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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 ML20211K1201999-08-30030 August 1999 Proposed Tech Specs,Adding New Specification That Addresses Use of Interim Provisions Upon Discovery of Unintended TS Action 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 ML20207F7631999-03-0202 March 1999 Proposed Tech Specs Pages Re Application for Amends to Licenses DPR-77 & DPR-79,deleting Iseg from License Conditions 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 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 ML20206S0131999-01-15015 January 1999 Proposed Tech Specs 3.3.3.3, Seismic Instrumentation & Associated Bases,Relocated to Plant Technical Requirements Manual 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 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 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 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 ML20202J7141998-02-13013 February 1998 Proposed Tech Specs Adding New LCO That Addresses Requirements for Main Feedwater Isolation,Regulating & Bypass Valves ML20202J7651998-02-13013 February 1998 Technical Requirements Manual 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 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 ML20094Q2111995-10-30030 October 1995 Rev 1 to ASME ISI Pump 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 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 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 ML20034F3191993-02-26026 February 1993 Rev 26 to Offsite Dose Calculation/Environ Monitoring Methodologies 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 ML20101F2011992-02-0808 February 1992 Rev 17 to Surveillance Instruction SI-114.1, ASME Section XI ISI Program Unit 1 ML20101F2081992-02-0808 February 1992 Rev 16 to Surveillance Instruction SI-114.2, ASME Section XI ISI Program Unit 2 ML20034C7451990-03-14014 March 1990 Rev 24 to ODCM ML20033F2631990-02-27027 February 1990 Rev 24 to Odcm 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 ML20148L9741987-11-0404 November 1987 Instruction Change 2172,Rev 8 to Essential Instrumentation Operability Verification 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 ML20235X0651987-10-10010 October 1987 Rev 0 to Special Maint Instruction SMI-2-74-1, Repair of 2-FCV-74-2 ML20235X0551987-10-10010 October 1987 Rev 0 to Sys Operating Instruction SOI-74.2, Removal of RHR for Repair of 2-FCV-74-2 ML20245D0661987-09-15015 September 1987 Rev 4 to Surveillance Instruction SI-673, RCS Level Verification Using Sight Glass or Tygon Hose ML20148M0661987-09-11011 September 1987 Rev 8 to SI-604, Essential Instrumentation Operability Verification ML20245D0591987-08-29029 August 1987 Rev 40 to Sys Operating Instruction SOI-74.1, RHR Sys 1999-06-22
[Table view] |
Text
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- LESSEE VALLEY AUTHORITY 1
SEQUOYAH NUCLEAR PLANT ABNORMAL OPERATING INSTRUCTION AOI-21.8 LOSS OF 125V DC VITAL BATTERY BOARD IV Unit'2 l
Revision 7
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PREPARED BY:
C. O. Brewer l
RESPONSIBLE SECTION:
Operations REVISED BY:
Jeff Epperson SUBMITTED BY-
.O, /
11 l._
pponsfbfeSectionSupervisor APR 2 71987 PORC REVIE DATE:
}
APPROVED BY:
Plant Manager APR 2 71987 DATE' APPROVED:
Reason for revision (include all Instruction Change Form Nos.):
Correct annunciations' delete PD charging pump reference.
The last page of this instruction is number:
8
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l 870817020587[PDRh27 PDR ADOCK
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'SEQUOYAH NUCLEAR PLANT PLANT INSTRUCTI'ON REVISION LOG
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1, ABNORMAL OPERATING INSTRUCTION AOI-21.8
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REVISION Date Pages REASON FOR REVISION (INCLUDE COMMIT-LEVEL Approved Affected MENTS AND ALL ICF FORM NUMBERS)
I 11/03/79 All 2
06/24/80 6
3' 12/19/80 2
^
4-07/21/83 All
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5 08/13/84 2,3,6 g
Revised to add Vital Battery V to plant
'l vital power sources and make correction 6
09/04/86 All to automatic action section.
Correct annunciators; delete PD charging 7 APR 2 7 1997 All pump reference.
4
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L SQN A01-21.8 Page 1 I.
SYMPTOMS A.
Possible Alarms 1.
125V DC VITAL CHARGER IV FAILURE OR VITAL BATTERY IV DISCHARGE.
