Proposed Tech Specs,Reducing Min Flow Rate Requirements for Safety Injection & Centrifugal Charging Pumps.Related Documentation EnclML20214J944 |
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Sequoyah ![Tennessee Valley Authority icon.png](/w/images/c/ce/Tennessee_Valley_Authority_icon.png) |
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08/08/1986 |
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TENNESSEE VALLEY AUTHORITY |
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ML20214J938 |
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NUDOCS 8608150240 |
Download: ML20214J944 (11) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217F9701999-10-14014 October 1999 Proposed Tech Specs,Incorporating ARC for Axial Primary Water Stress Corrosion Cracking at Dented Tube Support Plate Intersections ML20217E4301999-10-12012 October 1999 Proposed Tech Specs,Revising Requirements for Containment Penetrations During Refueling Operations ML20211M7341999-08-30030 August 1999 Marked-up & Revised TS Pages,Providing Alternative to Requirement of Actually Measuring Response Times ML20211K1721999-08-30030 August 1999 Proposed Tech Specs,Providing Clarification to Current TS Requirements for Containment Isolation Valves ML20209B7731999-06-30030 June 1999 Proposed Tech Specs Updating Requirmements for RCS Leakage Detection & RCS Operational Leakage Specifications to Be Consistent with NUREG-1431 ML20196F2211999-06-24024 June 1999 Proposed Tech Specs Pages for Amend to Licenses DPR-77 & DPR-79,allowing Use of Fully Qualified & Tested Spare Inverter in Place of Any of Eight Required Inverters ML20196G4701999-06-24024 June 1999 Proposed Tech Specs Pages Re Amends to Licenses DPR-77 & DPR-79,revising TS to Be Consistent with Rev to ISTS Presently Submitted to NEI TSTF for Submittal as Rev to NUREG-1431 ML20196G7961999-06-22022 June 1999 Proposed Tech Specs Bases,Clarifying Proper Application of TS Requirements for Power Distribution Systems & Functions That Inverters Provide to Maintain Operability & Providing Updated Info on Cold Leg Injection Accumulators ML20195E9841999-06-0707 June 1999 Proposed Tech Specs,Increasing Max Allowed Specific Activity of Primary Coolant from 0.35 Microcuries/Gram Dose Equivalent I-131 to 1.0 Microcuries/Gram Dose Equivalent I-131 for Plant Cycle 10 (U2C10) Core ML20206E1391999-04-29029 April 1999 Proposed Tech Spec Change 99-03, Main Control Room Emergency Ventilation Sys Versus Radiation Monitors. Changes Add LCOs 3.3.3.1 & 3.7.7 to Address Inoperability of Radiation Monitoring CREVS & NUREG-1431 Recommendations ML20206E1611999-04-29029 April 1999 Proposed Tech Spec Change 99-04, Auxiliary Suction Pressure Low Surveillance Frequency Rev. Change Deletes Surveillance ML20204H4081999-03-19019 March 1999 Proposed Tech Specs,Relocating TS 3.8.3.1,3.8.3.2,3.8.3.3 & Associated Bases Associated with Electrical Equipment Protective Devices to Technical Requirements Manual ML20207D6011999-02-26026 February 1999 Proposed Tech Specs Relocating TS 3.7.6, Flood Protection Plan & Associated Bases from TS to Plant TRM ML20207D6331999-02-26026 February 1999 Proposed Tech Specs Providing for Consistency When Exiting Action Statements Associated with EDG Sets ML20206S0131999-01-15015 January 1999 Proposed Tech Specs 3.3.3.3, Seismic Instrumentation & Associated Bases,Relocated to Plant Technical Requirements Manual ML20199K6001999-01-15015 January 1999 Proposed Tech Specs Adding New Action Statement to 3.1.3.2 That Would Eliminate Need to Enter TS 3.0.3 Whenever Two or More Individual RPIs Per Bank May Be Inoperable,While Maintaining Appropriate