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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] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20196G8071999-06-22022 June 1999 Revs to Technical Requirements Manual ML20209J1631998-08-0707 August 1998 Rev 41 to Sequoyah Nuclear Plant Odcm ML20202J7651998-02-13013 February 1998 Technical Requirements Manual ML20138F2581997-01-17017 January 1997 Rev 39 to Sequoyah Nuclear Plant Odcm ML20134J9991996-09-23023 September 1996 Fuel Assembly Insp Program ML20138F2531996-02-23023 February 1996 Rev 38 to Sequoyah Nuclear Plant Odcm ML20108B4121995-11-0303 November 1995 Rev 37 to Sequoyah Nuclear Plant Odcm ML20094Q2301995-10-30030 October 1995 ASME ISI Valve Testing Program Basis Document, Rev 0 ML20094Q1931995-10-30030 October 1995 Rev 1 to ASME Sys Pressure Testing Program Basis Document ML20094Q1971995-10-30030 October 1995 Rev 1 to SG Tubing ISI & Augmented Insps, Rev 1 to 0-SI-SXI-068-114.2 ML20094Q2111995-10-30030 October 1995 Rev 1 to ASME ISI Pump Testing Program Basis Document ML20094Q1761995-10-13013 October 1995 ASME Section XI Isi/Nde & Augmented Nondestructive Exam Programs, SSP-6.10,rev 2 ML20094Q1841995-10-13013 October 1995 ASME Section XI Isi/Nde Program Units 1 & 2, Rev 0 to 0-SI-DXI-000-114.2 ML20149L6811994-09-30030 September 1994 Concerns Resolution Program - Sequoyah Nuclear Plant ML20063D6691994-01-24024 January 1994 Rev 4 to Sequoyah Nuclear Plant Restart Plan ML20065Q6251993-10-13013 October 1993 Rev 31 to Sequoyah Nuclear Plant Odcm ML20056F3181993-08-20020 August 1993 Rev 0 of Post-Restart Plan ML20056G1841993-08-10010 August 1993 Rev 2 to Sequoyah Nuclear Plant Restart Plan ML20044F3081993-05-20020 May 1993 Rev 0 to Sequoyah Nuclear Plant Restart Plan. ML18036B1961993-01-27027 January 1993 Rev 2 to Nuclear Power Training Procedure TRN-31, Fire Brigade Training. ML20127P5461992-12-16016 December 1992 Rev 20 to Surveillance Instruction SI-114.1, ASME Section XI ISI Program,Unit 1 ML20127P6361992-12-16016 December 1992 Rev 19 to Surveillance Instruction SI-114.2, ASME Section XI ISI Program,Unit 2 ML20114C8131992-04-17017 April 1992 Rev 27 to Odcm ML20101F2081992-02-0808 February 1992 Rev 16 to Surveillance Instruction SI-114.2, ASME Section XI ISI Program Unit 2 ML20101F2011992-02-0808 February 1992 Rev 17 to Surveillance Instruction SI-114.1, ASME Section XI ISI Program Unit 1 ML19332D2241989-09-22022 September 1989 Rev 23 to Odcm. ML20245H1421989-08-15015 August 1989 Rev 22 to Offsite Dose Calculation Manual Changes ML20246H4861989-05-16016 May 1989 Rev 1 to Technical Instruction TI-115, Instructions for Sewage Mgt ML20244E2521989-04-28028 April 1989 Rev 14 to Surveillance Instruction SI-114.2, ASME Section XI Inservice Insp Program ML20246E7771989-04-25025 April 1989 Rev 14 to Surveillance Instruction SI-114.1, ASME Section XI Inservice Insp Program ML20206D3421988-10-15015 October 1988 Rev 13 to Surveillance Instruction SI-114.2, Inservice Insp Program ML20154J3221988-09-0909 September 1988 Procedure EA-OR-003-S, Sequoyah Nuclear Plant - Unit 1 Design Baseline & Verification Program,Supplemental Engineering Assurance Oversight Review Rept ML20150F9291988-06-17017 June 1988 Diesel Generator Voltage Response Improvement Plan ML20154L1421988-05-0909 May 1988 Rev 3 to Revised Sequoyah Nuclear Performance Plan ML20153H3891988-03-30030 March 1988 Rev 19 to Sequoyah Nuclear Plant Offsite Dose Calculation