2.
125V DC VITAL BATTERY BOARD IV ABNORMAL.
3.
6900V SHUTDOWN BOARD 1B-B FAILURE OR~ BUS / NORMAL FEEDER -
UNDERVOLTAGE OR OVERVOLTAGE (1-M-1).
4.
6900V SHUTDOWri BOARD 18-B FAILURE OR BUS / NORMAL FEEDER
'UNDERVOLTAGE (0-M-26).
I S.
480V SHUTDOWN BOARD 1B1-B FAILURE OR UNDERVOLTAGE (1-M-1 and 0-M-26).
6.
480V SHUTDOWN BOARD 182-8 FAILURE OR UNDERVOLTAGE (1-M-1 and 0-M-26).
7.
6900V SHUTDOWN BOARD 28-B FAILURE OR BUS / NORMAL FEEDER UNDERV0LTAGE OR OVERVOLTAGE (2-M-1).
8.
6900V SHUTDOWN BOARD 28-8 FAILURE OR BUS / NORMAL FEEDER UNDERVOLTAGE (0-M-26).
9.
480V SHUTDOWN BOARD 2B1-B FAILURE OR UNDERVOLTAGE (2-M-1 and 0-M-26).
- 10. 480V SHUTDOWN BOARD 282-B FAILURE OR UNDERVOLTAGE (2-M-1 and 0-M-26).
- 11. SERVICE-AIR COMPRESSOR SEQUENCER UNDERVOLTAGE OR CO ALARM (1-M-15).
B.
Indications 1.
Voltmeter on 1-M-1 and 2-M-1 indicates failure on 125V dc board IV.
2.
Ammeter on 1-M-1 and 2-M-1 for board IV battery shows zero.
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3.
Breaker position indicating lights for equipment feeding from
.]
6.9kV shutdown board 2B-B and 480V shutdown boards 2B1-B and 2B2-B will all be out.
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SQN A0I-21.8 Page 2 Revision 7 II. AUTOMATIC ACTIONS l
A.
Reactor-trip - turbine trip due to all four main feedwater regulating valves, all four MSIV's,'and number 1 and 3 S/G main feedwater regulating bypass valves falling closed resulting in loss of feedwater and-low steam generator water level in L
coincidence with steam flow / feed flow (SF/FF) mismatch and/or low-low steam generator water level.
l-B.
Motor-driven' auxiliary feedwater pump 2A-A and turbine driven, auxiliary feedwater pump 2A-S start on low-low steam generator water level (MDAFWP_28-B will not start).
C.
Steam dump valves and steam generator blowdown valves fail closed.
~
l' Letdown line isolation valve FCV-62-77 fails closed resulting in O.
loss of letdown from RCS to CVCS.
E.
All four diesel generators start but do not: tie onto the shutdown boards.
F.
All control and service air compressors will unload, resulting in decreasing control air pressure if sequencer power is from vital battery board IV (normally comes from vital battery board II).
5 III.
IMMEDIATE OPERATOR ACTION A.
Refer to emergency instructions IV.
SUBSEQUENT OPERATOR ACTION A.
Dispatch personnel to diagnose problem and attempt to restore power to 125V de vital battery board from:
1.
125V dc Battery IV or.
?
2.
125V de Battery Charger IV or 3.
125V dc Battery Charger 2-S or 4.
Spare Vital Battery IV with Battery V per SOI-250.5 B.
Initiate a REP per IP-1 (Engineered Safety Features) as required.
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Page 3 F
' Revision 7 IV. SUBSEQUENT 0PERATOR ACTION (continued)
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l C.
Check transfer switch on. air compressor control panel in NORMAL.
D.
Maintain the reactor in hot standby.
I 1.
Motor-driven auxiliary feedwater pump 2A-A will supply feedwater to steam generators 1 & 2 and turbine driven pump 2A-S will supply all four steam generators.
Steam generator
- level should control automatically at : 33 percent.
NOTE: Motor-driven auxiliary feedwater pump
{
'28-8 will not start.
2.
All four steam generator atmospheric relief l!
valves may be used for RCS heat removal
{
(modulating control only on steam generators 2 and 4).
