010 April 2007 License Amendment Request (LAR) 07-003, Revision to Technical Specifications 3.1, Reactivity Control Systems, 3.2, Power Distribution Limits, 3.3, Instrumentation, & 5.6.5b, Core Operating Limits Report CPSES-200700708, Evaluation of Pressurizer Weld Overlay Confirmatory Analyses2007-04-0505 April 2007 Evaluation of Pressurizer Weld Overlay Confirmatory Analyses CPSES-200700691, Core Operating Limits Report, Cycle 132007-04-0404 April 2007 Core Operating Limits Report, Cycle 13 CPSES-200700663, Transmittal of the Annual Radiological Environmental Operating Report for 20062007-03-30030 March 2007 Transmittal of the Annual Radiological Environmental Operating Report for 2006 CPSES-200700607, Property Damage Insurance2007-03-29029 March 2007 Property Damage Insurance CPSES-200700606, Decommissioning Report2007-03-29029 March 2007 Decommissioning Report CPSES-200700573, Request to Withdraw Relief Request A-72007-03-22022 March 2007 Request to Withdraw Relief Request A-7 CPSES-200700571, Supplement to License Amendment Request (LAR) 05-06; Revision to Technical Specification 5.6.5 Revise Listing of LOCA and Non-LOCA Analysis Methodologies (TAC Nos. MD0185/0186)2007-03-19019 March 2007 Supplement to License Amendment Request (LAR) 05-06; Revision to Technical Specification 5.6.5 Revise Listing of LOCA and Non-LOCA Analysis Methodologies (TAC Nos. MD0185/0186) CPSES-200700515, Day Response to NRC Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients.2007-03-0909 March 2007 Day Response to NRC Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients. CPSES-200700454, Transmittal of Second-Half 2006 Fitness-For-Duty Program Performance Data2007-02-28028 February 2007 Transmittal of Second-Half 2006 Fitness-For-Duty Program Performance Data CPSES-200700451, Annual Operating Report for 20062007-02-28028 February 2007 Annual Operating Report for 2006 CPSES-200700422, Response to Request for Additional Information Related to Txu Power'S Request for Review of Previously Submitted Topical Reports2007-02-22022 February 2007 Response to Request for Additional Information Related to Txu Power'S Request for Review of Previously Submitted Topical Reports CPSES-200700414, Transmittal of Inservice Inspection Program Plan, Revision 5 (Unit 1: ASME Code Section XI 1998 Edition, 1999 and 2000 Addenda, Interval Start Date - 08/13/200, Second Interval)2007-02-22022 February 2007 Transmittal of Inservice Inspection Program Plan, Revision 5 (Unit 1: ASME Code Section XI 1998 Edition, 1999 and 2000 Addenda, Interval Start Date - 08/13/200, Second Interval) CPSES-200700391, Inspection and Mitigation of Alloy 82/182 Pressurizer Butt Welds2007-02-20020 February 2007 Inspection and Mitigation of Alloy 82/182 Pressurizer Butt Welds CPSES-200700346, Guarantees of Payment of Deferred Premiums, Submits Form 10-Q for the Period Ending September 30, 20062007-02-0808 February 2007 Guarantees of Payment of Deferred Premiums, Submits Form 10-Q for the Period Ending September 30, 2006 CPSES-200700229, Comanche, Response to Request for Additional Information, Relief Request B-6 for the Unit 1 Inservice Inspection (ISI) Program Plan from the 1998 Edition of ASME Code, Section XI, Through 2000 Addenda (Interval Start Date..2007-02-0202 February 2007 Comanche, Response to Request for Additional Information, Relief Request B-6 for the Unit 1 Inservice Inspection (ISI) Program Plan from the 1998 Edition of ASME Code, Section XI, Through 2000 Addenda (Interval Start Date.. CPSES-200700169, Inspection and Mitigation of Alloy 82/182 Pressurizer Butt Welds2007-01-30030 January 2007 Inspection and Mitigation of Alloy 82/182 Pressurizer Butt Welds CPSES-200700147, Response to Request for Additional Information Regarding Resolution of Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power2007-01-29029 January 2007 Response to Request for Additional Information Regarding Resolution of Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power CPSES-200700127, Submittal of Unit 2 Ninth Refueling Outage (2RF09) Inservice