Overall Level of Protection ML20195H6111998-11-16016 November 1998 Proposed Tech Specs Revising EDG SRs by Adding Note That Allows SR to Be Performed in Modes 1,2,3 or 4 If Associated Components Are Already OOS for Testing or Maint & Removing SR Verifying Certain Lockout Features Prevent EDG Starting ML20154H7251998-10-0808 October 1998 Proposed Tech Specs Pages,Supplementing Proposed TS Change 96-08,rev 1 to Add CRMP to Administrative Controls Section & Bases of TS ML20238F1091998-08-27027 August 1998 Proposed Tech Specs Providing for Insertion of Limited Number of Lead Test Assemblies,Beginning W/Unit 2 Operating Cycle 10 Core ML20238F3001998-08-27027 August 1998 Proposed Tech Specs Replacing 72 H AOT of TS 3.8.1.1,Action b,w/7 Day AOT Requirement for Inoperability of One EDG or One Train of EDGs ML20236G5961998-06-29029 June 1998 Proposed Tech Specs Typed Pages for TS Change 95-19, Section 6 - Administrative Controls Deletions ML20249C6371998-06-26026 June 1998 Proposed Tech Specs Lowering Specific Activity of Primary Coolant from 1.0 Uci/G Dose Equivalent I-131 to 0.35 Uci/G Dose Equivalent I-131,as Provided in GL 95-05 ML20248F0051998-05-28028 May 1998 Proposed Tech Specs for Section 6, Administrative Controls Deletions ML20217N3511998-04-30030 April 1998 Proposed Tech Specs Pages,Modifying Surveillance Requirement 4.4.3.2.1.b to Change Mode Requirement to Allow PORV Stroke Testing in Modes 3,4 & 5 W/Steam Bubble in Pressurizer Rather than Only in Mode 4 ML20203J1681998-02-25025 February 1998 Proposed Tech Specs Pages,Revising EDG Surveillance Requirements to Delete Requirement for 18-month Insp IAW Procedures Prepared in Conjunction W/Vendor Recommendations & Modify SRs Associated W/Verifying Capability of DGs ML20202J7601998-02-13013 February 1998 Proposed Tech Specs Section 3.7.9 Re Relocation of Snubber Requirements ML20202J7141998-02-13013 February 1998 Proposed Tech Specs Adding New LCO That Addresses Requirements for Main Feedwater Isolation,Regulating & Bypass Valves ML20202J6961998-02-13013 February 1998 Proposed Tech Specs Incorporating MSIV Requirements to Be Consistent W/Std TS (NUREG-1431) ML20198T4311998-01-21021 January 1998 Proposed Tech Specs Re New Position Title & Update of Description of Nuclear Organization ML20199K4571997-11-21021 November 1997 Proposed Tech Specs Adding one-time Allowance Through Operating Cycle 9 to Surveillance Requirement 4.4.3.2.1.b to Perform Stroke Testing of PORVs in Mode 5 Rather than Mode 4,as Currently Required ML20211A3191997-09-17017 September 1997 Proposed Tech Specs Re Pressure Differential Surveillance Requirements for Containment Spray Pumps ML20137T0871997-04-0909 April 1997 Proposed Tech Specs Re Elimination of Cycle 8 Limitation for SG Alternate Plugging Criteria ML20137M8581997-04-0101 April 1997 Proposed Tech Specs 2.1 Re Safety Limits & TS 3/4.2 Re Power Distribution Limits ML20137C8421997-03-19019 March 1997 Proposed Tech Specs Re Conversion from Westinghouse Electric Corp Fuel to Framatome Cogema Fuel ML20136J0381997-03-13013 March 1997 Proposed Tech Specs Section 5.6.1.2,revising Enrichment of Fuel for New Fuel Pit Storage Racks ML20134P8631997-02-14014 February 1997 Proposed Tech Specs Requesting Discretionary Enforcement for 48 Hours Which Is in Addition to 72 Hours Allowed Outage Time Provided by TS Action 3.8.1.1.b ML20134K9981997-02-0707 February 1997 Proposed Tech Specs Revising TS Change Request 96-01, Conversion from W Electric Corp Fuel to Framatome Cogema Fuel (MARK-BW-17), to Ensure That Core Analysis Computer Code Output Actions Are Consistent W/Hot Channel Factor SRs