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 1 to Procedure GOP-OLC-001.01, Operator Licensed Candidate:Procedures Normal,Abnormal & Emergency,Loss of Instrument AirML20141N163 |
Person / Time |
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Site: |
Davis Besse |
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Issue date: |
12/31/1985 |
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From: |
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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1242, GOP-OLC-001.01, GOP-OLC-1.01, TAC-61015, NUDOCS 8603040432 |
Download: ML20141N163 (12) |
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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
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GOP-OLC-001.01 Attachment 36 Program
Title:
OPERATOR LICENSED CANDIDATE Course
Title:
PROCEDURES NORMAL, ABNORMAL, AND EMERGENCY Lesson
Title:
ABNORMAL OPERATING PROCEDURES Approximate Time: Hours Revision No.: 0 Date: 85 Resource Materials for the Instructor:
Job Aids: Applicable Abnormal Procedure Audio / Visual Equipment Needed: Overhead Projector List of Transparencies:
Equipment / Tools: None Safety Requirements: Davis-Besse Safety Practices Instructional Settina: 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
Reference:
AB 1203 Applicable 1 of 11
LOSS OF INSTRUMENT AIR AB 1203.36 GOP-OLC.001.01
- Attachment 36 l
4 OBJECTIVE. OBJECTIVE TEXT NUMBER O UPON SUCCESSFUL COMPLETION OF START-UP TRAINING, THE
- REACTOR OPERATORS AND SENIOR REACTOR OPERATORS WILL E ABLE TO PROPERLY APPLY TE ABNORMAL PROCEDURES NECESSARY FOR PROPER TASK PERFORMANCE.
i 00 TE FOLLOWING ENABLING OILJECTIVES ASSOCIATED WITH THIS 3 LESSON PLAN ARE DESIGNED TO SUPPORT TE " KNOWLEDGE" j REQUIREMENTS FOR TE ABOVE TERMINAL OBJECTIVE.
000 TE TRAINEE, WITHOUT REFERENCES (UNLESS OTERWISE SPECIFIED), ACCORDIDNG TO APPROVED PROCEDURES, WILL BE e ABLE TO:
01 GIVEN SPECIFIC SYMPTOMS, CORRECTLY RECOGNIZE THE APPLICABLE ABNORMAL PROCELURE.
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 AVAILABLE TO TE OPERATOR DURING TE PERFORMANCE OF THE ABNORMAL PROCEDURE.
- 04 LIST / STATE TE FINAL CONDITION OF SELECTED PLANT SYSTEM, WHEN TE ABNORMAL PROCEDURE IS COMPLETE.
1 05 WHEN PROVIDED WITH A SPECIFIC NOTE AND/OR CAUTION,
' CORRECTLY LIST / STATE TE REASON FOR THE NOTE AND/OR CAUTION.
li 06 LIST / STATE TE EMERGENCY ACTION LEVEL THE STATION / SITE IS IN WHEN TE ABNORMAL PROCEDURE IS: ENTERED, IN ,
PROGRESS, COMPLETED (SRO ONLY).
07 BRIEFLY DESCRIBE TE ACTION (S) THAT EACH INDIVIDUAL IS DIRECTED TO PERFORM, IN ACCORDANCE WITH TE ABNORMAL i
PROCEDURE (SRO ONLY - ALL INDIVIDUALS ACTIONS).
a t
l l 2 of II
)
LOS5 0F INSTR 1 MENT AIR AB 1203.36 GOP-OLC.001.01 Attachment 3o 1.0 INTF0DliCTION The intent of this lesson is to introduce / review the Loss of Instrument Air Abnormal Procedure. Tbc material (s) that you are responsible for is/are stated in the objectives for this lessoa. TP-1 2.0 PRESENTATION A. Symptoms that indicate entrance into this abnormal Obj. #1 procedure.
- 1. The following ant.unciator Alarms
- a. Station Air CMPSR Trcuble i
- b. Instrument Air Eng. CMPSR Trouble
- c. Air Faader Pressure Low (1) Station 97 psig (decreasing) 7 (2) Instrument 95 psig (decreasing) i
- 2. loss of Instrument Air is defined as < 75 psig on Inst, Air Header pressure indicator PI810 (located in the Control Room.