Inspection (ISI) Summary Report (Unit 2: 1998 Edition of ASME Code Section XI, Through 2000 Addenda, Interval Start Date - August 3, 2004, Second Interval)2007-01-24024 January 2007 Submittal of Unit 2 Ninth Refueling Outage (2RF09) Inservice Inspection (ISI) Summary Report (Unit 2: 1998 Edition of ASME Code Section XI, Through 2000 Addenda, Interval Start Date - August 3, 2004, Second Interval) CPSES-200700146, License Amendment Request (LAR) 06-007, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Offsite Circuits2007-01-18018 January 2007 License Amendment Request (LAR) 06-007, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Offsite Circuits CPSES-200700130, License Amendment Request (LAR) 06-009, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Diesel Generators2007-01-18018 January 2007 License Amendment Request (LAR) 06-009, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Diesel Generators CPSES-200700099, Annual Report of Changes in Peak Cladding Temperature2007-01-10010 January 2007 Annual Report of Changes in Peak Cladding Temperature CPSES-200602339, License Amendment Request (LAR) 06-010, Revision to Technical Specification 5.5.16, Containment Leakage Rate Testing Program.2006-12-19019 December 2006 License Amendment Request (LAR) 06-010, Revision to Technical Specification 5.5.16, Containment Leakage Rate Testing Program. CPSES-200602340, License Amendment Request (LAR) 06-012, Revision to Technical Specification 3.7.5, Auxiliary Feedwater System, TS 3.8.1, AC Sources - Operating, & TS 3.8.9, Distribution Systems - Operating.2006-12-19019 December 2006 License Amendment Request (LAR) 06-012, Revision to Technical Specification 3.7.5, Auxiliary Feedwater System, TS 3.8.1, AC Sources - Operating, & TS 3.8.9, Distribution Systems - Operating. 2010-07-28
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TXU C Power TXU Power Mike Blevins Comanche Peak Steam Senior Vice President & Ref. IOCFR50.90 Electric Station Chief Nuclear Officer P. O. Box 1002 (E01)
G$en Rose. TX 76043 Tel 254 897 5209 Fax: 254 897 6652 mike.blevins@ txu.com CPSES-200601 951 Log # TXX-06167 September 28, 2006 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 SUPPLEMENT TO LICENSE AMENDMENT REQUEST (LAR)05-010 AND RESPONSE TO REQUEST FOR INFORMATION (TAC Nos. MC9494 and MC9495)
REF: 1. Letter logged TXX-05199, dated December 16, 2005 from Mr. Mike Blevins of TXU Power to the NRC
- 2. Letter logged TXX-06097, dated June 26, 2006 from Mr. Mike Blevins of TXU Power to the NRC
- 3. Letter logged TXX-06144, dated August 25, 2006 from Mr. Mike Blevins of TXU Power to the NRC
- 4. Letter logged TXX-05162, dated September 1, 2005 from Mr. Mike Blevins of TXU Power to the NRC Gentlemen:
In Reference 1, TXU Generation Company LP (TXU Power) requested an amendment to the CPSES Unit I Operating License (NPF-87) and CPSES Unit 2 Operating License (NPF-89) to revise Technical Specifications 3.3.2, 3.5.2, and 3.6.7 entitled "ESFAS Instrumentation," "ECCS-Operating," and "Spray Additive System," respectively, in the CPSES Units I and 2 Technical Specifications (TS).
TXU Power supplemented the License Amendment Request via References 2 and 3.
This proposed License Amendment was requested to support resolution of Generic Safety Issue (GSI) 191 pursuant to the requirements of NRC Generic Letter 2004-02 as described in Reference 4.
A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
- Comanche Peak e Diablo Canyon
TXX-06167 Page 2 of 2 During teleconferences on September 20 and 25, 2006, the NRC requested that additional information be provided to support NRC review. The information requested is attached.
In accordance with IOCFR50.91(b), TXU Power is providing the State of Texas with a copy of this proposed supplement.
This communication contains no new licensing basis commitments regarding CPSES Units I and 2.
Should you have any questions, please contact Mr. J. D. Seawright at (254) 897-0140.
I state under penalty of perjury that the foregoing is true and correct.
Executed on September 28, 2006.