Steam generator relief valves can be adjusted to control RCS temperature at a 547'F.
')
NOTE:
Steam dump valves, main steam isolation valves, and all main feedwater regulating valves to all four steam generators failed closed.
c 3.
Place steam dump mode selector switch in pressure mode.
4.
. Isolate charging flow by closing FCV-62-90 or FCV-62-91. Verify or adjust reactor coolant pump seal water flow. 2A-A centrifugal charging pump may be started to establish seal injection flow.
5.
Reactor coolant pumps can be stopped to reduce the heat removal requirements; however, reactor coolant pump No. 2 should be left on to supply
~
pressurizer spray.
E.
Verify pressurizer pressure normal and level increasing slowly.
NOTE:
Excess letdown is not available since FCVs 62-54 and 55 fall closed.
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Page 4.
Revision 7 IV. SUBSEQUENT OPERATOR ACTION (continued)
NOTE: HIGH PRESSURE CONTROL - both pressurizer spray valves are operable and pressure relief valve PCV-68-340A is operable; however, pressurizer relief tank spray and RCDT pump
{
discharge is isojated.
(PRT drains to RCDT).
NOTE:
LOW PRESSURE CONTROL - pressurizer heaters control group 2D and backup group 2A-A are operable.
F.
Have local inspection performed on 125V de vital battery boar'd IV to determine.cause of the failure.
Try to restore voltage.
f Initiate maintenance if necessary',
G.
Transfer the following 125V de buses to alternate feed.
CAUTION: When transferring the 125V de bus to alternate or back to normal, have someone hold the B.O. reset button
. pushed in located in panel 4, of 6.9kV logic panel i
28-B.
This will prevent the 8.0. relays from going to.a B.O. condition, which would sequence the CCP, AFWP, ERCW, PZR heaters, and fire pumps if auto signal is present.
NOTE: After dc is restored to this bus, auxiliary feedwater pump 2B-B can be used to supply water to 3 and 4 steam generators.
Xfer to Alt Return to Normal 1.
normal bus.
6.9kV shutdown board 2B-B h,-
2.
480V shutdown board 281-B normal bus.
3.
480V shutdown board 2B2-B normal bus.
s H.
Trip auxiliary building general supply and exhaust
(
fans 2A and 2B and fuel-handling area exhaust fans A and B.
Place auxiliary building gas treatment system train A in service.
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SQN A0I-21.8 Page 5 Revision 7 IV. SUBSEQUENT OPERATOR ACTION (continued) 4 I.
Trip containment annulus vacuum fans and place EGTS train A in service for Unit 2.
1.
Open EGTS train A suction valve FCV-65-10.
2.
Open EGTS train A discharge valve FCV-65-26.
3.
Open EGTS train A PCO isolation valves FCV-65-81 and PCV-65-86 (HS-65-81 on M-278).
~ ~
4.
Start EGTS fan A-A JHS-65-23A on M-278).
J.
Stop containment instrument room cooler that is operating.
K.
If containment purge was in progress,.stop containment purge air supply and exhaust fans.
L.
Depending upon the amount of time required for restoring 125V dc bus voltage, the diesel generators can be left running or diesel generators lA-A, 2A-A, and 18-B can be stopped by the following procedure:
CAUTION: Coordinate this work with Unit 1 operator.
1.
Place 43T(L) switch (located on diesel generator logic panel 2B-B) in TEST position and leave'It in TEST.
2.
Place all 43T(L) switches (located on diesel generator logic panels 1A-A, 2A-A, and IB-B) in the TEST position simultaneously and then return them to NORMAL.
.L 3.
Reset the emergency start lockout relays for diesel generators 1A-A, 2A-A, and 18-B (located on each respective diesel generator relay panel in diesel generator building).
4 4.
Stop diesel generators 1A-A, 2A-A, and 18-B from 0-M-26 panel j
by placing HS-82-14, HS-82-74, and HS-82-44 in STOP position.
l l
5.
Diesel generator 2B-B should be left running.
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-IV.. SUBSEQUENT OPERATOR ACTION (continued)
.s M.