ML20134L9261996-11-0808 November 1996 Proposed Tech Specs Re Placing of Channel in Trip for Reactor Trip & Engineered Safety Feature Instrumentation Sys Solely to Perform Testing as Not Requiring Channel to Be Declared Inoperable ML20129D2661996-10-18018 October 1996 Proposed Tech Specs,Removing Existing Footnotes That Limit Application of Apc for Plant S/G Tubes to Cycle 8 Operation for Both Units ML20129G7301996-09-26026 September 1996 Proposed Tech Specs 3/4.3.3 Re Fire Detection instrumentation,3/4.7.11 Re Fire Suppression Systems & 3/4.7.12 Re Fire Protection Penetrations ML20113G2691996-09-20020 September 1996 Proposed Tech Specs Change 96-09, Clarification of Work Shift Durations for Overtime Limits ML20117J3391996-08-28028 August 1996 Proposed Tech Specs Revising Psv & MSSV Setpoint Tolerance from Plus or Minus 1% to Plus or Minus 3% ML20117D1651996-08-22022 August 1996 Proposed Tech Specs of SQN Units 1 & 2,deleting Table 4.8.1, DG Reliability, & Revising Section 3.8.1 to Allow Once Per 18 month,7 Day AOT for EDGs ML20117D3121996-08-22022 August 1996 Proposed Tech Specs,Lowering Minimum TS ice-basket Weight of 1,155 Lbs to 1,071 Lbs.Reduced Overall Ice Weight from 2,245,320 Lbs to 2,082,024 Lbs ML20117D3141996-08-21021 August 1996 Proposed TS 3.7.1.3 Re Condensate Storage Tank ML20117D3341996-08-21021 August 1996 Proposed Tech Specs Re Deletion of Surveillance Requirement 4.8.1.1.1.b ML20112H0431996-06-0707 June 1996 Proposed Tech Specs,Revising Section 6, Administrative Controls, to Be More Closely Aligned W/Requirements of STSs ML20101N7071996-04-0404 April 1996 Proposed Tech Specs,Allowing Conversion from Westinghouse Fuel to Fuel Provided by Framatome Cogema Fuels ML20096B3761996-01-0404 January 1996 Proposed Tech Specs Extending Radiation Monitoring Instrumentation Surveillance Period Per GL 93-05 ML20096C2481996-01-0303 January 1996 Proposed Tech Specs,Revising Bases Section 3/4.7.1.2 to Indicate Current Operational Functions of turbine-driven AFW Level Control Valves Modified During Unit 1 Cycle 7 Refueling Outage 1999-08-30
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217F9701999-10-14014 October 1999 Proposed Tech Specs,Incorporating ARC for Axial Primary Water Stress Corrosion Cracking at Dented Tube Support Plate Intersections ML20217E4301999-10-12012 October 1999 Proposed Tech Specs,Revising Requirements for Containment Penetrations During Refueling Operations ML20211M7341999-08-30030 August 1999 Marked-up & Revised TS Pages,Providing Alternative to Requirement of Actually Measuring Response Times ML20211K1721999-08-30030 August 1999 Proposed Tech Specs,Providing Clarification to Current TS Requirements for Containment Isolation Valves ML20209B7731999-06-30030 June 1999 Proposed Tech Specs Updating Requirmements for RCS Leakage Detection & RCS Operational Leakage Specifications to Be Consistent with NUREG-1431 ML20196F2211999-06-24024 June 1999 Proposed Tech Specs Pages for Amend to Licenses DPR-77 & DPR-79,allowing Use of Fully Qualified & Tested Spare Inverter in Place of Any of Eight Required Inverters ML20196G4701999-06-24024 June 1999 Proposed Tech Specs Pages Re Amends to Licenses DPR-77 & DPR-79,revising TS to Be Consistent with Rev to ISTS Presently Submitted to NEI TSTF for Submittal as Rev to NUREG-1431 ML20196G7961999-06-22022 June 1999 Proposed Tech Specs Bases,Clarifying Proper Application of TS Requirements for Power Distribution Systems & Functions That Inverters Provide to Maintain Operability & Providing Updated Info on Cold Leg Injection Accumulators ML20196G8071999-06-22022 June 1999 Revs to Technical Requirements Manual