Sincerely, TXU Generation Company LP By: TXU Generation Management Company LLC Its General Partner Mike BI vis
-_red W. Madden Director, Oversight and Regulatory Affairs JDS Attachment c - B. S. Mallett, Region IV M. C. Thadani, Region IV Resident Inspectors, CPSES Ms. Alice Rogers Bureau of Radiation Control Texas Department of Public Health 1100 West 49th Street Austin, Texas 78756-3189
Attachment to TXX-06167 Page 1 of 4 Response to NRC Request for Additional Information Regarding LAR 05-010 NRC Request:
- 1. In the License Amendment Request (LAR 05-010), the licensee proposes to decrease the RWST "Lo-Lo" alarm from 45% to 33%. In a previous license amendment LA 73 (LAR 98-01) TXU Power changed RWST Lo-Lo from 40% to 45% to support operator actions for RWST switchover to cold leg recirculation. Please explain these differences CPSES Response:
The change in delivered water volume between the current RWST Low-Low nominal setpoint at 45% and the proposed 33% is necessary to support the design of the new strainers for GSI-191. Design modifications are being implemented to support the change. In the previous license amendment LA 73 (LAR 98-01), TXU Power changed RWST Lo-Lo from 40% to 45% to support operator actions for RWST switchover to cold leg recirculation without the modifications now being performed to support GSI-191. The procedure and operator actions for ECCS switchover on which LA 73 (LAR 98-01) is based are not being changed. The criterion to complete ECCS switchover prior to the Empty alarm is also unchanged.
Changes to RWST setpoints and alarm logic are based on the RWST Setpoint calculation. The previous design with Lo-Lo set at 45% and empty at 12% was based on the fact that the existing analysis of a RWST Lo-Lo setpoint of 40% did not show enough water below the empty alarm to complete ECCS pump protection precautions and containment spray switchover prior to depleting the useable water in the tank. In order to complete ECCS and containment spray switchover before the empty alarm, a Lo-Lo setpoint of 45% was required. The primary problem was slow closing containment spray RWST isolation valves (e.g. 90 second stroke times).
In response to GSI-191 Generic Letter 2004-02 (TXX-05162 dated September 1, 2005), CPSES committed to install new sump strainers in 2RF09 and IRF12. Proper functioning of strainers is enhanced by full submergence. The containment water levels based on Lo-Lo at 45% and spray switchover prior to Empty at 12% are inadequate for the new strainers. Since the ECCS and spray injection in a Large Break LOCA will stop when the respective sump isolation valves open due to containment overpressure closing the RWST isolation check valves, the lower the setpoints, the higher the actual water level in containment. Therefore, CPSES committed to revise setpoints to ensure complete submergence of the strainers at the completion of RWST injection.
The RWST setpoint calculation was revised using revised input from Westinghouse on the required ECCS switchover volume with Lo-Lo assumed at 38% in lieu of 45% and the sump at a
Attachment to TXX-06167 Page 2 of 4 Response to NRC Request for Additional Information Regarding LAR 05-010 corresponding coincident level. The 38% assumption is conservative with respect to the 33%
final setpoint. Although no containment overpressure is assumed, the water head in containment relative to the RWST level is considered. When both the tank and sump isolation valve are open, the level in containment and the level in the RWST determine the percentage of pump flow provided by each. This refinement to the ECCS analysis reduces the calculated RWST outflow since there is more water provided by the ECCS sump and less by RWST outflow. This showed the benefit of more accurate calculations. Therefore, the calculation of Containment Spray Flowrates for RWST draindown was also revised to credit the water head in containment relative to the RWST level to reduce the calculated RWST to Containment Spray outflow with no credit for containment overpressure. It was then determined that containment spray switchover could start at 6% and be completed before depleting the useable water in the tank if the RWST isolation valve stroke time was reduced from 90 seconds to 30 seconds and the Transfer to Cold Leg Recirculation procedure was revised to make spray switchover a continuous action step (i.e. one step in lieu of two). Each of the isolation valve switches on the main control board is a two position (maintained) switch. The calculation assumes that the operator is anticipating the start of spray switchover at 6% and will begin within 10 seconds of the indication and be complete in one minute (70 seconds total).