Pressurizer. level will slowly increase due to reactor coolant pump; seal water supplied to the RCS; it may take as little as two hours (assuming 40 gpm total seal water flow) to fill the pressurizer.
b If pressurizer level regches 92'/. trip the reactor coolant pumps-and'stop the charging pump.
N.
Verify boron injection temperature > 145'F by TI-63-37 on panel r[.
M-6.
NOTE:
Boric acid recirculation valves through BIT have failed closed.
?.
O.
Depending-upon the cause of the failure, or after repairs, voltage can be restored to the bus by placing the normal charger or 2-S spare charger in service or by connect.ing the battery to the. bus by closing breaker 107.
s CAUTION:
If restoring voltage after a fault on the bus, use a battery charger for energizing the bus if possible.
NOTE:
If board cannot be restored within two hours or less, refer to Technical Specification 3.8.2.3.
/
P.
After normal voltage is restored to the bus:
l.
Transfer the de buses back to normal that were charged in step IV.G of this procedure. Observe the same precautions (check off when normal).
2.
Place 43T(L) switch (located on D.G. logic panel 28-B) to f
NORMAL position.
L 3.
Reset the emergency lockout relay for D.G. 2B-8, then stop
{
.D.G. 2B-B.
i 4.
Return the following systems to normal lineup and operation by their respective 50I.
i a.
CVCS System - S01-62.1.
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b.
Reactor Coolant System - S01-68.1, 68.2, 68.3.
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A01-21.8 Page 7 Revision 7 IV. SUBSEQUENT OPERATOR ACTION (continued)
L' P.
4..
'(continued)
Auxiliary Feedwater System - S0I-3.2.
c.
f d.
Main Steam System - S01-1.1.
j.
e.
Steam Dump System - 501-1.2.
V f.
Diesel Generators - SOI-82.1, 2, 3, 4.
g.
Boron Concentration Control - SOI-62.2.
h.
Emergency Core Cooling System - 50I-63.1.
i.
Containment Vent and Cooling Systems - S0I-30.2,.30.3, and 30.4.
f j..
Emergency Gas Treatment System - S0I-65.1.
k.
Auxiliary Building Heating and Ventilating System and l l1 Auxiliary Building Gas Treatment System - 501-30.5 and
(.
30.6.
l 1.
Control Building and Control Room Heating, Ventilation, and Air Conditioning System - S01-30.1.
m.
ERCW System - SOI-67.1.
n.
Component Cooling Water System - 50I-70.1.
Haste Disposal System - SOI-77.1, 77.2, and 77.4.
o.
h.
p.
Steam Generator Blowdown System - S0I-3.3.
q.
Reactor Protection System - S0I-99.1.
L Q.
In the event of a change in the rated thermal power level exceeding 15% in one hour, notify the Chem Lab to initiate the conditional portions of SI-407.2 and SI-415 due to the thermal power change.
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SQN A01-21.8 s
Page 8 Revision 7 V.
REFERENCES A.
Technical Specification 3.8.2.3 B.
FSAR 0.3.2 C.
Electrical Prints:
45N703-4 45N703-8 45N724-2 45N749-3 45N749-4 45N765-3,4 45N767-5, 45N779-5, 45N600 thru 45N699 D.
Logic Diagrams E.
Control Diagrams VI.
DISCUSSION l-This instruction covers the loss of 125V dc vital battery board IV
[
voltage.
This instruction is for Unit 2 operation only and assumes that Unit 2 is at power operation at the time of the event.
The other three vital battery boards remain in normal operation throughout the e
duration of this event.
The unit can be placed in and maintained in a safe shutdown condition.
Each 125V de circuit is protected by a fuse or breakers to clear a fault.
The 125V dc board is also divided into branch bases which are supplied with fuses or breakers to provide L.
redundant protection for a fault and prevent a loss of the board due to a fault in one circuit.
In any situation involving loss of a part of, or a whole 125V dc bus, actions should be taken to determine the j
cause and extent of the loss and restore as much of the bus to normal as soon as possible.
In general, 125V dc vital battery board IV supplies control power for i
Unit 2 train B equipment and solenoid valves.
125-V bus IV can be energized by 125V de battery IV, from 125V de vital battery charger IV, from 125V dc vital battery charger 2-S, or from 5th vital battery.
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