ML20195E9841999-06-0707 June 1999 Proposed Tech Specs,Increasing Max Allowed Specific Activity of Primary Coolant from 0.35 Microcuries/Gram Dose Equivalent I-131 to 1.0 Microcuries/Gram Dose Equivalent I-131 for Plant Cycle 10 (U2C10) Core ML20206E1611999-04-29029 April 1999 Proposed Tech Spec Change 99-04, Auxiliary Suction Pressure Low Surveillance Frequency Rev. Change Deletes Surveillance ML20206E1391999-04-29029 April 1999 Proposed Tech Spec Change 99-03, Main Control Room Emergency Ventilation Sys Versus Radiation Monitors. Changes Add LCOs 3.3.3.1 & 3.7.7 to Address Inoperability of Radiation Monitoring CREVS & NUREG-1431 Recommendations ML20204E8501999-03-21021 March 1999 Plant,Four Yr Simulator Test Rept for Period Ending 990321 ML20204H4081999-03-19019 March 1999 Proposed Tech Specs,Relocating TS 3.8.3.1,3.8.3.2,3.8.3.3 & Associated Bases Associated with Electrical Equipment Protective Devices to Technical Requirements Manual ML20207D6331999-02-26026 February 1999 Proposed Tech Specs Providing for Consistency When Exiting Action Statements Associated with EDG Sets ML20207D6011999-02-26026 February 1999 Proposed Tech Specs Relocating TS 3.7.6, Flood Protection Plan & Associated Bases from TS to Plant TRM ML20206S0131999-01-15015 January 1999 Proposed Tech Specs 3.3.3.3, Seismic Instrumentation & Associated Bases,Relocated to Plant Technical Requirements Manual ML20199K6001999-01-15015 January 1999 Proposed Tech Specs Adding New Action Statement to 3.1.3.2 That Would Eliminate Need to Enter TS 3.0.3 Whenever Two or More Individual RPIs Per Bank May Be Inoperable,While Maintaining Appropriate Overall Level of Protection ML20195H6111998-11-16016 November 1998 Proposed Tech Specs Revising EDG SRs by Adding Note That Allows SR to Be Performed in Modes 1,2,3 or 4 If Associated Components Are Already OOS for Testing or Maint & Removing SR Verifying Certain Lockout Features Prevent EDG Starting ML20154H7251998-10-0808 October 1998 Proposed Tech Specs Pages,Supplementing Proposed TS Change 96-08,rev 1 to Add CRMP to Administrative Controls Section & Bases of TS ML20238F1091998-08-27027 August 1998 Proposed Tech Specs Providing for Insertion of Limited Number of Lead Test Assemblies,Beginning W/Unit 2 Operating Cycle 10 Core ML20238F3001998-08-27027 August 1998 Proposed Tech Specs Replacing 72 H AOT of TS 3.8.1.1,Action b,w/7 Day AOT Requirement for Inoperability of One EDG or One Train of EDGs ML20209J1631998-08-0707 August 1998 Rev 41 to Sequoyah Nuclear Plant Odcm ML20236G5961998-06-29029 June 1998 Proposed Tech Specs Typed Pages for TS Change 95-19, Section 6 - Administrative Controls Deletions ML20249C6371998-06-26026 June 1998 Proposed Tech Specs Lowering Specific Activity of Primary Coolant from 1.0 Uci/G Dose Equivalent I-131 to 0.35 Uci/G Dose Equivalent I-131,as Provided in GL 95-05 ML20248F0051998-05-28028 May 1998 Proposed Tech Specs for Section 6, Administrative Controls Deletions ML20217N3511998-04-30030 April 1998 Proposed Tech Specs Pages,Modifying Surveillance Requirement 4.4.3.2.1.b to Change Mode Requirement to Allow PORV Stroke Testing in Modes 3,4 & 5 W/Steam Bubble in Pressurizer Rather than Only in Mode 4 ML20203J1681998-02-25025 February 1998 Proposed Tech Specs Pages,Revising EDG Surveillance Requirements to Delete Requirement for 18-month Insp IAW Procedures Prepared in Conjunction W/Vendor Recommendations & Modify SRs Associated W/Verifying Capability of DGs ML20202J7651998-02-13013 February 1998 Technical Requirements Manual ML20202J7141998-02-13013 February 1998 Proposed Tech Specs Adding New LCO That Addresses Requirements for Main