Letter Sequence Other |
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Results
Other: ML20141N147, ML20141N150, ML20141N153, ML20141N156, ML20141N160, ML20141N163, ML20141N168, ML20141N172, ML20141N176, ML20141N179, ML20141N180
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MONTHYEARML20141N1721980-01-31031 January 1980 Rev 0 to Procedure RES-OPS-006.00, Operator Training: Draeger Gas Analyzer Use,Function & Applicable Procedure Review. Marked-up AB 1203.14.3 & Ch 4025.01.0 Encl Project stage: Other ML20141N1801985-12-31031 December 1985 Rev 0 to Procedure GOP-OLC-001.00, Operator Licensed Candidate Abnormal Operating Procedures,Loss of Nni Power AB 1203.41 Project stage: Other ML20141N1791985-12-31031 December 1985 Rev 0 to Procedure GOP-OLC-001.00, Operator License Candidate:Abnormal Operating Procedures,Loss of Ac Bus Power Sources AB 1203.28 Project stage: Other ML20141N1631985-12-31031 December 1985 Rev 1 to Procedure GOP-OLC-001.01, Operator Licensed Candidate:Procedures Normal,Abnormal & Emergency,Loss of Instrument Air Project stage: Other ML20141N1601985-12-31031 December 1985 Rev 0 to Procedure RES-OPS-007.00, Operator Training: Infrequent Operations Project stage: Other ML20141N1471985-12-31031 December 1985 Rev 0 to Procedure RES-OP-002,0 Operator Training:Rapid Feedwater Reduction Project stage: Other ML20141N1761986-01-31031 January 1986 Rev 0 to Procedure GOP-OLC-001.00, Operator License Candidate:Abnormal Operating Procedures,Serious Control Room Fire AB-1203.26 Project stage: Other ML20141N1681986-01-31031 January 1986 Rev 0 to Procedure RES-OPS-008.00, Operator Training: Starting of Primary H2O Storage Tank Transfer Pumps Project stage: Other ML20141N1561986-02-26026 February 1986 Procedure Fcr 85-200, Main Feedwater Pumps Rapid Feedwater Reduction Speed Setpoint Project stage: Other ML20141N1531986-02-26026 February 1986 Procedure Fcr 85-201, Steam Generator Level Setpoint Project stage: Other ML20141N1501986-02-26026 February 1986 Procedure Fcr 85-227, Main Feedwater Block Valve Interlock Project stage: Other ML20141N1441986-02-26026 February 1986 Forwards Training Matls in Response to 851030 Request for Addl Info Re Course of Action & Draft SER (NUREG-1177).Matl Meets Commitment Made in Rev 4 of Course of Action Project stage: Draft Request ML20212G6021986-08-0404 August 1986 Safety Evaluation Accepting Util Response to NRC Request for Addl Info Re Question 29 Concerning Training for Infrequent, Critical & Difficult Tasks Project stage: Approval ML20212G5341986-08-0404 August 1986 Forwards SER W/Recommendations Re Util 851116 Response & 860226 Submittal in Response to NRC 851029 Request for Addl Info on Question 29 Concerning Training for Infrequent, Critical & Difficult Tasks Project stage: Approval 1986-01-31
[Table View] |
Rev 0 to Procedure GOP-OLC-001.00, Operator License Candidate:Abnormal Operating Procedures,Loss of Ac Bus Power Sources AB 1203.28ML20141N179 |
Person / Time |
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Site: |
Davis Besse ![Cleveland Electric icon.png](/w/images/7/78/Cleveland_Electric_icon.png) |
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Issue date: |
12/31/1985 |
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From: |
Gavioli M TOLEDO EDISON CO. |
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To: |
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Shared Package |
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ML20141N145 |
List: |
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References |
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GOP-OLC-001.00, GOP-OLC-1.00, TAC-61015, NUDOCS 8603040450 |