The draft procedure was tested on the CPSES simulator on September 21, 2006. Training of the operator consisted of a pre-job brief on the procedure change. At 6% indication, the operator repositions the switches in order: HS-4782 to open, HS-4783 to open, HS-4758 to closed, and HS-4759 to closed. HV-4782 and HV-4783 open in less than 20 seconds. The replacement valves for HV-4758 and HV-4759 (Containment Spray RWST isolation valves) close in less than 30 seconds. Adequate pump suction flow is maintained even if all four valves were switched simultaneously due to the flow versus position characteristics of the valves. On the first trial run, the operator completed switchover in 47 seconds. No failures were simulated.
A bounding single active failure of one sump isolation valve to open is assumed in the analysis.
On the second run simulating the single failure, the operator completed switchover of the operable train in 36 seconds and stopped the affected pump within the time assumed in the analysis. Starting spray switchover at 6% will ensure tank isolation complete before 3%
indicated.
Although not credited in the design basis cases or in the safety analysis, the failure to isolate the RWST or stop the affected spray pump was evaluated. The calculation of Containment Spray Flowrates for RWST draindown also shows that once the sump isolation valves are open, the pumps will have adequate NPSHa even if the RWST is not isolated and is completely depleted.
The sump will provide 100% of the required flow while the flow from the RWST will decrease to zero as level drops. This demonstrates the conservatism and margin in the design for containment spray switchover with no credit for containment overpressure. In addition,
Attachment to TXX-06167 Page 3 of 4 Response to NRC Request for Additional Information Regarding LAR 05-010 Containment backpressure from a real event will significantly reduce or tenninate RWST outflow.
The spray switchover change from 24% to 6% significantly increases the total RWST injection volume. The increase is (24%-6%) X 513 inches X 989 gallons per inch is approximately 91,324 gallons. This increase is needed to support the new strainer design for GSI-191.
The change in spray switchover is being made under the rules of IOCFR50.59.
NRC Request:
- 2. In section 4.1 RWST Setpoint, on page 3 of the submittal, the licensee states that: "In addition, the tank Empty alarm logic will be changed from a 1/4 logic to a 2/4 logic to match the 2/4 logic for the Low-Low alarm. These changes are required to provide consistency between the 'Low-Low' and the 'Empty' alarm logic and to ensure that there is enough water to preclude air entrainment in the suction of the ECCS pumps and sufficient time between receipt of the 'Low-Low' and the 'Empty' alarms for performance of the required manual actions to complete ECCS switchover." Please explain how the empty alarn logic change benefits sump performance.
CPSES Response:
The CPSES design for the RWST "low-low" level alarm (start of ECCS switchover) is a 2/4 logic. However, the current "empty" level alarm logic is 1/4. Because of this difference, the uncertainty in the alarms has a greater effect on the volume between the "low-low" level alarm and the "empty" level alarm setpoints. The total loop uncertainty for each channel is +/- 12 inches. Since one channel could be at +12 inches and the other three at -12 inches, the uncertainty in the volume between the setpoints for 1/4 logic is +/- 24 inches of water (i.e. the 2/4 1o-lo could occur at the nominal setpoint minus 12 inches and the 1/4 empty could occur at nominal empty setpoint plus 12 inches). Therefore, the volume between setpoints must be increased by 24 inches to assure the required deliverable volume.
If the empty alarm was also a 2/4 logic, the uncertainty in the volume of water between the setpoints would be the uncertainty in the alarm bistables. No matter which two level instruments actuate the 2/4 Lo-Lo alarm, the same two will actuate the 2/4 Empty alarm. Loss of one of the two instrument loops when the RWST level is between the Lo-Lo and empty setpoints will only increase the deliverable volume. The only uncertainty in the volume between the setpoints is the setability of the alarm bistables. The uncertainty in the bistables is much less than the total
Attachment to TXX-06167 Page 4 of 4 Response to NRC Request for Additional Information Regarding LAR 05-010 loop uncertainty and results in a lower uncertainty in the deliverable volume (2.6 inches vs 24 inches for the 1/4 logic). This consideration justifies a setpoint 4% lower than the 1/4 logic. By revising the "empty" level alarm logic to 2/4, the uncertainty in the volume between the setpoints is significantly reduced, thereby allowing an overall lower "low-low" level alarm setpoint and adding over 21,000 gallons to the containment before the start of switchover to cold leg recirculation. This increase is needed to support the new strainer design for GSI-191.
The change in alarm logic is being made under the rules of IOCFR50.59.