Feedwater Isolation,Regulating & Bypass Valves ML20202J6961998-02-13013 February 1998 Proposed Tech Specs Incorporating MSIV Requirements to Be Consistent W/Std TS (NUREG-1431) ML20202J7601998-02-13013 February 1998 Proposed Tech Specs Section 3.7.9 Re Relocation of Snubber Requirements ML20198T4311998-01-21021 January 1998 Proposed Tech Specs Re New Position Title & Update of Description of Nuclear Organization ML20199F8231997-11-30030 November 1997 Cycle 9 Restart Physics Test Summary, for 971011-971130 ML20199K4571997-11-21021 November 1997 Proposed Tech Specs Adding one-time Allowance Through Operating Cycle 9 to Surveillance Requirement 4.4.3.2.1.b to Perform Stroke Testing of PORVs in Mode 5 Rather than Mode 4,as Currently Required ML20211A3191997-09-17017 September 1997 Proposed Tech Specs Re Pressure Differential Surveillance Requirements for Containment Spray Pumps ML20203B9731997-08-0505 August 1997 Rev 1 to RD-466, Test & Calculated Results Pressure Locking ML20217J5581997-07-31031 July 1997 Cycle Restart Physics Test Summary, for Jul 1997 ML20210J1671997-04-30030 April 1997 Snp Unit 1 Cycle 8 Refueling Outage Mar-Apr 1997,Results of SG Tube ISI as Required by TS Section 4.4.5.5.b & Results of Alternate Plugging Criteria Implementation as Required by Commitment from TS License Condition 2C(9)(d) ML20137T0871997-04-0909 April 1997 Proposed Tech Specs Re Elimination of Cycle 8 Limitation for SG Alternate Plugging Criteria ML20137M8581997-04-0101 April 1997 Proposed Tech Specs 2.1 Re Safety Limits & TS 3/4.2 Re Power Distribution Limits ML20137C8421997-03-19019 March 1997 Proposed Tech Specs Re Conversion from Westinghouse Electric Corp Fuel to Framatome Cogema Fuel ML20136J0381997-03-13013 March 1997 Proposed Tech Specs Section 5.6.1.2,revising Enrichment of Fuel for New Fuel Pit Storage Racks ML20134P8631997-02-14014 February 1997 Proposed Tech Specs Requesting Discretionary Enforcement for 48 Hours Which Is in Addition to 72 Hours Allowed Outage Time Provided by TS Action 3.8.1.1.b ML20134K9981997-02-0707 February 1997 Proposed Tech Specs Revising TS Change Request 96-01, Conversion from W Electric Corp Fuel to Framatome Cogema Fuel (MARK-BW-17), to Ensure That Core Analysis Computer Code Output Actions Are Consistent W/Hot Channel Factor SRs ML20138F2581997-01-17017 January 1997 Rev 39 to Sequoyah Nuclear Plant Odcm ML20134L9261996-11-0808 November 1996 Proposed Tech Specs Re Placing of Channel in Trip for Reactor Trip & Engineered Safety Feature Instrumentation Sys Solely to Perform Testing as Not Requiring Channel to Be Declared Inoperable ML20129D2661996-10-18018 October 1996 Proposed Tech Specs,Removing Existing Footnotes That Limit Application of Apc for Plant S/G Tubes to Cycle 8 Operation for Both Units ML20129G7301996-09-26026 September 1996 Proposed Tech Specs 3/4.3.3 Re Fire Detection instrumentation,3/4.7.11 Re Fire Suppression Systems & 3/4.7.12 Re Fire Protection Penetrations ML20134J9991996-09-23023 September 1996 Fuel Assembly Insp Program 1999-08-30
[Table view] |
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EMERGENCY CORE COOLING SYSTEMS (ECCS)
SURVEILLANCE REQUIREMENTS (Continued)
- h. By performing a flow balance test during shutdown following completion of modifications to the ECCS subsystem that alter the subsystem flow characteristics and verifying the following flow rates:
- 1. For safety injection pump lines with a single pump running:
- a. The sum of the injection line flow rates, excluding the highest flow rate is greater than or equal to M gpm, and 444-
- b. The total pump flow rate is less than or equal to gpm.