Download: ML20141N179 (13) |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20216E6111999-09-0707 September 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210H0731999-07-28028 July 1999 Proposed Tech Specs 3/4.7.5.1, Ultimate Heat Sink, Allowing Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G4311999-07-27027 July 1999 Proposed Tech Specs,Changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20210G4801999-07-26026 July 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210G9161999-07-26026 July 1999 Proposed Tech Specs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrumentation - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5391999-07-26026 July 1999 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B for Type B & C Containment Leakage Rate Testing ML20195F9351999-06-10010 June 1999 Proposed Tech Specs,Revising TS 3/4.6.4.4, Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.6.5.1, Crevs ML20207E7941999-05-21021 May 1999 Proposed Tech Specs Allowing Use of Expanded Spent Fuel Storage Capability ML20205E5031999-03-19019 March 1999 Proposed Tech Specs Withdrawing Proposed New Action B, Previously Submitted in 981027 Application ML20204F1821999-03-0909 March 1999 Proposed Tech Specs,Adopting Changes in Frequency & Scope of Volumetric & Surface Exams Justified by W TR WCAP-14535A ML20155E4971998-10-28028 October 1998 Proposed Tech Specs 4.0.2 Re Applicability of 25% Surveillance Interval Extension Allowance ML20197G5521998-10-28028 October 1998 Rev 8 to Dbnps,Unit 1 Technical Requirements Manual ML20155E3231998-10-28028 October 1998 Proposed Tech Specs Revising Various Sections of 6.0, Administrative Controls, Including Relocation of 6.11 Contents to Plant Ufsar,Per NUREG-1430,Rev 1 ML20155D7791998-10-27027 October 1998 Proposed Tech Specs Relocating TS SR 4.6.5.1.d.4 Re Evs Negative Pressure Testing to TS 3/4.6.5.2,deleting TS Definition 1.24 & Making Related Changes Associated with Deletion of Subject Definition ML20155D8521998-10-27027 October 1998 Proposed Tech Specs Revising SRs 4.8.2.3.2.d,4.8.2.3.2.e, 4.8.2.3.2.f & Table 4.8-1 Re Testing of 125 Volt DC Station Batteries & Applicable TS Bases ML20155E0721998-10-27027 October 1998 Proposed Tech Specs Revising 3/4.3.1.1 Re RPS Instrumentation & 3/4.3.2.3 Re ARTS Instrumentation,To Provide Potential Reduction in Spurious Trip Rate for Potential Cost Savings in Excess of $50,000 ML20151W3071998-09-0808 September 1998 Proposed Tech Specs Permitting Use of Framatome Cogema Fuels M5 Advanced Alloy for Fuel Rod Cladding & Fuel Assembly Spacer Grids ML20151W2991998-09-0808 September 1998 Proposed Tech Specs Revising Section 3/4.7.6, Plant Systems - CREVS & Associated Bases ML20206D2721998-08-28028 August 1998 Rev 11,change 1 to Odcm ML20217P8351998-04-24024 April 1998 Proposed Tech Specs Clarifying Discussion of Margin Between RPS High Pressure Trip Setpoint & Lift Setting for Pressurizer Code Safety Valves ML20217P8811998-04-24024 April 1998 Proposed Tech Specs 3/4.3.1.1,3/4.3.2.1,3/4.3.2.2 & Associated Bases Relocating Tables of Response Time Limits to Plant USAR Technical Requirements Manual ML20217C4881998-03-20020 March 1998 Proposed Tech Specs SR 4.4.5.3.c.1,providing Greater Specificity as to Location of Addl Insps in Unaffected SG ML20217N4471998-02-27027 February 1998 Proposed Tech Specs Pages Provided to Modify Proposed New Action 3.7.6.1.b to Make More Consistent w/NUREG-1431 ML20203L1111998-02-26026 February 1998 Proposed Tech Specs Pages Re Amend to License NPF-3 Involving Incorporation of New Repair Roll Process for SG Tubes W/Defects in Upper Tube Sheet ML20197J2621997-12-23023 December 1997 Proposed Tech Specs Pages Re Changes to TS Definition 1.2, TS 3/4/9.5 & New TS 3.0.6 & Associated Bases.Ts Index Rev to Reflect Change to TS 3/4.9.5,included ML20197J5971997-12-23023 December 1997 Proposed Tech Specs Pages,Revising TS Surveillance