|
|---|
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
{{#Wiki_filter:-_
4 TENNESSEE, VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT ABNORMA'L OPERATING INSTRUCTION-4 A01-25.3 LOSS OF 120V AC VITAL INSTRUMENT POWER BOARD 1-III Unit 1 Revision 5 PREPARED BY:
J. M. Anthony RESPONSIBLE SECTION: Operations REVISED BY:
Jeff Epperson SUBMITTED BY:.
,l d_
' Ris onsible Section Supervisor PORC REVIEW ATE Ok APPROVED BY:
Plant Manager
~
DATE APPROVED:
~JUN 0 81987.
Reason for revision (include all Instruction Change Form Nos.):
Revised to streamline operator actions, delete erroneous appendices "A"and "B".
The last page of this instruction is number:
4 l~
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0029H/ SAT /vid g81{0g 87 7
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SEQUOYAH NUCLEAR PLANT PLANT INSTRUCTION REVISION LOG f
ABNORMAL OPERATING INSTRUCTION ADI-25.3 REVISION lDate l Pages l REASON FOR REVISION (INCLUDE COMMIT-LEVEL lADDrovedl Affected! MENTS AND ALL ICF FORM NUMBERS) 1 I
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1 9/12/83l A11 l
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1 7/31/8411 l
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l 10/4/8412 1
1 5 J U N OIR 1987 l All l Revised to streamline operator actions, l
l Idelete erroneous appendices "A" and "B".
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0029H/ SAT /vid
p SQN AOI-25.3 Page 1
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Revision 5 I.
SYMPTOMS A.
Alarms 1.
120V AC VITAL PWR BD 1-III UV OR BREAKER TRIP 2.
120V AC VITAL INVERTER 1-III ABNORMAL
(
B.
Indications 1.
Power Range Channel N-43 failure.
2.
Auto and manual Rod Block and Rod Stop due to High Flux Rod Stop, and C-5 Interlock.
3.
Loss or decrease of Feedwater Flow to all steam generators, a
4.
Loss of feedflow Portion of Signal to feedwater control
[
system resulting in failure to control steam generator level if channel 3 is selected.
5.
Possible reactor trip and Turbine Trip.
6.
Possible reactor trip due to Steam Generator Low-Low Level.
7.
Malfunction of trip status lights and safeguards systems annunciators.
C.
System Partial failures 1.
Reduction of feedwater flow due to demand signal from steam generator 3 failing low, 2.
Loss of power to both trains of Solid State Protection l
System input relays for Channel III.
{
3.
If pressurizer level is selected to channel LT-68-320 for l
control, pressurizer low level auto actions will occur.
4.
If Pressurizer Pressure is selected to channel PT-68-323 the sprays will be closed and the back-up heaters energized I
until locked out by the low level signal if LT-68-320 was selected for level control.
0147H/ SAT /vid l
SQN AOI-25.3
,r Page 2
-{
Revision 5
.I.
SYMPTOMS (continued)
C.
System Partial failures (cont)
[
5.
Loss of Steam Generator Power Operated Relief valves l
PIC-1-13A and PIC-1-24A if in normal mode.
NOTE:
The above failures are of greatest immediate
~f:
consequence, for complete loads list of vital board 1-III see Appendix A.
II. AUTOMATIC ACTIONS A.
Possible reactor trip due to low-low S/G level.
III.
IMMEDIATE OPERATOR ACTIONS A.
None I
IV SUBSE00ENT OPERATOR ACTIONS A..
If reactor trip occurs then refer to emergency instructions.
B.
Dispatch operator to turbine drive AFW pump 1A-S to transfer turbine controller to auxiliary control (located on west wall of room, outside near local control cabinet).
C.
If reactor does not trip, then, at the NIS panel defeat the PR rod stop.
D.
Assume and maintain manual rod control.
NOTE:
Do not use bank select; use of bank select will cause the bank overlap program to be lost.
E.
Dispatch operator to restore power to failed coard (transfer to auxiliary power supply).
F.
Assume Manual control of steam generator water level on the affected steam generators.
G.
Transfer Power Operated Relief Valves PIC-1-13A and PIC-1-24A to Auxiliary control room.
H.
Verify pressurizer level and pressure are not selected to LT-68-320 and PT-68-323 respectively.
L 0147H/ SAT /vid' A
9
(_--_-_____
SQN A0I-25.3 Page 3
- f..
Revision 5 IV. udBSE00ENT OPERATOR ACTION (cont)
I.
If power is restored to the failed boards return systems to normal operating mode.
NOTE:
Due to' feedback signals and time delays in circuitry controllers may not control immediately.
h J.
Evaluate the need to shttdown per TS 3.8.2.1 if power cannot be restored to the affected board.
If necessary, conaence orderly shutdown to the hot standby condition per G01-5 and GOI-3.
'I.
Initiate REP per IP-1 (Engineered Safety Features) as required.
Refer to TS 3.8.2.2.
NOTE:
Operation may be continued at the discretion of the
~
Manager, operations group, with respect to Tech. Spec. section 3.
'l K.
Dispatch operator to Cardox units to verify master valves are closed.
V.
REFERENCES A.
TS 3.8.2.1, 3.8.2.2 B.
S01-55 series C.
45N706-3
^
l i
0147H/ SAT /vid I
)
)
SQN
~
A01-25.3 l
Page 4 i
Revision 5 j
[
APPENDIX A I.
Page 1 of 1 l
f Load' List:
120V AC VITAL INST. POWER BD.1-III SSPS(A)CilIIIinputrelays(1-R-46)
SSPS (B) CH III input relays (1-R-49)
NIS instr. power CH III
~
NIS control power CH III
-[
Process protection set III (1-R-9) l UHI accumulator CH III isol. valve FCV-87-23 RCP 3 UV and UF relays AFWP turbine flow controller (normal) FIC-46-57 TOAFWP S/Gs 3 and 4 LIC-3-172, 175 TDAFWP S/Gs 3 and 4 instr. loop Incore temp. monitoring system I
Instr. bus 3 and transformer power FIC-3-48,70 Aux. control panel A instr. bus Process control group 3 (1-R-20) g.
B0P process instr. control rack (1-R-126) l Control room doors security lock AB instr. A bus 2 B0P process instr. control rack (1-R-128)
.f AB instr. A bus 1 Aux. relay rack, A bus (1-R-76)
Aux.. relay rack, C bus (1-R-76) l NSSS aux. relay rack, A bus (1-R-58)
~
L Aux, control panel, A bus Aux. relay rack, A bus (1-R-75)
SSPS control room demod.
Aux control panel, C relay bus
~
Aux, control panel, A instr. bus
~ Control air header A moisture alarm Aux. relay rack.A bus (1-R-72)
Post accident monitoring 1 LOCA Hp cntmt. flow monitor XI-43-200 Control bldg. CO2 fire protection C02 fire protection DG 1A, 2A, and lube oil room Loose parts monitor equipment panel (0-R-139)
Reactor vessel level instrumentation system fluid dynamic flow sensors
.Inplant VHF radio repeater F2 UHI instr. bus 3 j
0147H/ SAT /vid
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