- 2. For centrifugal charging pump lines with a single pump running:
- a. The sum of the injection line flow rates, excluding the highest flow rate is greater than or equal to g gpm, and
- b. The total pump flow rate is less than or equal to 555 gpm.
- 3. For all four cold leg injection lines with a single RHR pump running a flow rate greater than or equal to 3976 gpm.
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SEQUOYAH - UNIT 1 3/4 5-8 l
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O EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- h. By performing a flow balance test during shutdown following completion of . modifications to the ECCS suosystem that alter the subsystem flow characteristics and verifying the following flow rates:
- 1. For safety injection pump lines with a single pump running:
- a. The sum of the injection line flow rates, excluding the highest flow rate is greater than or equal to 464:gpm, and Mt
- b. The total pump flow rate is less than or equal to 4kd[gpm.
- 2. For centrifugal charging pump lines with a single pump running:
- a. The sum of the injection line ' low rates, excluding the righest flow rate is greater than or equal to 4>hv gpm, and J/6
- b. The total pump flow rate is less than or equal to 555 gpm.
- 3. For all four cold leg injection lines with a single RHR pump running a ficw rate greater than or equal to 3976 gpm.
! SEQUOYAH - UNIT 2 3/4 5-8 i .
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ENCLOSURE 2 Proposed Technical Specification Change SEQUOYAH NUCLEAR PLANT Docket Nos. 50-327, -328 (TVA SQN TS 73)
Description and Justification for Proposed Changes to Flow Rate Requirements For ECCS Pumps i
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, #. . ENCLOSURE 2 5,
Stradard Practice Page 5 SQA30 Rev. 2 ATTACHMENT 1 SEOUOYAH NUCLEAR PLANT UNIT 1 AND 2 PROPOSED APPENDIX A OR B TECHNICAL SPECIFICATION CHANGE NO. 127 Description of Change (Use additicnal pages as necessary)
This change will revise (ECCS) flowrate values as follows: Reduce the flowrate value in Surveillance Requirement (SR) 4.5.2.h.1.a to 444gpm; Increase the flowrate value in SR 4.5.2.h.1.b to 675gpm; and Reduce the flowrate value in SR 4.5.2.h.2.a to 316gpm. For resultant SR 4.5.2.h, see attached marked-up pages.
Reason for Change (Use additional pages as necessary)
The requested change in flowrate values for these Sks will update requirements to reflect actual system capabilities and the assumptions used in the current safety analysis. See attached pages for additional details.
Justification for Chang (Use additional pages as necessary)
Westinghouse analysis has evaluated that operation within the proposed limits meets all applicable 10CFR50.46 limits.
APPROVED: 2 7 Plant Operations Review Committee JUL 0 81986 Date O'R. Ot h < - 7/slac, Plant Manager iDalte ff $ll Wh//)V l b Site Director ' 'Date N
l g Radiological Health Staff (Radiological)1 Date
^>/A Assistant Manager of Natural Resources' Date (Environmental) l NOTE: All changes made to the above proposal shall be coordinated with the original signers.