Requirements for ISI Requirements of Internal Auxiliary Feedwater Header,Header to Shroud Attachment Welds & External Header Thermal Sleeves ML20217M5601997-09-0505 September 1997 Rev 11.0 to Davis-Besse Odcm ML20217R2821997-08-26026 August 1997 Proposed Tech Specs,Clarifying LCO 3.6.1.3.a & Revising Surveillance Requirement 4.6.1.3.c ML20217R2871997-08-26026 August 1997 Proposed Tech Specs,Modifying TS 3.2.5 Action Statement to Require Power Reduction to Less than 5% of Rated Thermal Power within Four Hrs If RCS Flow Rate Is Less than Specified Limit for Greater than Two Hrs ML20217G5981997-07-29029 July 1997 Proposed Tech Specs 3/4.4.3 Re Safety Valves & Pilot Operated Relief valve-operating ML20141F1101997-06-24024 June 1997 Proposed Tech Specs,Deleting Requirements for Safety Features Actuation Sys Containment High Radiation Monitors ML20138C3261997-04-18018 April 1997 Proposed Tech Specs 3/4.7.6 Revising Limiting Condition for Operation to Include New Required Actions in Event That One or Both Channels of Radiation Monitoring Instrumentation Becomes Inoperable ML20138A6891997-04-18018 April 1997 Proposed Tech Specs 3/4.5.3.2.1 & 3/4.5.2 Modifying Presently Specified 18-month Surveillance Frequencies to New Specified Frequencies of Once Each 24-months ML20140D9481997-04-0909 April 1997 ODCM, Rev 10 ML20138M1281997-02-14014 February 1997 Proposed Tech Specs 3.5.2 Re Emergency Core Cooling Systems & 4.5.2.f Re Surveillance Requirements ML20134L0561997-02-13013 February 1997 Proposed Tech Specs Re Changes Made Concerning Decay Heat Removal Sys Valve ML20134F1811997-01-30030 January 1997 Proposed Tech Specs Re Possession & Use of SNM as Reactor Fuel ML20134D7621997-01-30030 January 1997 Proposed Tech Specs Revising SR Intervals from 18 to 24 Months Based on Results of DBNPS Instrument Drift Study & TS 2.2, Limiting Safety Sys Settings, Based on Results of Revised Framatome RPS Instrument String Error ML20134B0591997-01-20020 January 1997 Proposed Tech Specs 3/4.5.3 Re ECCS Subsystems ML20132B7031996-12-11011 December 1996 Proposed Tech Specs Revising TS Definitions,Instrumentation TS & ECCS TS for Conversion to 24 Month Fuel Cycle for License NPF-3 ML20134F1891996-10-28028 October 1996 Proposed Tech Specs 3/4.8 Re Electrical Power Systems ML20117P5311996-09-17017 September 1996 Proposed Tech Specs,Supporting Conversion of DBNPS from 18 Month to 24 Month Fuel Cycle ML20117N8531996-09-12012 September 1996 Proposed Tech Specs Re Reactivity Control Systems & Emergency Core Cooling Systems ML20117M2201996-09-0404 September 1996 Proposed Tech Specs 6.2.3,removing Specific Overtime Limits & Working Hours ML20116K2631996-08-0707 August 1996 Proposed Tech Specs Re Definitions,Applicability Bases, Containment Spray Sys & Containment Isolation Valve for Conversion to 24 Month Fuel Cycle ML20117K1911996-05-28028 May 1996 Proposed Tech Specs 3/4.3.1.1 - RPS Instrumentation & TS 3/4.3.2.3 - Anticipatory RTS Instrumentation Increasing Trip Device Test Interval ML20101M1921996-03-29029 March 1996 Proposed Tech Specs 3/4.6.4.4 - HPS,3/4.6.5.1 - Shield Building Evs & 3.4.7.6.1 - CREVS Re Changing Surveillance Requirements for Charcoal Filter Lab Testing to Revise Methodology Used to Determine Operability in ESF AHUs ML20101C6961996-03-0606 March 1996 Proposed Tech Specs,Allowing Deferment of SR 4.5.2.b for ECCS Flowpath Containing HPI Pump 1-2 Until 10th Refueling Outage,Scheduled to Begin 960408 ML20100E0101996-02-0505 February 1996 Proposed TS 3/4.3.2.1,Table 3.3-3,safety Features Actuation Sys Instrumentation,Reflecting Design & Actuation Logic of Plant Sequencers & Essential Bus Undervoltage Relays ML20107C3101995-12-21021 December 1995 Rev 9 to Odcm 1999-09-07