- a. Atthispressuref>)5psig),theoperatorwill experience a loss of
(1) Velve Control Enclosure 2 of AB 1
(2) Indicators Enclosure 1 of AB (3) Alarms Enclosure 1 of AB B. Operator Actions i 1. The operators first action (s) is to follow the OBJ #3 and 7 appropriate alarm procedure (s),
(i.e.) a, Start Additional Compressors
- b. Correct the cause i
- 3 of 11
A LOSS OF INSThuMaNT AIR AB 1203.36 GOP-OLC.001.01 Attachment 36
- 2. The operators second action is to perform the Details of Actions Actions listed in the applicable procedure are given in the AB when the initiating condition (s) is/are met,
- a. PI 810 g 75 psig (1) Trip the Reactor (2) Actuate SFRCS on Low Steam Generator Level i
(3) Perform EP 1202.01, RPS, SFAS, SFRCS Trip or SG Tube Rupture.
a (4) Continue to correct the cause.
(5) Insure Station Air Header is isolated SA 2008. TP-2 (6) Insure Filter / Dryer Emergency Bypass Line Regulator and Filter are in service.
(7) Isolate the normal inst. air filters and dryers.
- 3. When header pressure decreases to 70 psig insure that the following header (s) is/are isolated.
- a. Turbine Building
- b. Water Treatment Building
- c. Perform the following actions (1) Trip both heater drain pumps '
(2) Shutdown the screen wash pumps (3) Shutdown the cooling tower makeup pumps (4) Open condenser vacuum breakers (5) Lockout the mechanical hogger (6) Shutdown the steam packing exhausters (7) Try to maintain one condensate pump running 4 of 11
LOSS OF INSTRUMENT AIR AB 1203.36 GOP-OLC.001.01 I Attachment 36 i
l t
(8) Maintain hotwell level using local valves; s
(9) Take manual control of service water to the component cooling and turbine plant cooling water heat exchangers (10) Throttle TPCW pump discharge valve to control discharge pressure ), 74 psig. Leave ene pump running.
(11) Provide a flow path for the flash tank pumps, blowdown six condenser and a vent for the flash tank.
(12) Isolate and bypass the condensate polishers.
(13) Place turbine on turning gear (manually engage)
(14) Restore demineralized water header if needed (15) Restore domestic water header is needed (16) Inform C&HP - check water treatment system
- 4. When header pressure decreases to5 65 psig, the Auxiliary Building non-essential header isolates. The following operational problems will/may occur.
- a. Pressurizer level - MU-32 fails open
- b. Divert path for letdown - alternate flow path to CWRT 1
- c. The following valves may close:
(1) MU-33 RCS MU CTNT Iso.
(2) MU-3 Letdown CTMT Iso.
(3) MU-66A thru D - SI CTMT Iso's (4) MU Seal Return Header CTMT Iso READ-CAUTION Any SFAS actuated valve overridden to a non-SA Read Aloud position will have to be manually placed in and Emphasize the.SA position if a SFAS occurs. OBJ. #5 5 of 11
LOSS OF INSTRUMENT AIR AB 1203.36 COP-OLC.001.01 Attachment 36
- d. Prevent damage to the running CCW pump by closing the CCW outlet valve from the DH cooler.
- e. Trip the primary water transfer pump
- f. Shutdown and lockout the following:
(1) Clean waste booster pumps (2) CWRT transfer pumps (3) CWMT transfer pumps (4) Conc. transfer pumps (5) Waste gas compressors (6) MWMT transfer pumps (7) Quench tank circ. pump (8) R.C. drain tank pumps (9) Boric acid addition tank immersion heaters
- g. Start the boric acid addition tank mixer
- h. To add boric acid: The boric acid pumps start Emphasize low level switch must be held in that position for the interlock will pump to run shutdown pump if switch is not held
- i. Place Control Room EVS system in service J. The following valves may also fail which could res:rlt in operational problems.
(1) ffU-6 letdown flow control valve (Closed)
(2) Loss of atmospheric vent valves (Closed)
(3) MU seal injection flow control valve (Open)
(4) Loss of deserator level control.
6 of 11
LOSS OF INSTRUMENT AIR AB 1203.36 GOP-OLC.001.01 Attachment 36 C. Initial and Final Plant Condition (s)
- 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) when the OBJ. #2 procedure is followed.
- 3. RCS Heat Removal is via the Steam Gen., Auxiliary OBJ. #4 Feedwater is supplying the SG's. The AVV's or the Steam Safeties are maintaining pressure (Tsat; RCS Temp)
- 4. The Emergency Action Level the plant is in at the: OBJ #6
^
- a. Start is: Unusual Event condition - Miscellaneous
- b. During: Dependent on plant conditions:
U.E., Alert
- c. Completed: Dependent on plant conditions:
)
U.E., Alert, Site Eng. No Action Level D. Valves Identified in the procedure that may require manual operation.