1 As required.
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Attachment ,
Reason for Change (continued)
Full flow testing of the safety injection pumps (SIPS) and centrifugal charging pumps (CCPs) performed each refueling outage (in response to Westinghouse Technical Bulletin NSD-TB-80-ll) indicated deficient pump performance when compared to Technical Specification SR 4.5.2 requirements and/or the FSAR minimum pump performance curves. Westinghouse, at the request of Sequoyah Nuclear Plant (SQN), performed an Appendix K analysis utilizing reduced pump flows with the current system hydraulics; the analysis yielded acceptable results. Revised minimum emergency core cooling ,
system (ECCS) performance curves and ECCS Technical Specification SRs were provided to reflect assumptions used in the new safety analysis. The requested change to SR 4.5.2.h.l.a and SR 4.5.2.h.2.a incorporates the revised surveillance requirements provided by Westinghouse letter, reference 1. A subsequent evaluation of this analysis was performed to assess the effect of increasing the assumed reactor coolant pump seal injection flowrate. The results of the evaluation did not affect the previous analysis, and the same proposed ECCS technical specification revision was attached to the resulting Westinghouse letter, reference 2.
l Additionally, SQN requested Westinghouse to evaluate the current SR value for maximum SIP flowrate to determine the available margin to pump runout.
The Westinghouse Pump Group, in coordination with the pump manufacturer, Pacific Pump, determined acceptable tested pump performance had been achieved at a test point of 675gpm. Accordingly, the requested change to SR 4.5.2.h.l.b incorporates the revised surveillance requirement transmitted by Westinghouse letter, reference 3.
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's s Apparent CCP and SIP performance deficiencies, relative to certified vendor performance and/or trending pump degradation, have in the past resulted in difficulty in meeting the FSAR minimum performance curves and/or the technical specification requirements for maximum allowable pump flow (pump runout protection) and minirsum injection flow (sum of three lowest branch injection lines). The maximum and minimum limits define an allowable band of acceptable system performance which must be satisfied for either the A- ,
or B-train pump supplying a common injection path. Any differences in A- and P-train pump performance exacerbate difficulty in balancing, resulting in the weaker pump being left at the lower end of the band in order to keep the stronger train below the .naximum allowable flowrate.
Relaxation of the band boundaries (upper or lower) without compromising nuclear safety, provides greater flexibility for balancing, greater margin for performance degradation, and more realistically reflects actual system capabilities and performance constraints.
In summary, the requested changes to SR 4.5.2.h.1.a and SR 4.5.2.h.2.a will update the technical specifications to reflect the assumptions used in the latest safety analysis. The reduced minimum flow requirements are necessary to accommodate actual pump and system hydraulic performance and provide adequate margin for performance degradation.
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Justification for Change (continued)
A nuclear safety evaluation has been performed by Westinghouse to evaluate the impact of reduced pump flowrates on the large break and small break LOCA analyses (see reference 1).
For large break LOCA's, Westinghouse evaluated that the reduced safety injection flow could be accommodated within the existing analysis due to built-in conservatism. This is due to the relatively low importance of these pump's injected flow during the blowdown phase of large break LOCA's.
For the small break LOCA analysis, the effect of reduced safety injection flow was to be evaluated for 4, 6, and 8-inch breaks. Existing LOCA FSAR analysis indicated the 6 and 8-inch breaks resulted in more than 400 F higher calculated PCT; therefore, only the 6 and 8-inch breaks were further evaluated as limiting cases. This evaluation consisted of using a correlation developed by a sensitivity study performed as a part of and documented by Westinghouse WCAP-9600, " Report on Small Break Accident for Westinghouse NSSS System." This study showed that for each percentage reduction of safety injection flow that the calcalated peak clad temperatuer increased approximately 15 F. For the case of SQN, an additional i
5-degrees per percent reduction in flow was added for conservatism due to the presence of the upper head injection system. This results in e factor of 20 F per percentage SI flow reduction. TVA asked Westinghouse to analyze the effects of a 10-percent reduction in SI flow in order to bound j the current situation. The results of the evaluation identified the 6-inch l
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-4 break as the most limiting, yielding a maximum 200*F increase in PCT resulting from the reduced injected flow. This increase would still result in PCTs well below the 2200*F 10CFR$0.46 limit since existing calculated PCTs were less than 1500*F for all SQN small breaks. See reference 1 for Westinghouse nuclear safety evaluation check list and additional details.