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20197G5521998-10-28028 October 1998 Rev 8 to Dbnps,Unit 1 Technical Requirements Manual ML20206D2721998-08-28028 August 1998 Rev 11,change 1 to Odcm ML20217M5601997-09-0505 September 1997 Rev 11.0 to Davis-Besse Odcm ML20140D9481997-04-0909 April 1997 ODCM, Rev 10 ML20107C3101995-12-21021 December 1995 Rev 9 to Odcm ML20107C3021995-10-16016 October 1995 Rev 8 to Odcm ML20199L1821995-09-0909 September 1995 Rev 3 to DB-OP-00000, Conduct of Operations ML20082V4071995-02-0303 February 1995 Offsite Dose Calculation Manual Rev 7 ML20072S8611994-06-22022 June 1994 Rev 6 to Davis-Besse Offsite Dose Calculation Manual ML20056F3071993-08-0808 August 1993 Rev 3 to Emergency Plan Off Normal (Epon) Occurrence Procedure HS-EP-02820, Earthquake. W/Rev 23 to Epon Occurrence Procedures Manual Table of Contents ML20072S8401992-12-18018 December 1992 Rev 5 to Davis-Besse Process Control Program ML20072S8501992-12-18018 December 1992 Rev 5.2 to Davis-Besse Offsite Dose Calculation Manual, Reflecting Rev 5,Change 2 to ODCM ML20101R1721992-06-11011 June 1992 Rev 1 to Vol I of Inservice Insp Plan,Second 10-Yr Nuclear Interval Pump & Valve Inservice Testing Program ML20114C6321992-05-19019 May 1992 Change 1 to Rev 5 to ODCM ML20114C6301992-03-0606 March 1992 Rev 5 to ODCM ML20217C3661991-07-0808 July 1991 Rev 3 to Administrative Procedure NG-IS-00002, General Nuclear Security Requirements. Pages 7,9,10 & 15 Only ML20084U5911991-02-22022 February 1991 Rev 4 to ODCM ML20217C3481990-12-18018 December 1990 Rev 1 to Security Dept Procedure IS-DP-04007, Performance Test for Alco-Sensor ML20059D4181990-08-28028 August 1990 Second 10-Yr Interval Pump & Valve Inservice Testing Program ML20217C3001990-08-23023 August 1990 Rev 5 to Security Dept Procedure IS-AC-00011, Protected & Vital Area Badge Issuance & Control ML20217C3571990-08-0909 August 1990 Rev 3 to Security Implementing Procedure IS-AC-00516, Unescorted Access Requirements ML20217C3071990-07-27027 July 1990 Rev 2 to Security Dept Procedure IS-AC-00015, Fingerprint Processing & Controls ML20217C3201990-06-27027 June 1990 Rev 1 to Security Dept Procedure IS-AC-00018, Drug & Alcohol Testing Process ML20217C3811990-06-22022 June 1990 Rev 4 to Nuclear Group Procedure NG-IS-00004, Fitness for Duty Program ML20217C4001990-04-0202 April 1990 Corporate Ref Manual - Nuclear NU-102, Fitness for Duty ML20217C3401990-01-12012 January 1990 Rev 1 to Security Dept Procedure IS-DP-00101, Bac Simulation ML20217C3281989-11-0909 November 1989 Rev 1 to Security Dept Procedure IS-DP-00100, Bac Exams ML20217C3141989-10-25025 October 1989 Rev 2 to Security Dept Procedure IS-AC-00017, Denied Access List Control ML20217C3941989-08-0101 August 1989 Corporate Ref Manual - Human Resource HR-604, Drug & Alcohol Policy ML20244A8421989-05-31031 May 1989 Pressurizer Surge Line Thermal Stratification Phase I Program ML20213A0311987-03-31031 March 1987 Rev 2 to Vol IV of Procedure Writers Manual:Operation Procedures Guidelines ML20213A0361987-03-31031 March 1987 Rev 1 to Davis Besse Emergency Procedure Verification & Validation Program ML20212D1621987-01-27027 January 1987 Rev 1 to Maint Procedure MP 1411.06, Preventive Maint for Type Smb & Smc Valve Operators ML20198D2551986-12-27027 December 1986 Rev 2 to Maint Procedure MP 1411.04, Maint & Repair of Limitorque Valve Operators Type SMB-000 & SMB-00. Temporary Mod Request T-9969,indicating Rewiring of Fcr 85-302 MU-11 to Torque Out in Open Direction,Encl ML20212B5721986-12-15015 December 1986 Rev 0 to Security Training & Qualification Plan, Superseding Rev 24 to App B of ISP AD1808.00.W/o Revised Pages ML20212C9481986-11-21021 November 1986 Rev 8 to Maint Procedure Mpo 1410.32, Testing of Motor- Operated Valves Using Movats ML20212D3131986-10-28028 October 1986 Change 3 to Temporary Mods T10161 & T10144 