- 1. KU-33 RCS Makeup Containment isolation Fail Position - Closed (75 psig)
Location - #2 Mechanical Penetration Room Location of Air Volume Tank - Outside #2 Mechanical Penetration Room Door Manual Operation - Isolate the air to the SL-1 Volume Tank (close valves), open the vent SL-2 Proceed to valve, open regulator drain, SL-3 remove fork device from handwheel spoke, turn handwheel.
1 7 of 11
a LOSS OF INSTRUMENT AIR AB 1203.36 GOP-OLC.001.01 Attachment 36
- 2. MU-3 Letdown Containment Isolation Fail Position - closed (75 psig)
Location - #1 Mechanical Penetration Room Location of Air volume tank - across from Motor Control Center E22B Manual Operation - same as MU-33
- 3. MU-66A thru 66D Seal Injection Containment Isolation Valve.
Fail Position - Closed (75 psig)
. Location - #1 Mechanical Penetration Roon Location of air volume tank - across from Motor Control Center E22B Manual Operation - same as MU-33
- 4. MU-38 Seal Return Header Containment Isolation Fail Position - Closed (30 psig)
Location - #1 Mechanical Penetration Room Location of Air Volume Tank - Across from Motor Control Center E22B Manual Operation - Same as MU-33
- 5. PW-6881 Primary Water Transfer Pump Suction Fail Position - closed (s65 psig)
Location - Clean Waste Monitor Tank Room SL-11 l
Manual Operation - isolate air to the regulator l (close valve). Open drain on Regulator, turn '
handwheel on top of valve diaphragm.
l l
8 of 11
LOSS OF INSTRUMENT AIR AB 1203.36 GOP-OLC.001.01 Attachment 36
- 6. CC-1460 Makeup Pump header 1 solation" Fail position - closed (s65 psig)
Location - Component Cooling Pump /Hx Roon N.E.
Corner above door.
Manual Operation - isolate air to regulator SL-4 (close valve). Open vent valve; turn handhweel on top of diaphragm.
- 7. CT-916 cooling Tower Makeup Valve Fail Position - Closed (* 70 psig)
Location - Service Water Structure - Lower elevation, south of bubbler pumps.
) Manual Operation - isolate air to the two SL-5 4
regulators (close valves). Open Drains on SL-6 regulators, open equalizing valve. Turn SL-7 handwheel to allow key to align with keyway.
Insert key into keyway; turn handwheel.
$ 8. CT-840 Cooling Tower Blowdown Valve i
Fail. Position - Open (* 70psig)
Location - Circulating Water Pump House S.W. corner Manual Operation - Same as CT-916 SL-8 SL-9
., SL-10 i
- 9. DW-6880 Demineralized Water Transfer Pump Discharge Valve Fail Position - Closed (70 psig)
~
Manual Operation - same as PW-6881 SL-11 i
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t LOSS OF INSTRUMENT AIR AB 1203.36 GOP-OLC.001.01 Attachment 36 i
- 10. Atmospheric Vent Valves
{ Fail Position - Closed
$ Location - In the radwaste ventilation area outside the Control Room (elevation 623') is located a manual handwheel and two valves for i each atmospheric vent valve. Instructions are posted near each handwheel as follows:
Manual Operation - Close Valve A (see drawing) SL-12 which isolates air from Valve V3.
Open Valve B (vent valve) which vents actuator air through V3 Check the handwheel counter at zero. Then open SL-13 the handhweel (CCW) to the desired position.
0 turns = closed
, 253 turns = open J
l NOTE: Valve does not start to open until approx.
13 turns.
If partial closing is desired, simply rotate the manual handwheel in the clockwise direction since the valve is spring assisted in the close direction.
If positive shutoff is desired, close the manual handwheel until it reaches the full closed position j (zero counts on counter).
Close B Valve CAUTION: Do NOT open A valve unless remote manual operator counter is at zero counts as damage can occur to the lifting fork on the valve stem.
Open A valve to restore closing air to the actuator.
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LOSS OF INSTRUMENT AIR AB 1203.36 GOP-OLC.001.01 Attachment 36
- 11. Discuss the process to return the hand jacked valves to auto.
- a. Basically go in reverse orcer of placing valves in manual. Emphasize that: Keys must be removed from keyways and hand jacks returned to the " neutral" position (if applicable) 3.0
SUMMARY
A. Review symptoms 4
B. Review initiating event f"
C. Review initial plant condition D. Review final plant condition E. Review Emergency Action Level the site may be in.
OPTION: At the instructors discretion - use TP's of TP's included Systems to indicate valves that will not control ~or fail.
4.0 EVALUATION A. Ask the students to answer the objectives. i 5.0 ASSIGNMENT A. None ;
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4
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GOP-OLC-Attach. 36 11 of 11
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