Westinghouse review of the safety injection system and applicable SIP pump curves, supported by conference with Pacific Pumps, confirmed adequate NPSH is available to operate beyond the current 660gpm technical specification limit. Acceptable test data was available to 675 gps. The actual requirements are not expected to be as conservative as represented beyond 675gpm by the NPSH required curve, however, Pacific Pump would not authorize operation beyond 675gpm due to lack of test data. See reference 3 for additional details.
The requested change to SR 4.5.2.h.1.b will increase the maximum allowable SIP flowrate to more accurately reflect actual pump limitations. By i
increasing the maximum ellowable flowrate, the acceptable operational band is widened, thereby allowing the SIPS to be balanced at an overall higher level. This can result in increased available SI flow and increased available margin for degradation.
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References
- 1. Westinghouse letter TVA-84-057 with attachments from R. S. Howard to J. A. Raulston dated March 16, 1984 (copy attached).
- 2. Westinghouse letter TVA-86-671 from L. L. Williams to J. A. Raulston dated June 27, 1986 (copy attached).
- 3. Westinghouse letter TVA-86-510 with attachments from L. L. Williams to C. C. Mason dated January 16, 1986 (copy attached).
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rch 16, 1984 Mr. John A. Raulston, Chief Nuclear Engineer = ,
Tennessee Valley Authority rn
400 West Summit Hill Drive c, W10C126 c4 ,; . .
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TENNESSEE VALLEY AUTHORITY u SEQUOYAH UNITS 1 & 2 s. -
Safety Injection Pump Test Data "'
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Dear Mr. Raulston:
ca Attached for TVA's information and use is an evaluation of the "
/- Sequoyah Unit II Centrifugal Charging Pump (CCP) and Intermediate High
_ Head Safety Injection Pumps Test Data. Westinghouse performed this 3 ,- -
. evaluation at the request of TVA. 4T5 The Appendix K Analysis was performed and found acceptable using the If the system hydraulics is changed, (such as a repositioning of the reduced pump flows and ofsystem '"* o wco branch line throttle valves) an evaluation the system hydraulicsperformance wil establishe '
be needed to determine the effect to the Appendix K. Analysis. ,,
l The CCP mini-flow path was analyzed as being open during the fl uay 7 h4 injection phase. Note,thecomponentcoolingwater(CCW)tosealwaterb wi"r 4fE heat exchanger must be assured. The CCW is to be supplied, assuming a -i$
single active failure in the CCW system. .s.
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IfTVAhasanyquestionsconcerningthisevaluation,Pleasecontact1* -l us. .c, t (,Pe v s, i:g.x E Very truly yours, ,'
E' Ws Tacincc< , l 'N WESTINGHOUSE ELECTRIC CORPORATION
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TVA-84-057
-J. A. Raulston March 16, 1984 cc: J. A. Raulston IL, 1A J. A. Coffey 11, IA C. C. Mason IL, 1A R. E. Alsup IL, IA R. U. Mathieson IL, IA S. A. Moser IL, TA 1 /lJAR:CJS:JLA - 5/3/84 C
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p lfll xc: J. P. Vineyard, W3D224 C-K MEDS, W5B63 C-K
*Per telecon between your Gary Terpstra and our Jeff Schermerhorn, we understand that this evaluation, including accumulation of additional pump head capacity data, is being handled by NUC PR. We have noted several editorial comments on this evaluation as shown on the marked copy.
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