to Rev 0 to Maint Procedure MP 1411.07, Maint & Repair of Limitorque Valve Opr Smc 04, Incorporating Fcr 86-0092,Rev a Re Removal & Installation of Limiter Plate ML20212D1091986-10-21021 October 1986 Change 1 to Rev 2 to Maint Procedure MP 1411.04, Maint & Repair of Limitorque Valve Operators Type SMB-000 & Smb 00, Addressing Need for Procedure to Address Replacement of Defectrive Parts ML20212D1471986-10-0303 October 1986 Rev 1 to Maint Procedure MP 1411.05, Maint & Repair of Limitorque Valve Operators Types SMB-0 Through SMB-4 ML20212C9181986-09-22022 September 1986 Rev 1 to Procedure NEP-092, Establishing D/P Limits & Tests for Q Motor Operated Valves ML20203M0201986-08-21021 August 1986 Specs for Mist Continuous - Venting Tests ML20210V1131986-08-20020 August 1986 Rev 0 to Emergency Plan Implementing Procedure EP-2320, Emergency Technical Assessment ML20206P6511986-06-30030 June 1986 GE Owners Group Action Plan as Result of Davis-Besse Event, June 1986 ML20198D2361986-05-0202 May 1986 Rev 5 to Maint Procedure MP 1410.32, Testing of Motor- Operated Valves Using Movats ML20141J5231986-04-18018 April 1986 Human Engineering Discrepancy Review & Closeout Process for Davis-Besse Dcrdr Program ML20205M6981986-04-0707 April 1986 Rev 0 to Nuclear Engineering Procedure NEP-092, Establish Differential Pressure Limits & Tests for Motor-Operated Valves ML20205M7031986-03-25025 March 1986 Rev 0 to Nuclear Engineering Procedure NEP-091, Motor- Operated Valve (MOV) Data Evaluation ML20141N1501986-02-26026 February 1986 Procedure Fcr 85-227, Main Feedwater Block Valve Interlock ML20141N1561986-02-26026 February 1986 Procedure Fcr 85-200, Main Feedwater Pumps Rapid Feedwater Reduction Speed Setpoint ML20141N1531986-02-26026 February 1986 Procedure Fcr 85-201, Steam Generator Level Setpoint 1998-08-28
[Table view] |
Text
Seri21 No. 1242 Att:chment 8 LES,gN PLAN REVISION / REVIEW HISTORY [Oss op[C b3 gg my gg.s /245.2d LESSON PL AN TITLE LESSON PLAN NUMBE R
$8vstins2 l Nkan17'4 octsxe Pr as- Gef Nd co/ de sy U 2 j' as visro m gy DATE SIGN ATU RE NUMBER
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8603040450 860226 i PDR ADOCK 05000346 PDR i
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GOP-OLC-001.00 Attachment 28 Program
Title:
OPERATOR LICENSED CANDIDATE Course
Title:
PROCEDURES NORMAL, ABNORMAL, and EMERGENCY Lesson
Title:
ABNORMAL OPERATING PROCEDURES Approximate Time: Revision No.: 00 Date: 8510 Resource Materials for the Instructor:
Job Aids: Applicable Abnormal Procedure Audio / Visual Equipment Needed: Overhead Projector List of Transparencies:
Equipment / Tools: N/A Safety Requirements: N/A Instructional Setting: Classroom Student Materials: Pen or Pencil, Paper, Handout Special Considerations: N/A Instructor
References:
AD 1828.10, AD 1805.00, AB 1203, Reg Guide 1, 33 10 CFR 50, Technical Specifications Student
References:
AB 1203 Applicable 1 of 7 1
LOSS OF AC BUS POWER SOURCES AB 1203.28 GOP-OLC-001.00 Attachment 28 OBJECTIVE. OBJECTIVE TEXT NUMBER 0 UPON SUCCESSFUL COMPLETION OF START' -
UP TRAINING, TE
. REACTOR OPERATORS AND SENIOR REACTOR OPERATORS WILL BE ABLE TO PROPERLY APPLY THE ABNORMAL PROCEDURES NECESSARY FOR PROPER TASK PERFORMANCE.
00 TE FOLLOWING ENABLING OBJECTIVES ASSOCIATED WITH THIS LESSON PLAN ARE DESIGNED TO SUPPORE TE " KNOWLEDGE" REQUIREMENTS FOR TE ABOVE TERMINAL OBJECTIVE.
000 TE TRAINEE, WITHOUT REFERENCES (UNLESS OTHERWISE SPECIFIED), ACCORIDNG TO APPROVED PROCEDURES, WILL BE ABLE TO:
01 GIVEN SPECIFIC SYMPTOMS, CORRECTLY RECOGNIZE LE APPLICABLE ABNORMAL PROCEDURE.
02 LIST / STATE TE FINAL PLANT CONDITION THAT THE ABNORMAL PROCEDURE DIRECTS TE PLANT TO BE PLACED IN.
03 RECALL / IDENTIFY TE PLANT EQUIPMENT / SYSTEMS AVAILBLE TO TE OPERATOR DURING TE PERFORMANCE OF TE ABNORMAL PROCEDURE.