Manual ML20196G3301988-02-24024 February 1988 Limited Test Program for Determining Axial Load Capacity of Cast One-Hole Conduit Clamps ML20147E9511988-01-21021 January 1988 Revised, Procedures Generation Package ML20153H3851988-01-0505 January 1988 Rev 18 to Sequoyah Nuclear Plant Offsite Dose Calculation Manual ML20147E5691987-12-17017 December 1987 Rev 4 to Special Maint Instruction SMI-0-317-61, Instrumentation Features Walkdown,Rework & Insp Instructions for CAR 87-014 ML20237C5451987-10-28028 October 1987 Rev 17 to Offsite Dose Calculation Manual ML20236E6931987-10-17017 October 1987 Rev 2 to Engineering Organization & Operating Procedures, TVA Employee Concerns Special Program ML20235X0551987-10-10010 October 1987 Rev 0 to Sys Operating Instruction SOI-74.2, Removal of RHR for Repair of 2-FCV-74-2 ML20235X0651987-10-10010 October 1987 Rev 0 to Special Maint Instruction SMI-2-74-1, Repair of 2-FCV-74-2 ML20237H2051987-08-28028 August 1987 Rev 0 to Civil Engineering Branch Instruction CEB-CI 21.89, Mod Priorities for Pipe Supports on Rigorously Analyzed Category I Piping - Sequoyah Unit 2 ML20207G5821987-08-24024 August 1987 Rev 14, Balance of Plant Temp Monitoring Sys ML20237L3651987-08-21021 August 1987 Unit 2,Regeneration of Support Design Calculations on Rigorously Analyzed Piping,Program Plan ML20236Q1771987-08-0707 August 1987 Rev 9 to Surveillance Instruction SI-114.1, ASME Section XI Inservice Insp Program. Rev Corrects Deficiencies Shown in Caqr CH5870006 & CH5870010,adds Punchlist & Incorporates Icf 87-708 ML20236N7601987-08-0606 August 1987 Revised Radiological Emergency Plan Implementing Procedures, Including Rev 13 to IP-8, Personnel Accountability & Evaluation & Rev 6 to IP-15, Emergency Exposure Guidelines ML20236M7181987-07-28028 July 1987 Rev 1 to WP-17-SQN, Vendor Weld Quality, Welding Project, TVA Employee Concerns Special Program ML20236M7351987-07-24024 July 1987 Rev 5 to 80503-SQN, Document Distribution Control, Element Rept,Tva Employee Concerns Special Program 1999-06-22
[Table view] |
Text
- SEQUOYAH NUCLEAR PLANT DIESEL GENERATOR VOLTAGE RESPONSE IMPROVEMENT PLAN PREPARED BY: M. D. Bowman Dates _6/1 88 -
TVA / ' ' '
Electrical Engineer W. H. Nelson TVA Date:[#!/I!8h Electrical Engineer [ l' / /
Technical Specialist REVIEWED BY: J. D. Hutson TVA
! Date: 4 TF Assistant Chief Electrical Engineer M. R. Sedlacik TVA MM/ A Date /,- n- FF l
SON Lead Electrical Engineer C. Concordia # O, O M *2 [ Dates d/ dN .9 Private Consultant '
J. V. Posoisil NEI Peebles, Inc.
4 2A .s'I
// Dates d/f8 Manager of Engineering Y' r b.c e n en Y4bb b
- u. vn a a s:A. .
APPROVED BY: W.
TVA S. Rauchiev (D 2<._ , 2 - Dates blN(
f) j Chief Electrical Engineer
() G J. B. Hosmer TVA
,'.-~ I R# Dates _ d//7M,9
~
/
SON Project Engineer P
4 i
I I
SEQUOYAH NUCLEAR PLANT DIESEL OENERATOR VOLTAGE RESPONSE IMPROVEMENT PLAN I. PURPOSE The purpose of this report is to document the acceptability of the voltage response improvement plan for the Sequoyah Nuclear Plant (SQN) ;
emergency diesel generators (DG). This report fulfills TVA's commitment to evaluate various ways of improving the DG transient-voltage response.
II. BACKGROUND On February 29, 1988 TVA provided NRC with the SQN Diesel Generator Evaluation Report (DGER) in reference 2. This report documented that the SQN safety-related systems / components would perform their intended safety function when powered by the DGs with acceptable margin.