04 LIST / STATE TE FINAL CONDITION OF SELECTED PLANT SYSTEM, WHEN TE ABNORMAL PROCEDURE IS COMPLETE.
05 WHEN PROVIDED WITH A SPECIFIC NOTE AND/0R CAUTION, CORRECTLY LIST / STATE THE REASON FOR TE NOTE AND/OR CAUTION.
06 LIST / STATE TE EMERGENCY ACTION LEVEL TE STATION / SITE IS IN WHEN THE ABNORMAL PROCEDURE IS: ENTERED, IN PROGRESS, COMPLETED (SR0 ONLY).
1 07 BRIEFLY DESCRIBE TE ACTION (S) THAT EACH INDIVIDUAL IS DIRECTED TO PERFORM, IN ACCORDANCE WITH TE ABNORMAL PROCEDURE (SR0 ONLY - ALL INDIVIDUALS ACTIONS).
l i
1 1
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LOSS OF AC BUS POWER SOURCES AB 1203.28 GOP-OLC-001.00 Attachment 28 i
1.0 INTRODNCTION The intent of thic lesson is to introduce / review the Loss of TP-1 AC Bus Power Sources Abnormal Procedure. The material (s) that you are responsible for is/are stated in the objectives for this lesson.
2.0 PRESENTATION A. Symptoms that indicate entrance into this abnormal OBJ. #1 procedure.
- 1. Zero volts on the following buses.
- a. A
- b. B
- c. C1
- d. C2
- e. D1
- f. D2
- 2. Loss of Normal Station Lighting B. The following Automatic Actions will occur OBJ #3 & 7
- 1. Reactor / Turbine Trip
- 2. Emergency Diesel Generators START and Energize C1/El and D1/F1 Buses
- 3. SFRCS Actuation C. Operator Actions
- 1. Determine the proper procedure section to enter and Details of actions perform the actions. are given in the AB
- a. Complete loss of AC power section 6.0
- b. Loss of AC to 13.8KV buses (D.G(s) available)
Section 3.
t 3 of 7 l
I
}
LOSS OF AC BUS POWER SOURCES AB 1203.28 GOP-OLC-001.00 Attachment 28 l o
- 2. Action for a complete loss of AC Section 6.0
- a. Dispatch operators te locally attempt to start the Diesel Generators and energize C1 or D1 Bus.
(1) If either C1 or D1 can be energized, proceed to EP 1202.01 RPS, SFAS, SFRCS Trip Step 4.1.2. ;
(2) If not contact Load Dispatcher "take necessary steps to restore offsite power.:
- b. Dispatch operators to line up and commence feeding the Steam Generators with the Auxiliary Feedwater System.
- c. Strip A, B, C2 and D2 buses TP-2, TP-3
- d. If offsite power is available attempt to energize A, B, C1 and D1 buses. If so, go to EP 1202.01 Step 4.1.2.
- e. Preserve RCS inventory -
(1) Isolate Letdown MU-3 (2) Isolate Seal return MU-38 (3) Isolate Pressurizer sample line RC-240B
- f. Place Diesel Air Compressor in Service
- g. Trip previously running MU pump isolate seal supply,
- b. IF offsite power is not restored within 20 Attachment 1 minutes reduce load on the station batteries. of A.B.
- i. Wait for offsite Power to be Restored.
- 3. Actions for loss of AC to 13.8KV buses Diesel Generator (s) available.
- a. Take Control of Atmospheric Vent Valves (SFRCS blocked) 4 of 7
LOSS OF AC BUS POWER SOURCES AB 1203.28 GOP-OLC-001.00 Attachment 28
- b. Trip the following breakers:
(1) Source Bkrs. to A and B Buses TP-2 (2) Load Bkrs. on A and B Buses (3) Source Bkrs to C2 and D2 Buses TP-3 (4) Load Bkrs on C2 an D2 Buses except lighting bkrs.
I READ CAUTION: Care should be taken not to overload the D.C.'s Read aloud when supplying C2 and D2 buses. If an SFAS trip and emphasize occurs, C2 and D2 may have to be deenergized to OBJ #5 prevent overloading the D.G.s.
- c. If DG-1 is on C1 close AC110 to TP-4 energize C2 Addendum 3
- d. If DG-2 is on D1 close AD1'10 to TP-4 energize D2
- e. Turn the essential pressurizer heater control switch to "0N" then "AUT0"
- f. Try to Restore Offsite Power
, g. If Not restored and Both D.G.s are available and No cooldown required go to PP 1102.10 (Plant Shutdown) i
- h. If Not restored and Both D.G.s are available and cooldown required, go to AB 1203.04 (Depressurization with only Safety Grade Equi ment) i
- i. If Not restored and only one D.G. available s Addendum 1 (1) Recover essential bus F1 or El TP-5 i By supplying from:
- 1 D.G. available C1 to C2 to D1 ,
or l
C1 to D2 to D1 l l
l 5 of 7
- l. . -- . . - - - - -
LOSS OF AC BUS POWER SOURCES AB 1203.28 GOP-OLC-001.00 Attachment 28
- 2 D.G. available D1 to D2 to C1 TP-6 or D1 to C2 to C1
- j. If restored, reenergize the buses from th'eir normal or alternate sources.
(1) C2 and D2 buses to normal AC source Emphasize
" dead bus" transfer isolate from diesci Addendum 2 by opening bus tie breakers.
(a) Energize C2 and D2 kuses from AC or BD transformers.
(b) Place Isocronous droop switch in DOUBLE EMPHASIZE
" droop" (c) Place voltage regulator droop switch in "On" (d) Parallel the D.G. with the normal power source close incoming bus
' breaker unload the D.G. trip D.G.
b reak.t r .
- k. Restart one RCP per loop
- 1. Restart a TPCW pump
- m. Start a Station Air Compressor
- a. Refer to either PP 1102.10 or AB 1203.03 depending on plant conditions.
D. Initial and Final Plant Conditions
- 1. The plant is assumed to be in mode 1 or 2 at the start of the event.
- 2. The plant is taken to Mode 3 (hot standby) Obj . #2 when the procedure is followed.
6 of 7
LOSS OF AC BUS POWER SOURCES AB 1203.28 GOP-OLC-001.00 Attachment 28
- 3. RCS Heat Removal is via the Steam Generators, Obj. #4
, Auxiliary Feedwater is supplying the S.G.'s, the AVVs or steam safeties are maintaining pressure (Tsat; RCS Temp) Natural circulation is in progress.
- 4. The Emergency Action Level the plant is in at the: Obj. #6
- a. Start is: Unusual Event
- b. During: Dependent on plant conditions AC lost > 15 minutes - Site Emergency i
- c. Completed: Dependent on plant conditions j refer to (b.) above.
READ CAUTION: If D.G.s are supplying C1 and C2 buses, DO NOT Read Aloud j reset SFAS until off-site power is available.
3.0
SUMMARY
A. Review symptoms B. Review initial plant conditions i
C. Review final plant conditions D. Review Emergency Action levels E. Review cautions 4.0 EVALUATION l A. Ask students to answer the objectives 5.0 ASSIGNMENT l
GOP-OLC-ATTACH. 28 2
7 of 7 i
1 LOSS OF AC BUS POWER SOURCES AB 'a203.28 GOP-OLC-001.00 Attachment 28 Addendue 1 ADDENDUM 1 TO ATTAC}DfENT 28 Reasons (s) for recovering of the opposite side essential bus with only one Diesel Generator operating.
- 1. Restore Power to the Battery Chargers and the Instrument Buses - Prevent Degradation of Plant Control and recovery.
- a. Loss of E-1 Buss will result in loss of the following: (assuming no operator action).
- 1. Inverter YVA - Bus YAU
- 2. Dip 125VDC
- 3. Rectifier YRFI - Alt. Pwr. tu Inv YVI
- 4. Inverter YFI
- 5. Channel #1 120VAC Y1
- 6. Inverter YA - Emerg. Pwr to Channel #1 (Y1)
- 7. Din 125VDC
- 8. Rectifier YRF3 - Alt Pwr to Inv. YV3
- 9. Inverter YF3
- 10. Channel #3 120VAC Y3 Example of Loads Lost SFAS Solenoid Valves Channel Emg. D.G. 1-1 and ACT RPS I and 3 SFAS 1 and 3 SFRCS i i
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LOSS OF AC BUS POWER SOURCES AB 1203.28 GOP-OLC-001.00
. Attachment 28
. Addendum I
- b. Loss of F-1 Buss will result in loss of the following:
(Assuming no operator action)
- 1. Inverter YVB -- Bus YBU
- 2. D2P 125VDC
- 3. Rectdfier Y1F Alt Pwr to Inv. YV4
- 4. Inverter TV4
- 5. Channel #4 120 VAC T4
- 6. Inverter YB - Emerg Pwr to Channel #4 (Y4)
- 7. D2N 125VDC
- 8. Rectifier YRF Alt Pwr to Inv YV2
- 9. Inverter YF3
- 10. Channel #2 120 VAC Y2 Examples of loads lost:
SFAS Solenoid Valves Channel 2 Emg DG 1-2 and Alt RPS 2 and 4 SFAS 2 and 4 SFRCS
- 2. Restore Power to a needed safety function
- a. Loss of C1 or Di Bus will result in Loss of the following:
- 1. Service Water Pump
- 2. HP Inj. Pump
- 3. DH Pump i
- 4. CC Pump i
l CAf' TION: Closelv monitor the Diesel Generator Load
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i LOSS OF AC BUS POWER SOURCES AB 1203.28 GOP-OLC-001.00 Attachment 28 Addendum 2 Procedure For Removing Diesel Generator 1-1 (1-2) from Service by Powering 1 (D1) from Buss Tie Transformers or C2 (D2).