Charles Concordia, a recognized industry expert retained by TVA to review this report, mentioned several factors that could be considered to improve the transient-voltage performance of the DGs. TVA subsequently committed to review these recommendations to determine the optimum improvement.
t III. EVALUATION OF OPTIONS TVA has conducted an extensive evaluation of several DG improvement options. The options considered for evaluation included those previously mentioned by Mr. Concordia in reference 2 as well as other options that were recognized as having a high possibility of improving the DG voltage response after further review of the existing DG test data. The evaluation was performed by TVA engineers along with Mr.
Concordia and SQN's generator vendor, NEI Peebles - Electric Products, Inc. Each of the selected options was evaluated to determine the expected effect on exciter performance, system-voltage response, and DG reliability.
IV. OPTIMUM IMPROVEMENT The following options have been selected as the optimum improvement.
- 1. Optimize the load current compounding of the existing exciter by resetting the exciter-current transformer taps such that the current transformer contribution to field current is increased to achieve flat compounding.
- 2. Replace the existing pneumatic-load-sequence timers with more
- a. curate electronic timers as previously planned.
- 3. Install a voltage overshoot-reduction device on the existing exciter. This device will consist of silicon-controlled rectifiers (SCR) placed across each phase of the exciter's bridge rectifier which are triggered by an electronic circuit when it senses en overvoltage condition beyond a preset value.
. .- VJ EXPECTED RESULTS
.0ption 1 will improve the inherent voltage regulation of the excitation system, thereby reducing the amount of required voltage regulator action. This will result in less transient voltage dip and better overall performance of the excitation system, and it is expected to reduce transient-voltage overshoot.
Option 2 will increase the accuracy and repeatability of the DG load sequence. This sill enhance the diesel generator voltage response by increasing the starting time bandwidth for those loads whose starting time intsrval is less than that predicted. This enhancement will allow more time for voltage recovery in the load sequence time intervals.
Option 3 will instantly remove the exciter field-forcing voltage during excessive transient-voltage overshoot conditions. This will significantly reduce the amount of transient-voltage overshoot.
VI. CONCLUSION Options 1, 2, and 3 have been selected as the optimum improvement with respect to DG voltage response. A qualitative evaluation of these options has shown that they will improve the voltage response. However, further testing of the DG system is necessary in order to quantify the amount of improvement related to each option.
Initially, option 1 and 2 will be performed on one DG unit followed by the performance'of the appropriate postmodification test (PMT) to j ascertain the amount of voltage response improvement. An evaluation of the results from options 1 and 2 will be performed. If further improvement is desired, option 3 will also be performed on the same unit !
and the amount of additional improvement determined using another FMT. l Upon completion of this effort, implementation of the appropriate options will be performed on the remaining diesel generators by the end !
of the unit 1 cycle 4 outage. '
. . . _ _ . . _ - _ , _ -m -
_ - .r, ,,- yr
ENCLOSURE 2 l
COMMID1ENT LIST
- 1. TVA will perform the following modificaticas to enhance the DG transient-voltage response for one SQN DG:
- a. Reset the exciter-current transformer taps to achieve flat
~
compounding and,
- b. Replace the existing pneumatic-load-sequence timers with more i accurate electronic timers, i
- 2. Upon completion of item 1 above, TVA will perform a PMT on the affected DG and evaluate the results to determine if the improvement in the DG transient-voltage response is acceptable.
- 3. If the evaluation from item 2 above is found to be unacceptable. TVA will install a voltage-overshoot-reduction device on the existing DG exciter '
in which item 1 above was implemented.
- 4. TVA will perform another PMT on the DG sffected by item 3 above, evaluate the results, and determine if the transient-voltage response improvement is acceptable.
- 5. TVA will implement the modifications (i.e., either item 1 or 3 above) that provide an acceptable improvement in the transient-voltage response on the three remaining SQN DGs.
- 6. TVA will perform the associated PMTs upon completion of item 5 above on I the three remaining DGs, evaluate the results, and determine if the transient-voltage response for these DGs is acceptable.
- 7. TVA will provide NRC with the evaluation and test results of the PMTs which provide acceptable improvement in ' he four SQN DG transient-voltage responses.
I