No. 1-1 (1-2) Diesel Generator is running and tied to Bus C1 (D1).
Bus C1 (D1) is isolated from the system. Breakers AC110 (AD110) and ABDCI (AACD1) are TRIPPED.
The Emergency Control Transfer Switches located on Bus C1 (D1) cubicles for Breakers AC110 (AD110) and ABDCI (AACD1) are in the NORMAL position.
The Shift Supervisor has given his permission to parallel with the system.
Bus C2 (D2) is energized by the system with Breaker AC110 (AD110) TRIPPED or XFMR BD (AC) is energized by
- the system with Breaker ABDCI (AACD1) TRIPPED.
Place ISOCHRONOUTS-DROOP SWITCH on Panel C3617 (C3618) in DG Room 1 (2) in the " DROOP" position unless in this position.
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' Place VOLTAGE REGULATOR DROOP SWITCH on Panel C3617 (C3618) in DG Room 1 (2) in the "0N" position unless in this position.
Place DG1 (2) SYNC SELECTOR switch in the BKR TO C2 i
(D2) or TIE BKR TO XBD (XAC) position on Local Control Panel C3615 (C3616).
Adjust the Diesel Generator speed using DG1 (2) SPD control switch on Local Control Panel C3615 (C3616) so that the DG1 (2) SYNCHRON0 SCOPE pointer is revolving slowly in the FAST (clockwise) direction. Adjust the DG voltage using Voltage Reg. Control switch until the INCOMING voltage > the RUNNING voltage.
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1 LOSS OF AC BUS POWER SOURCES AB 1203.28 GOP-OLC-001.00 Attachment 28 Addendum 2 Close the BUS C1 (Di) to BUS C2 (D2) TIE BREAKER control switch for AC110 (AD110) or XFUR BD (AC) to BUS C1 (D1) Control Switch for ABDCI (AACD1) on Local Control Panel C3615 (C3616) when the DG1 (2)
. SYNCHRON0 SCOPE pointer is at the twelve o' clock position or slightly before the twelve o' clock position.
CAUTION: When the DG's receive an auto start signal,
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they automatically go to isochronous mode and remain in isochronous mode. Therefore,
, when the DG is parallelled to the system immediately decrease load and trip the DG output breaker AC101 (AD101).
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LOSS OF'AC BUS. POWER SOURCES AB 1203.28 GOP-OLC-001.00.
Attachment 28 ,
Addendum 3~
$ Procedure for Powering Busa C2 (D2) from C1 (D1) with C1 (D1) being Powered Only from DG 1-1 (1-2).
1 The Diesel Generator is running and serving C1 (D1) bus load only.
! Bus C2 (D2) is de-energized and all breakers are TRIPPED including Breakers AACC2 (ABDD2) and AC110
- (AD110).
The Shift Supervisor has given his permission to apply load from Bus C2 (D2) to No. 1-1 (1-2) Diesel Generator.
i The Emergency Control T1ansfer Switch located on Bus C1 (D1) for Breaker AC110 (AL110) is in the NORMAL position.
Place the DG1 (2) SYNC switch HS 6221 (HS6231) in the BKR TO C2 (D2) position on Control Room Panel C5715 or -
place DG1 (2) SYNC SELECTOR switch in the BKR TO C2 (D2)
, position on Local Control Panel C3615 (C3616). t i Place the BUS C1 (D1) TO BUS C2 (D2) TIE BRER control switch for AC110 (AD110) located on Control Room Panel ;
C5715 in the CLOSE position or place the BUS C1 (D1) '
to BUS C2 (D2) TIE BRKR control switch for AC110 (AD110) located on Local Control panel C3615 (C3616) in the CLOSE position. l Apply load to Bus C2 (D2) as directed by the Shift
! Supervisor.
.i CAUTION: Do not exceed rating limitations of the Diesel
! Genera tor.
t Completed _ Time Date ,
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GOP-OLC-Attach. 28 3 of 3 1
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